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June 2009 INFO-0775 Occupational Dose Data for Major Canadian Nuclear Facilities 2001¬07 Canada’s Nuclear Regulator

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June 2009

INFO-0775

Occupational Dose Data for Major Canadian Nuclear Facilities 2001not07

Canadarsquos Nuclear Regulator

Occupational Dose Data for Major Canadian Nuclear Facilities 2001ndash07

copy Minister of Public Works and Government Services Canada 2009 Catalogue number CC172-482009E-PDF ISBN 978-1-100-12843-6

Published by the Canadian Nuclear Safety Commission CNSC Catalogue number INFO-0775

Extracts from this document may be reproduced for individual use without permission provided the source is fully acknowledged However reproduction in whole or in part for purposes of resale or redistribution requires prior written permission from the Canadian Nuclear Safety Commission

Eacutegalement publieacute en franccedilais sous le titre de Donneacutees sur les doses reccedilues par les travailleurs dans les grandes installations nucleacuteaires canadiennes 2001-2007

Document availability This document can be viewed on the CNSC Web site at nuclearsafetygcca To order a printed copy of the document in English or French please contact

Canadian Nuclear Safety Commission 280 Slater Street PO Box 1046 Station B Ottawa Ontario K1P 5S9 CANADA

Tel (613) 995-5894 or 1-800-668-5284 (in Canada only) Facsimile (613) 995-5086 E-mail infocnsc-ccsngcca Web site nuclearsafetygcca

Occupational Dose Data for Major Canadian Nuclear Facilities 2001ndash07 INFO-0775

June 2009

Table of Contents List of Figures iv Introduction 1 10 Facility-Wide Comparisons of Average Effective Doses 4

11 Average Effective Doses Based on Non-Zero Results at All Selected Facilities 4 12 Average Effective Doses Based on All Monitoring Results at All Selected Facilities 8

20 Facility-Specific Overview of Occupational Doses 12 21 Nuclear Power Plants 12

211 Bruce Nuclear Generating Stations 13 212 Pickering Nuclear Generating Stations 16 213 Darlington Nuclear Generating Station 19 214 Gentilly-2 Nuclear Generating Station 22 215 Point Lepreau Nuclear Generating Station 25

22 Uranium Mines and Mills 28 221 Cluff Lake Operation 28 222 McClean Lake Operation 31 223 McArthur River Operation 34 224 Key Lake Operation 37 225 Cigar Lake Operation 40 226 Rabbit Lake Operation 43

23 Uranium Refineries 46 231 Blind River Refinery 46 232 Port Hope Conversion Facility 49

24 Fuel Fabrication Facilities 52 241 General Electric Nuclear Fuel Facilities 52 242 Zircatec Nuclear Fuel Facility 55

25 Research and Radioisotope Production Facilities 58 251 Chalk River Laboratories and Whiteshell Laboratories 58 252 MDS Nordion (Nuclear Substance Processing Facility and Canadian

Irradiation Centre) 62 253 Tri-University Meson Facility 65

26 Tritium Light Source Production Facilities68 261 Shield Source Incorporated 68 262 SRB Technologies (Canada) Inc 71

Glossary 74 Bibliography 76

List of Figures

Figures 11ndash114 Facility-wide Average Doses

Figures 21ndash24 Bruce Nuclear Generating Stations Figures 25ndash28 Pickering Nuclear Generating Stations Figures 29ndash212 Darlington Nuclear Generating Station Figures 213ndash216 Gentilly-2 Nuclear Generating Station Figures 217ndash220 Point Lepreau Nuclear Generating Station

Figures 221ndash224 Cluff Lake Operation Figures 225ndash228 McClean Lake Operation Figures 229ndash232 McArthur River Operation Figures 233ndash236 Key Lake Operation Figures 237ndash240 Cigar Lake Operation Figures 241ndash244 Rabbit Lake Operation

Figures 245ndash248 Blind River Refinery Figures 249ndash252 Port Hope Conversion Facility

Figures 253ndash256 General Electric Nuclear Fuel Facilities Figures 257ndash260 Zircatec Nuclear Fuel Facility

Figures 261ndash264 Chalk River Laboratories and Whiteshell Laboratories Figures 265ndash268 MDS Nordion Figures 269ndash272 Tri-University Meson Facility (TRIUMF)

Figures 273ndash276 Shield Source Incorporated Figures 277ndash280 SRB Technologies (Canada) Inc

Table 1 Effective Dose Limits in Canada as Specified by the Radiation Protection Regulations Person Period Effective Dose

(mSv) Nuclear energy workers including pregnant (a) One-year dosimetry period 50 nuclear energy workers

(b) Five-year dosimetry period 100 Pregnant nuclear energy worker Balance of the pregnancy 4

A person who is not a nuclear energy worker One calendar year 1

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Introduction Workers at nuclear facilities are exposed to radiation Their dose is monitored and subject to Canadian Nuclear Safety Commission (CNSC) regulatory requirements which aim to protect their health and safety The amount of radiation to which employees are exposed is referred to as ldquooccupational doserdquo This report provides an overview of occupational radiation doses from 2001 to 2007 at the major nuclear facilities licensed by the CNSC It presents an objective summary of occupational dose information and includes a glossary of terminology

The data collected shows that the average doses for all facilities are far below the individual annual effective dose limit of 50 milliSieverts (mSv) set out in the Radiation Protection Regulations

The report includes data for the following types of facilities

bull nuclear power plants bull uranium mines and mills bull uranium refineries bull fuel fabrication facilities bull research and radioisotope production facilities bull tritium light source production facilities

Each facility is unique in regards to the type of work performed as well its current lifecycle stage (ie operating at reduced or full capacity or in a phase of refurbishment for example) and each provides varying programs to mitigate radiation doses to workers The resulting collective and average doses are based on complex and differing work environments Therefore direct comparisons between facilities in terms of occupational dose are not possible

Regulatory Radiation Dose Limits The Radiation Protection Regulations limit the amount of radiation to which persons may be exposed Table 1 presents the effective dose limits as set out in paragraphs 13 and 14 of the regulations

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

The Radiation Protection Regulations also require CNSC licensees to implement radiation protection programs and to keep radiation doses as low as reasonably achievable (a concept referred to as the ALARA principle) The CNSC evaluates licensee radiation protection programs and these evaluations include reviews of the occupational dose data which is one among several indicators of a radiation protection programrsquos effectiveness

About the Data

Source Statistics in this document are gathered from the National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses1 Maintained by Health Canadarsquos Radiation Protection Bureau the NDR publishes annual reports on occupational dose information and trends according to job type

Due to the large number of CNSC-licensed facilities this report does not include occupational dose information for every CNSC licensees Please refer to the NDR Web site2 to review Health Canadarsquos reports

Analysis This report presents the following types of data

a average doses b collective doses c distribution of effective doses

a Average doses provide a common means of indicating central tendencies of dose distribution and show where doses lie on average with respect to annual dose limits

Notes on average effective doses

1 This report presents two types3 of arithmetic averages for individual effective doses bull averages that include only non-zero (positive) results bull averages that include all monitoring results (including zero-value doses)

2 When assessing regulatory compliance individual doses mdash not average doses mdash must be compared to individual dose limits in the Radiation Protection Regulations

1 In Canada the Radiation Protection Regulations require licensed dosimetry services to submit dose information for nuclear energy workers (NEWs) While not required by law dose information for non-NEWs is also typically submitted to the NDR The data in this report does not distinguish between personnel designated as NEWs versus those who are not 2 httpwwwhc-scgccaewh-semtoccup-travailradiationregistindex_ehtml 3 Some licensees monitor most or all workers (including those unlikely to be directly exposed to sources of occupational radiation) whereas other licensees monitor only employees likely to receive radiation doses Therefore two types of averages are presented averages that consider only non-zero results and averages that consider all results Both statistical approaches have merit and are included in this report (Note The exclusion of zero value doses in the averaging could unfairly bias findings against licensees with effective radiation protection programs)

2

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

b Collective doses indicate the sum of all the doses associated with a facilityrsquos operation and can be used to estimate a facilityrsquos control of occupational doses

Note on collective doses

1 The Radiation Protection Regulations do not set limits on collective doses however the CNSC recommends that licensee radiation protection programs should aim to reduce collective doses These values can indicate a facilityrsquos radiological detriment and help assess whether a facility is operating in accordance with the ALARA principle

c Distribution of effective doses shows the ranges in which effective doses are concentrated

Effective dose calculations By definition effective doses cannot be measured precisely but they can be approximated in order to determine radiation exposure and to assess the associated risks Section 13 of the Radiation Protection Regulations defines the dose calculation methods used to determine effective doses as expressed in millisieverts (mSv) which are based on measurable quantities in the operational environment

Effective radiation doses are made up of various components of which the most common (in Canada) are as follows

bull photons and neutrons from sources outside the body bull radon progeny radon gas long-lived radioactive dust (uranium dust) and tritium that are

taken into the body

The effective doses reported to the NDR represent the sum of their applicable components For example the effective dose to a worker who received radiation doses from both neutrons and tritium would be the sum of these two quantities

Note on average dose values

1 Average values for each dose type (for example tritium) are based on the total collective dose for that type divided by the number of all the workers monitored for any dose type

3

yrenfi R

erev

Ri

dnilB

noid N

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SM

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

10 Facility-Wide Comparisons of Average Effective Doses This section presents comparisons of average effective doses at all CNSC-licensed nuclear facilities included in this report for each year within the 2001ndash07 reporting period

bull Figures 11ndash17 present averages based on non-zero (positive) results (Section 11)bull Figures 18ndash114 present averages based on all monitoring results (Section 12)

Notes on facility-wide comparisons of average effective doses

1 Each facility type is represented by a different colour bull nuclear power plants ndash green bull uranium mines and mills ndash purple bull uranium refineries ndash yellow bull fuel fabrication facilities ndash orange bull research and radioisotope facilities ndash blue bull tritium light source production facilities ndash red

2 See Sections 21ndash26 for facility-specific data depicted in Figures 11ndash114

11 Average Effective Doses Based on Non-Zero Results at All Selected Facilities Figures 11ndash17 show average effective doses based on non-zero results for each year from 2001 to 2007 for all the facilities presented in this document

Figure 11 Average Effective Doses at All Selected F acilities for the Year 2001 (Based o n N on-Zero R esults)

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Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 12 Average Effective Doses at All Selected Facilities for the Year 2002 (Based on Non-Zero Results)

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Figure 13 Average Effective Doses at All Selected Facilities for the Year 2003 (Based on Non-Zero Results)

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Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 14 Average Effective Doses at All Selected Facilities for the Year 2004 (Based on Non-Zero Results)

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Figure 15 Average Effective Doses at All Selected Facilities for the Year 2005 (Based on Non-Zero Results)

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Figure 17 Average Effective Doses at All Selected Facilities for the Year 2007 (Based on Non-Zero Results)

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Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 16 Average Effective Doses at All Selected Facilities for the Year 2006 (Based on Non-Zero Results)

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Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

12 Average Effective Doses Based on All Monitoring Results at All Selected Facilities Figures 18ndash114 show average effective doses based on all the monitoring results for each year from 2001 to 2007 for every facility listed in this document

Figure 18 Average Effective Doses at All Selected F acilities for the Year 2001 (Based o n A ll Monitoring R esults)

8

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Figure 110 Average Effective Doses at All Selected F acilities for the Year 2003 (Based o n A ll Monitoring R esults)

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n

Rab

bit L

ake

Ope

ratio

n

Blin

d R

iver

Ref

iner

y

Port

Hop

e C

onve

rsio

n Fa

cilit

y

Gen

eral

Ele

ctric

Nuc

lear

Fue

l Fac

ilitie

s

Zirc

atec

Nuc

lear

Fue

l Fac

ility llehs

teih Wdn

a ses ie rir toto ara or bo ab La

Lrev R

ikla

Ch

MD

S N

o rdi

on

Tri-U

nive

r sity

Mes

on F

acilit

y

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 19 Average Effective Doses at All Selected Facilities for the Year 2002 (Based on All Monitoring Results)

4

35

3

25

2

15

1

05

0

Shie

ld S

ourc

e In

corp

orat

edSh

ield

Sou

rce

Inco

rpor

ated

c In)adan

Ca

(seigolonhce T

RB

SSR

B Te

chno

logi

es (C

anad

a) In

c

9

Dos

e (m

Sv)

)

Sv

(me

osD

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 111 Average Effective Doses at All Selected F acilities for the Year 2004 (Based o n A ll Monitoring R esults)

4

35

3

25

2

15

1

05

0

Bruc

e N

ucle

ar G

ener

atin

g St

atio

ns

Pick

erin

g N

ucle

ar G

ener

atin

g St

atio

ns

Dar

lingt

on N

ucle

ar G

ener

atin

g St

atio

n

Gen

tilly

-2 N

ucle

ar G

ener

atin

g St

atio

n

Poin

t Lep

reau

Nuc

lear

Gen

erat

ing

Stat

ion

Clu

ff La

ke O

pera

tion

McC

lean

Lak

e O

pera

tion

McA

rthur

Riv

er

Key

Lake

Ope

ratio

n

Cig

ar L

ake

Ope

ratio

n

Rab

bit L

ake

Ope

ratio

n

Blin

d R

iver

Ref

iner

y

Port

Hop

e C

onve

rsio

n Fa

cilit

y

Gen

eral

Ele

ctric

Nuc

lear

Fue

l Fac

ilitie

s

Zirc

atec

Nuc

lear

Fue

l Fac

ility llehs

teih Wdn

a ses ie rir toto ara or bo ab La

Lre v R

ikla

Ch

MD

S N

ordi

on

T ri-U

nive

rsity

Mes

on F

acilit

y

Figure 112 Average Effective Doses at All Selected F acilities for the Year 2005 (Based o n A ll Monitoring R esults)

4

35

3

25

2

15

1

05

0

Bruc

e N

ucle

ar G

ener

atin

g St

atio

ns

Pick

erin

g N

ucle

ar G

ener

atin

g St

atio

ns

Dar

lingt

on N

ucle

ar G

ener

atin

g St

atio

n

Gen

tilly

-2 N

ucle

ar G

ener

atin

g St

atio

n

Poin

t Lep

reau

Nuc

lear

Gen

erat

ing

Stat

ion

Clu

ff La

ke O

pera

tion

McC

lean

Lak

e O

pera

tion

McA

rthur

Riv

er

Key

Lake

Ope

ratio

n

Cig

ar L

ake

Ope

ratio

n

Rab

bit L

ake

Ope

ratio

n

Blin

d R

iver

Ref

iner

y

Port

Hop

e C

onve

rsio

n Fa

cilit

y

Gen

eral

Ele

ctric

Nuc

lear

Fue

l Fac

ilitie

s

Zirc

atec

Nuc

lear

Fue

l Fac

ility llehs

teih Wdn

a ses ie rir toto ara or bo ab La

Lrev R

ikl a

Ch

MD

S N

ordi

on

Tri-U

n ive

rsity

Mes

on F

acilit

y

Shie

ld S

ourc

e In

corp

orat

edSh

ield

Sou

rce

Inco

rpor

ated

SRB

Tech

nolo

gies

(Can

ada)

Inc

SR

B Te

chno

logi

es (C

anad

a) In

c

10

r s s n n n n n n n n ty s ty l l ty de y n cn n o o o o o o o o r i il e e o ivo o ti l h lti ti ti ti ti ti ti ti i i

Ri i tee

ta c c iil c ati ti ta ta a a a a a n i s d Inr ata r )r r r r ata a

S

fi cr te S S F F

Nor F o ae e e e e

S S au p p p i p dp p hg g g n F l n r ae og g n n n Re

o nti O O th O l orti i e cn r O O un ti se e A e e e e s Wti ti a a a u d er k k kc k k v r F DS

a a r r e n In Ca

r r e a a M a re e a a Ri F M e (n L r s Me e n n L v a

L n e a c sa en n e e e ff L

y t L s r en lr d ty

G

i

Co e c ie G a il e r i ue G nu a e b

G G g i s

K b toCl c

Nu i ge l r r o or r r C

i B

Nu to e

Cl er a a Sa Ra a lr a vp r oa ce e ae i

t Ho doe l te ll c r bl c M cc Un ne lc o e hlc c

Nu

Nu

Nu i a ab i ctr

Nu

Nu - hc L i er c a rri So en 2 u l Z L T TPe gc to ayn g l E

r- el RB

u i l e vrr atir Sn pe r

B i nk l e er Ri

e

Da t L n kc li G e aP ni Go C

h

P

) S

v(m

e os

D

4

35

3

25

2

15

1

05

0

) vS

m( e soD

Figure 114 Average Effective Doses at All Selected F acilities for the Year 2007 (Based o n A ll Monitoring R esults)

Bru

ce N

ucle

ar G

ener

atin

g S

tatio

ns

Pic

kerin

g N

ucle

ar G

ener

atin

g S

tatio

ns

Dar

lingt

on N

ucle

ar G

ener

atin

g S

tatio

n

Gen

tilly

-2 N

ucle

ar G

ener

atin

g S

tatio

n

Poi

nt L

epre

au N

ucle

ar G

ener

atin

g S

tatio

n

Clu

ff La

ke O

pera

tion

McC

lean

Lak

e O

pera

tion

McA

rthur

Riv

er

Key

Lak

e O

pera

tion

Cig

ar L

ake

Ope

ratio

n

Rab

bit L

ake

Ope

ratio

n

Blin

d R

iver

Ref

iner

y

Por

t Hop

e C

onve

rsio

n Fa

cilit

y

Gen

eral

Ele

ctric

Nuc

lear

Fue

l Fac

ilitie

s

Zirc

atec

Nuc

lear

Fue

l Fac

ility llehsetih

W d na s s ee iri oro tat ra or bo ab La Lr evi

Rk lah

C

MD

S N

ordi

on

Tri-U

nive

rsity

Mes

on F

acili

ty

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 113 Average Effective Doses at All Selected Facilities for the Year 2006 (Based on All Monitoring Results)

4

35

3

25

2

15

1

05

0

Shi

eld

Sou

rce

Inco

rpor

ated

SR

B T

echn

olog

ies

(Can

ada)

Inc

11

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

20 Facility-Specific Overview of Occupational Doses This section presents data for the following types of facilities

bull nuclear power plants (Section 21) bull uranium mines and mills (Section 22) bull uranium refineries (Section 23) bull fuel fabrication facilities (Section 24) bull research and radioisotope production facilities (Section 25) bull tritium production facilities (Section 26)

21 Nuclear Power Plants This section presents dose information for the following nuclear power plants

bull Bruce A and Bruce B Nuclear Generating Stations (Section 211) bull Pickering Nuclear Generating Stations (Section 212) bull Darlington Nuclear Generating Station Section 213) bull Gentilly-2 Nuclear Generating Station (Section 214) bull Point Lepreau Generating Station (Section 215)

Graphs in this section indicate the following data for each nuclear power plant from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for nuclear power plants

1 Effective doses are composed of the following reported components bull doses from photons (labeled on the charts as ldquoexternalrdquo) bull neutron doses bull tritium doses

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of photon neutron and tritium doses Intakes of other radionuclides (for example Iodine-131 or Carbon-14) occasionally occur but these radionuclides are not included here because the associated collective dose is very small For this reason certain collective dose values in this report may be slightly lower than the sum of their respective components as listed

12

1 2 3 4 5 6 70 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

211 Bruce Nuclear Generating Stations

Bruce Power owns and operates the Bruce Nuclear Generating Stations located near Kincardine Ontario on the shore of Lake Huron

bull Bruce A consists of four nuclear reactors (units 1ndash4) and began operating in 1976 bull Bruce B has four nuclear reactors (units 5ndash8) and started operating in 1984

As part of its extensive recovery program in 1997 the sitersquos previous operator Ontario Hydro (now Ontario Power Generation) temporarily shut down all Bruce A reactors and maintained them in a guaranteed shutdown state Units 3 and 4 were later returned to service (in October 2003 and January 2004) while Units 1 and 2 remained in a guaranteed shutdown state

Figures 21ndash24 present dose information for the Bruce Nuclear Generating Stations from 2001 to 2007 Graphs do not distinguish between doses received at Bruce A versus Bruce B

Fig 21 Average Dose Trends for Bruce Nuclear Generating Stati on (Based o n N on-Zero R esults)

Dos

e (m

Sv)

4

35

3

25

2

15

1

05

0

Tritium Neutron External Effective

Year

13

Neutrons External Tritium

0 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 21 2 3 4 5 6 7

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

0

2

4

6

8

1

2

4

0

0

0

0

1

1

Figure 22 Average Dose Trends for Bruce Nuclear Generating Stati on (Based o n A ll Monitoring R esults)

16

)S

v(m

e os

D

Tritium Neutrons External Effective

Year

Figure 23 Collective Dose Trends for Bruce Nuclear Generating Stati on

8000

7000

6000

5000

4000

3000

2000

1000

0

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Year

14

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 24 Distribution of Effective Doses Among All Workers at Bruce Nuclear Generating Station

6000

5000

4000

3000

2000

1000

0 9 0 0

1-50 0 0 1 0 0 0 0 00 5 0 0 0

0-000

000 1-1 1-1 1-20 1-3 3gt0 0 0 05 0 5 01 1 2

Num

ber o

f Wor

kers

Dose Range (mSv)

15

1 2 3 4 5 6 7 0 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

212 Pickering Nuclear Generating Stations

Located in Pickering Ontario the Pickering Nuclear Generating Stations are owned and operated by Ontario Power Generation Two generating stations are located within one enclosure

bull Pickering A consists of four nuclear reactors (units 1 to 4) that began operating in 1971 bull Pickering B consists of four nuclear reactors (units 5 to 8) that began operating in 1982

As part of its extensive recovery program Ontario Hydro (now Ontario Power Generation) temporarily shut down all Pickering A reactors in 1997 and maintained them in a guaranteed shutdown state Unit 4 was restarted in September 2003 and Unit 1 was restarted in March 2005 Units 2 and 3 remain in a guaranteed shutdown state

Figures 25ndash28 present dose information for the Pickering Nuclear Generating Stations from 2001 to 2007 Graphs do not distinguish between doses received at Pickering A versus those received at Pickering B

Figure 25 Average Dose Trends for Pickering N uclear Generating Stati on (Based o n N on-Zero R esults)

25

2

15

1

05

0

)S

v(m

e os

D

Tritium Neutrons External Effective

Year

16

Tritium Neutrons External Effective

Neutrons External Tritium

1 2 3 4 5 6 70 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

1 2 3 4 5 6 7 0 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 26 Average Dose Trends for Pickering N uclear Generating Stati on (Based o n A ll Monitoring R esults)

12

1

08

06

04

02

0

Year

Figure 27 Collective Dose Trends for Pickering N uclear Generating Stati on

12000

10000

8000

6000

4000

2000

0

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

)

Sv

(me

osD

Year

17

2001 2002 2003 2004 2005 2006 2007

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 28 Distribution o f Effective Doses Among A ll Workers at Pickering Nuclear Generating Stati on

6000

5000

4000

3000

2000

1000

0

Num

ber o

f Wor

kers

Dose Range (mSv)

18

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

213 Darlington Nuclear Generating Station

Owned and operated by Ontario Power Generation the Darlington Nuclear Generating Station has four nuclear reactors the first of which began operating in 1989 The facility is located near Bowmanville on the shore of Lake Ontario

Figures 29ndash212 present dose information for the Darlington Nuclear Generating Station from 2001 to 2007

Figure 29 Average Dose Trends for Darlington N uclear Generating Stati on (Non- Zero R esults Only)

)S

v(m

e os

D

250

200

150

100

050

000

Year

19

Tritium Neutrons External Effective

Neutrons External Tritium

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 210 Average Dose Trends for Darlington N uclear Generating Stati on (All Monitoring R esults)

090

080

070

060

050

040

030

020

010

000

)S

v(m

e os

D

Year

Figure 211 Collective Dose Trends for Darlington N uclear Generating Stati on

4500

4000

3500

3000

2500

2000

1500

1000

500

0

)vSm-nosrep (es

Do

eiv

llect

Co

Year

20

2001 2002 2003 2004 2005 2006 2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 212 Distribution o f Effective Doses Among A ll Workers at Darlington Nuclear Generating Stati on

0

500

1000

1500

2000

2500

3000

3500

ers

ork

W of

be

r um

N

Dose Range (mSv)

21

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

214 Gentilly-2 Nuclear Generating Station

The Gentilly-2 Nuclear Generating Station owned and operated by Hydro-Queacutebec has a single reactor that began operating in 1982 The facility is located on the south shore of the St Lawrence River near Trois-Riviegraveres Queacutebec

Figures 213ndash216 present dose information for the Gentilly-2 Nuclear Generating Station from 2001 to 2007

Figure 213 Average Dose Trends for Gentilly-2 Nuclear Generating Stati on (Based o n N on-Zero R esults)

0

05

1

15

2

25

3

35

4

45

)S

v(m

e os

D

Year

22

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 214 Average Dose Trends for Gentilly-2 Nuclear Generating Stati on (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

)S

v(m

e os

D

Year

Figure 215 Collective Dose Trends for Gentilly-2 Nuclear Generating Stati on

0

500

1000

1500

2000

2500

3000

3500

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Neutrons

External

Tritium

Year

23

000-0

009

001-5

00

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 216 Distribution of Effective Doses Among All Workers at Gentilly-2 Nuclear Generating Station

2500

2000

1500

1000

500

0

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

24

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

215 Point Lepreau Nuclear Generating Station

The Point Lepreau Nuclear Generating Station has one reactor that began operating in 1982 Owned and operated by New Brunswick Power Nuclear the station is located in Point Lepreau New Brunswick about 40 km west of Saint John on the shores of the Bay of Fundy

Figures 217ndash220 present dose information for the Point Lepreau Nuclear Generating Station from 2001 to 2007

Figure 217 Average Dose Trends for Point Lepreau N uclear Generating Stati on (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

)S

v(m

e os

D

Tritium Neutron External Effective

Year

25

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 218 Average Dose Trends for Point Lepreau N uclear Generating Stati on (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

)S

v(m

e os

D

Tritium Neutrons External Effective

Year

Figure 219 Collective Dose Trends for Point Lepreau N uclear Generating Station

0

200

400

600

800

1000

1200

1400

1600

1800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Neutrons

External

Tritium

Year

26

0

1400

1200

1000

800

600

400

200

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 220 Distribution of Effective Doses Among All Workers at Point Lepreau Nuclear Generating Station

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

27

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

22 Uranium Mines and Mills This section presents dose information for mine and mill sites in the following regions

bull Cluff Lake (Section 221) bull McClean Lake (Section 222) bull McArthur River (Section 223) bull Key Lake (Section 224) bull Cigar Lake (Section 225) bull Rabbit Lake (Section 226)

Graphs indicate the following data for each site from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for uranium mines and mills

1 Effective doses are composed of the following reported components bull doses from photons (labelled on the charts as ldquoexternalrdquo) bull doses from radon progeny bull doses from long-lived radioactive dust bull doses from radon gas (in some cases)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of photon radon progeny long-lived radioactive dust and radon gas doses

3 The NDR lists radon progeny in working level months (WLM) For this report radon progeny exposures were converted4 to doses expressed in mSv

221 Cluff Lake Operation

The Cluff Lake mining facilities operated by AREVA Resources Canada Inc are located in northwestern Saskatchewan Work began in 1980 and ended in 2002 with the site now being decommissioned The site consisted of three open-pit and two underground mines a mill and a tailings management facility During 2005 and 2006 most of the infrastructure was removed and the affected areas were remediated

Figures 221ndash224 present dose information for the Cluff Lake operation from 2001 to 2007

4 Doses were converted using the International Commission on Radiation Protection (ICRP)rsquos conversion convention of 1 WLM = 5 mSv This convention was established in the ICRP publication Protection against Radon at Home and at Work (ICRP 65)

28

Long-lived radioactive dust Radon progeny External Effective

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 221 Average Dose Trends for the Cluff Lake Operation (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

Year

Figure 222 Average Dose Trends for the Cluff Lake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

200

Long-lived radioactive dust Radon progeny External Effective

)S

v(m

e os

D)

Sv

(me

osD

Year

29

600

500

400

300

200

100

0

External Radon progeny Long-lived radioactive dust

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 223 Collective Dose Trends for the Cluff Lake Operation s

erkor

of W

ber

Num

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Year

Figure 224 Distribution o f Effective Doses Among A ll Workers at the Cluff Lake Operation

0

20

40

60

80

100

120

140

160

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

30

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

222 McClean Lake Operation

AREVA Resources Canada Inc runs the McClean Lake mining operation in northeastern Saskatchewan It comprises open pit mines a mill and a tailings management facility Mining began in 1995 while milling started in 1999

Figures 225ndash228 present dose information for the McClean Lake operation from 2001 to 2007

Figure 225 Average Dose Trends for the McClean L ake Operation (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

31

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 226 Average Dose Trends for the McClean L ake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 227 Collective Dose Trends for the McClean L ake Operation

0

100

200

300

400

500

600

700

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External

Radon progeny

Long-lived radioactive dust

Year

32

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 228 Distribution o f Effective Doses Among A ll Workers at the McClean Lake Operation

0

100

200

300

400

500

600

700

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

33

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

223 McArthur River Operation

Cameco Corporation operates the McArthur River underground mine in north-central Saskatchewan Ore from the mine which began production in 1999 is processed at the Key Lake Mill located 80 km south of McArthur River

Figures 229ndash232 present dose information for the McArthur River operation from 2001 to 2007

Figure 229 Average Dose Trends for the McArthur River Operation (Based o n N on-Zero R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

34

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 230 Average Dose Trends for the McArthur River Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

Figure 231 Collective Dose Trends for the McArthur River Operation

0

200

400

600

800

1000

1200

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Radon gas External Radon progeny Long-lived radioactive dust

Year

35

00

0-000

9

001-5

00

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 232 Distribution o f Effective Doses Among A ll Workers at the McArthur River Operation

0

100

200

300

400

500

600

700

800

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

36

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

224 Key Lake Operation

Cameco Corporation operates mining facilities in Key Lake located in north-central Saskatchewan The Key Lake operation includes two mined-out open pit mines (used for tailings management) a mill and two dry tailings management facilities Mining began in 1983 and ceased in 1997 the mill continued to process ore from the McArthur River mine during the reporting period

Figures 233ndash236 present dose information for the Key Lake operation from 2001 to 2007

Figure 233 Average Dose Trends for the Key Lake Operation (Based o n N on-Zero R esults)

00

20

40

60

80

00

20

40

60

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

37

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

00

20

40

60

80

00

20

40

60

Figure 234 Average Dose Trends for the Key Lake Operation (Based o n A ll Monitoring R esults)

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 235 Collective Dose Trends for the Key Lake Operation

0

100

200

300

400

500

600

700

800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External Radon progeny Long-lived radioactive dust

Year

38

00

0-000

9

001-5

0

501-1

000

gt 1001

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 236 Distribution o f Effective Doses Among A ll Workers at the Key Lake Operation

0

200

400

600

800

1000

1200

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose Range (mSv)

39

se

(mS

v)o

D

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

225 Cigar Lake Operation

Cameco Corporation manages the Cigar Lake underground mine located in northern Saskatchewan at the southern end of Waterbury Lake The mine was under construction at the time of this reportrsquos publication Test mining in ore was carried out in 1991 1992 and 2000

Figures 237ndash240 present dose information for the Cigar Lake operation from

Figure 2 37 Average D ose T rends fo r th e C igar L ake O peration (Based on Non-Zero Results)

2001 to 2007

Year

000

005

010

015

020

025

Long-lived radioactive dust Radon Progeny External Effective

40

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 238 Average Dose Trends for the Cigar Lake Operation (Based on All Monitoring Results)

000

005

010

015

020

025

030

035

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny

External

Effective

Year

Figure 239 Collective Dose Trends for the Cigar Lake Operation

0

50

100

150

200

250

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

External Radon progeny Long-lived radioactive dust

Year

41

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 240 Distribution of Effective Doses Among All Workers at the Cigar Lake Operation

0

200

400

600

800

1000

1200

1400

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

42

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

226 Rabbit Lake Operation

Cameco Corporation owns and operates mining facilities in Rabbit Lake located in north-eastern Saskatchewan Facilities include an underground mine four mined-out open-pit mines a mill and two tailings management facilities Mining and milling began in 1975

Figures 241ndash244 present dose information for the Rabbit Lake operation from 2001 to 2007

Figure 241 Average Dose Trends for the Rabbit Lake Operation (Based on Non-Zero Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

43

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 242 Average Dose Trends for the Rabbit Lake Operation (Based on All Monitoring Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

Figure 243 Collective Dose Trends for the Rabbit Lake Operation

0

200

400

600

800

1000

1200

1400

1600

1800

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Radon gas External Radon progeny Long-lived radioactive dust

Year

44

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

gt300

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 244 Distribution of Effective Doses Among All Workers at the Rabbit Lake Operation

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

900

800

700

600

500

400

300

200

100

0

Dose (mSv)

45

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

23 Uranium Refineries This section presents data for the following two facilities

bull a uranium refining facility in Blind River (Section 231) bull a uranium conversion facility in Port Hope (Section 232)

Graphs indicate the following average doses at each facility from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Note on data for uranium refineries

1 Doses from photons from external sources are measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay and lung counting Historically while these internal doses have been measured they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

231 Blind River Refinery

Cameco Corporation owns and is licensed to operate a uranium refinery in Blind River Ontario The facility which began operating in 1983 converts uranium ore concentrate to uranium trioxide The uranium trioxide is shipped to Camecorsquos uranium conversion facility in Port Hope Ontario where it is processed into uranium dioxide (for use in the fabrication of fuel for nuclear reactors in Canada) or uranium hexafluoride (exported for enrichment and fabrication into fuel for nuclear power reactors around the world)

Figures 245ndash248 present dose information for the Blind River refinery from 2001 to 2007

46

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 245 Average Dose Trends for the Blind River Refinery (Based on Non-Zero Results)

0

05

1

15

2

25

Year

Figure 246 Average Dose Trends for the Blind River Refinery (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

47

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 247 Collective Dose Trends for the Blind River Refinery

0

50

100

150

200

250

300 C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 248 Distribution of Effective Doses Among All Workers at the Blind River Refinery

0

20

40

60

80

100

120

140

160

180

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

48

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

232 Port Hope Conversion Facility

Cameco Corporation owns and is licensed to operate a uranium conversion facility in Port Hope Ontario The facility processes uranium trioxide received from the refinery in Blind River into uranium dioxide and uranium hexafluoride

Figures 249ndash252 present dose information for the Port Hope uranium conversion facility from 2001 to 2007

Figure 249 Average Dose Trends for the Port Hope Conversion Facility (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

49

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 250 Average Dose Trends for the Port Hope Conversion Facility (Based on All Monitoring Results)

0

01

02

03

04

05

06

07

08

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 251 Collective Dose Trends for the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

50

000-0

009

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 252 Distribution of Effective Doses Among All Workers at the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

400

450

500

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

51

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

24 Fuel Fabrication Facilities This section presents data for three nuclear fuel fabrication facilities

bull Two facilities owned and operated by General Electric Canada Inc (Section 241) bull One facility in Port Hope operated by Zircatec Precision Industries (Section 242)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average doses

Notes on data for fuel fabrication facilities

1 Effective doses for the three facilities are composed of the following reported components bull dose from photons (labelled on the charts as ldquoexternalrdquo) bull doses from internal intakes of uranium dust (long-lived radioactive dust) from

uranium in air concentrations (for General Electricrsquos Toronto facility only)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components photon doses and doses from long-lived radioactive dust

241 General Electric Nuclear Fuel Facilities

General Electric Canada Inc operates two nuclear fuel facilities in Ontario

bull At the Toronto facility uranium dioxide pellets are produced from natural or depleted uranium dioxide powder

bull At the Peterborough facility uranium dioxide fuel bundles are created from the pellets produced at the Toronto facility

Figures 253ndash256 present dose information for General Electric Canada Incrsquos fuel fabrication facilities from 2001 to 2007 Graphs do not distinguish between the doses received at the Peterborough facility versus those at the Toronto facility

52

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 253 Average Dose Trends for the General Electric Fuel Facility (Based on Non-Zero Results Only)

0

05

1

15

2

25

3

35

Long Lived Radioactive Dust External Effective

Year

Figure 254 Average Dose Trends for the General Electric Fuel Facility (Based on All Monitoring Results)

0

05

1

15

2

25

3

Long Lived Radioactive Dust External Effective

Year

Dos

e (m

Sv)

Dos

e (m

Sv)

53

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 255 Collective Dose Trends for the General Electric Fuel Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Long Lived Radioactive Dust External

Year

Figure 256 Distribution of Effective Doses among all Workers at the General Electric Fuel Facility

0

10

20

30

40

50

60

70

80

90

100

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

54

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

242 Zircatec Nuclear Fuel Facility

Zircatec Precision Industries Inc operates a nuclear fuel facility in Port Hope Ontario where it makes fuel pellets from uranium dioxide powder received from Port Hopersquos uranium conversion facility The nuclear fuel facility also manufactures fuel bundles for nuclear reactors in Canada

Notes on data for the Zircatec nuclear fuel facility

1 Graphs indicate the following data bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of average effective doses

2 Doses from photons from external sources were measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay Historically although these internal doses have been measured and submitted to the CNSC they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

Figures 257ndash260 present dose information for the Zircatec nuclear fuel facility from 2001 to 2007

Figure 257 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on Non-Zero Results)

0

05

1

15

2

25

3

35

Effe

ctiv

e D

ose

(mS

v)

Year

55

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 258 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

18

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 259 Collective Dose Trends for the Zircatec Nuclear Fuel Facility

0

50

100

150

200

250

300

350

400

450

500

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

56

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 260 Distribution of Effective Doses Among All Workers at the Zircatec Nuclear Fuel Facility

300

Num

ber o

f Wor

kers

250

200

150

100

50

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

57

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

25 Research and Radioisotope Production Facilities This section presents dose information for the following research and radioisotope production facilities from 2001 to 2007

bull Chalk River Laboratories and Whiteshell Laboratories (Section 251) bull A radioisotope production facility operated by MDS Nordion (Section 252) bull The Tri-University Meson Facility (TRIUMF) (Section 253)

Note on data for research and radioisotope production facilities

1 Graphs indicate the following data for each facility bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of effective doses

251 Chalk River Laboratories and Whiteshell Laboratories

Atomic Energy of Canada Limited (AECL) owns and is licensed to operate Chalk River Laboratories and Whiteshell Laboratories

Situated in Renfrew County on the south shore of the Ottawa River the Chalk River Laboratories site hosts the National Research Universal Reactor along with numerous other facilities occupying some 160 buildings in an area of approximately 40 km2 Activities consist of radioisotope production for nuclear medicine testing and development of structural materials in support of power reactor operations fuel fabrication research and radioactive waste management and storage

The Whiteshell Laboratories site is located approximately 10 km west of Pinawa Manitoba and 100 km northeast of Winnipeg on the east bank of the Winnipeg River AECL established the laboratories for nuclear research and testing during the early 1960s and has since discontinued operations which are being decommissioned under a licence from the CNSC

Figures 261ndash264 present dose information for Chalk River Laboratories and Whiteshell Laboratories from 2001 to 2007

Notes on data for Chalk River Laboratories and Whiteshell Laboratories

1 Effective doses are composed of the following reported components bull external doses5 (from both photon and neutron doses) bull tritium doses

Due to issues with AECLrsquos in-house dosimetry management system neutron doses were not reported separately to the NDR during the reporting period As a result external doses from photons and neutrons were totaled The reporting discrepancy has since been rectified

58

5

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of external (photon and neutron) and tritium doses Intakes of other radionuclides occasionally occur and these radionuclides are not included here because their associated doses are very small For this reason certain collective doses in this report may have values slightly lower than the sum of their respective components as listed

Figure 261 Average Dose Trends for Chalk River and Whiteshell Laboratories (Non-Zero Results Only)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Tritium External Effective

Year

59

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 262 Average Dose Trends for Chalk River and Whiteshell Laboratories (All Monitoring Results)

000

020

040

060

080

100

120

Dos

e (m

Sv)

Tritium External Effective

Year

Figure 263 Collective Dose Trends for Chalk River and Whiteshell Laboratories

0

500

1000

1500

2000

2500

3000

3500

Col

lect

ive

Dos

e (p

erso

n- m

Sv)

External Tritium

Year

60

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 264 Distribution of Effective Doses Among All Workers at Chalk River and Whiteshell Laboratories

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

3500

3000

2500

2000

1500

1000

500

Dose (mSv)

61

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

252 MDS Nordion (Nuclear Substance Processing Facility and Canadian Irradiation Centre)

MDS Nordion owns and operates a nuclear substance processing facility in Ottawa Ontario where it processes unsealed radioisotopes and manufactures sealed radiation sources In operation since the early 1970s the facility was purchased by Nordion International in 1991

In cooperation with the Universiteacute du Queacutebecrsquos Institut Armand-Frappier MDS Nordion also operates the Canadian Irradiation Centre which conducts various irradiation services which include training testing and development The centre is located in Laval Quebec on the Universiteacute du Queacutebec campus

Figures 265ndash268 present dose information for MDS Nordionrsquos Ottawa nuclear substance processing facility and for the Canadian Irradiation Centre from 2001 to 2007

Notes on data for MDS Nordionrsquos nuclear substance processing facility and the Canadian Irradiation Centre

1 Doses from photons from external sources were measured and reported to the NDR MDS Nordion also has a routine thyroid monitoring program very occasionally small recordable doses of radiation have occurred from thyroid uptake of iodine The resulting doses have not been historically submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided

Figure 265 Average Dose Trends for MDS Nordion (Based on Non-Zero Results)

0

05

1

15

2

25

Effe

ctiv

e D

ose

(mS

v)

Year

62

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 266 Average Dose Trends for MDS Nordion (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

Figure 267 Collective Dose Trends for MDS Nordion

0

100

200

300

400

500

600

700

800

Year

63

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 268 Distribution of Effective Doses Among All Workers at MDS Nordion

0

5 0

1 0 0

1 5 0

2 0 0

2 5 0

3 0 0

3 5 0

4 0 0

4 5 0

5 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

64

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

253 Tri-University Meson Facility

The Tri-University Meson facility (TRIUMF) is situated in Vancouver on the campus of the University of British Columbia TRIUMF which began operating in the early 1970s with one cyclotron now has two cyclotrons and associated laboratories for research and radioisotope production The laboratory provides research facilities for Canadian and international users and also produces radioisotopes which are used by medical facilities and by a commercial organization (MDS Nordion) MDS Nordion staff also work at the TRIUMF site however MDS Nordion oversees this work and has its own radiation protection program

Figures 269ndash272 present dose information for the TRIUMF facility from 2001 to 2007 Please note that data sets do not distinguish between doses received by TRIUMF staff and MDS Nordion staff who work on the site as the data for these two groups was submitted collectively to the NDR for the reporting period shown Future data for each group will be submitted separately to the NDR

Note on data for TRIUMF

1 Effective doses are composed of the following reported components bull doses from photons (labeled as ldquoexternalrdquo in the charts) bull neutron doses

Figure 269 Average Dose Trends for TRIUMF (Non-Zero Results Only)

000

020

040

060

080

100

120

140

160

Dos

e (m

Sv)

Neutrons External Effective

Year

65

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 2: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

Occupational Dose Data for Major Canadian Nuclear Facilities 2001ndash07

copy Minister of Public Works and Government Services Canada 2009 Catalogue number CC172-482009E-PDF ISBN 978-1-100-12843-6

Published by the Canadian Nuclear Safety Commission CNSC Catalogue number INFO-0775

Extracts from this document may be reproduced for individual use without permission provided the source is fully acknowledged However reproduction in whole or in part for purposes of resale or redistribution requires prior written permission from the Canadian Nuclear Safety Commission

Eacutegalement publieacute en franccedilais sous le titre de Donneacutees sur les doses reccedilues par les travailleurs dans les grandes installations nucleacuteaires canadiennes 2001-2007

Document availability This document can be viewed on the CNSC Web site at nuclearsafetygcca To order a printed copy of the document in English or French please contact

Canadian Nuclear Safety Commission 280 Slater Street PO Box 1046 Station B Ottawa Ontario K1P 5S9 CANADA

Tel (613) 995-5894 or 1-800-668-5284 (in Canada only) Facsimile (613) 995-5086 E-mail infocnsc-ccsngcca Web site nuclearsafetygcca

Occupational Dose Data for Major Canadian Nuclear Facilities 2001ndash07 INFO-0775

June 2009

Table of Contents List of Figures iv Introduction 1 10 Facility-Wide Comparisons of Average Effective Doses 4

11 Average Effective Doses Based on Non-Zero Results at All Selected Facilities 4 12 Average Effective Doses Based on All Monitoring Results at All Selected Facilities 8

20 Facility-Specific Overview of Occupational Doses 12 21 Nuclear Power Plants 12

211 Bruce Nuclear Generating Stations 13 212 Pickering Nuclear Generating Stations 16 213 Darlington Nuclear Generating Station 19 214 Gentilly-2 Nuclear Generating Station 22 215 Point Lepreau Nuclear Generating Station 25

22 Uranium Mines and Mills 28 221 Cluff Lake Operation 28 222 McClean Lake Operation 31 223 McArthur River Operation 34 224 Key Lake Operation 37 225 Cigar Lake Operation 40 226 Rabbit Lake Operation 43

23 Uranium Refineries 46 231 Blind River Refinery 46 232 Port Hope Conversion Facility 49

24 Fuel Fabrication Facilities 52 241 General Electric Nuclear Fuel Facilities 52 242 Zircatec Nuclear Fuel Facility 55

25 Research and Radioisotope Production Facilities 58 251 Chalk River Laboratories and Whiteshell Laboratories 58 252 MDS Nordion (Nuclear Substance Processing Facility and Canadian

Irradiation Centre) 62 253 Tri-University Meson Facility 65

26 Tritium Light Source Production Facilities68 261 Shield Source Incorporated 68 262 SRB Technologies (Canada) Inc 71

Glossary 74 Bibliography 76

List of Figures

Figures 11ndash114 Facility-wide Average Doses

Figures 21ndash24 Bruce Nuclear Generating Stations Figures 25ndash28 Pickering Nuclear Generating Stations Figures 29ndash212 Darlington Nuclear Generating Station Figures 213ndash216 Gentilly-2 Nuclear Generating Station Figures 217ndash220 Point Lepreau Nuclear Generating Station

Figures 221ndash224 Cluff Lake Operation Figures 225ndash228 McClean Lake Operation Figures 229ndash232 McArthur River Operation Figures 233ndash236 Key Lake Operation Figures 237ndash240 Cigar Lake Operation Figures 241ndash244 Rabbit Lake Operation

Figures 245ndash248 Blind River Refinery Figures 249ndash252 Port Hope Conversion Facility

Figures 253ndash256 General Electric Nuclear Fuel Facilities Figures 257ndash260 Zircatec Nuclear Fuel Facility

Figures 261ndash264 Chalk River Laboratories and Whiteshell Laboratories Figures 265ndash268 MDS Nordion Figures 269ndash272 Tri-University Meson Facility (TRIUMF)

Figures 273ndash276 Shield Source Incorporated Figures 277ndash280 SRB Technologies (Canada) Inc

Table 1 Effective Dose Limits in Canada as Specified by the Radiation Protection Regulations Person Period Effective Dose

(mSv) Nuclear energy workers including pregnant (a) One-year dosimetry period 50 nuclear energy workers

(b) Five-year dosimetry period 100 Pregnant nuclear energy worker Balance of the pregnancy 4

A person who is not a nuclear energy worker One calendar year 1

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Introduction Workers at nuclear facilities are exposed to radiation Their dose is monitored and subject to Canadian Nuclear Safety Commission (CNSC) regulatory requirements which aim to protect their health and safety The amount of radiation to which employees are exposed is referred to as ldquooccupational doserdquo This report provides an overview of occupational radiation doses from 2001 to 2007 at the major nuclear facilities licensed by the CNSC It presents an objective summary of occupational dose information and includes a glossary of terminology

The data collected shows that the average doses for all facilities are far below the individual annual effective dose limit of 50 milliSieverts (mSv) set out in the Radiation Protection Regulations

The report includes data for the following types of facilities

bull nuclear power plants bull uranium mines and mills bull uranium refineries bull fuel fabrication facilities bull research and radioisotope production facilities bull tritium light source production facilities

Each facility is unique in regards to the type of work performed as well its current lifecycle stage (ie operating at reduced or full capacity or in a phase of refurbishment for example) and each provides varying programs to mitigate radiation doses to workers The resulting collective and average doses are based on complex and differing work environments Therefore direct comparisons between facilities in terms of occupational dose are not possible

Regulatory Radiation Dose Limits The Radiation Protection Regulations limit the amount of radiation to which persons may be exposed Table 1 presents the effective dose limits as set out in paragraphs 13 and 14 of the regulations

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

The Radiation Protection Regulations also require CNSC licensees to implement radiation protection programs and to keep radiation doses as low as reasonably achievable (a concept referred to as the ALARA principle) The CNSC evaluates licensee radiation protection programs and these evaluations include reviews of the occupational dose data which is one among several indicators of a radiation protection programrsquos effectiveness

About the Data

Source Statistics in this document are gathered from the National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses1 Maintained by Health Canadarsquos Radiation Protection Bureau the NDR publishes annual reports on occupational dose information and trends according to job type

Due to the large number of CNSC-licensed facilities this report does not include occupational dose information for every CNSC licensees Please refer to the NDR Web site2 to review Health Canadarsquos reports

Analysis This report presents the following types of data

a average doses b collective doses c distribution of effective doses

a Average doses provide a common means of indicating central tendencies of dose distribution and show where doses lie on average with respect to annual dose limits

Notes on average effective doses

1 This report presents two types3 of arithmetic averages for individual effective doses bull averages that include only non-zero (positive) results bull averages that include all monitoring results (including zero-value doses)

2 When assessing regulatory compliance individual doses mdash not average doses mdash must be compared to individual dose limits in the Radiation Protection Regulations

1 In Canada the Radiation Protection Regulations require licensed dosimetry services to submit dose information for nuclear energy workers (NEWs) While not required by law dose information for non-NEWs is also typically submitted to the NDR The data in this report does not distinguish between personnel designated as NEWs versus those who are not 2 httpwwwhc-scgccaewh-semtoccup-travailradiationregistindex_ehtml 3 Some licensees monitor most or all workers (including those unlikely to be directly exposed to sources of occupational radiation) whereas other licensees monitor only employees likely to receive radiation doses Therefore two types of averages are presented averages that consider only non-zero results and averages that consider all results Both statistical approaches have merit and are included in this report (Note The exclusion of zero value doses in the averaging could unfairly bias findings against licensees with effective radiation protection programs)

2

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

b Collective doses indicate the sum of all the doses associated with a facilityrsquos operation and can be used to estimate a facilityrsquos control of occupational doses

Note on collective doses

1 The Radiation Protection Regulations do not set limits on collective doses however the CNSC recommends that licensee radiation protection programs should aim to reduce collective doses These values can indicate a facilityrsquos radiological detriment and help assess whether a facility is operating in accordance with the ALARA principle

c Distribution of effective doses shows the ranges in which effective doses are concentrated

Effective dose calculations By definition effective doses cannot be measured precisely but they can be approximated in order to determine radiation exposure and to assess the associated risks Section 13 of the Radiation Protection Regulations defines the dose calculation methods used to determine effective doses as expressed in millisieverts (mSv) which are based on measurable quantities in the operational environment

Effective radiation doses are made up of various components of which the most common (in Canada) are as follows

bull photons and neutrons from sources outside the body bull radon progeny radon gas long-lived radioactive dust (uranium dust) and tritium that are

taken into the body

The effective doses reported to the NDR represent the sum of their applicable components For example the effective dose to a worker who received radiation doses from both neutrons and tritium would be the sum of these two quantities

Note on average dose values

1 Average values for each dose type (for example tritium) are based on the total collective dose for that type divided by the number of all the workers monitored for any dose type

3

yrenfi R

erev

Ri

dnilB

noid N

orD

SM

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

10 Facility-Wide Comparisons of Average Effective Doses This section presents comparisons of average effective doses at all CNSC-licensed nuclear facilities included in this report for each year within the 2001ndash07 reporting period

bull Figures 11ndash17 present averages based on non-zero (positive) results (Section 11)bull Figures 18ndash114 present averages based on all monitoring results (Section 12)

Notes on facility-wide comparisons of average effective doses

1 Each facility type is represented by a different colour bull nuclear power plants ndash green bull uranium mines and mills ndash purple bull uranium refineries ndash yellow bull fuel fabrication facilities ndash orange bull research and radioisotope facilities ndash blue bull tritium light source production facilities ndash red

2 See Sections 21ndash26 for facility-specific data depicted in Figures 11ndash114

11 Average Effective Doses Based on Non-Zero Results at All Selected Facilities Figures 11ndash17 show average effective doses based on non-zero results for each year from 2001 to 2007 for all the facilities presented in this document

Figure 11 Average Effective Doses at All Selected F acilities for the Year 2001 (Based o n N on-Zero R esults)

4

35

3

25

2

15

1

05

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) Sv

(me

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e N

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ener

atin

g St

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ns snotita

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y

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Dos

e (m

Sv)

) Sv

(me

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4

35

3

25

2

15

1

05

0

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 12 Average Effective Doses at All Selected Facilities for the Year 2002 (Based on Non-Zero Results)

4

35

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25

2

15

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05

0

Bruc

e N

ucle

ar G

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on F

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Figure 13 Average Effective Doses at All Selected Facilities for the Year 2003 (Based on Non-Zero Results)

Pick

erin

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ar G

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Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 14 Average Effective Doses at All Selected Facilities for the Year 2004 (Based on Non-Zero Results)

4

05

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Figure 15 Average Effective Doses at All Selected Facilities for the Year 2005 (Based on Non-Zero Results)

4

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er

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nive

rsity

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on F

acilit

y

Figure 17 Average Effective Doses at All Selected Facilities for the Year 2007 (Based on Non-Zero Results)

4

35

3

25

2

15

1

05

0

Bru

ce N

ucle

ar G

ener

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tatio

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ty

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 16 Average Effective Doses at All Selected Facilities for the Year 2006 (Based on Non-Zero Results)

4

35

3

25

2

15

1

05

0

Shie

ld S

ourc

e In

corp

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a) In

c

7

yrenfi R

erev

Ri

dnilB

noid N

orD

SM

snotita

Sgntiarene Graelc

Nu

ecurB

snotita

Sgntiarene Graelc

Nu

gnirekciP

notita

Sgntiarene Graelc

Nu

ntognilr

Da

notita

Sgntiarene Graelc

Nu

2-ylltineG

notita

Sgntiarene Graelc

Nu

uaerpet LnioP

notiarep Oeka

ff L

uC

l

notiarep Oeka

LnaeC

lc

M

rev R

iru

thrAcM

notiarep Oeka

LyeK

noitarep Oeka

LragC

i

notiarep Oeka

it L

bbR

a

tyilica Fnoisrevn

Co

ept H

oroP

setiilica Fleu

Fraelc N

ucitrcel

ElareneG

tyilical Feu

Fraelc N

uc

teacriZ

llehsteih

Wdn a ses ie rir to

to ara or bo ab La Lrev

Ri

klaC

h

tyilica Fnose

Mtyisrev

Uni

-irT

dtearoproc

Inecruo SdleihS

c In)adan

Ca

(seigolonhce T

RB

S

4

35

3

25

2

15

1

05

0

Dos

e (m

Sv)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

12 Average Effective Doses Based on All Monitoring Results at All Selected Facilities Figures 18ndash114 show average effective doses based on all the monitoring results for each year from 2001 to 2007 for every facility listed in this document

Figure 18 Average Effective Doses at All Selected F acilities for the Year 2001 (Based o n A ll Monitoring R esults)

8

r

Dos

e (m

Sv)

)

Sv

(me

osD

Bruc

e N

ucle

ar G

ener

atin

g St

atio

ns

Pick

erin

g N

ucle

ar G

ener

atin

g St

atio

ns

Dar

lingt

on N

ucle

ar G

ener

atin

g St

atio

n

Gen

tilly

-2 N

ucle

ar G

ener

atin

g St

atio

n

Poin

t Lep

reau

Nuc

lear

Gen

erat

ing

Stat

ion

Clu

ff La

ke O

pera

tion

McC

lean

Lak

e O

pera

tion

McA

rthur

Riv

e

Key

Lake

Ope

ratio

n

Cig

ar L

ake

Ope

ratio

n

Rab

bit L

ake

Ope

ratio

n

Blin

d R

iver

Ref

iner

y

Port

Hop

e C

onve

rsio

n Fa

cilit

y

Gen

eral

Ele

ctric

Nuc

lear

Fue

l Fac

ilitie

s

Zirc

atec

Nuc

lear

Fue

l Fac

ility llehs

teih Wdn

a ses ie rir toto ara or bo ab La

Lrev R

ikl a

Ch

MD

S N

ordi

on

Tri-U

n ive

rsity

Mes

on F

acilit

y

Figure 110 Average Effective Doses at All Selected F acilities for the Year 2003 (Based o n A ll Monitoring R esults)

4

35

3

25

2

15

1

05

0

Bruc

e N

ucle

ar G

ener

atin

g St

atio

ns

Pick

erin

g N

ucle

ar G

ener

atin

g St

atio

ns

Dar

lingt

on N

ucle

ar G

ener

atin

g St

atio

n

Gen

tilly

-2 N

ucle

ar G

ener

atin

g St

atio

n

Poin

t Lep

reau

Nuc

lear

Gen

erat

ing

Stat

ion

Clu

ff La

ke O

pera

tion

McC

lean

Lak

e O

pera

tion

McA

rthur

Riv

er

Key

Lake

Ope

ratio

n

Cig

ar L

ake

Ope

ratio

n

Rab

bit L

ake

Ope

ratio

n

Blin

d R

iver

Ref

iner

y

Port

Hop

e C

onve

rsio

n Fa

cilit

y

Gen

eral

Ele

ctric

Nuc

lear

Fue

l Fac

ilitie

s

Zirc

atec

Nuc

lear

Fue

l Fac

ility llehs

teih Wdn

a ses ie rir toto ara or bo ab La

Lrev R

ikla

Ch

MD

S N

o rdi

on

Tri-U

nive

r sity

Mes

on F

acilit

y

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 19 Average Effective Doses at All Selected Facilities for the Year 2002 (Based on All Monitoring Results)

4

35

3

25

2

15

1

05

0

Shie

ld S

ourc

e In

corp

orat

edSh

ield

Sou

rce

Inco

rpor

ated

c In)adan

Ca

(seigolonhce T

RB

SSR

B Te

chno

logi

es (C

anad

a) In

c

9

Dos

e (m

Sv)

)

Sv

(me

osD

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 111 Average Effective Doses at All Selected F acilities for the Year 2004 (Based o n A ll Monitoring R esults)

4

35

3

25

2

15

1

05

0

Bruc

e N

ucle

ar G

ener

atin

g St

atio

ns

Pick

erin

g N

ucle

ar G

ener

atin

g St

atio

ns

Dar

lingt

on N

ucle

ar G

ener

atin

g St

atio

n

Gen

tilly

-2 N

ucle

ar G

ener

atin

g St

atio

n

Poin

t Lep

reau

Nuc

lear

Gen

erat

ing

Stat

ion

Clu

ff La

ke O

pera

tion

McC

lean

Lak

e O

pera

tion

McA

rthur

Riv

er

Key

Lake

Ope

ratio

n

Cig

ar L

ake

Ope

ratio

n

Rab

bit L

ake

Ope

ratio

n

Blin

d R

iver

Ref

iner

y

Port

Hop

e C

onve

rsio

n Fa

cilit

y

Gen

eral

Ele

ctric

Nuc

lear

Fue

l Fac

ilitie

s

Zirc

atec

Nuc

lear

Fue

l Fac

ility llehs

teih Wdn

a ses ie rir toto ara or bo ab La

Lre v R

ikla

Ch

MD

S N

ordi

on

T ri-U

nive

rsity

Mes

on F

acilit

y

Figure 112 Average Effective Doses at All Selected F acilities for the Year 2005 (Based o n A ll Monitoring R esults)

4

35

3

25

2

15

1

05

0

Bruc

e N

ucle

ar G

ener

atin

g St

atio

ns

Pick

erin

g N

ucle

ar G

ener

atin

g St

atio

ns

Dar

lingt

on N

ucle

ar G

ener

atin

g St

atio

n

Gen

tilly

-2 N

ucle

ar G

ener

atin

g St

atio

n

Poin

t Lep

reau

Nuc

lear

Gen

erat

ing

Stat

ion

Clu

ff La

ke O

pera

tion

McC

lean

Lak

e O

pera

tion

McA

rthur

Riv

er

Key

Lake

Ope

ratio

n

Cig

ar L

ake

Ope

ratio

n

Rab

bit L

ake

Ope

ratio

n

Blin

d R

iver

Ref

iner

y

Port

Hop

e C

onve

rsio

n Fa

cilit

y

Gen

eral

Ele

ctric

Nuc

lear

Fue

l Fac

ilitie

s

Zirc

atec

Nuc

lear

Fue

l Fac

ility llehs

teih Wdn

a ses ie rir toto ara or bo ab La

Lrev R

ikl a

Ch

MD

S N

ordi

on

Tri-U

n ive

rsity

Mes

on F

acilit

y

Shie

ld S

ourc

e In

corp

orat

edSh

ield

Sou

rce

Inco

rpor

ated

SRB

Tech

nolo

gies

(Can

ada)

Inc

SR

B Te

chno

logi

es (C

anad

a) In

c

10

r s s n n n n n n n n ty s ty l l ty de y n cn n o o o o o o o o r i il e e o ivo o ti l h lti ti ti ti ti ti ti ti i i

Ri i tee

ta c c iil c ati ti ta ta a a a a a n i s d Inr ata r )r r r r ata a

S

fi cr te S S F F

Nor F o ae e e e e

S S au p p p i p dp p hg g g n F l n r ae og g n n n Re

o nti O O th O l orti i e cn r O O un ti se e A e e e e s Wti ti a a a u d er k k kc k k v r F DS

a a r r e n In Ca

r r e a a M a re e a a Ri F M e (n L r s Me e n n L v a

L n e a c sa en n e e e ff L

y t L s r en lr d ty

G

i

Co e c ie G a il e r i ue G nu a e b

G G g i s

K b toCl c

Nu i ge l r r o or r r C

i B

Nu to e

Cl er a a Sa Ra a lr a vp r oa ce e ae i

t Ho doe l te ll c r bl c M cc Un ne lc o e hlc c

Nu

Nu

Nu i a ab i ctr

Nu

Nu - hc L i er c a rri So en 2 u l Z L T TPe gc to ayn g l E

r- el RB

u i l e vrr atir Sn pe r

B i nk l e er Ri

e

Da t L n kc li G e aP ni Go C

h

P

) S

v(m

e os

D

4

35

3

25

2

15

1

05

0

) vS

m( e soD

Figure 114 Average Effective Doses at All Selected F acilities for the Year 2007 (Based o n A ll Monitoring R esults)

Bru

ce N

ucle

ar G

ener

atin

g S

tatio

ns

Pic

kerin

g N

ucle

ar G

ener

atin

g S

tatio

ns

Dar

lingt

on N

ucle

ar G

ener

atin

g S

tatio

n

Gen

tilly

-2 N

ucle

ar G

ener

atin

g S

tatio

n

Poi

nt L

epre

au N

ucle

ar G

ener

atin

g S

tatio

n

Clu

ff La

ke O

pera

tion

McC

lean

Lak

e O

pera

tion

McA

rthur

Riv

er

Key

Lak

e O

pera

tion

Cig

ar L

ake

Ope

ratio

n

Rab

bit L

ake

Ope

ratio

n

Blin

d R

iver

Ref

iner

y

Por

t Hop

e C

onve

rsio

n Fa

cilit

y

Gen

eral

Ele

ctric

Nuc

lear

Fue

l Fac

ilitie

s

Zirc

atec

Nuc

lear

Fue

l Fac

ility llehsetih

W d na s s ee iri oro tat ra or bo ab La Lr evi

Rk lah

C

MD

S N

ordi

on

Tri-U

nive

rsity

Mes

on F

acili

ty

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 113 Average Effective Doses at All Selected Facilities for the Year 2006 (Based on All Monitoring Results)

4

35

3

25

2

15

1

05

0

Shi

eld

Sou

rce

Inco

rpor

ated

SR

B T

echn

olog

ies

(Can

ada)

Inc

11

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

20 Facility-Specific Overview of Occupational Doses This section presents data for the following types of facilities

bull nuclear power plants (Section 21) bull uranium mines and mills (Section 22) bull uranium refineries (Section 23) bull fuel fabrication facilities (Section 24) bull research and radioisotope production facilities (Section 25) bull tritium production facilities (Section 26)

21 Nuclear Power Plants This section presents dose information for the following nuclear power plants

bull Bruce A and Bruce B Nuclear Generating Stations (Section 211) bull Pickering Nuclear Generating Stations (Section 212) bull Darlington Nuclear Generating Station Section 213) bull Gentilly-2 Nuclear Generating Station (Section 214) bull Point Lepreau Generating Station (Section 215)

Graphs in this section indicate the following data for each nuclear power plant from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for nuclear power plants

1 Effective doses are composed of the following reported components bull doses from photons (labeled on the charts as ldquoexternalrdquo) bull neutron doses bull tritium doses

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of photon neutron and tritium doses Intakes of other radionuclides (for example Iodine-131 or Carbon-14) occasionally occur but these radionuclides are not included here because the associated collective dose is very small For this reason certain collective dose values in this report may be slightly lower than the sum of their respective components as listed

12

1 2 3 4 5 6 70 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

211 Bruce Nuclear Generating Stations

Bruce Power owns and operates the Bruce Nuclear Generating Stations located near Kincardine Ontario on the shore of Lake Huron

bull Bruce A consists of four nuclear reactors (units 1ndash4) and began operating in 1976 bull Bruce B has four nuclear reactors (units 5ndash8) and started operating in 1984

As part of its extensive recovery program in 1997 the sitersquos previous operator Ontario Hydro (now Ontario Power Generation) temporarily shut down all Bruce A reactors and maintained them in a guaranteed shutdown state Units 3 and 4 were later returned to service (in October 2003 and January 2004) while Units 1 and 2 remained in a guaranteed shutdown state

Figures 21ndash24 present dose information for the Bruce Nuclear Generating Stations from 2001 to 2007 Graphs do not distinguish between doses received at Bruce A versus Bruce B

Fig 21 Average Dose Trends for Bruce Nuclear Generating Stati on (Based o n N on-Zero R esults)

Dos

e (m

Sv)

4

35

3

25

2

15

1

05

0

Tritium Neutron External Effective

Year

13

Neutrons External Tritium

0 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 21 2 3 4 5 6 7

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

0

2

4

6

8

1

2

4

0

0

0

0

1

1

Figure 22 Average Dose Trends for Bruce Nuclear Generating Stati on (Based o n A ll Monitoring R esults)

16

)S

v(m

e os

D

Tritium Neutrons External Effective

Year

Figure 23 Collective Dose Trends for Bruce Nuclear Generating Stati on

8000

7000

6000

5000

4000

3000

2000

1000

0

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Year

14

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 24 Distribution of Effective Doses Among All Workers at Bruce Nuclear Generating Station

6000

5000

4000

3000

2000

1000

0 9 0 0

1-50 0 0 1 0 0 0 0 00 5 0 0 0

0-000

000 1-1 1-1 1-20 1-3 3gt0 0 0 05 0 5 01 1 2

Num

ber o

f Wor

kers

Dose Range (mSv)

15

1 2 3 4 5 6 7 0 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

212 Pickering Nuclear Generating Stations

Located in Pickering Ontario the Pickering Nuclear Generating Stations are owned and operated by Ontario Power Generation Two generating stations are located within one enclosure

bull Pickering A consists of four nuclear reactors (units 1 to 4) that began operating in 1971 bull Pickering B consists of four nuclear reactors (units 5 to 8) that began operating in 1982

As part of its extensive recovery program Ontario Hydro (now Ontario Power Generation) temporarily shut down all Pickering A reactors in 1997 and maintained them in a guaranteed shutdown state Unit 4 was restarted in September 2003 and Unit 1 was restarted in March 2005 Units 2 and 3 remain in a guaranteed shutdown state

Figures 25ndash28 present dose information for the Pickering Nuclear Generating Stations from 2001 to 2007 Graphs do not distinguish between doses received at Pickering A versus those received at Pickering B

Figure 25 Average Dose Trends for Pickering N uclear Generating Stati on (Based o n N on-Zero R esults)

25

2

15

1

05

0

)S

v(m

e os

D

Tritium Neutrons External Effective

Year

16

Tritium Neutrons External Effective

Neutrons External Tritium

1 2 3 4 5 6 70 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

1 2 3 4 5 6 7 0 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 26 Average Dose Trends for Pickering N uclear Generating Stati on (Based o n A ll Monitoring R esults)

12

1

08

06

04

02

0

Year

Figure 27 Collective Dose Trends for Pickering N uclear Generating Stati on

12000

10000

8000

6000

4000

2000

0

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

)

Sv

(me

osD

Year

17

2001 2002 2003 2004 2005 2006 2007

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 28 Distribution o f Effective Doses Among A ll Workers at Pickering Nuclear Generating Stati on

6000

5000

4000

3000

2000

1000

0

Num

ber o

f Wor

kers

Dose Range (mSv)

18

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

213 Darlington Nuclear Generating Station

Owned and operated by Ontario Power Generation the Darlington Nuclear Generating Station has four nuclear reactors the first of which began operating in 1989 The facility is located near Bowmanville on the shore of Lake Ontario

Figures 29ndash212 present dose information for the Darlington Nuclear Generating Station from 2001 to 2007

Figure 29 Average Dose Trends for Darlington N uclear Generating Stati on (Non- Zero R esults Only)

)S

v(m

e os

D

250

200

150

100

050

000

Year

19

Tritium Neutrons External Effective

Neutrons External Tritium

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 210 Average Dose Trends for Darlington N uclear Generating Stati on (All Monitoring R esults)

090

080

070

060

050

040

030

020

010

000

)S

v(m

e os

D

Year

Figure 211 Collective Dose Trends for Darlington N uclear Generating Stati on

4500

4000

3500

3000

2500

2000

1500

1000

500

0

)vSm-nosrep (es

Do

eiv

llect

Co

Year

20

2001 2002 2003 2004 2005 2006 2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 212 Distribution o f Effective Doses Among A ll Workers at Darlington Nuclear Generating Stati on

0

500

1000

1500

2000

2500

3000

3500

ers

ork

W of

be

r um

N

Dose Range (mSv)

21

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

214 Gentilly-2 Nuclear Generating Station

The Gentilly-2 Nuclear Generating Station owned and operated by Hydro-Queacutebec has a single reactor that began operating in 1982 The facility is located on the south shore of the St Lawrence River near Trois-Riviegraveres Queacutebec

Figures 213ndash216 present dose information for the Gentilly-2 Nuclear Generating Station from 2001 to 2007

Figure 213 Average Dose Trends for Gentilly-2 Nuclear Generating Stati on (Based o n N on-Zero R esults)

0

05

1

15

2

25

3

35

4

45

)S

v(m

e os

D

Year

22

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 214 Average Dose Trends for Gentilly-2 Nuclear Generating Stati on (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

)S

v(m

e os

D

Year

Figure 215 Collective Dose Trends for Gentilly-2 Nuclear Generating Stati on

0

500

1000

1500

2000

2500

3000

3500

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Neutrons

External

Tritium

Year

23

000-0

009

001-5

00

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 216 Distribution of Effective Doses Among All Workers at Gentilly-2 Nuclear Generating Station

2500

2000

1500

1000

500

0

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

24

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

215 Point Lepreau Nuclear Generating Station

The Point Lepreau Nuclear Generating Station has one reactor that began operating in 1982 Owned and operated by New Brunswick Power Nuclear the station is located in Point Lepreau New Brunswick about 40 km west of Saint John on the shores of the Bay of Fundy

Figures 217ndash220 present dose information for the Point Lepreau Nuclear Generating Station from 2001 to 2007

Figure 217 Average Dose Trends for Point Lepreau N uclear Generating Stati on (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

)S

v(m

e os

D

Tritium Neutron External Effective

Year

25

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 218 Average Dose Trends for Point Lepreau N uclear Generating Stati on (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

)S

v(m

e os

D

Tritium Neutrons External Effective

Year

Figure 219 Collective Dose Trends for Point Lepreau N uclear Generating Station

0

200

400

600

800

1000

1200

1400

1600

1800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Neutrons

External

Tritium

Year

26

0

1400

1200

1000

800

600

400

200

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 220 Distribution of Effective Doses Among All Workers at Point Lepreau Nuclear Generating Station

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

27

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

22 Uranium Mines and Mills This section presents dose information for mine and mill sites in the following regions

bull Cluff Lake (Section 221) bull McClean Lake (Section 222) bull McArthur River (Section 223) bull Key Lake (Section 224) bull Cigar Lake (Section 225) bull Rabbit Lake (Section 226)

Graphs indicate the following data for each site from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for uranium mines and mills

1 Effective doses are composed of the following reported components bull doses from photons (labelled on the charts as ldquoexternalrdquo) bull doses from radon progeny bull doses from long-lived radioactive dust bull doses from radon gas (in some cases)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of photon radon progeny long-lived radioactive dust and radon gas doses

3 The NDR lists radon progeny in working level months (WLM) For this report radon progeny exposures were converted4 to doses expressed in mSv

221 Cluff Lake Operation

The Cluff Lake mining facilities operated by AREVA Resources Canada Inc are located in northwestern Saskatchewan Work began in 1980 and ended in 2002 with the site now being decommissioned The site consisted of three open-pit and two underground mines a mill and a tailings management facility During 2005 and 2006 most of the infrastructure was removed and the affected areas were remediated

Figures 221ndash224 present dose information for the Cluff Lake operation from 2001 to 2007

4 Doses were converted using the International Commission on Radiation Protection (ICRP)rsquos conversion convention of 1 WLM = 5 mSv This convention was established in the ICRP publication Protection against Radon at Home and at Work (ICRP 65)

28

Long-lived radioactive dust Radon progeny External Effective

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 221 Average Dose Trends for the Cluff Lake Operation (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

Year

Figure 222 Average Dose Trends for the Cluff Lake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

200

Long-lived radioactive dust Radon progeny External Effective

)S

v(m

e os

D)

Sv

(me

osD

Year

29

600

500

400

300

200

100

0

External Radon progeny Long-lived radioactive dust

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 223 Collective Dose Trends for the Cluff Lake Operation s

erkor

of W

ber

Num

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Year

Figure 224 Distribution o f Effective Doses Among A ll Workers at the Cluff Lake Operation

0

20

40

60

80

100

120

140

160

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

30

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

222 McClean Lake Operation

AREVA Resources Canada Inc runs the McClean Lake mining operation in northeastern Saskatchewan It comprises open pit mines a mill and a tailings management facility Mining began in 1995 while milling started in 1999

Figures 225ndash228 present dose information for the McClean Lake operation from 2001 to 2007

Figure 225 Average Dose Trends for the McClean L ake Operation (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

31

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 226 Average Dose Trends for the McClean L ake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 227 Collective Dose Trends for the McClean L ake Operation

0

100

200

300

400

500

600

700

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External

Radon progeny

Long-lived radioactive dust

Year

32

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 228 Distribution o f Effective Doses Among A ll Workers at the McClean Lake Operation

0

100

200

300

400

500

600

700

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

33

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

223 McArthur River Operation

Cameco Corporation operates the McArthur River underground mine in north-central Saskatchewan Ore from the mine which began production in 1999 is processed at the Key Lake Mill located 80 km south of McArthur River

Figures 229ndash232 present dose information for the McArthur River operation from 2001 to 2007

Figure 229 Average Dose Trends for the McArthur River Operation (Based o n N on-Zero R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

34

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 230 Average Dose Trends for the McArthur River Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

Figure 231 Collective Dose Trends for the McArthur River Operation

0

200

400

600

800

1000

1200

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Radon gas External Radon progeny Long-lived radioactive dust

Year

35

00

0-000

9

001-5

00

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 232 Distribution o f Effective Doses Among A ll Workers at the McArthur River Operation

0

100

200

300

400

500

600

700

800

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

36

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

224 Key Lake Operation

Cameco Corporation operates mining facilities in Key Lake located in north-central Saskatchewan The Key Lake operation includes two mined-out open pit mines (used for tailings management) a mill and two dry tailings management facilities Mining began in 1983 and ceased in 1997 the mill continued to process ore from the McArthur River mine during the reporting period

Figures 233ndash236 present dose information for the Key Lake operation from 2001 to 2007

Figure 233 Average Dose Trends for the Key Lake Operation (Based o n N on-Zero R esults)

00

20

40

60

80

00

20

40

60

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

37

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

00

20

40

60

80

00

20

40

60

Figure 234 Average Dose Trends for the Key Lake Operation (Based o n A ll Monitoring R esults)

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 235 Collective Dose Trends for the Key Lake Operation

0

100

200

300

400

500

600

700

800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External Radon progeny Long-lived radioactive dust

Year

38

00

0-000

9

001-5

0

501-1

000

gt 1001

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 236 Distribution o f Effective Doses Among A ll Workers at the Key Lake Operation

0

200

400

600

800

1000

1200

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose Range (mSv)

39

se

(mS

v)o

D

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

225 Cigar Lake Operation

Cameco Corporation manages the Cigar Lake underground mine located in northern Saskatchewan at the southern end of Waterbury Lake The mine was under construction at the time of this reportrsquos publication Test mining in ore was carried out in 1991 1992 and 2000

Figures 237ndash240 present dose information for the Cigar Lake operation from

Figure 2 37 Average D ose T rends fo r th e C igar L ake O peration (Based on Non-Zero Results)

2001 to 2007

Year

000

005

010

015

020

025

Long-lived radioactive dust Radon Progeny External Effective

40

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 238 Average Dose Trends for the Cigar Lake Operation (Based on All Monitoring Results)

000

005

010

015

020

025

030

035

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny

External

Effective

Year

Figure 239 Collective Dose Trends for the Cigar Lake Operation

0

50

100

150

200

250

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

External Radon progeny Long-lived radioactive dust

Year

41

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 240 Distribution of Effective Doses Among All Workers at the Cigar Lake Operation

0

200

400

600

800

1000

1200

1400

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

42

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

226 Rabbit Lake Operation

Cameco Corporation owns and operates mining facilities in Rabbit Lake located in north-eastern Saskatchewan Facilities include an underground mine four mined-out open-pit mines a mill and two tailings management facilities Mining and milling began in 1975

Figures 241ndash244 present dose information for the Rabbit Lake operation from 2001 to 2007

Figure 241 Average Dose Trends for the Rabbit Lake Operation (Based on Non-Zero Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

43

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 242 Average Dose Trends for the Rabbit Lake Operation (Based on All Monitoring Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

Figure 243 Collective Dose Trends for the Rabbit Lake Operation

0

200

400

600

800

1000

1200

1400

1600

1800

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Radon gas External Radon progeny Long-lived radioactive dust

Year

44

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

gt300

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 244 Distribution of Effective Doses Among All Workers at the Rabbit Lake Operation

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

900

800

700

600

500

400

300

200

100

0

Dose (mSv)

45

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

23 Uranium Refineries This section presents data for the following two facilities

bull a uranium refining facility in Blind River (Section 231) bull a uranium conversion facility in Port Hope (Section 232)

Graphs indicate the following average doses at each facility from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Note on data for uranium refineries

1 Doses from photons from external sources are measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay and lung counting Historically while these internal doses have been measured they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

231 Blind River Refinery

Cameco Corporation owns and is licensed to operate a uranium refinery in Blind River Ontario The facility which began operating in 1983 converts uranium ore concentrate to uranium trioxide The uranium trioxide is shipped to Camecorsquos uranium conversion facility in Port Hope Ontario where it is processed into uranium dioxide (for use in the fabrication of fuel for nuclear reactors in Canada) or uranium hexafluoride (exported for enrichment and fabrication into fuel for nuclear power reactors around the world)

Figures 245ndash248 present dose information for the Blind River refinery from 2001 to 2007

46

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 245 Average Dose Trends for the Blind River Refinery (Based on Non-Zero Results)

0

05

1

15

2

25

Year

Figure 246 Average Dose Trends for the Blind River Refinery (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

47

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 247 Collective Dose Trends for the Blind River Refinery

0

50

100

150

200

250

300 C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 248 Distribution of Effective Doses Among All Workers at the Blind River Refinery

0

20

40

60

80

100

120

140

160

180

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

48

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

232 Port Hope Conversion Facility

Cameco Corporation owns and is licensed to operate a uranium conversion facility in Port Hope Ontario The facility processes uranium trioxide received from the refinery in Blind River into uranium dioxide and uranium hexafluoride

Figures 249ndash252 present dose information for the Port Hope uranium conversion facility from 2001 to 2007

Figure 249 Average Dose Trends for the Port Hope Conversion Facility (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

49

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 250 Average Dose Trends for the Port Hope Conversion Facility (Based on All Monitoring Results)

0

01

02

03

04

05

06

07

08

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 251 Collective Dose Trends for the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

50

000-0

009

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 252 Distribution of Effective Doses Among All Workers at the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

400

450

500

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

51

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

24 Fuel Fabrication Facilities This section presents data for three nuclear fuel fabrication facilities

bull Two facilities owned and operated by General Electric Canada Inc (Section 241) bull One facility in Port Hope operated by Zircatec Precision Industries (Section 242)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average doses

Notes on data for fuel fabrication facilities

1 Effective doses for the three facilities are composed of the following reported components bull dose from photons (labelled on the charts as ldquoexternalrdquo) bull doses from internal intakes of uranium dust (long-lived radioactive dust) from

uranium in air concentrations (for General Electricrsquos Toronto facility only)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components photon doses and doses from long-lived radioactive dust

241 General Electric Nuclear Fuel Facilities

General Electric Canada Inc operates two nuclear fuel facilities in Ontario

bull At the Toronto facility uranium dioxide pellets are produced from natural or depleted uranium dioxide powder

bull At the Peterborough facility uranium dioxide fuel bundles are created from the pellets produced at the Toronto facility

Figures 253ndash256 present dose information for General Electric Canada Incrsquos fuel fabrication facilities from 2001 to 2007 Graphs do not distinguish between the doses received at the Peterborough facility versus those at the Toronto facility

52

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 253 Average Dose Trends for the General Electric Fuel Facility (Based on Non-Zero Results Only)

0

05

1

15

2

25

3

35

Long Lived Radioactive Dust External Effective

Year

Figure 254 Average Dose Trends for the General Electric Fuel Facility (Based on All Monitoring Results)

0

05

1

15

2

25

3

Long Lived Radioactive Dust External Effective

Year

Dos

e (m

Sv)

Dos

e (m

Sv)

53

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 255 Collective Dose Trends for the General Electric Fuel Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Long Lived Radioactive Dust External

Year

Figure 256 Distribution of Effective Doses among all Workers at the General Electric Fuel Facility

0

10

20

30

40

50

60

70

80

90

100

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

54

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

242 Zircatec Nuclear Fuel Facility

Zircatec Precision Industries Inc operates a nuclear fuel facility in Port Hope Ontario where it makes fuel pellets from uranium dioxide powder received from Port Hopersquos uranium conversion facility The nuclear fuel facility also manufactures fuel bundles for nuclear reactors in Canada

Notes on data for the Zircatec nuclear fuel facility

1 Graphs indicate the following data bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of average effective doses

2 Doses from photons from external sources were measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay Historically although these internal doses have been measured and submitted to the CNSC they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

Figures 257ndash260 present dose information for the Zircatec nuclear fuel facility from 2001 to 2007

Figure 257 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on Non-Zero Results)

0

05

1

15

2

25

3

35

Effe

ctiv

e D

ose

(mS

v)

Year

55

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 258 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

18

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 259 Collective Dose Trends for the Zircatec Nuclear Fuel Facility

0

50

100

150

200

250

300

350

400

450

500

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

56

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 260 Distribution of Effective Doses Among All Workers at the Zircatec Nuclear Fuel Facility

300

Num

ber o

f Wor

kers

250

200

150

100

50

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

57

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

25 Research and Radioisotope Production Facilities This section presents dose information for the following research and radioisotope production facilities from 2001 to 2007

bull Chalk River Laboratories and Whiteshell Laboratories (Section 251) bull A radioisotope production facility operated by MDS Nordion (Section 252) bull The Tri-University Meson Facility (TRIUMF) (Section 253)

Note on data for research and radioisotope production facilities

1 Graphs indicate the following data for each facility bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of effective doses

251 Chalk River Laboratories and Whiteshell Laboratories

Atomic Energy of Canada Limited (AECL) owns and is licensed to operate Chalk River Laboratories and Whiteshell Laboratories

Situated in Renfrew County on the south shore of the Ottawa River the Chalk River Laboratories site hosts the National Research Universal Reactor along with numerous other facilities occupying some 160 buildings in an area of approximately 40 km2 Activities consist of radioisotope production for nuclear medicine testing and development of structural materials in support of power reactor operations fuel fabrication research and radioactive waste management and storage

The Whiteshell Laboratories site is located approximately 10 km west of Pinawa Manitoba and 100 km northeast of Winnipeg on the east bank of the Winnipeg River AECL established the laboratories for nuclear research and testing during the early 1960s and has since discontinued operations which are being decommissioned under a licence from the CNSC

Figures 261ndash264 present dose information for Chalk River Laboratories and Whiteshell Laboratories from 2001 to 2007

Notes on data for Chalk River Laboratories and Whiteshell Laboratories

1 Effective doses are composed of the following reported components bull external doses5 (from both photon and neutron doses) bull tritium doses

Due to issues with AECLrsquos in-house dosimetry management system neutron doses were not reported separately to the NDR during the reporting period As a result external doses from photons and neutrons were totaled The reporting discrepancy has since been rectified

58

5

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of external (photon and neutron) and tritium doses Intakes of other radionuclides occasionally occur and these radionuclides are not included here because their associated doses are very small For this reason certain collective doses in this report may have values slightly lower than the sum of their respective components as listed

Figure 261 Average Dose Trends for Chalk River and Whiteshell Laboratories (Non-Zero Results Only)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Tritium External Effective

Year

59

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 262 Average Dose Trends for Chalk River and Whiteshell Laboratories (All Monitoring Results)

000

020

040

060

080

100

120

Dos

e (m

Sv)

Tritium External Effective

Year

Figure 263 Collective Dose Trends for Chalk River and Whiteshell Laboratories

0

500

1000

1500

2000

2500

3000

3500

Col

lect

ive

Dos

e (p

erso

n- m

Sv)

External Tritium

Year

60

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 264 Distribution of Effective Doses Among All Workers at Chalk River and Whiteshell Laboratories

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

3500

3000

2500

2000

1500

1000

500

Dose (mSv)

61

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

252 MDS Nordion (Nuclear Substance Processing Facility and Canadian Irradiation Centre)

MDS Nordion owns and operates a nuclear substance processing facility in Ottawa Ontario where it processes unsealed radioisotopes and manufactures sealed radiation sources In operation since the early 1970s the facility was purchased by Nordion International in 1991

In cooperation with the Universiteacute du Queacutebecrsquos Institut Armand-Frappier MDS Nordion also operates the Canadian Irradiation Centre which conducts various irradiation services which include training testing and development The centre is located in Laval Quebec on the Universiteacute du Queacutebec campus

Figures 265ndash268 present dose information for MDS Nordionrsquos Ottawa nuclear substance processing facility and for the Canadian Irradiation Centre from 2001 to 2007

Notes on data for MDS Nordionrsquos nuclear substance processing facility and the Canadian Irradiation Centre

1 Doses from photons from external sources were measured and reported to the NDR MDS Nordion also has a routine thyroid monitoring program very occasionally small recordable doses of radiation have occurred from thyroid uptake of iodine The resulting doses have not been historically submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided

Figure 265 Average Dose Trends for MDS Nordion (Based on Non-Zero Results)

0

05

1

15

2

25

Effe

ctiv

e D

ose

(mS

v)

Year

62

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 266 Average Dose Trends for MDS Nordion (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

Figure 267 Collective Dose Trends for MDS Nordion

0

100

200

300

400

500

600

700

800

Year

63

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 268 Distribution of Effective Doses Among All Workers at MDS Nordion

0

5 0

1 0 0

1 5 0

2 0 0

2 5 0

3 0 0

3 5 0

4 0 0

4 5 0

5 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

64

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

253 Tri-University Meson Facility

The Tri-University Meson facility (TRIUMF) is situated in Vancouver on the campus of the University of British Columbia TRIUMF which began operating in the early 1970s with one cyclotron now has two cyclotrons and associated laboratories for research and radioisotope production The laboratory provides research facilities for Canadian and international users and also produces radioisotopes which are used by medical facilities and by a commercial organization (MDS Nordion) MDS Nordion staff also work at the TRIUMF site however MDS Nordion oversees this work and has its own radiation protection program

Figures 269ndash272 present dose information for the TRIUMF facility from 2001 to 2007 Please note that data sets do not distinguish between doses received by TRIUMF staff and MDS Nordion staff who work on the site as the data for these two groups was submitted collectively to the NDR for the reporting period shown Future data for each group will be submitted separately to the NDR

Note on data for TRIUMF

1 Effective doses are composed of the following reported components bull doses from photons (labeled as ldquoexternalrdquo in the charts) bull neutron doses

Figure 269 Average Dose Trends for TRIUMF (Non-Zero Results Only)

000

020

040

060

080

100

120

140

160

Dos

e (m

Sv)

Neutrons External Effective

Year

65

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 3: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

Occupational Dose Data for Major Canadian Nuclear Facilities 2001ndash07 INFO-0775

June 2009

Table of Contents List of Figures iv Introduction 1 10 Facility-Wide Comparisons of Average Effective Doses 4

11 Average Effective Doses Based on Non-Zero Results at All Selected Facilities 4 12 Average Effective Doses Based on All Monitoring Results at All Selected Facilities 8

20 Facility-Specific Overview of Occupational Doses 12 21 Nuclear Power Plants 12

211 Bruce Nuclear Generating Stations 13 212 Pickering Nuclear Generating Stations 16 213 Darlington Nuclear Generating Station 19 214 Gentilly-2 Nuclear Generating Station 22 215 Point Lepreau Nuclear Generating Station 25

22 Uranium Mines and Mills 28 221 Cluff Lake Operation 28 222 McClean Lake Operation 31 223 McArthur River Operation 34 224 Key Lake Operation 37 225 Cigar Lake Operation 40 226 Rabbit Lake Operation 43

23 Uranium Refineries 46 231 Blind River Refinery 46 232 Port Hope Conversion Facility 49

24 Fuel Fabrication Facilities 52 241 General Electric Nuclear Fuel Facilities 52 242 Zircatec Nuclear Fuel Facility 55

25 Research and Radioisotope Production Facilities 58 251 Chalk River Laboratories and Whiteshell Laboratories 58 252 MDS Nordion (Nuclear Substance Processing Facility and Canadian

Irradiation Centre) 62 253 Tri-University Meson Facility 65

26 Tritium Light Source Production Facilities68 261 Shield Source Incorporated 68 262 SRB Technologies (Canada) Inc 71

Glossary 74 Bibliography 76

List of Figures

Figures 11ndash114 Facility-wide Average Doses

Figures 21ndash24 Bruce Nuclear Generating Stations Figures 25ndash28 Pickering Nuclear Generating Stations Figures 29ndash212 Darlington Nuclear Generating Station Figures 213ndash216 Gentilly-2 Nuclear Generating Station Figures 217ndash220 Point Lepreau Nuclear Generating Station

Figures 221ndash224 Cluff Lake Operation Figures 225ndash228 McClean Lake Operation Figures 229ndash232 McArthur River Operation Figures 233ndash236 Key Lake Operation Figures 237ndash240 Cigar Lake Operation Figures 241ndash244 Rabbit Lake Operation

Figures 245ndash248 Blind River Refinery Figures 249ndash252 Port Hope Conversion Facility

Figures 253ndash256 General Electric Nuclear Fuel Facilities Figures 257ndash260 Zircatec Nuclear Fuel Facility

Figures 261ndash264 Chalk River Laboratories and Whiteshell Laboratories Figures 265ndash268 MDS Nordion Figures 269ndash272 Tri-University Meson Facility (TRIUMF)

Figures 273ndash276 Shield Source Incorporated Figures 277ndash280 SRB Technologies (Canada) Inc

Table 1 Effective Dose Limits in Canada as Specified by the Radiation Protection Regulations Person Period Effective Dose

(mSv) Nuclear energy workers including pregnant (a) One-year dosimetry period 50 nuclear energy workers

(b) Five-year dosimetry period 100 Pregnant nuclear energy worker Balance of the pregnancy 4

A person who is not a nuclear energy worker One calendar year 1

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Introduction Workers at nuclear facilities are exposed to radiation Their dose is monitored and subject to Canadian Nuclear Safety Commission (CNSC) regulatory requirements which aim to protect their health and safety The amount of radiation to which employees are exposed is referred to as ldquooccupational doserdquo This report provides an overview of occupational radiation doses from 2001 to 2007 at the major nuclear facilities licensed by the CNSC It presents an objective summary of occupational dose information and includes a glossary of terminology

The data collected shows that the average doses for all facilities are far below the individual annual effective dose limit of 50 milliSieverts (mSv) set out in the Radiation Protection Regulations

The report includes data for the following types of facilities

bull nuclear power plants bull uranium mines and mills bull uranium refineries bull fuel fabrication facilities bull research and radioisotope production facilities bull tritium light source production facilities

Each facility is unique in regards to the type of work performed as well its current lifecycle stage (ie operating at reduced or full capacity or in a phase of refurbishment for example) and each provides varying programs to mitigate radiation doses to workers The resulting collective and average doses are based on complex and differing work environments Therefore direct comparisons between facilities in terms of occupational dose are not possible

Regulatory Radiation Dose Limits The Radiation Protection Regulations limit the amount of radiation to which persons may be exposed Table 1 presents the effective dose limits as set out in paragraphs 13 and 14 of the regulations

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

The Radiation Protection Regulations also require CNSC licensees to implement radiation protection programs and to keep radiation doses as low as reasonably achievable (a concept referred to as the ALARA principle) The CNSC evaluates licensee radiation protection programs and these evaluations include reviews of the occupational dose data which is one among several indicators of a radiation protection programrsquos effectiveness

About the Data

Source Statistics in this document are gathered from the National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses1 Maintained by Health Canadarsquos Radiation Protection Bureau the NDR publishes annual reports on occupational dose information and trends according to job type

Due to the large number of CNSC-licensed facilities this report does not include occupational dose information for every CNSC licensees Please refer to the NDR Web site2 to review Health Canadarsquos reports

Analysis This report presents the following types of data

a average doses b collective doses c distribution of effective doses

a Average doses provide a common means of indicating central tendencies of dose distribution and show where doses lie on average with respect to annual dose limits

Notes on average effective doses

1 This report presents two types3 of arithmetic averages for individual effective doses bull averages that include only non-zero (positive) results bull averages that include all monitoring results (including zero-value doses)

2 When assessing regulatory compliance individual doses mdash not average doses mdash must be compared to individual dose limits in the Radiation Protection Regulations

1 In Canada the Radiation Protection Regulations require licensed dosimetry services to submit dose information for nuclear energy workers (NEWs) While not required by law dose information for non-NEWs is also typically submitted to the NDR The data in this report does not distinguish between personnel designated as NEWs versus those who are not 2 httpwwwhc-scgccaewh-semtoccup-travailradiationregistindex_ehtml 3 Some licensees monitor most or all workers (including those unlikely to be directly exposed to sources of occupational radiation) whereas other licensees monitor only employees likely to receive radiation doses Therefore two types of averages are presented averages that consider only non-zero results and averages that consider all results Both statistical approaches have merit and are included in this report (Note The exclusion of zero value doses in the averaging could unfairly bias findings against licensees with effective radiation protection programs)

2

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

b Collective doses indicate the sum of all the doses associated with a facilityrsquos operation and can be used to estimate a facilityrsquos control of occupational doses

Note on collective doses

1 The Radiation Protection Regulations do not set limits on collective doses however the CNSC recommends that licensee radiation protection programs should aim to reduce collective doses These values can indicate a facilityrsquos radiological detriment and help assess whether a facility is operating in accordance with the ALARA principle

c Distribution of effective doses shows the ranges in which effective doses are concentrated

Effective dose calculations By definition effective doses cannot be measured precisely but they can be approximated in order to determine radiation exposure and to assess the associated risks Section 13 of the Radiation Protection Regulations defines the dose calculation methods used to determine effective doses as expressed in millisieverts (mSv) which are based on measurable quantities in the operational environment

Effective radiation doses are made up of various components of which the most common (in Canada) are as follows

bull photons and neutrons from sources outside the body bull radon progeny radon gas long-lived radioactive dust (uranium dust) and tritium that are

taken into the body

The effective doses reported to the NDR represent the sum of their applicable components For example the effective dose to a worker who received radiation doses from both neutrons and tritium would be the sum of these two quantities

Note on average dose values

1 Average values for each dose type (for example tritium) are based on the total collective dose for that type divided by the number of all the workers monitored for any dose type

3

yrenfi R

erev

Ri

dnilB

noid N

orD

SM

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

10 Facility-Wide Comparisons of Average Effective Doses This section presents comparisons of average effective doses at all CNSC-licensed nuclear facilities included in this report for each year within the 2001ndash07 reporting period

bull Figures 11ndash17 present averages based on non-zero (positive) results (Section 11)bull Figures 18ndash114 present averages based on all monitoring results (Section 12)

Notes on facility-wide comparisons of average effective doses

1 Each facility type is represented by a different colour bull nuclear power plants ndash green bull uranium mines and mills ndash purple bull uranium refineries ndash yellow bull fuel fabrication facilities ndash orange bull research and radioisotope facilities ndash blue bull tritium light source production facilities ndash red

2 See Sections 21ndash26 for facility-specific data depicted in Figures 11ndash114

11 Average Effective Doses Based on Non-Zero Results at All Selected Facilities Figures 11ndash17 show average effective doses based on non-zero results for each year from 2001 to 2007 for all the facilities presented in this document

Figure 11 Average Effective Doses at All Selected F acilities for the Year 2001 (Based o n N on-Zero R esults)

4

35

3

25

2

15

1

05

0

) Sv

(me

osD

Bruc

e N

ucle

ar G

ener

atin

g St

atio

ns snotita

Sgntiarene Graelc

Nu

gnirekciP

notita

Sgntiarene Graelc

Nu

ntognilr

Da

notita

Sgntiarene Graelc

Nu

2-ylltineG

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Sgntiarene Graelc

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uaerpet LnioP

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ff L

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l

notiarep Oeka

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lc

M

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LyeK

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LragC

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it L

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a

tyilica Fnoisrevn

Co

ept H

oroP

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Fraelc N

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Fraelc N

uc

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Cha

lk R

iver

Lab

orat

orie

s an

d W

hite

shel

lLa

bora

torie

s

tyilica Fnose

Mtyisrev

Uni

-irT

dtearoproc

Inecruo SdleihS

c In)adan

Ca

(seigolonhce T

RB

S

4

y

s n

Dos

e (m

Sv)

) Sv

(me

osD

4

35

3

25

2

15

1

05

0

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 12 Average Effective Doses at All Selected Facilities for the Year 2002 (Based on Non-Zero Results)

4

35

3

25

2

15

1

05

0

Bruc

e N

ucle

ar G

ener

atin

g St

atio

nsBr

uce

Nuc

lear

Gen

erat

ing

Stat

ions

Pick

erin

g N

ucle

ar G

ener

atin

g St

atio

n

Dar

lingt

on N

ucle

ar G

ener

atin

g St

atio

n

Gen

tilly

-2 N

ucle

ar G

ener

atin

g St

atio

n

Poin

t Lep

reau

Nuc

lear

Gen

erat

ing

Stat

ion

Clu

ff La

ke O

pera

tion

McC

lean

Lak

e O

pera

tio

McA

rthur

Riv

er

Key

Lake

Ope

ratio

n

Cig

ar L

ake

Ope

ratio

n

Rab

bit L

ake

Ope

ratio

n

Blin

d R

iver

Ref

iner

y

Port

Hop

e C

onve

rsio

n Fa

cilit

y

Gen

eral

Ele

ctric

Nuc

lear

Fue

l Fac

ilitie

s

Zirc

atec

Nuc

lear

Fue

l Fac

ility llehs

teih Wdn

a ses ie rir toto ara or bo ab La

Lrev R

ikla

Ch

MD

S N

ordi

on

Tri- U

nive

rsity

Mes

on F

acilit

y

Figure 13 Average Effective Doses at All Selected Facilities for the Year 2003 (Based on Non-Zero Results)

Pick

erin

g N

ucle

ar G

ener

atin

g St

atio

ns

Dar

lingt

on N

ucle

ar G

ener

atin

g St

atio

n

Gen

tilly

-2 N

ucle

ar G

ener

atin

g St

atio

n

Poin

t Lep

reau

Nuc

lear

Gen

erat

ing

Stat

ion

Clu

ff La

ke O

pera

tion

McC

lean

Lak

e O

pera

tion

McA

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er

Key

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Ope

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Cig

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ake

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n

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Ope

ratio

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iver

Ref

iner

y

Port

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onve

rsio

n Fa

cilit

y

Gen

eral

Ele

ctric

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Fue

l Fac

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atec

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lear

Fue

l Fac

ilit

llehsteih

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to ara or bo ab La Lrev

Ri

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h

MD

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ord i

on

Tri-U

nive

rsity

Mes

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acilit

y

Shie

ld S

ourc

e In

corp

orat

edSh

ield

Sou

rce

Inco

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ated

SRB

Tech

nolo

gies

(Can

ada)

Inc

SR

B Te

chno

logi

es (C

anad

a) In

c

5

n

2

1

35

3

5

2

5

1

Dos

e (m

Sv)

) Sv

(me

osD

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 14 Average Effective Doses at All Selected Facilities for the Year 2004 (Based on Non-Zero Results)

4

05

0

Figure 15 Average Effective Doses at All Selected Facilities for the Year 2005 (Based on Non-Zero Results)

4

35

3

25

2

15

1

05

0

Bruc

e N

ucle

ar G

ener

atin

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Nuc

lear

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Stat

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erin

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ucle

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Nuc

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Stat

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Ope

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Cig

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ratio

n

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bit L

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ratio

n

Blin

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iver

Ref

iner

y

Port

Hop

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onve

rsio

n Fa

cilit

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Gen

eral

Ele

ctric

Nuc

lear

Fue

l Fac

ilitie

s

Zirc

atec

Nuc

lear

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l Fac

ility llehs

teih Wdn

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Lrev R

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Ch

MD

S N

ordi

on

Tri-U

n ive

rsity

Mes

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acilit

y

Pick

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ar G

ener

atin

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Dar

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-2 N

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Nuc

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e O

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er

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iver

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n Fa

cilit

y

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eral

Ele

ctric

Nuc

lear

Fue

l Fac

ilitie

s

Zirc

atec

Nuc

lear

Fue

l Fac

ility llehs

teih Wdn

a ses ie rir toto ara or bo ab La

Lrev R

ikla

Ch

MD

S N

ordi

on

Tri-U

niv e

rsity

Mes

on F

acilit

y

Shie

ld S

ourc

e In

corp

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edSh

ield

Sou

rce

Inco

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SRB

Tech

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(Can

ada)

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SR

B Te

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logi

es (C

anad

a) In

c

6

ty

Dos

e (m

Sv)

) v

Sm( e so

D

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e N

ucle

ar G

ener

atin

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ff La

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er

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ake

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n Fa

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klaC

h

MD

S N

ordi

on

Tri-U

nive

rsity

Mes

on F

acilit

y

Figure 17 Average Effective Doses at All Selected Facilities for the Year 2007 (Based on Non-Zero Results)

4

35

3

25

2

15

1

05

0

Bru

ce N

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C

MD

S N

ordi

on

Tri-U

nive

rsity

Mes

on F

acili

ty

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 16 Average Effective Doses at All Selected Facilities for the Year 2006 (Based on Non-Zero Results)

4

35

3

25

2

15

1

05

0

Shie

ld S

ourc

e In

corp

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corp

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SRB

Tech

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(Can

ada)

Inc

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4

35

3

25

2

15

1

05

0

Dos

e (m

Sv)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

12 Average Effective Doses Based on All Monitoring Results at All Selected Facilities Figures 18ndash114 show average effective doses based on all the monitoring results for each year from 2001 to 2007 for every facility listed in this document

Figure 18 Average Effective Doses at All Selected F acilities for the Year 2001 (Based o n A ll Monitoring R esults)

8

r

Dos

e (m

Sv)

)

Sv

(me

osD

Bruc

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Tri-U

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acilit

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Figure 110 Average Effective Doses at All Selected F acilities for the Year 2003 (Based o n A ll Monitoring R esults)

4

35

3

25

2

15

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0

Bruc

e N

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MD

S N

o rdi

on

Tri-U

nive

r sity

Mes

on F

acilit

y

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 19 Average Effective Doses at All Selected Facilities for the Year 2002 (Based on All Monitoring Results)

4

35

3

25

2

15

1

05

0

Shie

ld S

ourc

e In

corp

orat

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rpor

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c In)adan

Ca

(seigolonhce T

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B Te

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logi

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anad

a) In

c

9

Dos

e (m

Sv)

)

Sv

(me

osD

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 111 Average Effective Doses at All Selected F acilities for the Year 2004 (Based o n A ll Monitoring R esults)

4

35

3

25

2

15

1

05

0

Bruc

e N

ucle

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Lre v R

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T ri-U

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Mes

on F

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Figure 112 Average Effective Doses at All Selected F acilities for the Year 2005 (Based o n A ll Monitoring R esults)

4

35

3

25

2

15

1

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0

Bruc

e N

ucle

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r s s n n n n n n n n ty s ty l l ty de y n cn n o o o o o o o o r i il e e o ivo o ti l h lti ti ti ti ti ti ti ti i i

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o nti O O th O l orti i e cn r O O un ti se e A e e e e s Wti ti a a a u d er k k kc k k v r F DS

a a r r e n In Ca

r r e a a M a re e a a Ri F M e (n L r s Me e n n L v a

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4

35

3

25

2

15

1

05

0

) vS

m( e soD

Figure 114 Average Effective Doses at All Selected F acilities for the Year 2007 (Based o n A ll Monitoring R esults)

Bru

ce N

ucle

ar G

ener

atin

g S

tatio

ns

Pic

kerin

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tilly

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nt L

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au N

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ff La

ke O

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d R

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Rk lah

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MD

S N

ordi

on

Tri-U

nive

rsity

Mes

on F

acili

ty

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 113 Average Effective Doses at All Selected Facilities for the Year 2006 (Based on All Monitoring Results)

4

35

3

25

2

15

1

05

0

Shi

eld

Sou

rce

Inco

rpor

ated

SR

B T

echn

olog

ies

(Can

ada)

Inc

11

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

20 Facility-Specific Overview of Occupational Doses This section presents data for the following types of facilities

bull nuclear power plants (Section 21) bull uranium mines and mills (Section 22) bull uranium refineries (Section 23) bull fuel fabrication facilities (Section 24) bull research and radioisotope production facilities (Section 25) bull tritium production facilities (Section 26)

21 Nuclear Power Plants This section presents dose information for the following nuclear power plants

bull Bruce A and Bruce B Nuclear Generating Stations (Section 211) bull Pickering Nuclear Generating Stations (Section 212) bull Darlington Nuclear Generating Station Section 213) bull Gentilly-2 Nuclear Generating Station (Section 214) bull Point Lepreau Generating Station (Section 215)

Graphs in this section indicate the following data for each nuclear power plant from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for nuclear power plants

1 Effective doses are composed of the following reported components bull doses from photons (labeled on the charts as ldquoexternalrdquo) bull neutron doses bull tritium doses

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of photon neutron and tritium doses Intakes of other radionuclides (for example Iodine-131 or Carbon-14) occasionally occur but these radionuclides are not included here because the associated collective dose is very small For this reason certain collective dose values in this report may be slightly lower than the sum of their respective components as listed

12

1 2 3 4 5 6 70 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

211 Bruce Nuclear Generating Stations

Bruce Power owns and operates the Bruce Nuclear Generating Stations located near Kincardine Ontario on the shore of Lake Huron

bull Bruce A consists of four nuclear reactors (units 1ndash4) and began operating in 1976 bull Bruce B has four nuclear reactors (units 5ndash8) and started operating in 1984

As part of its extensive recovery program in 1997 the sitersquos previous operator Ontario Hydro (now Ontario Power Generation) temporarily shut down all Bruce A reactors and maintained them in a guaranteed shutdown state Units 3 and 4 were later returned to service (in October 2003 and January 2004) while Units 1 and 2 remained in a guaranteed shutdown state

Figures 21ndash24 present dose information for the Bruce Nuclear Generating Stations from 2001 to 2007 Graphs do not distinguish between doses received at Bruce A versus Bruce B

Fig 21 Average Dose Trends for Bruce Nuclear Generating Stati on (Based o n N on-Zero R esults)

Dos

e (m

Sv)

4

35

3

25

2

15

1

05

0

Tritium Neutron External Effective

Year

13

Neutrons External Tritium

0 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 21 2 3 4 5 6 7

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

0

2

4

6

8

1

2

4

0

0

0

0

1

1

Figure 22 Average Dose Trends for Bruce Nuclear Generating Stati on (Based o n A ll Monitoring R esults)

16

)S

v(m

e os

D

Tritium Neutrons External Effective

Year

Figure 23 Collective Dose Trends for Bruce Nuclear Generating Stati on

8000

7000

6000

5000

4000

3000

2000

1000

0

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Year

14

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 24 Distribution of Effective Doses Among All Workers at Bruce Nuclear Generating Station

6000

5000

4000

3000

2000

1000

0 9 0 0

1-50 0 0 1 0 0 0 0 00 5 0 0 0

0-000

000 1-1 1-1 1-20 1-3 3gt0 0 0 05 0 5 01 1 2

Num

ber o

f Wor

kers

Dose Range (mSv)

15

1 2 3 4 5 6 7 0 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

212 Pickering Nuclear Generating Stations

Located in Pickering Ontario the Pickering Nuclear Generating Stations are owned and operated by Ontario Power Generation Two generating stations are located within one enclosure

bull Pickering A consists of four nuclear reactors (units 1 to 4) that began operating in 1971 bull Pickering B consists of four nuclear reactors (units 5 to 8) that began operating in 1982

As part of its extensive recovery program Ontario Hydro (now Ontario Power Generation) temporarily shut down all Pickering A reactors in 1997 and maintained them in a guaranteed shutdown state Unit 4 was restarted in September 2003 and Unit 1 was restarted in March 2005 Units 2 and 3 remain in a guaranteed shutdown state

Figures 25ndash28 present dose information for the Pickering Nuclear Generating Stations from 2001 to 2007 Graphs do not distinguish between doses received at Pickering A versus those received at Pickering B

Figure 25 Average Dose Trends for Pickering N uclear Generating Stati on (Based o n N on-Zero R esults)

25

2

15

1

05

0

)S

v(m

e os

D

Tritium Neutrons External Effective

Year

16

Tritium Neutrons External Effective

Neutrons External Tritium

1 2 3 4 5 6 70 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

1 2 3 4 5 6 7 0 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 26 Average Dose Trends for Pickering N uclear Generating Stati on (Based o n A ll Monitoring R esults)

12

1

08

06

04

02

0

Year

Figure 27 Collective Dose Trends for Pickering N uclear Generating Stati on

12000

10000

8000

6000

4000

2000

0

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

)

Sv

(me

osD

Year

17

2001 2002 2003 2004 2005 2006 2007

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 28 Distribution o f Effective Doses Among A ll Workers at Pickering Nuclear Generating Stati on

6000

5000

4000

3000

2000

1000

0

Num

ber o

f Wor

kers

Dose Range (mSv)

18

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

213 Darlington Nuclear Generating Station

Owned and operated by Ontario Power Generation the Darlington Nuclear Generating Station has four nuclear reactors the first of which began operating in 1989 The facility is located near Bowmanville on the shore of Lake Ontario

Figures 29ndash212 present dose information for the Darlington Nuclear Generating Station from 2001 to 2007

Figure 29 Average Dose Trends for Darlington N uclear Generating Stati on (Non- Zero R esults Only)

)S

v(m

e os

D

250

200

150

100

050

000

Year

19

Tritium Neutrons External Effective

Neutrons External Tritium

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 210 Average Dose Trends for Darlington N uclear Generating Stati on (All Monitoring R esults)

090

080

070

060

050

040

030

020

010

000

)S

v(m

e os

D

Year

Figure 211 Collective Dose Trends for Darlington N uclear Generating Stati on

4500

4000

3500

3000

2500

2000

1500

1000

500

0

)vSm-nosrep (es

Do

eiv

llect

Co

Year

20

2001 2002 2003 2004 2005 2006 2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 212 Distribution o f Effective Doses Among A ll Workers at Darlington Nuclear Generating Stati on

0

500

1000

1500

2000

2500

3000

3500

ers

ork

W of

be

r um

N

Dose Range (mSv)

21

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

214 Gentilly-2 Nuclear Generating Station

The Gentilly-2 Nuclear Generating Station owned and operated by Hydro-Queacutebec has a single reactor that began operating in 1982 The facility is located on the south shore of the St Lawrence River near Trois-Riviegraveres Queacutebec

Figures 213ndash216 present dose information for the Gentilly-2 Nuclear Generating Station from 2001 to 2007

Figure 213 Average Dose Trends for Gentilly-2 Nuclear Generating Stati on (Based o n N on-Zero R esults)

0

05

1

15

2

25

3

35

4

45

)S

v(m

e os

D

Year

22

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 214 Average Dose Trends for Gentilly-2 Nuclear Generating Stati on (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

)S

v(m

e os

D

Year

Figure 215 Collective Dose Trends for Gentilly-2 Nuclear Generating Stati on

0

500

1000

1500

2000

2500

3000

3500

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Neutrons

External

Tritium

Year

23

000-0

009

001-5

00

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 216 Distribution of Effective Doses Among All Workers at Gentilly-2 Nuclear Generating Station

2500

2000

1500

1000

500

0

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

24

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

215 Point Lepreau Nuclear Generating Station

The Point Lepreau Nuclear Generating Station has one reactor that began operating in 1982 Owned and operated by New Brunswick Power Nuclear the station is located in Point Lepreau New Brunswick about 40 km west of Saint John on the shores of the Bay of Fundy

Figures 217ndash220 present dose information for the Point Lepreau Nuclear Generating Station from 2001 to 2007

Figure 217 Average Dose Trends for Point Lepreau N uclear Generating Stati on (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

)S

v(m

e os

D

Tritium Neutron External Effective

Year

25

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 218 Average Dose Trends for Point Lepreau N uclear Generating Stati on (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

)S

v(m

e os

D

Tritium Neutrons External Effective

Year

Figure 219 Collective Dose Trends for Point Lepreau N uclear Generating Station

0

200

400

600

800

1000

1200

1400

1600

1800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Neutrons

External

Tritium

Year

26

0

1400

1200

1000

800

600

400

200

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 220 Distribution of Effective Doses Among All Workers at Point Lepreau Nuclear Generating Station

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

27

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

22 Uranium Mines and Mills This section presents dose information for mine and mill sites in the following regions

bull Cluff Lake (Section 221) bull McClean Lake (Section 222) bull McArthur River (Section 223) bull Key Lake (Section 224) bull Cigar Lake (Section 225) bull Rabbit Lake (Section 226)

Graphs indicate the following data for each site from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for uranium mines and mills

1 Effective doses are composed of the following reported components bull doses from photons (labelled on the charts as ldquoexternalrdquo) bull doses from radon progeny bull doses from long-lived radioactive dust bull doses from radon gas (in some cases)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of photon radon progeny long-lived radioactive dust and radon gas doses

3 The NDR lists radon progeny in working level months (WLM) For this report radon progeny exposures were converted4 to doses expressed in mSv

221 Cluff Lake Operation

The Cluff Lake mining facilities operated by AREVA Resources Canada Inc are located in northwestern Saskatchewan Work began in 1980 and ended in 2002 with the site now being decommissioned The site consisted of three open-pit and two underground mines a mill and a tailings management facility During 2005 and 2006 most of the infrastructure was removed and the affected areas were remediated

Figures 221ndash224 present dose information for the Cluff Lake operation from 2001 to 2007

4 Doses were converted using the International Commission on Radiation Protection (ICRP)rsquos conversion convention of 1 WLM = 5 mSv This convention was established in the ICRP publication Protection against Radon at Home and at Work (ICRP 65)

28

Long-lived radioactive dust Radon progeny External Effective

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 221 Average Dose Trends for the Cluff Lake Operation (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

Year

Figure 222 Average Dose Trends for the Cluff Lake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

200

Long-lived radioactive dust Radon progeny External Effective

)S

v(m

e os

D)

Sv

(me

osD

Year

29

600

500

400

300

200

100

0

External Radon progeny Long-lived radioactive dust

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 223 Collective Dose Trends for the Cluff Lake Operation s

erkor

of W

ber

Num

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Year

Figure 224 Distribution o f Effective Doses Among A ll Workers at the Cluff Lake Operation

0

20

40

60

80

100

120

140

160

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

30

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

222 McClean Lake Operation

AREVA Resources Canada Inc runs the McClean Lake mining operation in northeastern Saskatchewan It comprises open pit mines a mill and a tailings management facility Mining began in 1995 while milling started in 1999

Figures 225ndash228 present dose information for the McClean Lake operation from 2001 to 2007

Figure 225 Average Dose Trends for the McClean L ake Operation (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

31

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 226 Average Dose Trends for the McClean L ake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 227 Collective Dose Trends for the McClean L ake Operation

0

100

200

300

400

500

600

700

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External

Radon progeny

Long-lived radioactive dust

Year

32

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 228 Distribution o f Effective Doses Among A ll Workers at the McClean Lake Operation

0

100

200

300

400

500

600

700

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

33

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

223 McArthur River Operation

Cameco Corporation operates the McArthur River underground mine in north-central Saskatchewan Ore from the mine which began production in 1999 is processed at the Key Lake Mill located 80 km south of McArthur River

Figures 229ndash232 present dose information for the McArthur River operation from 2001 to 2007

Figure 229 Average Dose Trends for the McArthur River Operation (Based o n N on-Zero R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

34

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 230 Average Dose Trends for the McArthur River Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

Figure 231 Collective Dose Trends for the McArthur River Operation

0

200

400

600

800

1000

1200

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Radon gas External Radon progeny Long-lived radioactive dust

Year

35

00

0-000

9

001-5

00

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 232 Distribution o f Effective Doses Among A ll Workers at the McArthur River Operation

0

100

200

300

400

500

600

700

800

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

36

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

224 Key Lake Operation

Cameco Corporation operates mining facilities in Key Lake located in north-central Saskatchewan The Key Lake operation includes two mined-out open pit mines (used for tailings management) a mill and two dry tailings management facilities Mining began in 1983 and ceased in 1997 the mill continued to process ore from the McArthur River mine during the reporting period

Figures 233ndash236 present dose information for the Key Lake operation from 2001 to 2007

Figure 233 Average Dose Trends for the Key Lake Operation (Based o n N on-Zero R esults)

00

20

40

60

80

00

20

40

60

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

37

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

00

20

40

60

80

00

20

40

60

Figure 234 Average Dose Trends for the Key Lake Operation (Based o n A ll Monitoring R esults)

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 235 Collective Dose Trends for the Key Lake Operation

0

100

200

300

400

500

600

700

800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External Radon progeny Long-lived radioactive dust

Year

38

00

0-000

9

001-5

0

501-1

000

gt 1001

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 236 Distribution o f Effective Doses Among A ll Workers at the Key Lake Operation

0

200

400

600

800

1000

1200

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose Range (mSv)

39

se

(mS

v)o

D

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

225 Cigar Lake Operation

Cameco Corporation manages the Cigar Lake underground mine located in northern Saskatchewan at the southern end of Waterbury Lake The mine was under construction at the time of this reportrsquos publication Test mining in ore was carried out in 1991 1992 and 2000

Figures 237ndash240 present dose information for the Cigar Lake operation from

Figure 2 37 Average D ose T rends fo r th e C igar L ake O peration (Based on Non-Zero Results)

2001 to 2007

Year

000

005

010

015

020

025

Long-lived radioactive dust Radon Progeny External Effective

40

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 238 Average Dose Trends for the Cigar Lake Operation (Based on All Monitoring Results)

000

005

010

015

020

025

030

035

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny

External

Effective

Year

Figure 239 Collective Dose Trends for the Cigar Lake Operation

0

50

100

150

200

250

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

External Radon progeny Long-lived radioactive dust

Year

41

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 240 Distribution of Effective Doses Among All Workers at the Cigar Lake Operation

0

200

400

600

800

1000

1200

1400

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

42

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

226 Rabbit Lake Operation

Cameco Corporation owns and operates mining facilities in Rabbit Lake located in north-eastern Saskatchewan Facilities include an underground mine four mined-out open-pit mines a mill and two tailings management facilities Mining and milling began in 1975

Figures 241ndash244 present dose information for the Rabbit Lake operation from 2001 to 2007

Figure 241 Average Dose Trends for the Rabbit Lake Operation (Based on Non-Zero Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

43

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 242 Average Dose Trends for the Rabbit Lake Operation (Based on All Monitoring Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

Figure 243 Collective Dose Trends for the Rabbit Lake Operation

0

200

400

600

800

1000

1200

1400

1600

1800

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Radon gas External Radon progeny Long-lived radioactive dust

Year

44

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

gt300

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 244 Distribution of Effective Doses Among All Workers at the Rabbit Lake Operation

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

900

800

700

600

500

400

300

200

100

0

Dose (mSv)

45

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

23 Uranium Refineries This section presents data for the following two facilities

bull a uranium refining facility in Blind River (Section 231) bull a uranium conversion facility in Port Hope (Section 232)

Graphs indicate the following average doses at each facility from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Note on data for uranium refineries

1 Doses from photons from external sources are measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay and lung counting Historically while these internal doses have been measured they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

231 Blind River Refinery

Cameco Corporation owns and is licensed to operate a uranium refinery in Blind River Ontario The facility which began operating in 1983 converts uranium ore concentrate to uranium trioxide The uranium trioxide is shipped to Camecorsquos uranium conversion facility in Port Hope Ontario where it is processed into uranium dioxide (for use in the fabrication of fuel for nuclear reactors in Canada) or uranium hexafluoride (exported for enrichment and fabrication into fuel for nuclear power reactors around the world)

Figures 245ndash248 present dose information for the Blind River refinery from 2001 to 2007

46

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 245 Average Dose Trends for the Blind River Refinery (Based on Non-Zero Results)

0

05

1

15

2

25

Year

Figure 246 Average Dose Trends for the Blind River Refinery (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

47

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 247 Collective Dose Trends for the Blind River Refinery

0

50

100

150

200

250

300 C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 248 Distribution of Effective Doses Among All Workers at the Blind River Refinery

0

20

40

60

80

100

120

140

160

180

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

48

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

232 Port Hope Conversion Facility

Cameco Corporation owns and is licensed to operate a uranium conversion facility in Port Hope Ontario The facility processes uranium trioxide received from the refinery in Blind River into uranium dioxide and uranium hexafluoride

Figures 249ndash252 present dose information for the Port Hope uranium conversion facility from 2001 to 2007

Figure 249 Average Dose Trends for the Port Hope Conversion Facility (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

49

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 250 Average Dose Trends for the Port Hope Conversion Facility (Based on All Monitoring Results)

0

01

02

03

04

05

06

07

08

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 251 Collective Dose Trends for the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

50

000-0

009

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 252 Distribution of Effective Doses Among All Workers at the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

400

450

500

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

51

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

24 Fuel Fabrication Facilities This section presents data for three nuclear fuel fabrication facilities

bull Two facilities owned and operated by General Electric Canada Inc (Section 241) bull One facility in Port Hope operated by Zircatec Precision Industries (Section 242)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average doses

Notes on data for fuel fabrication facilities

1 Effective doses for the three facilities are composed of the following reported components bull dose from photons (labelled on the charts as ldquoexternalrdquo) bull doses from internal intakes of uranium dust (long-lived radioactive dust) from

uranium in air concentrations (for General Electricrsquos Toronto facility only)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components photon doses and doses from long-lived radioactive dust

241 General Electric Nuclear Fuel Facilities

General Electric Canada Inc operates two nuclear fuel facilities in Ontario

bull At the Toronto facility uranium dioxide pellets are produced from natural or depleted uranium dioxide powder

bull At the Peterborough facility uranium dioxide fuel bundles are created from the pellets produced at the Toronto facility

Figures 253ndash256 present dose information for General Electric Canada Incrsquos fuel fabrication facilities from 2001 to 2007 Graphs do not distinguish between the doses received at the Peterborough facility versus those at the Toronto facility

52

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 253 Average Dose Trends for the General Electric Fuel Facility (Based on Non-Zero Results Only)

0

05

1

15

2

25

3

35

Long Lived Radioactive Dust External Effective

Year

Figure 254 Average Dose Trends for the General Electric Fuel Facility (Based on All Monitoring Results)

0

05

1

15

2

25

3

Long Lived Radioactive Dust External Effective

Year

Dos

e (m

Sv)

Dos

e (m

Sv)

53

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 255 Collective Dose Trends for the General Electric Fuel Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Long Lived Radioactive Dust External

Year

Figure 256 Distribution of Effective Doses among all Workers at the General Electric Fuel Facility

0

10

20

30

40

50

60

70

80

90

100

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

54

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

242 Zircatec Nuclear Fuel Facility

Zircatec Precision Industries Inc operates a nuclear fuel facility in Port Hope Ontario where it makes fuel pellets from uranium dioxide powder received from Port Hopersquos uranium conversion facility The nuclear fuel facility also manufactures fuel bundles for nuclear reactors in Canada

Notes on data for the Zircatec nuclear fuel facility

1 Graphs indicate the following data bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of average effective doses

2 Doses from photons from external sources were measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay Historically although these internal doses have been measured and submitted to the CNSC they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

Figures 257ndash260 present dose information for the Zircatec nuclear fuel facility from 2001 to 2007

Figure 257 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on Non-Zero Results)

0

05

1

15

2

25

3

35

Effe

ctiv

e D

ose

(mS

v)

Year

55

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 258 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

18

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 259 Collective Dose Trends for the Zircatec Nuclear Fuel Facility

0

50

100

150

200

250

300

350

400

450

500

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

56

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 260 Distribution of Effective Doses Among All Workers at the Zircatec Nuclear Fuel Facility

300

Num

ber o

f Wor

kers

250

200

150

100

50

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

57

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

25 Research and Radioisotope Production Facilities This section presents dose information for the following research and radioisotope production facilities from 2001 to 2007

bull Chalk River Laboratories and Whiteshell Laboratories (Section 251) bull A radioisotope production facility operated by MDS Nordion (Section 252) bull The Tri-University Meson Facility (TRIUMF) (Section 253)

Note on data for research and radioisotope production facilities

1 Graphs indicate the following data for each facility bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of effective doses

251 Chalk River Laboratories and Whiteshell Laboratories

Atomic Energy of Canada Limited (AECL) owns and is licensed to operate Chalk River Laboratories and Whiteshell Laboratories

Situated in Renfrew County on the south shore of the Ottawa River the Chalk River Laboratories site hosts the National Research Universal Reactor along with numerous other facilities occupying some 160 buildings in an area of approximately 40 km2 Activities consist of radioisotope production for nuclear medicine testing and development of structural materials in support of power reactor operations fuel fabrication research and radioactive waste management and storage

The Whiteshell Laboratories site is located approximately 10 km west of Pinawa Manitoba and 100 km northeast of Winnipeg on the east bank of the Winnipeg River AECL established the laboratories for nuclear research and testing during the early 1960s and has since discontinued operations which are being decommissioned under a licence from the CNSC

Figures 261ndash264 present dose information for Chalk River Laboratories and Whiteshell Laboratories from 2001 to 2007

Notes on data for Chalk River Laboratories and Whiteshell Laboratories

1 Effective doses are composed of the following reported components bull external doses5 (from both photon and neutron doses) bull tritium doses

Due to issues with AECLrsquos in-house dosimetry management system neutron doses were not reported separately to the NDR during the reporting period As a result external doses from photons and neutrons were totaled The reporting discrepancy has since been rectified

58

5

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of external (photon and neutron) and tritium doses Intakes of other radionuclides occasionally occur and these radionuclides are not included here because their associated doses are very small For this reason certain collective doses in this report may have values slightly lower than the sum of their respective components as listed

Figure 261 Average Dose Trends for Chalk River and Whiteshell Laboratories (Non-Zero Results Only)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Tritium External Effective

Year

59

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 262 Average Dose Trends for Chalk River and Whiteshell Laboratories (All Monitoring Results)

000

020

040

060

080

100

120

Dos

e (m

Sv)

Tritium External Effective

Year

Figure 263 Collective Dose Trends for Chalk River and Whiteshell Laboratories

0

500

1000

1500

2000

2500

3000

3500

Col

lect

ive

Dos

e (p

erso

n- m

Sv)

External Tritium

Year

60

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 264 Distribution of Effective Doses Among All Workers at Chalk River and Whiteshell Laboratories

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

3500

3000

2500

2000

1500

1000

500

Dose (mSv)

61

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

252 MDS Nordion (Nuclear Substance Processing Facility and Canadian Irradiation Centre)

MDS Nordion owns and operates a nuclear substance processing facility in Ottawa Ontario where it processes unsealed radioisotopes and manufactures sealed radiation sources In operation since the early 1970s the facility was purchased by Nordion International in 1991

In cooperation with the Universiteacute du Queacutebecrsquos Institut Armand-Frappier MDS Nordion also operates the Canadian Irradiation Centre which conducts various irradiation services which include training testing and development The centre is located in Laval Quebec on the Universiteacute du Queacutebec campus

Figures 265ndash268 present dose information for MDS Nordionrsquos Ottawa nuclear substance processing facility and for the Canadian Irradiation Centre from 2001 to 2007

Notes on data for MDS Nordionrsquos nuclear substance processing facility and the Canadian Irradiation Centre

1 Doses from photons from external sources were measured and reported to the NDR MDS Nordion also has a routine thyroid monitoring program very occasionally small recordable doses of radiation have occurred from thyroid uptake of iodine The resulting doses have not been historically submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided

Figure 265 Average Dose Trends for MDS Nordion (Based on Non-Zero Results)

0

05

1

15

2

25

Effe

ctiv

e D

ose

(mS

v)

Year

62

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 266 Average Dose Trends for MDS Nordion (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

Figure 267 Collective Dose Trends for MDS Nordion

0

100

200

300

400

500

600

700

800

Year

63

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 268 Distribution of Effective Doses Among All Workers at MDS Nordion

0

5 0

1 0 0

1 5 0

2 0 0

2 5 0

3 0 0

3 5 0

4 0 0

4 5 0

5 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

64

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

253 Tri-University Meson Facility

The Tri-University Meson facility (TRIUMF) is situated in Vancouver on the campus of the University of British Columbia TRIUMF which began operating in the early 1970s with one cyclotron now has two cyclotrons and associated laboratories for research and radioisotope production The laboratory provides research facilities for Canadian and international users and also produces radioisotopes which are used by medical facilities and by a commercial organization (MDS Nordion) MDS Nordion staff also work at the TRIUMF site however MDS Nordion oversees this work and has its own radiation protection program

Figures 269ndash272 present dose information for the TRIUMF facility from 2001 to 2007 Please note that data sets do not distinguish between doses received by TRIUMF staff and MDS Nordion staff who work on the site as the data for these two groups was submitted collectively to the NDR for the reporting period shown Future data for each group will be submitted separately to the NDR

Note on data for TRIUMF

1 Effective doses are composed of the following reported components bull doses from photons (labeled as ldquoexternalrdquo in the charts) bull neutron doses

Figure 269 Average Dose Trends for TRIUMF (Non-Zero Results Only)

000

020

040

060

080

100

120

140

160

Dos

e (m

Sv)

Neutrons External Effective

Year

65

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 4: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

Table of Contents List of Figures iv Introduction 1 10 Facility-Wide Comparisons of Average Effective Doses 4

11 Average Effective Doses Based on Non-Zero Results at All Selected Facilities 4 12 Average Effective Doses Based on All Monitoring Results at All Selected Facilities 8

20 Facility-Specific Overview of Occupational Doses 12 21 Nuclear Power Plants 12

211 Bruce Nuclear Generating Stations 13 212 Pickering Nuclear Generating Stations 16 213 Darlington Nuclear Generating Station 19 214 Gentilly-2 Nuclear Generating Station 22 215 Point Lepreau Nuclear Generating Station 25

22 Uranium Mines and Mills 28 221 Cluff Lake Operation 28 222 McClean Lake Operation 31 223 McArthur River Operation 34 224 Key Lake Operation 37 225 Cigar Lake Operation 40 226 Rabbit Lake Operation 43

23 Uranium Refineries 46 231 Blind River Refinery 46 232 Port Hope Conversion Facility 49

24 Fuel Fabrication Facilities 52 241 General Electric Nuclear Fuel Facilities 52 242 Zircatec Nuclear Fuel Facility 55

25 Research and Radioisotope Production Facilities 58 251 Chalk River Laboratories and Whiteshell Laboratories 58 252 MDS Nordion (Nuclear Substance Processing Facility and Canadian

Irradiation Centre) 62 253 Tri-University Meson Facility 65

26 Tritium Light Source Production Facilities68 261 Shield Source Incorporated 68 262 SRB Technologies (Canada) Inc 71

Glossary 74 Bibliography 76

List of Figures

Figures 11ndash114 Facility-wide Average Doses

Figures 21ndash24 Bruce Nuclear Generating Stations Figures 25ndash28 Pickering Nuclear Generating Stations Figures 29ndash212 Darlington Nuclear Generating Station Figures 213ndash216 Gentilly-2 Nuclear Generating Station Figures 217ndash220 Point Lepreau Nuclear Generating Station

Figures 221ndash224 Cluff Lake Operation Figures 225ndash228 McClean Lake Operation Figures 229ndash232 McArthur River Operation Figures 233ndash236 Key Lake Operation Figures 237ndash240 Cigar Lake Operation Figures 241ndash244 Rabbit Lake Operation

Figures 245ndash248 Blind River Refinery Figures 249ndash252 Port Hope Conversion Facility

Figures 253ndash256 General Electric Nuclear Fuel Facilities Figures 257ndash260 Zircatec Nuclear Fuel Facility

Figures 261ndash264 Chalk River Laboratories and Whiteshell Laboratories Figures 265ndash268 MDS Nordion Figures 269ndash272 Tri-University Meson Facility (TRIUMF)

Figures 273ndash276 Shield Source Incorporated Figures 277ndash280 SRB Technologies (Canada) Inc

Table 1 Effective Dose Limits in Canada as Specified by the Radiation Protection Regulations Person Period Effective Dose

(mSv) Nuclear energy workers including pregnant (a) One-year dosimetry period 50 nuclear energy workers

(b) Five-year dosimetry period 100 Pregnant nuclear energy worker Balance of the pregnancy 4

A person who is not a nuclear energy worker One calendar year 1

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Introduction Workers at nuclear facilities are exposed to radiation Their dose is monitored and subject to Canadian Nuclear Safety Commission (CNSC) regulatory requirements which aim to protect their health and safety The amount of radiation to which employees are exposed is referred to as ldquooccupational doserdquo This report provides an overview of occupational radiation doses from 2001 to 2007 at the major nuclear facilities licensed by the CNSC It presents an objective summary of occupational dose information and includes a glossary of terminology

The data collected shows that the average doses for all facilities are far below the individual annual effective dose limit of 50 milliSieverts (mSv) set out in the Radiation Protection Regulations

The report includes data for the following types of facilities

bull nuclear power plants bull uranium mines and mills bull uranium refineries bull fuel fabrication facilities bull research and radioisotope production facilities bull tritium light source production facilities

Each facility is unique in regards to the type of work performed as well its current lifecycle stage (ie operating at reduced or full capacity or in a phase of refurbishment for example) and each provides varying programs to mitigate radiation doses to workers The resulting collective and average doses are based on complex and differing work environments Therefore direct comparisons between facilities in terms of occupational dose are not possible

Regulatory Radiation Dose Limits The Radiation Protection Regulations limit the amount of radiation to which persons may be exposed Table 1 presents the effective dose limits as set out in paragraphs 13 and 14 of the regulations

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

The Radiation Protection Regulations also require CNSC licensees to implement radiation protection programs and to keep radiation doses as low as reasonably achievable (a concept referred to as the ALARA principle) The CNSC evaluates licensee radiation protection programs and these evaluations include reviews of the occupational dose data which is one among several indicators of a radiation protection programrsquos effectiveness

About the Data

Source Statistics in this document are gathered from the National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses1 Maintained by Health Canadarsquos Radiation Protection Bureau the NDR publishes annual reports on occupational dose information and trends according to job type

Due to the large number of CNSC-licensed facilities this report does not include occupational dose information for every CNSC licensees Please refer to the NDR Web site2 to review Health Canadarsquos reports

Analysis This report presents the following types of data

a average doses b collective doses c distribution of effective doses

a Average doses provide a common means of indicating central tendencies of dose distribution and show where doses lie on average with respect to annual dose limits

Notes on average effective doses

1 This report presents two types3 of arithmetic averages for individual effective doses bull averages that include only non-zero (positive) results bull averages that include all monitoring results (including zero-value doses)

2 When assessing regulatory compliance individual doses mdash not average doses mdash must be compared to individual dose limits in the Radiation Protection Regulations

1 In Canada the Radiation Protection Regulations require licensed dosimetry services to submit dose information for nuclear energy workers (NEWs) While not required by law dose information for non-NEWs is also typically submitted to the NDR The data in this report does not distinguish between personnel designated as NEWs versus those who are not 2 httpwwwhc-scgccaewh-semtoccup-travailradiationregistindex_ehtml 3 Some licensees monitor most or all workers (including those unlikely to be directly exposed to sources of occupational radiation) whereas other licensees monitor only employees likely to receive radiation doses Therefore two types of averages are presented averages that consider only non-zero results and averages that consider all results Both statistical approaches have merit and are included in this report (Note The exclusion of zero value doses in the averaging could unfairly bias findings against licensees with effective radiation protection programs)

2

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

b Collective doses indicate the sum of all the doses associated with a facilityrsquos operation and can be used to estimate a facilityrsquos control of occupational doses

Note on collective doses

1 The Radiation Protection Regulations do not set limits on collective doses however the CNSC recommends that licensee radiation protection programs should aim to reduce collective doses These values can indicate a facilityrsquos radiological detriment and help assess whether a facility is operating in accordance with the ALARA principle

c Distribution of effective doses shows the ranges in which effective doses are concentrated

Effective dose calculations By definition effective doses cannot be measured precisely but they can be approximated in order to determine radiation exposure and to assess the associated risks Section 13 of the Radiation Protection Regulations defines the dose calculation methods used to determine effective doses as expressed in millisieverts (mSv) which are based on measurable quantities in the operational environment

Effective radiation doses are made up of various components of which the most common (in Canada) are as follows

bull photons and neutrons from sources outside the body bull radon progeny radon gas long-lived radioactive dust (uranium dust) and tritium that are

taken into the body

The effective doses reported to the NDR represent the sum of their applicable components For example the effective dose to a worker who received radiation doses from both neutrons and tritium would be the sum of these two quantities

Note on average dose values

1 Average values for each dose type (for example tritium) are based on the total collective dose for that type divided by the number of all the workers monitored for any dose type

3

yrenfi R

erev

Ri

dnilB

noid N

orD

SM

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

10 Facility-Wide Comparisons of Average Effective Doses This section presents comparisons of average effective doses at all CNSC-licensed nuclear facilities included in this report for each year within the 2001ndash07 reporting period

bull Figures 11ndash17 present averages based on non-zero (positive) results (Section 11)bull Figures 18ndash114 present averages based on all monitoring results (Section 12)

Notes on facility-wide comparisons of average effective doses

1 Each facility type is represented by a different colour bull nuclear power plants ndash green bull uranium mines and mills ndash purple bull uranium refineries ndash yellow bull fuel fabrication facilities ndash orange bull research and radioisotope facilities ndash blue bull tritium light source production facilities ndash red

2 See Sections 21ndash26 for facility-specific data depicted in Figures 11ndash114

11 Average Effective Doses Based on Non-Zero Results at All Selected Facilities Figures 11ndash17 show average effective doses based on non-zero results for each year from 2001 to 2007 for all the facilities presented in this document

Figure 11 Average Effective Doses at All Selected F acilities for the Year 2001 (Based o n N on-Zero R esults)

4

35

3

25

2

15

1

05

0

) Sv

(me

osD

Bruc

e N

ucle

ar G

ener

atin

g St

atio

ns snotita

Sgntiarene Graelc

Nu

gnirekciP

notita

Sgntiarene Graelc

Nu

ntognilr

Da

notita

Sgntiarene Graelc

Nu

2-ylltineG

notita

Sgntiarene Graelc

Nu

uaerpet LnioP

notiarep Oeka

ff L

uC

l

notiarep Oeka

LnaeC

lc

M

rev R

iru

thrAcM

notiarep Oeka

LyeK

notiarep Oeka

LragC

i

notiarep Oeka

it L

bbR

a

tyilica Fnoisrevn

Co

ept H

oroP

setiilica Fleu

Fraelc N

ucitrcel

ElareneG

tyilical Feu

Fraelc N

uc

teacriZ

Cha

lk R

iver

Lab

orat

orie

s an

d W

hite

shel

lLa

bora

torie

s

tyilica Fnose

Mtyisrev

Uni

-irT

dtearoproc

Inecruo SdleihS

c In)adan

Ca

(seigolonhce T

RB

S

4

y

s n

Dos

e (m

Sv)

) Sv

(me

osD

4

35

3

25

2

15

1

05

0

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 12 Average Effective Doses at All Selected Facilities for the Year 2002 (Based on Non-Zero Results)

4

35

3

25

2

15

1

05

0

Bruc

e N

ucle

ar G

ener

atin

g St

atio

nsBr

uce

Nuc

lear

Gen

erat

ing

Stat

ions

Pick

erin

g N

ucle

ar G

ener

atin

g St

atio

n

Dar

lingt

on N

ucle

ar G

ener

atin

g St

atio

n

Gen

tilly

-2 N

ucle

ar G

ener

atin

g St

atio

n

Poin

t Lep

reau

Nuc

lear

Gen

erat

ing

Stat

ion

Clu

ff La

ke O

pera

tion

McC

lean

Lak

e O

pera

tio

McA

rthur

Riv

er

Key

Lake

Ope

ratio

n

Cig

ar L

ake

Ope

ratio

n

Rab

bit L

ake

Ope

ratio

n

Blin

d R

iver

Ref

iner

y

Port

Hop

e C

onve

rsio

n Fa

cilit

y

Gen

eral

Ele

ctric

Nuc

lear

Fue

l Fac

ilitie

s

Zirc

atec

Nuc

lear

Fue

l Fac

ility llehs

teih Wdn

a ses ie rir toto ara or bo ab La

Lrev R

ikla

Ch

MD

S N

ordi

on

Tri- U

nive

rsity

Mes

on F

acilit

y

Figure 13 Average Effective Doses at All Selected Facilities for the Year 2003 (Based on Non-Zero Results)

Pick

erin

g N

ucle

ar G

ener

atin

g St

atio

ns

Dar

lingt

on N

ucle

ar G

ener

atin

g St

atio

n

Gen

tilly

-2 N

ucle

ar G

ener

atin

g St

atio

n

Poin

t Lep

reau

Nuc

lear

Gen

erat

ing

Stat

ion

Clu

ff La

ke O

pera

tion

McC

lean

Lak

e O

pera

tion

McA

rthur

Riv

er

Key

Lake

Ope

ratio

n

Cig

ar L

ake

Ope

rat io

n

Rab

bit L

ake

Ope

ratio

n

Blin

d R

iver

Ref

iner

y

Port

Hop

e C

onve

rsio

n Fa

cilit

y

Gen

eral

Ele

ctric

Nuc

lear

Fue

l Fac

ilitie

s

Zirc

atec

Nuc

lear

Fue

l Fac

ilit

llehsteih

Wdn a ses ie rir to

to ara or bo ab La Lrev

Ri

klaC

h

MD

S N

ord i

on

Tri-U

nive

rsity

Mes

on F

acilit

y

Shie

ld S

ourc

e In

corp

orat

edSh

ield

Sou

rce

Inco

rpor

ated

SRB

Tech

nolo

gies

(Can

ada)

Inc

SR

B Te

chno

logi

es (C

anad

a) In

c

5

n

2

1

35

3

5

2

5

1

Dos

e (m

Sv)

) Sv

(me

osD

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 14 Average Effective Doses at All Selected Facilities for the Year 2004 (Based on Non-Zero Results)

4

05

0

Figure 15 Average Effective Doses at All Selected Facilities for the Year 2005 (Based on Non-Zero Results)

4

35

3

25

2

15

1

05

0

Bruc

e N

ucle

ar G

ener

atin

g St

atio

nsBr

uce

Nuc

lear

Gen

erat

ing

Stat

ions

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Figure 17 Average Effective Doses at All Selected Facilities for the Year 2007 (Based on Non-Zero Results)

4

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Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 16 Average Effective Doses at All Selected Facilities for the Year 2006 (Based on Non-Zero Results)

4

35

3

25

2

15

1

05

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Shie

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Sv)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

12 Average Effective Doses Based on All Monitoring Results at All Selected Facilities Figures 18ndash114 show average effective doses based on all the monitoring results for each year from 2001 to 2007 for every facility listed in this document

Figure 18 Average Effective Doses at All Selected F acilities for the Year 2001 (Based o n A ll Monitoring R esults)

8

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Figure 110 Average Effective Doses at All Selected F acilities for the Year 2003 (Based o n A ll Monitoring R esults)

4

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Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 19 Average Effective Doses at All Selected Facilities for the Year 2002 (Based on All Monitoring Results)

4

35

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25

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Shie

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Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 111 Average Effective Doses at All Selected F acilities for the Year 2004 (Based o n A ll Monitoring R esults)

4

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Figure 112 Average Effective Doses at All Selected F acilities for the Year 2005 (Based o n A ll Monitoring R esults)

4

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4

35

3

25

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Figure 114 Average Effective Doses at All Selected F acilities for the Year 2007 (Based o n A ll Monitoring R esults)

Bru

ce N

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ar G

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Pic

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Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 113 Average Effective Doses at All Selected Facilities for the Year 2006 (Based on All Monitoring Results)

4

35

3

25

2

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1

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0

Shi

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(Can

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11

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

20 Facility-Specific Overview of Occupational Doses This section presents data for the following types of facilities

bull nuclear power plants (Section 21) bull uranium mines and mills (Section 22) bull uranium refineries (Section 23) bull fuel fabrication facilities (Section 24) bull research and radioisotope production facilities (Section 25) bull tritium production facilities (Section 26)

21 Nuclear Power Plants This section presents dose information for the following nuclear power plants

bull Bruce A and Bruce B Nuclear Generating Stations (Section 211) bull Pickering Nuclear Generating Stations (Section 212) bull Darlington Nuclear Generating Station Section 213) bull Gentilly-2 Nuclear Generating Station (Section 214) bull Point Lepreau Generating Station (Section 215)

Graphs in this section indicate the following data for each nuclear power plant from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for nuclear power plants

1 Effective doses are composed of the following reported components bull doses from photons (labeled on the charts as ldquoexternalrdquo) bull neutron doses bull tritium doses

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of photon neutron and tritium doses Intakes of other radionuclides (for example Iodine-131 or Carbon-14) occasionally occur but these radionuclides are not included here because the associated collective dose is very small For this reason certain collective dose values in this report may be slightly lower than the sum of their respective components as listed

12

1 2 3 4 5 6 70 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

211 Bruce Nuclear Generating Stations

Bruce Power owns and operates the Bruce Nuclear Generating Stations located near Kincardine Ontario on the shore of Lake Huron

bull Bruce A consists of four nuclear reactors (units 1ndash4) and began operating in 1976 bull Bruce B has four nuclear reactors (units 5ndash8) and started operating in 1984

As part of its extensive recovery program in 1997 the sitersquos previous operator Ontario Hydro (now Ontario Power Generation) temporarily shut down all Bruce A reactors and maintained them in a guaranteed shutdown state Units 3 and 4 were later returned to service (in October 2003 and January 2004) while Units 1 and 2 remained in a guaranteed shutdown state

Figures 21ndash24 present dose information for the Bruce Nuclear Generating Stations from 2001 to 2007 Graphs do not distinguish between doses received at Bruce A versus Bruce B

Fig 21 Average Dose Trends for Bruce Nuclear Generating Stati on (Based o n N on-Zero R esults)

Dos

e (m

Sv)

4

35

3

25

2

15

1

05

0

Tritium Neutron External Effective

Year

13

Neutrons External Tritium

0 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 21 2 3 4 5 6 7

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

0

2

4

6

8

1

2

4

0

0

0

0

1

1

Figure 22 Average Dose Trends for Bruce Nuclear Generating Stati on (Based o n A ll Monitoring R esults)

16

)S

v(m

e os

D

Tritium Neutrons External Effective

Year

Figure 23 Collective Dose Trends for Bruce Nuclear Generating Stati on

8000

7000

6000

5000

4000

3000

2000

1000

0

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Year

14

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 24 Distribution of Effective Doses Among All Workers at Bruce Nuclear Generating Station

6000

5000

4000

3000

2000

1000

0 9 0 0

1-50 0 0 1 0 0 0 0 00 5 0 0 0

0-000

000 1-1 1-1 1-20 1-3 3gt0 0 0 05 0 5 01 1 2

Num

ber o

f Wor

kers

Dose Range (mSv)

15

1 2 3 4 5 6 7 0 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

212 Pickering Nuclear Generating Stations

Located in Pickering Ontario the Pickering Nuclear Generating Stations are owned and operated by Ontario Power Generation Two generating stations are located within one enclosure

bull Pickering A consists of four nuclear reactors (units 1 to 4) that began operating in 1971 bull Pickering B consists of four nuclear reactors (units 5 to 8) that began operating in 1982

As part of its extensive recovery program Ontario Hydro (now Ontario Power Generation) temporarily shut down all Pickering A reactors in 1997 and maintained them in a guaranteed shutdown state Unit 4 was restarted in September 2003 and Unit 1 was restarted in March 2005 Units 2 and 3 remain in a guaranteed shutdown state

Figures 25ndash28 present dose information for the Pickering Nuclear Generating Stations from 2001 to 2007 Graphs do not distinguish between doses received at Pickering A versus those received at Pickering B

Figure 25 Average Dose Trends for Pickering N uclear Generating Stati on (Based o n N on-Zero R esults)

25

2

15

1

05

0

)S

v(m

e os

D

Tritium Neutrons External Effective

Year

16

Tritium Neutrons External Effective

Neutrons External Tritium

1 2 3 4 5 6 70 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

1 2 3 4 5 6 7 0 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 26 Average Dose Trends for Pickering N uclear Generating Stati on (Based o n A ll Monitoring R esults)

12

1

08

06

04

02

0

Year

Figure 27 Collective Dose Trends for Pickering N uclear Generating Stati on

12000

10000

8000

6000

4000

2000

0

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

)

Sv

(me

osD

Year

17

2001 2002 2003 2004 2005 2006 2007

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 28 Distribution o f Effective Doses Among A ll Workers at Pickering Nuclear Generating Stati on

6000

5000

4000

3000

2000

1000

0

Num

ber o

f Wor

kers

Dose Range (mSv)

18

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

213 Darlington Nuclear Generating Station

Owned and operated by Ontario Power Generation the Darlington Nuclear Generating Station has four nuclear reactors the first of which began operating in 1989 The facility is located near Bowmanville on the shore of Lake Ontario

Figures 29ndash212 present dose information for the Darlington Nuclear Generating Station from 2001 to 2007

Figure 29 Average Dose Trends for Darlington N uclear Generating Stati on (Non- Zero R esults Only)

)S

v(m

e os

D

250

200

150

100

050

000

Year

19

Tritium Neutrons External Effective

Neutrons External Tritium

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 210 Average Dose Trends for Darlington N uclear Generating Stati on (All Monitoring R esults)

090

080

070

060

050

040

030

020

010

000

)S

v(m

e os

D

Year

Figure 211 Collective Dose Trends for Darlington N uclear Generating Stati on

4500

4000

3500

3000

2500

2000

1500

1000

500

0

)vSm-nosrep (es

Do

eiv

llect

Co

Year

20

2001 2002 2003 2004 2005 2006 2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 212 Distribution o f Effective Doses Among A ll Workers at Darlington Nuclear Generating Stati on

0

500

1000

1500

2000

2500

3000

3500

ers

ork

W of

be

r um

N

Dose Range (mSv)

21

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

214 Gentilly-2 Nuclear Generating Station

The Gentilly-2 Nuclear Generating Station owned and operated by Hydro-Queacutebec has a single reactor that began operating in 1982 The facility is located on the south shore of the St Lawrence River near Trois-Riviegraveres Queacutebec

Figures 213ndash216 present dose information for the Gentilly-2 Nuclear Generating Station from 2001 to 2007

Figure 213 Average Dose Trends for Gentilly-2 Nuclear Generating Stati on (Based o n N on-Zero R esults)

0

05

1

15

2

25

3

35

4

45

)S

v(m

e os

D

Year

22

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 214 Average Dose Trends for Gentilly-2 Nuclear Generating Stati on (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

)S

v(m

e os

D

Year

Figure 215 Collective Dose Trends for Gentilly-2 Nuclear Generating Stati on

0

500

1000

1500

2000

2500

3000

3500

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Neutrons

External

Tritium

Year

23

000-0

009

001-5

00

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 216 Distribution of Effective Doses Among All Workers at Gentilly-2 Nuclear Generating Station

2500

2000

1500

1000

500

0

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

24

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

215 Point Lepreau Nuclear Generating Station

The Point Lepreau Nuclear Generating Station has one reactor that began operating in 1982 Owned and operated by New Brunswick Power Nuclear the station is located in Point Lepreau New Brunswick about 40 km west of Saint John on the shores of the Bay of Fundy

Figures 217ndash220 present dose information for the Point Lepreau Nuclear Generating Station from 2001 to 2007

Figure 217 Average Dose Trends for Point Lepreau N uclear Generating Stati on (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

)S

v(m

e os

D

Tritium Neutron External Effective

Year

25

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 218 Average Dose Trends for Point Lepreau N uclear Generating Stati on (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

)S

v(m

e os

D

Tritium Neutrons External Effective

Year

Figure 219 Collective Dose Trends for Point Lepreau N uclear Generating Station

0

200

400

600

800

1000

1200

1400

1600

1800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Neutrons

External

Tritium

Year

26

0

1400

1200

1000

800

600

400

200

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 220 Distribution of Effective Doses Among All Workers at Point Lepreau Nuclear Generating Station

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

27

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

22 Uranium Mines and Mills This section presents dose information for mine and mill sites in the following regions

bull Cluff Lake (Section 221) bull McClean Lake (Section 222) bull McArthur River (Section 223) bull Key Lake (Section 224) bull Cigar Lake (Section 225) bull Rabbit Lake (Section 226)

Graphs indicate the following data for each site from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for uranium mines and mills

1 Effective doses are composed of the following reported components bull doses from photons (labelled on the charts as ldquoexternalrdquo) bull doses from radon progeny bull doses from long-lived radioactive dust bull doses from radon gas (in some cases)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of photon radon progeny long-lived radioactive dust and radon gas doses

3 The NDR lists radon progeny in working level months (WLM) For this report radon progeny exposures were converted4 to doses expressed in mSv

221 Cluff Lake Operation

The Cluff Lake mining facilities operated by AREVA Resources Canada Inc are located in northwestern Saskatchewan Work began in 1980 and ended in 2002 with the site now being decommissioned The site consisted of three open-pit and two underground mines a mill and a tailings management facility During 2005 and 2006 most of the infrastructure was removed and the affected areas were remediated

Figures 221ndash224 present dose information for the Cluff Lake operation from 2001 to 2007

4 Doses were converted using the International Commission on Radiation Protection (ICRP)rsquos conversion convention of 1 WLM = 5 mSv This convention was established in the ICRP publication Protection against Radon at Home and at Work (ICRP 65)

28

Long-lived radioactive dust Radon progeny External Effective

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 221 Average Dose Trends for the Cluff Lake Operation (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

Year

Figure 222 Average Dose Trends for the Cluff Lake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

200

Long-lived radioactive dust Radon progeny External Effective

)S

v(m

e os

D)

Sv

(me

osD

Year

29

600

500

400

300

200

100

0

External Radon progeny Long-lived radioactive dust

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 223 Collective Dose Trends for the Cluff Lake Operation s

erkor

of W

ber

Num

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Year

Figure 224 Distribution o f Effective Doses Among A ll Workers at the Cluff Lake Operation

0

20

40

60

80

100

120

140

160

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

30

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

222 McClean Lake Operation

AREVA Resources Canada Inc runs the McClean Lake mining operation in northeastern Saskatchewan It comprises open pit mines a mill and a tailings management facility Mining began in 1995 while milling started in 1999

Figures 225ndash228 present dose information for the McClean Lake operation from 2001 to 2007

Figure 225 Average Dose Trends for the McClean L ake Operation (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

31

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 226 Average Dose Trends for the McClean L ake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 227 Collective Dose Trends for the McClean L ake Operation

0

100

200

300

400

500

600

700

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External

Radon progeny

Long-lived radioactive dust

Year

32

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 228 Distribution o f Effective Doses Among A ll Workers at the McClean Lake Operation

0

100

200

300

400

500

600

700

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

33

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

223 McArthur River Operation

Cameco Corporation operates the McArthur River underground mine in north-central Saskatchewan Ore from the mine which began production in 1999 is processed at the Key Lake Mill located 80 km south of McArthur River

Figures 229ndash232 present dose information for the McArthur River operation from 2001 to 2007

Figure 229 Average Dose Trends for the McArthur River Operation (Based o n N on-Zero R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

34

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 230 Average Dose Trends for the McArthur River Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

Figure 231 Collective Dose Trends for the McArthur River Operation

0

200

400

600

800

1000

1200

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Radon gas External Radon progeny Long-lived radioactive dust

Year

35

00

0-000

9

001-5

00

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 232 Distribution o f Effective Doses Among A ll Workers at the McArthur River Operation

0

100

200

300

400

500

600

700

800

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

36

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

224 Key Lake Operation

Cameco Corporation operates mining facilities in Key Lake located in north-central Saskatchewan The Key Lake operation includes two mined-out open pit mines (used for tailings management) a mill and two dry tailings management facilities Mining began in 1983 and ceased in 1997 the mill continued to process ore from the McArthur River mine during the reporting period

Figures 233ndash236 present dose information for the Key Lake operation from 2001 to 2007

Figure 233 Average Dose Trends for the Key Lake Operation (Based o n N on-Zero R esults)

00

20

40

60

80

00

20

40

60

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

37

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

00

20

40

60

80

00

20

40

60

Figure 234 Average Dose Trends for the Key Lake Operation (Based o n A ll Monitoring R esults)

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 235 Collective Dose Trends for the Key Lake Operation

0

100

200

300

400

500

600

700

800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External Radon progeny Long-lived radioactive dust

Year

38

00

0-000

9

001-5

0

501-1

000

gt 1001

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 236 Distribution o f Effective Doses Among A ll Workers at the Key Lake Operation

0

200

400

600

800

1000

1200

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose Range (mSv)

39

se

(mS

v)o

D

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

225 Cigar Lake Operation

Cameco Corporation manages the Cigar Lake underground mine located in northern Saskatchewan at the southern end of Waterbury Lake The mine was under construction at the time of this reportrsquos publication Test mining in ore was carried out in 1991 1992 and 2000

Figures 237ndash240 present dose information for the Cigar Lake operation from

Figure 2 37 Average D ose T rends fo r th e C igar L ake O peration (Based on Non-Zero Results)

2001 to 2007

Year

000

005

010

015

020

025

Long-lived radioactive dust Radon Progeny External Effective

40

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 238 Average Dose Trends for the Cigar Lake Operation (Based on All Monitoring Results)

000

005

010

015

020

025

030

035

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny

External

Effective

Year

Figure 239 Collective Dose Trends for the Cigar Lake Operation

0

50

100

150

200

250

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

External Radon progeny Long-lived radioactive dust

Year

41

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 240 Distribution of Effective Doses Among All Workers at the Cigar Lake Operation

0

200

400

600

800

1000

1200

1400

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

42

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

226 Rabbit Lake Operation

Cameco Corporation owns and operates mining facilities in Rabbit Lake located in north-eastern Saskatchewan Facilities include an underground mine four mined-out open-pit mines a mill and two tailings management facilities Mining and milling began in 1975

Figures 241ndash244 present dose information for the Rabbit Lake operation from 2001 to 2007

Figure 241 Average Dose Trends for the Rabbit Lake Operation (Based on Non-Zero Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

43

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 242 Average Dose Trends for the Rabbit Lake Operation (Based on All Monitoring Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

Figure 243 Collective Dose Trends for the Rabbit Lake Operation

0

200

400

600

800

1000

1200

1400

1600

1800

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Radon gas External Radon progeny Long-lived radioactive dust

Year

44

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

gt300

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 244 Distribution of Effective Doses Among All Workers at the Rabbit Lake Operation

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

900

800

700

600

500

400

300

200

100

0

Dose (mSv)

45

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

23 Uranium Refineries This section presents data for the following two facilities

bull a uranium refining facility in Blind River (Section 231) bull a uranium conversion facility in Port Hope (Section 232)

Graphs indicate the following average doses at each facility from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Note on data for uranium refineries

1 Doses from photons from external sources are measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay and lung counting Historically while these internal doses have been measured they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

231 Blind River Refinery

Cameco Corporation owns and is licensed to operate a uranium refinery in Blind River Ontario The facility which began operating in 1983 converts uranium ore concentrate to uranium trioxide The uranium trioxide is shipped to Camecorsquos uranium conversion facility in Port Hope Ontario where it is processed into uranium dioxide (for use in the fabrication of fuel for nuclear reactors in Canada) or uranium hexafluoride (exported for enrichment and fabrication into fuel for nuclear power reactors around the world)

Figures 245ndash248 present dose information for the Blind River refinery from 2001 to 2007

46

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 245 Average Dose Trends for the Blind River Refinery (Based on Non-Zero Results)

0

05

1

15

2

25

Year

Figure 246 Average Dose Trends for the Blind River Refinery (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

47

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 247 Collective Dose Trends for the Blind River Refinery

0

50

100

150

200

250

300 C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 248 Distribution of Effective Doses Among All Workers at the Blind River Refinery

0

20

40

60

80

100

120

140

160

180

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

48

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

232 Port Hope Conversion Facility

Cameco Corporation owns and is licensed to operate a uranium conversion facility in Port Hope Ontario The facility processes uranium trioxide received from the refinery in Blind River into uranium dioxide and uranium hexafluoride

Figures 249ndash252 present dose information for the Port Hope uranium conversion facility from 2001 to 2007

Figure 249 Average Dose Trends for the Port Hope Conversion Facility (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

49

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 250 Average Dose Trends for the Port Hope Conversion Facility (Based on All Monitoring Results)

0

01

02

03

04

05

06

07

08

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 251 Collective Dose Trends for the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

50

000-0

009

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 252 Distribution of Effective Doses Among All Workers at the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

400

450

500

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

51

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

24 Fuel Fabrication Facilities This section presents data for three nuclear fuel fabrication facilities

bull Two facilities owned and operated by General Electric Canada Inc (Section 241) bull One facility in Port Hope operated by Zircatec Precision Industries (Section 242)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average doses

Notes on data for fuel fabrication facilities

1 Effective doses for the three facilities are composed of the following reported components bull dose from photons (labelled on the charts as ldquoexternalrdquo) bull doses from internal intakes of uranium dust (long-lived radioactive dust) from

uranium in air concentrations (for General Electricrsquos Toronto facility only)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components photon doses and doses from long-lived radioactive dust

241 General Electric Nuclear Fuel Facilities

General Electric Canada Inc operates two nuclear fuel facilities in Ontario

bull At the Toronto facility uranium dioxide pellets are produced from natural or depleted uranium dioxide powder

bull At the Peterborough facility uranium dioxide fuel bundles are created from the pellets produced at the Toronto facility

Figures 253ndash256 present dose information for General Electric Canada Incrsquos fuel fabrication facilities from 2001 to 2007 Graphs do not distinguish between the doses received at the Peterborough facility versus those at the Toronto facility

52

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 253 Average Dose Trends for the General Electric Fuel Facility (Based on Non-Zero Results Only)

0

05

1

15

2

25

3

35

Long Lived Radioactive Dust External Effective

Year

Figure 254 Average Dose Trends for the General Electric Fuel Facility (Based on All Monitoring Results)

0

05

1

15

2

25

3

Long Lived Radioactive Dust External Effective

Year

Dos

e (m

Sv)

Dos

e (m

Sv)

53

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 255 Collective Dose Trends for the General Electric Fuel Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Long Lived Radioactive Dust External

Year

Figure 256 Distribution of Effective Doses among all Workers at the General Electric Fuel Facility

0

10

20

30

40

50

60

70

80

90

100

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

54

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

242 Zircatec Nuclear Fuel Facility

Zircatec Precision Industries Inc operates a nuclear fuel facility in Port Hope Ontario where it makes fuel pellets from uranium dioxide powder received from Port Hopersquos uranium conversion facility The nuclear fuel facility also manufactures fuel bundles for nuclear reactors in Canada

Notes on data for the Zircatec nuclear fuel facility

1 Graphs indicate the following data bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of average effective doses

2 Doses from photons from external sources were measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay Historically although these internal doses have been measured and submitted to the CNSC they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

Figures 257ndash260 present dose information for the Zircatec nuclear fuel facility from 2001 to 2007

Figure 257 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on Non-Zero Results)

0

05

1

15

2

25

3

35

Effe

ctiv

e D

ose

(mS

v)

Year

55

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 258 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

18

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 259 Collective Dose Trends for the Zircatec Nuclear Fuel Facility

0

50

100

150

200

250

300

350

400

450

500

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

56

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 260 Distribution of Effective Doses Among All Workers at the Zircatec Nuclear Fuel Facility

300

Num

ber o

f Wor

kers

250

200

150

100

50

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

57

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

25 Research and Radioisotope Production Facilities This section presents dose information for the following research and radioisotope production facilities from 2001 to 2007

bull Chalk River Laboratories and Whiteshell Laboratories (Section 251) bull A radioisotope production facility operated by MDS Nordion (Section 252) bull The Tri-University Meson Facility (TRIUMF) (Section 253)

Note on data for research and radioisotope production facilities

1 Graphs indicate the following data for each facility bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of effective doses

251 Chalk River Laboratories and Whiteshell Laboratories

Atomic Energy of Canada Limited (AECL) owns and is licensed to operate Chalk River Laboratories and Whiteshell Laboratories

Situated in Renfrew County on the south shore of the Ottawa River the Chalk River Laboratories site hosts the National Research Universal Reactor along with numerous other facilities occupying some 160 buildings in an area of approximately 40 km2 Activities consist of radioisotope production for nuclear medicine testing and development of structural materials in support of power reactor operations fuel fabrication research and radioactive waste management and storage

The Whiteshell Laboratories site is located approximately 10 km west of Pinawa Manitoba and 100 km northeast of Winnipeg on the east bank of the Winnipeg River AECL established the laboratories for nuclear research and testing during the early 1960s and has since discontinued operations which are being decommissioned under a licence from the CNSC

Figures 261ndash264 present dose information for Chalk River Laboratories and Whiteshell Laboratories from 2001 to 2007

Notes on data for Chalk River Laboratories and Whiteshell Laboratories

1 Effective doses are composed of the following reported components bull external doses5 (from both photon and neutron doses) bull tritium doses

Due to issues with AECLrsquos in-house dosimetry management system neutron doses were not reported separately to the NDR during the reporting period As a result external doses from photons and neutrons were totaled The reporting discrepancy has since been rectified

58

5

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of external (photon and neutron) and tritium doses Intakes of other radionuclides occasionally occur and these radionuclides are not included here because their associated doses are very small For this reason certain collective doses in this report may have values slightly lower than the sum of their respective components as listed

Figure 261 Average Dose Trends for Chalk River and Whiteshell Laboratories (Non-Zero Results Only)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Tritium External Effective

Year

59

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 262 Average Dose Trends for Chalk River and Whiteshell Laboratories (All Monitoring Results)

000

020

040

060

080

100

120

Dos

e (m

Sv)

Tritium External Effective

Year

Figure 263 Collective Dose Trends for Chalk River and Whiteshell Laboratories

0

500

1000

1500

2000

2500

3000

3500

Col

lect

ive

Dos

e (p

erso

n- m

Sv)

External Tritium

Year

60

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 264 Distribution of Effective Doses Among All Workers at Chalk River and Whiteshell Laboratories

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

3500

3000

2500

2000

1500

1000

500

Dose (mSv)

61

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

252 MDS Nordion (Nuclear Substance Processing Facility and Canadian Irradiation Centre)

MDS Nordion owns and operates a nuclear substance processing facility in Ottawa Ontario where it processes unsealed radioisotopes and manufactures sealed radiation sources In operation since the early 1970s the facility was purchased by Nordion International in 1991

In cooperation with the Universiteacute du Queacutebecrsquos Institut Armand-Frappier MDS Nordion also operates the Canadian Irradiation Centre which conducts various irradiation services which include training testing and development The centre is located in Laval Quebec on the Universiteacute du Queacutebec campus

Figures 265ndash268 present dose information for MDS Nordionrsquos Ottawa nuclear substance processing facility and for the Canadian Irradiation Centre from 2001 to 2007

Notes on data for MDS Nordionrsquos nuclear substance processing facility and the Canadian Irradiation Centre

1 Doses from photons from external sources were measured and reported to the NDR MDS Nordion also has a routine thyroid monitoring program very occasionally small recordable doses of radiation have occurred from thyroid uptake of iodine The resulting doses have not been historically submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided

Figure 265 Average Dose Trends for MDS Nordion (Based on Non-Zero Results)

0

05

1

15

2

25

Effe

ctiv

e D

ose

(mS

v)

Year

62

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 266 Average Dose Trends for MDS Nordion (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

Figure 267 Collective Dose Trends for MDS Nordion

0

100

200

300

400

500

600

700

800

Year

63

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 268 Distribution of Effective Doses Among All Workers at MDS Nordion

0

5 0

1 0 0

1 5 0

2 0 0

2 5 0

3 0 0

3 5 0

4 0 0

4 5 0

5 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

64

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

253 Tri-University Meson Facility

The Tri-University Meson facility (TRIUMF) is situated in Vancouver on the campus of the University of British Columbia TRIUMF which began operating in the early 1970s with one cyclotron now has two cyclotrons and associated laboratories for research and radioisotope production The laboratory provides research facilities for Canadian and international users and also produces radioisotopes which are used by medical facilities and by a commercial organization (MDS Nordion) MDS Nordion staff also work at the TRIUMF site however MDS Nordion oversees this work and has its own radiation protection program

Figures 269ndash272 present dose information for the TRIUMF facility from 2001 to 2007 Please note that data sets do not distinguish between doses received by TRIUMF staff and MDS Nordion staff who work on the site as the data for these two groups was submitted collectively to the NDR for the reporting period shown Future data for each group will be submitted separately to the NDR

Note on data for TRIUMF

1 Effective doses are composed of the following reported components bull doses from photons (labeled as ldquoexternalrdquo in the charts) bull neutron doses

Figure 269 Average Dose Trends for TRIUMF (Non-Zero Results Only)

000

020

040

060

080

100

120

140

160

Dos

e (m

Sv)

Neutrons External Effective

Year

65

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 5: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

List of Figures

Figures 11ndash114 Facility-wide Average Doses

Figures 21ndash24 Bruce Nuclear Generating Stations Figures 25ndash28 Pickering Nuclear Generating Stations Figures 29ndash212 Darlington Nuclear Generating Station Figures 213ndash216 Gentilly-2 Nuclear Generating Station Figures 217ndash220 Point Lepreau Nuclear Generating Station

Figures 221ndash224 Cluff Lake Operation Figures 225ndash228 McClean Lake Operation Figures 229ndash232 McArthur River Operation Figures 233ndash236 Key Lake Operation Figures 237ndash240 Cigar Lake Operation Figures 241ndash244 Rabbit Lake Operation

Figures 245ndash248 Blind River Refinery Figures 249ndash252 Port Hope Conversion Facility

Figures 253ndash256 General Electric Nuclear Fuel Facilities Figures 257ndash260 Zircatec Nuclear Fuel Facility

Figures 261ndash264 Chalk River Laboratories and Whiteshell Laboratories Figures 265ndash268 MDS Nordion Figures 269ndash272 Tri-University Meson Facility (TRIUMF)

Figures 273ndash276 Shield Source Incorporated Figures 277ndash280 SRB Technologies (Canada) Inc

Table 1 Effective Dose Limits in Canada as Specified by the Radiation Protection Regulations Person Period Effective Dose

(mSv) Nuclear energy workers including pregnant (a) One-year dosimetry period 50 nuclear energy workers

(b) Five-year dosimetry period 100 Pregnant nuclear energy worker Balance of the pregnancy 4

A person who is not a nuclear energy worker One calendar year 1

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Introduction Workers at nuclear facilities are exposed to radiation Their dose is monitored and subject to Canadian Nuclear Safety Commission (CNSC) regulatory requirements which aim to protect their health and safety The amount of radiation to which employees are exposed is referred to as ldquooccupational doserdquo This report provides an overview of occupational radiation doses from 2001 to 2007 at the major nuclear facilities licensed by the CNSC It presents an objective summary of occupational dose information and includes a glossary of terminology

The data collected shows that the average doses for all facilities are far below the individual annual effective dose limit of 50 milliSieverts (mSv) set out in the Radiation Protection Regulations

The report includes data for the following types of facilities

bull nuclear power plants bull uranium mines and mills bull uranium refineries bull fuel fabrication facilities bull research and radioisotope production facilities bull tritium light source production facilities

Each facility is unique in regards to the type of work performed as well its current lifecycle stage (ie operating at reduced or full capacity or in a phase of refurbishment for example) and each provides varying programs to mitigate radiation doses to workers The resulting collective and average doses are based on complex and differing work environments Therefore direct comparisons between facilities in terms of occupational dose are not possible

Regulatory Radiation Dose Limits The Radiation Protection Regulations limit the amount of radiation to which persons may be exposed Table 1 presents the effective dose limits as set out in paragraphs 13 and 14 of the regulations

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

The Radiation Protection Regulations also require CNSC licensees to implement radiation protection programs and to keep radiation doses as low as reasonably achievable (a concept referred to as the ALARA principle) The CNSC evaluates licensee radiation protection programs and these evaluations include reviews of the occupational dose data which is one among several indicators of a radiation protection programrsquos effectiveness

About the Data

Source Statistics in this document are gathered from the National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses1 Maintained by Health Canadarsquos Radiation Protection Bureau the NDR publishes annual reports on occupational dose information and trends according to job type

Due to the large number of CNSC-licensed facilities this report does not include occupational dose information for every CNSC licensees Please refer to the NDR Web site2 to review Health Canadarsquos reports

Analysis This report presents the following types of data

a average doses b collective doses c distribution of effective doses

a Average doses provide a common means of indicating central tendencies of dose distribution and show where doses lie on average with respect to annual dose limits

Notes on average effective doses

1 This report presents two types3 of arithmetic averages for individual effective doses bull averages that include only non-zero (positive) results bull averages that include all monitoring results (including zero-value doses)

2 When assessing regulatory compliance individual doses mdash not average doses mdash must be compared to individual dose limits in the Radiation Protection Regulations

1 In Canada the Radiation Protection Regulations require licensed dosimetry services to submit dose information for nuclear energy workers (NEWs) While not required by law dose information for non-NEWs is also typically submitted to the NDR The data in this report does not distinguish between personnel designated as NEWs versus those who are not 2 httpwwwhc-scgccaewh-semtoccup-travailradiationregistindex_ehtml 3 Some licensees monitor most or all workers (including those unlikely to be directly exposed to sources of occupational radiation) whereas other licensees monitor only employees likely to receive radiation doses Therefore two types of averages are presented averages that consider only non-zero results and averages that consider all results Both statistical approaches have merit and are included in this report (Note The exclusion of zero value doses in the averaging could unfairly bias findings against licensees with effective radiation protection programs)

2

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

b Collective doses indicate the sum of all the doses associated with a facilityrsquos operation and can be used to estimate a facilityrsquos control of occupational doses

Note on collective doses

1 The Radiation Protection Regulations do not set limits on collective doses however the CNSC recommends that licensee radiation protection programs should aim to reduce collective doses These values can indicate a facilityrsquos radiological detriment and help assess whether a facility is operating in accordance with the ALARA principle

c Distribution of effective doses shows the ranges in which effective doses are concentrated

Effective dose calculations By definition effective doses cannot be measured precisely but they can be approximated in order to determine radiation exposure and to assess the associated risks Section 13 of the Radiation Protection Regulations defines the dose calculation methods used to determine effective doses as expressed in millisieverts (mSv) which are based on measurable quantities in the operational environment

Effective radiation doses are made up of various components of which the most common (in Canada) are as follows

bull photons and neutrons from sources outside the body bull radon progeny radon gas long-lived radioactive dust (uranium dust) and tritium that are

taken into the body

The effective doses reported to the NDR represent the sum of their applicable components For example the effective dose to a worker who received radiation doses from both neutrons and tritium would be the sum of these two quantities

Note on average dose values

1 Average values for each dose type (for example tritium) are based on the total collective dose for that type divided by the number of all the workers monitored for any dose type

3

yrenfi R

erev

Ri

dnilB

noid N

orD

SM

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

10 Facility-Wide Comparisons of Average Effective Doses This section presents comparisons of average effective doses at all CNSC-licensed nuclear facilities included in this report for each year within the 2001ndash07 reporting period

bull Figures 11ndash17 present averages based on non-zero (positive) results (Section 11)bull Figures 18ndash114 present averages based on all monitoring results (Section 12)

Notes on facility-wide comparisons of average effective doses

1 Each facility type is represented by a different colour bull nuclear power plants ndash green bull uranium mines and mills ndash purple bull uranium refineries ndash yellow bull fuel fabrication facilities ndash orange bull research and radioisotope facilities ndash blue bull tritium light source production facilities ndash red

2 See Sections 21ndash26 for facility-specific data depicted in Figures 11ndash114

11 Average Effective Doses Based on Non-Zero Results at All Selected Facilities Figures 11ndash17 show average effective doses based on non-zero results for each year from 2001 to 2007 for all the facilities presented in this document

Figure 11 Average Effective Doses at All Selected F acilities for the Year 2001 (Based o n N on-Zero R esults)

4

35

3

25

2

15

1

05

0

) Sv

(me

osD

Bruc

e N

ucle

ar G

ener

atin

g St

atio

ns snotita

Sgntiarene Graelc

Nu

gnirekciP

notita

Sgntiarene Graelc

Nu

ntognilr

Da

notita

Sgntiarene Graelc

Nu

2-ylltineG

notita

Sgntiarene Graelc

Nu

uaerpet LnioP

notiarep Oeka

ff L

uC

l

notiarep Oeka

LnaeC

lc

M

rev R

iru

thrAcM

notiarep Oeka

LyeK

notiarep Oeka

LragC

i

notiarep Oeka

it L

bbR

a

tyilica Fnoisrevn

Co

ept H

oroP

setiilica Fleu

Fraelc N

ucitrcel

ElareneG

tyilical Feu

Fraelc N

uc

teacriZ

Cha

lk R

iver

Lab

orat

orie

s an

d W

hite

shel

lLa

bora

torie

s

tyilica Fnose

Mtyisrev

Uni

-irT

dtearoproc

Inecruo SdleihS

c In)adan

Ca

(seigolonhce T

RB

S

4

y

s n

Dos

e (m

Sv)

) Sv

(me

osD

4

35

3

25

2

15

1

05

0

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 12 Average Effective Doses at All Selected Facilities for the Year 2002 (Based on Non-Zero Results)

4

35

3

25

2

15

1

05

0

Bruc

e N

ucle

ar G

ener

atin

g St

atio

nsBr

uce

Nuc

lear

Gen

erat

ing

Stat

ions

Pick

erin

g N

ucle

ar G

ener

atin

g St

atio

n

Dar

lingt

on N

ucle

ar G

ener

atin

g St

atio

n

Gen

tilly

-2 N

ucle

ar G

ener

atin

g St

atio

n

Poin

t Lep

reau

Nuc

lear

Gen

erat

ing

Stat

ion

Clu

ff La

ke O

pera

tion

McC

lean

Lak

e O

pera

tio

McA

rthur

Riv

er

Key

Lake

Ope

ratio

n

Cig

ar L

ake

Ope

ratio

n

Rab

bit L

ake

Ope

ratio

n

Blin

d R

iver

Ref

iner

y

Port

Hop

e C

onve

rsio

n Fa

cilit

y

Gen

eral

Ele

ctric

Nuc

lear

Fue

l Fac

ilitie

s

Zirc

atec

Nuc

lear

Fue

l Fac

ility llehs

teih Wdn

a ses ie rir toto ara or bo ab La

Lrev R

ikla

Ch

MD

S N

ordi

on

Tri- U

nive

rsity

Mes

on F

acilit

y

Figure 13 Average Effective Doses at All Selected Facilities for the Year 2003 (Based on Non-Zero Results)

Pick

erin

g N

ucle

ar G

ener

atin

g St

atio

ns

Dar

lingt

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Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 14 Average Effective Doses at All Selected Facilities for the Year 2004 (Based on Non-Zero Results)

4

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Figure 15 Average Effective Doses at All Selected Facilities for the Year 2005 (Based on Non-Zero Results)

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Figure 17 Average Effective Doses at All Selected Facilities for the Year 2007 (Based on Non-Zero Results)

4

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Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 16 Average Effective Doses at All Selected Facilities for the Year 2006 (Based on Non-Zero Results)

4

35

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Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

12 Average Effective Doses Based on All Monitoring Results at All Selected Facilities Figures 18ndash114 show average effective doses based on all the monitoring results for each year from 2001 to 2007 for every facility listed in this document

Figure 18 Average Effective Doses at All Selected F acilities for the Year 2001 (Based o n A ll Monitoring R esults)

8

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Figure 110 Average Effective Doses at All Selected F acilities for the Year 2003 (Based o n A ll Monitoring R esults)

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Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 19 Average Effective Doses at All Selected Facilities for the Year 2002 (Based on All Monitoring Results)

4

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Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 111 Average Effective Doses at All Selected F acilities for the Year 2004 (Based o n A ll Monitoring R esults)

4

35

3

25

2

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Figure 112 Average Effective Doses at All Selected F acilities for the Year 2005 (Based o n A ll Monitoring R esults)

4

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4

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Figure 114 Average Effective Doses at All Selected F acilities for the Year 2007 (Based o n A ll Monitoring R esults)

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Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 113 Average Effective Doses at All Selected Facilities for the Year 2006 (Based on All Monitoring Results)

4

35

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(Can

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11

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

20 Facility-Specific Overview of Occupational Doses This section presents data for the following types of facilities

bull nuclear power plants (Section 21) bull uranium mines and mills (Section 22) bull uranium refineries (Section 23) bull fuel fabrication facilities (Section 24) bull research and radioisotope production facilities (Section 25) bull tritium production facilities (Section 26)

21 Nuclear Power Plants This section presents dose information for the following nuclear power plants

bull Bruce A and Bruce B Nuclear Generating Stations (Section 211) bull Pickering Nuclear Generating Stations (Section 212) bull Darlington Nuclear Generating Station Section 213) bull Gentilly-2 Nuclear Generating Station (Section 214) bull Point Lepreau Generating Station (Section 215)

Graphs in this section indicate the following data for each nuclear power plant from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for nuclear power plants

1 Effective doses are composed of the following reported components bull doses from photons (labeled on the charts as ldquoexternalrdquo) bull neutron doses bull tritium doses

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of photon neutron and tritium doses Intakes of other radionuclides (for example Iodine-131 or Carbon-14) occasionally occur but these radionuclides are not included here because the associated collective dose is very small For this reason certain collective dose values in this report may be slightly lower than the sum of their respective components as listed

12

1 2 3 4 5 6 70 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

211 Bruce Nuclear Generating Stations

Bruce Power owns and operates the Bruce Nuclear Generating Stations located near Kincardine Ontario on the shore of Lake Huron

bull Bruce A consists of four nuclear reactors (units 1ndash4) and began operating in 1976 bull Bruce B has four nuclear reactors (units 5ndash8) and started operating in 1984

As part of its extensive recovery program in 1997 the sitersquos previous operator Ontario Hydro (now Ontario Power Generation) temporarily shut down all Bruce A reactors and maintained them in a guaranteed shutdown state Units 3 and 4 were later returned to service (in October 2003 and January 2004) while Units 1 and 2 remained in a guaranteed shutdown state

Figures 21ndash24 present dose information for the Bruce Nuclear Generating Stations from 2001 to 2007 Graphs do not distinguish between doses received at Bruce A versus Bruce B

Fig 21 Average Dose Trends for Bruce Nuclear Generating Stati on (Based o n N on-Zero R esults)

Dos

e (m

Sv)

4

35

3

25

2

15

1

05

0

Tritium Neutron External Effective

Year

13

Neutrons External Tritium

0 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 21 2 3 4 5 6 7

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

0

2

4

6

8

1

2

4

0

0

0

0

1

1

Figure 22 Average Dose Trends for Bruce Nuclear Generating Stati on (Based o n A ll Monitoring R esults)

16

)S

v(m

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D

Tritium Neutrons External Effective

Year

Figure 23 Collective Dose Trends for Bruce Nuclear Generating Stati on

8000

7000

6000

5000

4000

3000

2000

1000

0

)S

von

-m(p

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De

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C

Year

14

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 24 Distribution of Effective Doses Among All Workers at Bruce Nuclear Generating Station

6000

5000

4000

3000

2000

1000

0 9 0 0

1-50 0 0 1 0 0 0 0 00 5 0 0 0

0-000

000 1-1 1-1 1-20 1-3 3gt0 0 0 05 0 5 01 1 2

Num

ber o

f Wor

kers

Dose Range (mSv)

15

1 2 3 4 5 6 7 0 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

212 Pickering Nuclear Generating Stations

Located in Pickering Ontario the Pickering Nuclear Generating Stations are owned and operated by Ontario Power Generation Two generating stations are located within one enclosure

bull Pickering A consists of four nuclear reactors (units 1 to 4) that began operating in 1971 bull Pickering B consists of four nuclear reactors (units 5 to 8) that began operating in 1982

As part of its extensive recovery program Ontario Hydro (now Ontario Power Generation) temporarily shut down all Pickering A reactors in 1997 and maintained them in a guaranteed shutdown state Unit 4 was restarted in September 2003 and Unit 1 was restarted in March 2005 Units 2 and 3 remain in a guaranteed shutdown state

Figures 25ndash28 present dose information for the Pickering Nuclear Generating Stations from 2001 to 2007 Graphs do not distinguish between doses received at Pickering A versus those received at Pickering B

Figure 25 Average Dose Trends for Pickering N uclear Generating Stati on (Based o n N on-Zero R esults)

25

2

15

1

05

0

)S

v(m

e os

D

Tritium Neutrons External Effective

Year

16

Tritium Neutrons External Effective

Neutrons External Tritium

1 2 3 4 5 6 70 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

1 2 3 4 5 6 7 0 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 26 Average Dose Trends for Pickering N uclear Generating Stati on (Based o n A ll Monitoring R esults)

12

1

08

06

04

02

0

Year

Figure 27 Collective Dose Trends for Pickering N uclear Generating Stati on

12000

10000

8000

6000

4000

2000

0

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

)

Sv

(me

osD

Year

17

2001 2002 2003 2004 2005 2006 2007

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 28 Distribution o f Effective Doses Among A ll Workers at Pickering Nuclear Generating Stati on

6000

5000

4000

3000

2000

1000

0

Num

ber o

f Wor

kers

Dose Range (mSv)

18

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

213 Darlington Nuclear Generating Station

Owned and operated by Ontario Power Generation the Darlington Nuclear Generating Station has four nuclear reactors the first of which began operating in 1989 The facility is located near Bowmanville on the shore of Lake Ontario

Figures 29ndash212 present dose information for the Darlington Nuclear Generating Station from 2001 to 2007

Figure 29 Average Dose Trends for Darlington N uclear Generating Stati on (Non- Zero R esults Only)

)S

v(m

e os

D

250

200

150

100

050

000

Year

19

Tritium Neutrons External Effective

Neutrons External Tritium

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 210 Average Dose Trends for Darlington N uclear Generating Stati on (All Monitoring R esults)

090

080

070

060

050

040

030

020

010

000

)S

v(m

e os

D

Year

Figure 211 Collective Dose Trends for Darlington N uclear Generating Stati on

4500

4000

3500

3000

2500

2000

1500

1000

500

0

)vSm-nosrep (es

Do

eiv

llect

Co

Year

20

2001 2002 2003 2004 2005 2006 2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 212 Distribution o f Effective Doses Among A ll Workers at Darlington Nuclear Generating Stati on

0

500

1000

1500

2000

2500

3000

3500

ers

ork

W of

be

r um

N

Dose Range (mSv)

21

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

214 Gentilly-2 Nuclear Generating Station

The Gentilly-2 Nuclear Generating Station owned and operated by Hydro-Queacutebec has a single reactor that began operating in 1982 The facility is located on the south shore of the St Lawrence River near Trois-Riviegraveres Queacutebec

Figures 213ndash216 present dose information for the Gentilly-2 Nuclear Generating Station from 2001 to 2007

Figure 213 Average Dose Trends for Gentilly-2 Nuclear Generating Stati on (Based o n N on-Zero R esults)

0

05

1

15

2

25

3

35

4

45

)S

v(m

e os

D

Year

22

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 214 Average Dose Trends for Gentilly-2 Nuclear Generating Stati on (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

)S

v(m

e os

D

Year

Figure 215 Collective Dose Trends for Gentilly-2 Nuclear Generating Stati on

0

500

1000

1500

2000

2500

3000

3500

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Neutrons

External

Tritium

Year

23

000-0

009

001-5

00

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 216 Distribution of Effective Doses Among All Workers at Gentilly-2 Nuclear Generating Station

2500

2000

1500

1000

500

0

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

24

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

215 Point Lepreau Nuclear Generating Station

The Point Lepreau Nuclear Generating Station has one reactor that began operating in 1982 Owned and operated by New Brunswick Power Nuclear the station is located in Point Lepreau New Brunswick about 40 km west of Saint John on the shores of the Bay of Fundy

Figures 217ndash220 present dose information for the Point Lepreau Nuclear Generating Station from 2001 to 2007

Figure 217 Average Dose Trends for Point Lepreau N uclear Generating Stati on (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

)S

v(m

e os

D

Tritium Neutron External Effective

Year

25

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 218 Average Dose Trends for Point Lepreau N uclear Generating Stati on (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

)S

v(m

e os

D

Tritium Neutrons External Effective

Year

Figure 219 Collective Dose Trends for Point Lepreau N uclear Generating Station

0

200

400

600

800

1000

1200

1400

1600

1800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Neutrons

External

Tritium

Year

26

0

1400

1200

1000

800

600

400

200

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 220 Distribution of Effective Doses Among All Workers at Point Lepreau Nuclear Generating Station

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

27

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

22 Uranium Mines and Mills This section presents dose information for mine and mill sites in the following regions

bull Cluff Lake (Section 221) bull McClean Lake (Section 222) bull McArthur River (Section 223) bull Key Lake (Section 224) bull Cigar Lake (Section 225) bull Rabbit Lake (Section 226)

Graphs indicate the following data for each site from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for uranium mines and mills

1 Effective doses are composed of the following reported components bull doses from photons (labelled on the charts as ldquoexternalrdquo) bull doses from radon progeny bull doses from long-lived radioactive dust bull doses from radon gas (in some cases)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of photon radon progeny long-lived radioactive dust and radon gas doses

3 The NDR lists radon progeny in working level months (WLM) For this report radon progeny exposures were converted4 to doses expressed in mSv

221 Cluff Lake Operation

The Cluff Lake mining facilities operated by AREVA Resources Canada Inc are located in northwestern Saskatchewan Work began in 1980 and ended in 2002 with the site now being decommissioned The site consisted of three open-pit and two underground mines a mill and a tailings management facility During 2005 and 2006 most of the infrastructure was removed and the affected areas were remediated

Figures 221ndash224 present dose information for the Cluff Lake operation from 2001 to 2007

4 Doses were converted using the International Commission on Radiation Protection (ICRP)rsquos conversion convention of 1 WLM = 5 mSv This convention was established in the ICRP publication Protection against Radon at Home and at Work (ICRP 65)

28

Long-lived radioactive dust Radon progeny External Effective

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 221 Average Dose Trends for the Cluff Lake Operation (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

Year

Figure 222 Average Dose Trends for the Cluff Lake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

200

Long-lived radioactive dust Radon progeny External Effective

)S

v(m

e os

D)

Sv

(me

osD

Year

29

600

500

400

300

200

100

0

External Radon progeny Long-lived radioactive dust

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 223 Collective Dose Trends for the Cluff Lake Operation s

erkor

of W

ber

Num

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Year

Figure 224 Distribution o f Effective Doses Among A ll Workers at the Cluff Lake Operation

0

20

40

60

80

100

120

140

160

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

30

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

222 McClean Lake Operation

AREVA Resources Canada Inc runs the McClean Lake mining operation in northeastern Saskatchewan It comprises open pit mines a mill and a tailings management facility Mining began in 1995 while milling started in 1999

Figures 225ndash228 present dose information for the McClean Lake operation from 2001 to 2007

Figure 225 Average Dose Trends for the McClean L ake Operation (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

31

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 226 Average Dose Trends for the McClean L ake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 227 Collective Dose Trends for the McClean L ake Operation

0

100

200

300

400

500

600

700

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External

Radon progeny

Long-lived radioactive dust

Year

32

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 228 Distribution o f Effective Doses Among A ll Workers at the McClean Lake Operation

0

100

200

300

400

500

600

700

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

33

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

223 McArthur River Operation

Cameco Corporation operates the McArthur River underground mine in north-central Saskatchewan Ore from the mine which began production in 1999 is processed at the Key Lake Mill located 80 km south of McArthur River

Figures 229ndash232 present dose information for the McArthur River operation from 2001 to 2007

Figure 229 Average Dose Trends for the McArthur River Operation (Based o n N on-Zero R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

34

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 230 Average Dose Trends for the McArthur River Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

Figure 231 Collective Dose Trends for the McArthur River Operation

0

200

400

600

800

1000

1200

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Radon gas External Radon progeny Long-lived radioactive dust

Year

35

00

0-000

9

001-5

00

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 232 Distribution o f Effective Doses Among A ll Workers at the McArthur River Operation

0

100

200

300

400

500

600

700

800

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

36

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

224 Key Lake Operation

Cameco Corporation operates mining facilities in Key Lake located in north-central Saskatchewan The Key Lake operation includes two mined-out open pit mines (used for tailings management) a mill and two dry tailings management facilities Mining began in 1983 and ceased in 1997 the mill continued to process ore from the McArthur River mine during the reporting period

Figures 233ndash236 present dose information for the Key Lake operation from 2001 to 2007

Figure 233 Average Dose Trends for the Key Lake Operation (Based o n N on-Zero R esults)

00

20

40

60

80

00

20

40

60

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

37

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

00

20

40

60

80

00

20

40

60

Figure 234 Average Dose Trends for the Key Lake Operation (Based o n A ll Monitoring R esults)

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 235 Collective Dose Trends for the Key Lake Operation

0

100

200

300

400

500

600

700

800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External Radon progeny Long-lived radioactive dust

Year

38

00

0-000

9

001-5

0

501-1

000

gt 1001

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 236 Distribution o f Effective Doses Among A ll Workers at the Key Lake Operation

0

200

400

600

800

1000

1200

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose Range (mSv)

39

se

(mS

v)o

D

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

225 Cigar Lake Operation

Cameco Corporation manages the Cigar Lake underground mine located in northern Saskatchewan at the southern end of Waterbury Lake The mine was under construction at the time of this reportrsquos publication Test mining in ore was carried out in 1991 1992 and 2000

Figures 237ndash240 present dose information for the Cigar Lake operation from

Figure 2 37 Average D ose T rends fo r th e C igar L ake O peration (Based on Non-Zero Results)

2001 to 2007

Year

000

005

010

015

020

025

Long-lived radioactive dust Radon Progeny External Effective

40

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 238 Average Dose Trends for the Cigar Lake Operation (Based on All Monitoring Results)

000

005

010

015

020

025

030

035

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny

External

Effective

Year

Figure 239 Collective Dose Trends for the Cigar Lake Operation

0

50

100

150

200

250

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

External Radon progeny Long-lived radioactive dust

Year

41

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 240 Distribution of Effective Doses Among All Workers at the Cigar Lake Operation

0

200

400

600

800

1000

1200

1400

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

42

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

226 Rabbit Lake Operation

Cameco Corporation owns and operates mining facilities in Rabbit Lake located in north-eastern Saskatchewan Facilities include an underground mine four mined-out open-pit mines a mill and two tailings management facilities Mining and milling began in 1975

Figures 241ndash244 present dose information for the Rabbit Lake operation from 2001 to 2007

Figure 241 Average Dose Trends for the Rabbit Lake Operation (Based on Non-Zero Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

43

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 242 Average Dose Trends for the Rabbit Lake Operation (Based on All Monitoring Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

Figure 243 Collective Dose Trends for the Rabbit Lake Operation

0

200

400

600

800

1000

1200

1400

1600

1800

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Radon gas External Radon progeny Long-lived radioactive dust

Year

44

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

gt300

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 244 Distribution of Effective Doses Among All Workers at the Rabbit Lake Operation

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

900

800

700

600

500

400

300

200

100

0

Dose (mSv)

45

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

23 Uranium Refineries This section presents data for the following two facilities

bull a uranium refining facility in Blind River (Section 231) bull a uranium conversion facility in Port Hope (Section 232)

Graphs indicate the following average doses at each facility from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Note on data for uranium refineries

1 Doses from photons from external sources are measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay and lung counting Historically while these internal doses have been measured they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

231 Blind River Refinery

Cameco Corporation owns and is licensed to operate a uranium refinery in Blind River Ontario The facility which began operating in 1983 converts uranium ore concentrate to uranium trioxide The uranium trioxide is shipped to Camecorsquos uranium conversion facility in Port Hope Ontario where it is processed into uranium dioxide (for use in the fabrication of fuel for nuclear reactors in Canada) or uranium hexafluoride (exported for enrichment and fabrication into fuel for nuclear power reactors around the world)

Figures 245ndash248 present dose information for the Blind River refinery from 2001 to 2007

46

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 245 Average Dose Trends for the Blind River Refinery (Based on Non-Zero Results)

0

05

1

15

2

25

Year

Figure 246 Average Dose Trends for the Blind River Refinery (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

47

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 247 Collective Dose Trends for the Blind River Refinery

0

50

100

150

200

250

300 C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 248 Distribution of Effective Doses Among All Workers at the Blind River Refinery

0

20

40

60

80

100

120

140

160

180

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

48

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

232 Port Hope Conversion Facility

Cameco Corporation owns and is licensed to operate a uranium conversion facility in Port Hope Ontario The facility processes uranium trioxide received from the refinery in Blind River into uranium dioxide and uranium hexafluoride

Figures 249ndash252 present dose information for the Port Hope uranium conversion facility from 2001 to 2007

Figure 249 Average Dose Trends for the Port Hope Conversion Facility (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

49

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 250 Average Dose Trends for the Port Hope Conversion Facility (Based on All Monitoring Results)

0

01

02

03

04

05

06

07

08

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 251 Collective Dose Trends for the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

50

000-0

009

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 252 Distribution of Effective Doses Among All Workers at the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

400

450

500

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

51

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

24 Fuel Fabrication Facilities This section presents data for three nuclear fuel fabrication facilities

bull Two facilities owned and operated by General Electric Canada Inc (Section 241) bull One facility in Port Hope operated by Zircatec Precision Industries (Section 242)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average doses

Notes on data for fuel fabrication facilities

1 Effective doses for the three facilities are composed of the following reported components bull dose from photons (labelled on the charts as ldquoexternalrdquo) bull doses from internal intakes of uranium dust (long-lived radioactive dust) from

uranium in air concentrations (for General Electricrsquos Toronto facility only)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components photon doses and doses from long-lived radioactive dust

241 General Electric Nuclear Fuel Facilities

General Electric Canada Inc operates two nuclear fuel facilities in Ontario

bull At the Toronto facility uranium dioxide pellets are produced from natural or depleted uranium dioxide powder

bull At the Peterborough facility uranium dioxide fuel bundles are created from the pellets produced at the Toronto facility

Figures 253ndash256 present dose information for General Electric Canada Incrsquos fuel fabrication facilities from 2001 to 2007 Graphs do not distinguish between the doses received at the Peterborough facility versus those at the Toronto facility

52

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 253 Average Dose Trends for the General Electric Fuel Facility (Based on Non-Zero Results Only)

0

05

1

15

2

25

3

35

Long Lived Radioactive Dust External Effective

Year

Figure 254 Average Dose Trends for the General Electric Fuel Facility (Based on All Monitoring Results)

0

05

1

15

2

25

3

Long Lived Radioactive Dust External Effective

Year

Dos

e (m

Sv)

Dos

e (m

Sv)

53

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 255 Collective Dose Trends for the General Electric Fuel Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Long Lived Radioactive Dust External

Year

Figure 256 Distribution of Effective Doses among all Workers at the General Electric Fuel Facility

0

10

20

30

40

50

60

70

80

90

100

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

54

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

242 Zircatec Nuclear Fuel Facility

Zircatec Precision Industries Inc operates a nuclear fuel facility in Port Hope Ontario where it makes fuel pellets from uranium dioxide powder received from Port Hopersquos uranium conversion facility The nuclear fuel facility also manufactures fuel bundles for nuclear reactors in Canada

Notes on data for the Zircatec nuclear fuel facility

1 Graphs indicate the following data bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of average effective doses

2 Doses from photons from external sources were measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay Historically although these internal doses have been measured and submitted to the CNSC they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

Figures 257ndash260 present dose information for the Zircatec nuclear fuel facility from 2001 to 2007

Figure 257 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on Non-Zero Results)

0

05

1

15

2

25

3

35

Effe

ctiv

e D

ose

(mS

v)

Year

55

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 258 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

18

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 259 Collective Dose Trends for the Zircatec Nuclear Fuel Facility

0

50

100

150

200

250

300

350

400

450

500

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

56

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 260 Distribution of Effective Doses Among All Workers at the Zircatec Nuclear Fuel Facility

300

Num

ber o

f Wor

kers

250

200

150

100

50

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

57

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

25 Research and Radioisotope Production Facilities This section presents dose information for the following research and radioisotope production facilities from 2001 to 2007

bull Chalk River Laboratories and Whiteshell Laboratories (Section 251) bull A radioisotope production facility operated by MDS Nordion (Section 252) bull The Tri-University Meson Facility (TRIUMF) (Section 253)

Note on data for research and radioisotope production facilities

1 Graphs indicate the following data for each facility bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of effective doses

251 Chalk River Laboratories and Whiteshell Laboratories

Atomic Energy of Canada Limited (AECL) owns and is licensed to operate Chalk River Laboratories and Whiteshell Laboratories

Situated in Renfrew County on the south shore of the Ottawa River the Chalk River Laboratories site hosts the National Research Universal Reactor along with numerous other facilities occupying some 160 buildings in an area of approximately 40 km2 Activities consist of radioisotope production for nuclear medicine testing and development of structural materials in support of power reactor operations fuel fabrication research and radioactive waste management and storage

The Whiteshell Laboratories site is located approximately 10 km west of Pinawa Manitoba and 100 km northeast of Winnipeg on the east bank of the Winnipeg River AECL established the laboratories for nuclear research and testing during the early 1960s and has since discontinued operations which are being decommissioned under a licence from the CNSC

Figures 261ndash264 present dose information for Chalk River Laboratories and Whiteshell Laboratories from 2001 to 2007

Notes on data for Chalk River Laboratories and Whiteshell Laboratories

1 Effective doses are composed of the following reported components bull external doses5 (from both photon and neutron doses) bull tritium doses

Due to issues with AECLrsquos in-house dosimetry management system neutron doses were not reported separately to the NDR during the reporting period As a result external doses from photons and neutrons were totaled The reporting discrepancy has since been rectified

58

5

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of external (photon and neutron) and tritium doses Intakes of other radionuclides occasionally occur and these radionuclides are not included here because their associated doses are very small For this reason certain collective doses in this report may have values slightly lower than the sum of their respective components as listed

Figure 261 Average Dose Trends for Chalk River and Whiteshell Laboratories (Non-Zero Results Only)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Tritium External Effective

Year

59

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 262 Average Dose Trends for Chalk River and Whiteshell Laboratories (All Monitoring Results)

000

020

040

060

080

100

120

Dos

e (m

Sv)

Tritium External Effective

Year

Figure 263 Collective Dose Trends for Chalk River and Whiteshell Laboratories

0

500

1000

1500

2000

2500

3000

3500

Col

lect

ive

Dos

e (p

erso

n- m

Sv)

External Tritium

Year

60

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 264 Distribution of Effective Doses Among All Workers at Chalk River and Whiteshell Laboratories

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

3500

3000

2500

2000

1500

1000

500

Dose (mSv)

61

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

252 MDS Nordion (Nuclear Substance Processing Facility and Canadian Irradiation Centre)

MDS Nordion owns and operates a nuclear substance processing facility in Ottawa Ontario where it processes unsealed radioisotopes and manufactures sealed radiation sources In operation since the early 1970s the facility was purchased by Nordion International in 1991

In cooperation with the Universiteacute du Queacutebecrsquos Institut Armand-Frappier MDS Nordion also operates the Canadian Irradiation Centre which conducts various irradiation services which include training testing and development The centre is located in Laval Quebec on the Universiteacute du Queacutebec campus

Figures 265ndash268 present dose information for MDS Nordionrsquos Ottawa nuclear substance processing facility and for the Canadian Irradiation Centre from 2001 to 2007

Notes on data for MDS Nordionrsquos nuclear substance processing facility and the Canadian Irradiation Centre

1 Doses from photons from external sources were measured and reported to the NDR MDS Nordion also has a routine thyroid monitoring program very occasionally small recordable doses of radiation have occurred from thyroid uptake of iodine The resulting doses have not been historically submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided

Figure 265 Average Dose Trends for MDS Nordion (Based on Non-Zero Results)

0

05

1

15

2

25

Effe

ctiv

e D

ose

(mS

v)

Year

62

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 266 Average Dose Trends for MDS Nordion (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

Figure 267 Collective Dose Trends for MDS Nordion

0

100

200

300

400

500

600

700

800

Year

63

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 268 Distribution of Effective Doses Among All Workers at MDS Nordion

0

5 0

1 0 0

1 5 0

2 0 0

2 5 0

3 0 0

3 5 0

4 0 0

4 5 0

5 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

64

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

253 Tri-University Meson Facility

The Tri-University Meson facility (TRIUMF) is situated in Vancouver on the campus of the University of British Columbia TRIUMF which began operating in the early 1970s with one cyclotron now has two cyclotrons and associated laboratories for research and radioisotope production The laboratory provides research facilities for Canadian and international users and also produces radioisotopes which are used by medical facilities and by a commercial organization (MDS Nordion) MDS Nordion staff also work at the TRIUMF site however MDS Nordion oversees this work and has its own radiation protection program

Figures 269ndash272 present dose information for the TRIUMF facility from 2001 to 2007 Please note that data sets do not distinguish between doses received by TRIUMF staff and MDS Nordion staff who work on the site as the data for these two groups was submitted collectively to the NDR for the reporting period shown Future data for each group will be submitted separately to the NDR

Note on data for TRIUMF

1 Effective doses are composed of the following reported components bull doses from photons (labeled as ldquoexternalrdquo in the charts) bull neutron doses

Figure 269 Average Dose Trends for TRIUMF (Non-Zero Results Only)

000

020

040

060

080

100

120

140

160

Dos

e (m

Sv)

Neutrons External Effective

Year

65

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 6: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

Table 1 Effective Dose Limits in Canada as Specified by the Radiation Protection Regulations Person Period Effective Dose

(mSv) Nuclear energy workers including pregnant (a) One-year dosimetry period 50 nuclear energy workers

(b) Five-year dosimetry period 100 Pregnant nuclear energy worker Balance of the pregnancy 4

A person who is not a nuclear energy worker One calendar year 1

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Introduction Workers at nuclear facilities are exposed to radiation Their dose is monitored and subject to Canadian Nuclear Safety Commission (CNSC) regulatory requirements which aim to protect their health and safety The amount of radiation to which employees are exposed is referred to as ldquooccupational doserdquo This report provides an overview of occupational radiation doses from 2001 to 2007 at the major nuclear facilities licensed by the CNSC It presents an objective summary of occupational dose information and includes a glossary of terminology

The data collected shows that the average doses for all facilities are far below the individual annual effective dose limit of 50 milliSieverts (mSv) set out in the Radiation Protection Regulations

The report includes data for the following types of facilities

bull nuclear power plants bull uranium mines and mills bull uranium refineries bull fuel fabrication facilities bull research and radioisotope production facilities bull tritium light source production facilities

Each facility is unique in regards to the type of work performed as well its current lifecycle stage (ie operating at reduced or full capacity or in a phase of refurbishment for example) and each provides varying programs to mitigate radiation doses to workers The resulting collective and average doses are based on complex and differing work environments Therefore direct comparisons between facilities in terms of occupational dose are not possible

Regulatory Radiation Dose Limits The Radiation Protection Regulations limit the amount of radiation to which persons may be exposed Table 1 presents the effective dose limits as set out in paragraphs 13 and 14 of the regulations

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

The Radiation Protection Regulations also require CNSC licensees to implement radiation protection programs and to keep radiation doses as low as reasonably achievable (a concept referred to as the ALARA principle) The CNSC evaluates licensee radiation protection programs and these evaluations include reviews of the occupational dose data which is one among several indicators of a radiation protection programrsquos effectiveness

About the Data

Source Statistics in this document are gathered from the National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses1 Maintained by Health Canadarsquos Radiation Protection Bureau the NDR publishes annual reports on occupational dose information and trends according to job type

Due to the large number of CNSC-licensed facilities this report does not include occupational dose information for every CNSC licensees Please refer to the NDR Web site2 to review Health Canadarsquos reports

Analysis This report presents the following types of data

a average doses b collective doses c distribution of effective doses

a Average doses provide a common means of indicating central tendencies of dose distribution and show where doses lie on average with respect to annual dose limits

Notes on average effective doses

1 This report presents two types3 of arithmetic averages for individual effective doses bull averages that include only non-zero (positive) results bull averages that include all monitoring results (including zero-value doses)

2 When assessing regulatory compliance individual doses mdash not average doses mdash must be compared to individual dose limits in the Radiation Protection Regulations

1 In Canada the Radiation Protection Regulations require licensed dosimetry services to submit dose information for nuclear energy workers (NEWs) While not required by law dose information for non-NEWs is also typically submitted to the NDR The data in this report does not distinguish between personnel designated as NEWs versus those who are not 2 httpwwwhc-scgccaewh-semtoccup-travailradiationregistindex_ehtml 3 Some licensees monitor most or all workers (including those unlikely to be directly exposed to sources of occupational radiation) whereas other licensees monitor only employees likely to receive radiation doses Therefore two types of averages are presented averages that consider only non-zero results and averages that consider all results Both statistical approaches have merit and are included in this report (Note The exclusion of zero value doses in the averaging could unfairly bias findings against licensees with effective radiation protection programs)

2

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

b Collective doses indicate the sum of all the doses associated with a facilityrsquos operation and can be used to estimate a facilityrsquos control of occupational doses

Note on collective doses

1 The Radiation Protection Regulations do not set limits on collective doses however the CNSC recommends that licensee radiation protection programs should aim to reduce collective doses These values can indicate a facilityrsquos radiological detriment and help assess whether a facility is operating in accordance with the ALARA principle

c Distribution of effective doses shows the ranges in which effective doses are concentrated

Effective dose calculations By definition effective doses cannot be measured precisely but they can be approximated in order to determine radiation exposure and to assess the associated risks Section 13 of the Radiation Protection Regulations defines the dose calculation methods used to determine effective doses as expressed in millisieverts (mSv) which are based on measurable quantities in the operational environment

Effective radiation doses are made up of various components of which the most common (in Canada) are as follows

bull photons and neutrons from sources outside the body bull radon progeny radon gas long-lived radioactive dust (uranium dust) and tritium that are

taken into the body

The effective doses reported to the NDR represent the sum of their applicable components For example the effective dose to a worker who received radiation doses from both neutrons and tritium would be the sum of these two quantities

Note on average dose values

1 Average values for each dose type (for example tritium) are based on the total collective dose for that type divided by the number of all the workers monitored for any dose type

3

yrenfi R

erev

Ri

dnilB

noid N

orD

SM

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

10 Facility-Wide Comparisons of Average Effective Doses This section presents comparisons of average effective doses at all CNSC-licensed nuclear facilities included in this report for each year within the 2001ndash07 reporting period

bull Figures 11ndash17 present averages based on non-zero (positive) results (Section 11)bull Figures 18ndash114 present averages based on all monitoring results (Section 12)

Notes on facility-wide comparisons of average effective doses

1 Each facility type is represented by a different colour bull nuclear power plants ndash green bull uranium mines and mills ndash purple bull uranium refineries ndash yellow bull fuel fabrication facilities ndash orange bull research and radioisotope facilities ndash blue bull tritium light source production facilities ndash red

2 See Sections 21ndash26 for facility-specific data depicted in Figures 11ndash114

11 Average Effective Doses Based on Non-Zero Results at All Selected Facilities Figures 11ndash17 show average effective doses based on non-zero results for each year from 2001 to 2007 for all the facilities presented in this document

Figure 11 Average Effective Doses at All Selected F acilities for the Year 2001 (Based o n N on-Zero R esults)

4

35

3

25

2

15

1

05

0

) Sv

(me

osD

Bruc

e N

ucle

ar G

ener

atin

g St

atio

ns snotita

Sgntiarene Graelc

Nu

gnirekciP

notita

Sgntiarene Graelc

Nu

ntognilr

Da

notita

Sgntiarene Graelc

Nu

2-ylltineG

notita

Sgntiarene Graelc

Nu

uaerpet LnioP

notiarep Oeka

ff L

uC

l

notiarep Oeka

LnaeC

lc

M

rev R

iru

thrAcM

notiarep Oeka

LyeK

notiarep Oeka

LragC

i

notiarep Oeka

it L

bbR

a

tyilica Fnoisrevn

Co

ept H

oroP

setiilica Fleu

Fraelc N

ucitrcel

ElareneG

tyilical Feu

Fraelc N

uc

teacriZ

Cha

lk R

iver

Lab

orat

orie

s an

d W

hite

shel

lLa

bora

torie

s

tyilica Fnose

Mtyisrev

Uni

-irT

dtearoproc

Inecruo SdleihS

c In)adan

Ca

(seigolonhce T

RB

S

4

y

s n

Dos

e (m

Sv)

) Sv

(me

osD

4

35

3

25

2

15

1

05

0

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 12 Average Effective Doses at All Selected Facilities for the Year 2002 (Based on Non-Zero Results)

4

35

3

25

2

15

1

05

0

Bruc

e N

ucle

ar G

ener

atin

g St

atio

nsBr

uce

Nuc

lear

Gen

erat

ing

Stat

ions

Pick

erin

g N

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Figure 13 Average Effective Doses at All Selected Facilities for the Year 2003 (Based on Non-Zero Results)

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Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 14 Average Effective Doses at All Selected Facilities for the Year 2004 (Based on Non-Zero Results)

4

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Figure 15 Average Effective Doses at All Selected Facilities for the Year 2005 (Based on Non-Zero Results)

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Figure 17 Average Effective Doses at All Selected Facilities for the Year 2007 (Based on Non-Zero Results)

4

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Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 16 Average Effective Doses at All Selected Facilities for the Year 2006 (Based on Non-Zero Results)

4

35

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Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

12 Average Effective Doses Based on All Monitoring Results at All Selected Facilities Figures 18ndash114 show average effective doses based on all the monitoring results for each year from 2001 to 2007 for every facility listed in this document

Figure 18 Average Effective Doses at All Selected F acilities for the Year 2001 (Based o n A ll Monitoring R esults)

8

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Figure 110 Average Effective Doses at All Selected F acilities for the Year 2003 (Based o n A ll Monitoring R esults)

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Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 19 Average Effective Doses at All Selected Facilities for the Year 2002 (Based on All Monitoring Results)

4

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Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 111 Average Effective Doses at All Selected F acilities for the Year 2004 (Based o n A ll Monitoring R esults)

4

35

3

25

2

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Figure 112 Average Effective Doses at All Selected F acilities for the Year 2005 (Based o n A ll Monitoring R esults)

4

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Figure 114 Average Effective Doses at All Selected F acilities for the Year 2007 (Based o n A ll Monitoring R esults)

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Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 113 Average Effective Doses at All Selected Facilities for the Year 2006 (Based on All Monitoring Results)

4

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11

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

20 Facility-Specific Overview of Occupational Doses This section presents data for the following types of facilities

bull nuclear power plants (Section 21) bull uranium mines and mills (Section 22) bull uranium refineries (Section 23) bull fuel fabrication facilities (Section 24) bull research and radioisotope production facilities (Section 25) bull tritium production facilities (Section 26)

21 Nuclear Power Plants This section presents dose information for the following nuclear power plants

bull Bruce A and Bruce B Nuclear Generating Stations (Section 211) bull Pickering Nuclear Generating Stations (Section 212) bull Darlington Nuclear Generating Station Section 213) bull Gentilly-2 Nuclear Generating Station (Section 214) bull Point Lepreau Generating Station (Section 215)

Graphs in this section indicate the following data for each nuclear power plant from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for nuclear power plants

1 Effective doses are composed of the following reported components bull doses from photons (labeled on the charts as ldquoexternalrdquo) bull neutron doses bull tritium doses

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of photon neutron and tritium doses Intakes of other radionuclides (for example Iodine-131 or Carbon-14) occasionally occur but these radionuclides are not included here because the associated collective dose is very small For this reason certain collective dose values in this report may be slightly lower than the sum of their respective components as listed

12

1 2 3 4 5 6 70 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

211 Bruce Nuclear Generating Stations

Bruce Power owns and operates the Bruce Nuclear Generating Stations located near Kincardine Ontario on the shore of Lake Huron

bull Bruce A consists of four nuclear reactors (units 1ndash4) and began operating in 1976 bull Bruce B has four nuclear reactors (units 5ndash8) and started operating in 1984

As part of its extensive recovery program in 1997 the sitersquos previous operator Ontario Hydro (now Ontario Power Generation) temporarily shut down all Bruce A reactors and maintained them in a guaranteed shutdown state Units 3 and 4 were later returned to service (in October 2003 and January 2004) while Units 1 and 2 remained in a guaranteed shutdown state

Figures 21ndash24 present dose information for the Bruce Nuclear Generating Stations from 2001 to 2007 Graphs do not distinguish between doses received at Bruce A versus Bruce B

Fig 21 Average Dose Trends for Bruce Nuclear Generating Stati on (Based o n N on-Zero R esults)

Dos

e (m

Sv)

4

35

3

25

2

15

1

05

0

Tritium Neutron External Effective

Year

13

Neutrons External Tritium

0 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 21 2 3 4 5 6 7

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

0

2

4

6

8

1

2

4

0

0

0

0

1

1

Figure 22 Average Dose Trends for Bruce Nuclear Generating Stati on (Based o n A ll Monitoring R esults)

16

)S

v(m

e os

D

Tritium Neutrons External Effective

Year

Figure 23 Collective Dose Trends for Bruce Nuclear Generating Stati on

8000

7000

6000

5000

4000

3000

2000

1000

0

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Year

14

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 24 Distribution of Effective Doses Among All Workers at Bruce Nuclear Generating Station

6000

5000

4000

3000

2000

1000

0 9 0 0

1-50 0 0 1 0 0 0 0 00 5 0 0 0

0-000

000 1-1 1-1 1-20 1-3 3gt0 0 0 05 0 5 01 1 2

Num

ber o

f Wor

kers

Dose Range (mSv)

15

1 2 3 4 5 6 7 0 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

212 Pickering Nuclear Generating Stations

Located in Pickering Ontario the Pickering Nuclear Generating Stations are owned and operated by Ontario Power Generation Two generating stations are located within one enclosure

bull Pickering A consists of four nuclear reactors (units 1 to 4) that began operating in 1971 bull Pickering B consists of four nuclear reactors (units 5 to 8) that began operating in 1982

As part of its extensive recovery program Ontario Hydro (now Ontario Power Generation) temporarily shut down all Pickering A reactors in 1997 and maintained them in a guaranteed shutdown state Unit 4 was restarted in September 2003 and Unit 1 was restarted in March 2005 Units 2 and 3 remain in a guaranteed shutdown state

Figures 25ndash28 present dose information for the Pickering Nuclear Generating Stations from 2001 to 2007 Graphs do not distinguish between doses received at Pickering A versus those received at Pickering B

Figure 25 Average Dose Trends for Pickering N uclear Generating Stati on (Based o n N on-Zero R esults)

25

2

15

1

05

0

)S

v(m

e os

D

Tritium Neutrons External Effective

Year

16

Tritium Neutrons External Effective

Neutrons External Tritium

1 2 3 4 5 6 70 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

1 2 3 4 5 6 7 0 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 26 Average Dose Trends for Pickering N uclear Generating Stati on (Based o n A ll Monitoring R esults)

12

1

08

06

04

02

0

Year

Figure 27 Collective Dose Trends for Pickering N uclear Generating Stati on

12000

10000

8000

6000

4000

2000

0

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

)

Sv

(me

osD

Year

17

2001 2002 2003 2004 2005 2006 2007

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 28 Distribution o f Effective Doses Among A ll Workers at Pickering Nuclear Generating Stati on

6000

5000

4000

3000

2000

1000

0

Num

ber o

f Wor

kers

Dose Range (mSv)

18

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

213 Darlington Nuclear Generating Station

Owned and operated by Ontario Power Generation the Darlington Nuclear Generating Station has four nuclear reactors the first of which began operating in 1989 The facility is located near Bowmanville on the shore of Lake Ontario

Figures 29ndash212 present dose information for the Darlington Nuclear Generating Station from 2001 to 2007

Figure 29 Average Dose Trends for Darlington N uclear Generating Stati on (Non- Zero R esults Only)

)S

v(m

e os

D

250

200

150

100

050

000

Year

19

Tritium Neutrons External Effective

Neutrons External Tritium

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 210 Average Dose Trends for Darlington N uclear Generating Stati on (All Monitoring R esults)

090

080

070

060

050

040

030

020

010

000

)S

v(m

e os

D

Year

Figure 211 Collective Dose Trends for Darlington N uclear Generating Stati on

4500

4000

3500

3000

2500

2000

1500

1000

500

0

)vSm-nosrep (es

Do

eiv

llect

Co

Year

20

2001 2002 2003 2004 2005 2006 2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 212 Distribution o f Effective Doses Among A ll Workers at Darlington Nuclear Generating Stati on

0

500

1000

1500

2000

2500

3000

3500

ers

ork

W of

be

r um

N

Dose Range (mSv)

21

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

214 Gentilly-2 Nuclear Generating Station

The Gentilly-2 Nuclear Generating Station owned and operated by Hydro-Queacutebec has a single reactor that began operating in 1982 The facility is located on the south shore of the St Lawrence River near Trois-Riviegraveres Queacutebec

Figures 213ndash216 present dose information for the Gentilly-2 Nuclear Generating Station from 2001 to 2007

Figure 213 Average Dose Trends for Gentilly-2 Nuclear Generating Stati on (Based o n N on-Zero R esults)

0

05

1

15

2

25

3

35

4

45

)S

v(m

e os

D

Year

22

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 214 Average Dose Trends for Gentilly-2 Nuclear Generating Stati on (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

)S

v(m

e os

D

Year

Figure 215 Collective Dose Trends for Gentilly-2 Nuclear Generating Stati on

0

500

1000

1500

2000

2500

3000

3500

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Neutrons

External

Tritium

Year

23

000-0

009

001-5

00

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 216 Distribution of Effective Doses Among All Workers at Gentilly-2 Nuclear Generating Station

2500

2000

1500

1000

500

0

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

24

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

215 Point Lepreau Nuclear Generating Station

The Point Lepreau Nuclear Generating Station has one reactor that began operating in 1982 Owned and operated by New Brunswick Power Nuclear the station is located in Point Lepreau New Brunswick about 40 km west of Saint John on the shores of the Bay of Fundy

Figures 217ndash220 present dose information for the Point Lepreau Nuclear Generating Station from 2001 to 2007

Figure 217 Average Dose Trends for Point Lepreau N uclear Generating Stati on (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

)S

v(m

e os

D

Tritium Neutron External Effective

Year

25

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 218 Average Dose Trends for Point Lepreau N uclear Generating Stati on (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

)S

v(m

e os

D

Tritium Neutrons External Effective

Year

Figure 219 Collective Dose Trends for Point Lepreau N uclear Generating Station

0

200

400

600

800

1000

1200

1400

1600

1800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Neutrons

External

Tritium

Year

26

0

1400

1200

1000

800

600

400

200

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 220 Distribution of Effective Doses Among All Workers at Point Lepreau Nuclear Generating Station

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

27

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

22 Uranium Mines and Mills This section presents dose information for mine and mill sites in the following regions

bull Cluff Lake (Section 221) bull McClean Lake (Section 222) bull McArthur River (Section 223) bull Key Lake (Section 224) bull Cigar Lake (Section 225) bull Rabbit Lake (Section 226)

Graphs indicate the following data for each site from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for uranium mines and mills

1 Effective doses are composed of the following reported components bull doses from photons (labelled on the charts as ldquoexternalrdquo) bull doses from radon progeny bull doses from long-lived radioactive dust bull doses from radon gas (in some cases)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of photon radon progeny long-lived radioactive dust and radon gas doses

3 The NDR lists radon progeny in working level months (WLM) For this report radon progeny exposures were converted4 to doses expressed in mSv

221 Cluff Lake Operation

The Cluff Lake mining facilities operated by AREVA Resources Canada Inc are located in northwestern Saskatchewan Work began in 1980 and ended in 2002 with the site now being decommissioned The site consisted of three open-pit and two underground mines a mill and a tailings management facility During 2005 and 2006 most of the infrastructure was removed and the affected areas were remediated

Figures 221ndash224 present dose information for the Cluff Lake operation from 2001 to 2007

4 Doses were converted using the International Commission on Radiation Protection (ICRP)rsquos conversion convention of 1 WLM = 5 mSv This convention was established in the ICRP publication Protection against Radon at Home and at Work (ICRP 65)

28

Long-lived radioactive dust Radon progeny External Effective

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 221 Average Dose Trends for the Cluff Lake Operation (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

Year

Figure 222 Average Dose Trends for the Cluff Lake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

200

Long-lived radioactive dust Radon progeny External Effective

)S

v(m

e os

D)

Sv

(me

osD

Year

29

600

500

400

300

200

100

0

External Radon progeny Long-lived radioactive dust

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 223 Collective Dose Trends for the Cluff Lake Operation s

erkor

of W

ber

Num

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Year

Figure 224 Distribution o f Effective Doses Among A ll Workers at the Cluff Lake Operation

0

20

40

60

80

100

120

140

160

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

30

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

222 McClean Lake Operation

AREVA Resources Canada Inc runs the McClean Lake mining operation in northeastern Saskatchewan It comprises open pit mines a mill and a tailings management facility Mining began in 1995 while milling started in 1999

Figures 225ndash228 present dose information for the McClean Lake operation from 2001 to 2007

Figure 225 Average Dose Trends for the McClean L ake Operation (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

31

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 226 Average Dose Trends for the McClean L ake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 227 Collective Dose Trends for the McClean L ake Operation

0

100

200

300

400

500

600

700

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External

Radon progeny

Long-lived radioactive dust

Year

32

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 228 Distribution o f Effective Doses Among A ll Workers at the McClean Lake Operation

0

100

200

300

400

500

600

700

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

33

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

223 McArthur River Operation

Cameco Corporation operates the McArthur River underground mine in north-central Saskatchewan Ore from the mine which began production in 1999 is processed at the Key Lake Mill located 80 km south of McArthur River

Figures 229ndash232 present dose information for the McArthur River operation from 2001 to 2007

Figure 229 Average Dose Trends for the McArthur River Operation (Based o n N on-Zero R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

34

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 230 Average Dose Trends for the McArthur River Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

Figure 231 Collective Dose Trends for the McArthur River Operation

0

200

400

600

800

1000

1200

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Radon gas External Radon progeny Long-lived radioactive dust

Year

35

00

0-000

9

001-5

00

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 232 Distribution o f Effective Doses Among A ll Workers at the McArthur River Operation

0

100

200

300

400

500

600

700

800

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

36

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

224 Key Lake Operation

Cameco Corporation operates mining facilities in Key Lake located in north-central Saskatchewan The Key Lake operation includes two mined-out open pit mines (used for tailings management) a mill and two dry tailings management facilities Mining began in 1983 and ceased in 1997 the mill continued to process ore from the McArthur River mine during the reporting period

Figures 233ndash236 present dose information for the Key Lake operation from 2001 to 2007

Figure 233 Average Dose Trends for the Key Lake Operation (Based o n N on-Zero R esults)

00

20

40

60

80

00

20

40

60

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

37

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

00

20

40

60

80

00

20

40

60

Figure 234 Average Dose Trends for the Key Lake Operation (Based o n A ll Monitoring R esults)

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 235 Collective Dose Trends for the Key Lake Operation

0

100

200

300

400

500

600

700

800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External Radon progeny Long-lived radioactive dust

Year

38

00

0-000

9

001-5

0

501-1

000

gt 1001

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 236 Distribution o f Effective Doses Among A ll Workers at the Key Lake Operation

0

200

400

600

800

1000

1200

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose Range (mSv)

39

se

(mS

v)o

D

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

225 Cigar Lake Operation

Cameco Corporation manages the Cigar Lake underground mine located in northern Saskatchewan at the southern end of Waterbury Lake The mine was under construction at the time of this reportrsquos publication Test mining in ore was carried out in 1991 1992 and 2000

Figures 237ndash240 present dose information for the Cigar Lake operation from

Figure 2 37 Average D ose T rends fo r th e C igar L ake O peration (Based on Non-Zero Results)

2001 to 2007

Year

000

005

010

015

020

025

Long-lived radioactive dust Radon Progeny External Effective

40

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 238 Average Dose Trends for the Cigar Lake Operation (Based on All Monitoring Results)

000

005

010

015

020

025

030

035

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny

External

Effective

Year

Figure 239 Collective Dose Trends for the Cigar Lake Operation

0

50

100

150

200

250

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

External Radon progeny Long-lived radioactive dust

Year

41

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 240 Distribution of Effective Doses Among All Workers at the Cigar Lake Operation

0

200

400

600

800

1000

1200

1400

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

42

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

226 Rabbit Lake Operation

Cameco Corporation owns and operates mining facilities in Rabbit Lake located in north-eastern Saskatchewan Facilities include an underground mine four mined-out open-pit mines a mill and two tailings management facilities Mining and milling began in 1975

Figures 241ndash244 present dose information for the Rabbit Lake operation from 2001 to 2007

Figure 241 Average Dose Trends for the Rabbit Lake Operation (Based on Non-Zero Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

43

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 242 Average Dose Trends for the Rabbit Lake Operation (Based on All Monitoring Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

Figure 243 Collective Dose Trends for the Rabbit Lake Operation

0

200

400

600

800

1000

1200

1400

1600

1800

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Radon gas External Radon progeny Long-lived radioactive dust

Year

44

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

gt300

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 244 Distribution of Effective Doses Among All Workers at the Rabbit Lake Operation

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

900

800

700

600

500

400

300

200

100

0

Dose (mSv)

45

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

23 Uranium Refineries This section presents data for the following two facilities

bull a uranium refining facility in Blind River (Section 231) bull a uranium conversion facility in Port Hope (Section 232)

Graphs indicate the following average doses at each facility from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Note on data for uranium refineries

1 Doses from photons from external sources are measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay and lung counting Historically while these internal doses have been measured they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

231 Blind River Refinery

Cameco Corporation owns and is licensed to operate a uranium refinery in Blind River Ontario The facility which began operating in 1983 converts uranium ore concentrate to uranium trioxide The uranium trioxide is shipped to Camecorsquos uranium conversion facility in Port Hope Ontario where it is processed into uranium dioxide (for use in the fabrication of fuel for nuclear reactors in Canada) or uranium hexafluoride (exported for enrichment and fabrication into fuel for nuclear power reactors around the world)

Figures 245ndash248 present dose information for the Blind River refinery from 2001 to 2007

46

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 245 Average Dose Trends for the Blind River Refinery (Based on Non-Zero Results)

0

05

1

15

2

25

Year

Figure 246 Average Dose Trends for the Blind River Refinery (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

47

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 247 Collective Dose Trends for the Blind River Refinery

0

50

100

150

200

250

300 C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 248 Distribution of Effective Doses Among All Workers at the Blind River Refinery

0

20

40

60

80

100

120

140

160

180

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

48

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

232 Port Hope Conversion Facility

Cameco Corporation owns and is licensed to operate a uranium conversion facility in Port Hope Ontario The facility processes uranium trioxide received from the refinery in Blind River into uranium dioxide and uranium hexafluoride

Figures 249ndash252 present dose information for the Port Hope uranium conversion facility from 2001 to 2007

Figure 249 Average Dose Trends for the Port Hope Conversion Facility (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

49

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 250 Average Dose Trends for the Port Hope Conversion Facility (Based on All Monitoring Results)

0

01

02

03

04

05

06

07

08

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 251 Collective Dose Trends for the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

50

000-0

009

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 252 Distribution of Effective Doses Among All Workers at the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

400

450

500

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

51

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

24 Fuel Fabrication Facilities This section presents data for three nuclear fuel fabrication facilities

bull Two facilities owned and operated by General Electric Canada Inc (Section 241) bull One facility in Port Hope operated by Zircatec Precision Industries (Section 242)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average doses

Notes on data for fuel fabrication facilities

1 Effective doses for the three facilities are composed of the following reported components bull dose from photons (labelled on the charts as ldquoexternalrdquo) bull doses from internal intakes of uranium dust (long-lived radioactive dust) from

uranium in air concentrations (for General Electricrsquos Toronto facility only)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components photon doses and doses from long-lived radioactive dust

241 General Electric Nuclear Fuel Facilities

General Electric Canada Inc operates two nuclear fuel facilities in Ontario

bull At the Toronto facility uranium dioxide pellets are produced from natural or depleted uranium dioxide powder

bull At the Peterborough facility uranium dioxide fuel bundles are created from the pellets produced at the Toronto facility

Figures 253ndash256 present dose information for General Electric Canada Incrsquos fuel fabrication facilities from 2001 to 2007 Graphs do not distinguish between the doses received at the Peterborough facility versus those at the Toronto facility

52

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 253 Average Dose Trends for the General Electric Fuel Facility (Based on Non-Zero Results Only)

0

05

1

15

2

25

3

35

Long Lived Radioactive Dust External Effective

Year

Figure 254 Average Dose Trends for the General Electric Fuel Facility (Based on All Monitoring Results)

0

05

1

15

2

25

3

Long Lived Radioactive Dust External Effective

Year

Dos

e (m

Sv)

Dos

e (m

Sv)

53

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 255 Collective Dose Trends for the General Electric Fuel Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Long Lived Radioactive Dust External

Year

Figure 256 Distribution of Effective Doses among all Workers at the General Electric Fuel Facility

0

10

20

30

40

50

60

70

80

90

100

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

54

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

242 Zircatec Nuclear Fuel Facility

Zircatec Precision Industries Inc operates a nuclear fuel facility in Port Hope Ontario where it makes fuel pellets from uranium dioxide powder received from Port Hopersquos uranium conversion facility The nuclear fuel facility also manufactures fuel bundles for nuclear reactors in Canada

Notes on data for the Zircatec nuclear fuel facility

1 Graphs indicate the following data bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of average effective doses

2 Doses from photons from external sources were measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay Historically although these internal doses have been measured and submitted to the CNSC they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

Figures 257ndash260 present dose information for the Zircatec nuclear fuel facility from 2001 to 2007

Figure 257 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on Non-Zero Results)

0

05

1

15

2

25

3

35

Effe

ctiv

e D

ose

(mS

v)

Year

55

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 258 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

18

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 259 Collective Dose Trends for the Zircatec Nuclear Fuel Facility

0

50

100

150

200

250

300

350

400

450

500

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

56

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 260 Distribution of Effective Doses Among All Workers at the Zircatec Nuclear Fuel Facility

300

Num

ber o

f Wor

kers

250

200

150

100

50

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

57

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

25 Research and Radioisotope Production Facilities This section presents dose information for the following research and radioisotope production facilities from 2001 to 2007

bull Chalk River Laboratories and Whiteshell Laboratories (Section 251) bull A radioisotope production facility operated by MDS Nordion (Section 252) bull The Tri-University Meson Facility (TRIUMF) (Section 253)

Note on data for research and radioisotope production facilities

1 Graphs indicate the following data for each facility bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of effective doses

251 Chalk River Laboratories and Whiteshell Laboratories

Atomic Energy of Canada Limited (AECL) owns and is licensed to operate Chalk River Laboratories and Whiteshell Laboratories

Situated in Renfrew County on the south shore of the Ottawa River the Chalk River Laboratories site hosts the National Research Universal Reactor along with numerous other facilities occupying some 160 buildings in an area of approximately 40 km2 Activities consist of radioisotope production for nuclear medicine testing and development of structural materials in support of power reactor operations fuel fabrication research and radioactive waste management and storage

The Whiteshell Laboratories site is located approximately 10 km west of Pinawa Manitoba and 100 km northeast of Winnipeg on the east bank of the Winnipeg River AECL established the laboratories for nuclear research and testing during the early 1960s and has since discontinued operations which are being decommissioned under a licence from the CNSC

Figures 261ndash264 present dose information for Chalk River Laboratories and Whiteshell Laboratories from 2001 to 2007

Notes on data for Chalk River Laboratories and Whiteshell Laboratories

1 Effective doses are composed of the following reported components bull external doses5 (from both photon and neutron doses) bull tritium doses

Due to issues with AECLrsquos in-house dosimetry management system neutron doses were not reported separately to the NDR during the reporting period As a result external doses from photons and neutrons were totaled The reporting discrepancy has since been rectified

58

5

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of external (photon and neutron) and tritium doses Intakes of other radionuclides occasionally occur and these radionuclides are not included here because their associated doses are very small For this reason certain collective doses in this report may have values slightly lower than the sum of their respective components as listed

Figure 261 Average Dose Trends for Chalk River and Whiteshell Laboratories (Non-Zero Results Only)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Tritium External Effective

Year

59

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 262 Average Dose Trends for Chalk River and Whiteshell Laboratories (All Monitoring Results)

000

020

040

060

080

100

120

Dos

e (m

Sv)

Tritium External Effective

Year

Figure 263 Collective Dose Trends for Chalk River and Whiteshell Laboratories

0

500

1000

1500

2000

2500

3000

3500

Col

lect

ive

Dos

e (p

erso

n- m

Sv)

External Tritium

Year

60

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 264 Distribution of Effective Doses Among All Workers at Chalk River and Whiteshell Laboratories

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

3500

3000

2500

2000

1500

1000

500

Dose (mSv)

61

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

252 MDS Nordion (Nuclear Substance Processing Facility and Canadian Irradiation Centre)

MDS Nordion owns and operates a nuclear substance processing facility in Ottawa Ontario where it processes unsealed radioisotopes and manufactures sealed radiation sources In operation since the early 1970s the facility was purchased by Nordion International in 1991

In cooperation with the Universiteacute du Queacutebecrsquos Institut Armand-Frappier MDS Nordion also operates the Canadian Irradiation Centre which conducts various irradiation services which include training testing and development The centre is located in Laval Quebec on the Universiteacute du Queacutebec campus

Figures 265ndash268 present dose information for MDS Nordionrsquos Ottawa nuclear substance processing facility and for the Canadian Irradiation Centre from 2001 to 2007

Notes on data for MDS Nordionrsquos nuclear substance processing facility and the Canadian Irradiation Centre

1 Doses from photons from external sources were measured and reported to the NDR MDS Nordion also has a routine thyroid monitoring program very occasionally small recordable doses of radiation have occurred from thyroid uptake of iodine The resulting doses have not been historically submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided

Figure 265 Average Dose Trends for MDS Nordion (Based on Non-Zero Results)

0

05

1

15

2

25

Effe

ctiv

e D

ose

(mS

v)

Year

62

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 266 Average Dose Trends for MDS Nordion (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

Figure 267 Collective Dose Trends for MDS Nordion

0

100

200

300

400

500

600

700

800

Year

63

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 268 Distribution of Effective Doses Among All Workers at MDS Nordion

0

5 0

1 0 0

1 5 0

2 0 0

2 5 0

3 0 0

3 5 0

4 0 0

4 5 0

5 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

64

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

253 Tri-University Meson Facility

The Tri-University Meson facility (TRIUMF) is situated in Vancouver on the campus of the University of British Columbia TRIUMF which began operating in the early 1970s with one cyclotron now has two cyclotrons and associated laboratories for research and radioisotope production The laboratory provides research facilities for Canadian and international users and also produces radioisotopes which are used by medical facilities and by a commercial organization (MDS Nordion) MDS Nordion staff also work at the TRIUMF site however MDS Nordion oversees this work and has its own radiation protection program

Figures 269ndash272 present dose information for the TRIUMF facility from 2001 to 2007 Please note that data sets do not distinguish between doses received by TRIUMF staff and MDS Nordion staff who work on the site as the data for these two groups was submitted collectively to the NDR for the reporting period shown Future data for each group will be submitted separately to the NDR

Note on data for TRIUMF

1 Effective doses are composed of the following reported components bull doses from photons (labeled as ldquoexternalrdquo in the charts) bull neutron doses

Figure 269 Average Dose Trends for TRIUMF (Non-Zero Results Only)

000

020

040

060

080

100

120

140

160

Dos

e (m

Sv)

Neutrons External Effective

Year

65

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 7: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

The Radiation Protection Regulations also require CNSC licensees to implement radiation protection programs and to keep radiation doses as low as reasonably achievable (a concept referred to as the ALARA principle) The CNSC evaluates licensee radiation protection programs and these evaluations include reviews of the occupational dose data which is one among several indicators of a radiation protection programrsquos effectiveness

About the Data

Source Statistics in this document are gathered from the National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses1 Maintained by Health Canadarsquos Radiation Protection Bureau the NDR publishes annual reports on occupational dose information and trends according to job type

Due to the large number of CNSC-licensed facilities this report does not include occupational dose information for every CNSC licensees Please refer to the NDR Web site2 to review Health Canadarsquos reports

Analysis This report presents the following types of data

a average doses b collective doses c distribution of effective doses

a Average doses provide a common means of indicating central tendencies of dose distribution and show where doses lie on average with respect to annual dose limits

Notes on average effective doses

1 This report presents two types3 of arithmetic averages for individual effective doses bull averages that include only non-zero (positive) results bull averages that include all monitoring results (including zero-value doses)

2 When assessing regulatory compliance individual doses mdash not average doses mdash must be compared to individual dose limits in the Radiation Protection Regulations

1 In Canada the Radiation Protection Regulations require licensed dosimetry services to submit dose information for nuclear energy workers (NEWs) While not required by law dose information for non-NEWs is also typically submitted to the NDR The data in this report does not distinguish between personnel designated as NEWs versus those who are not 2 httpwwwhc-scgccaewh-semtoccup-travailradiationregistindex_ehtml 3 Some licensees monitor most or all workers (including those unlikely to be directly exposed to sources of occupational radiation) whereas other licensees monitor only employees likely to receive radiation doses Therefore two types of averages are presented averages that consider only non-zero results and averages that consider all results Both statistical approaches have merit and are included in this report (Note The exclusion of zero value doses in the averaging could unfairly bias findings against licensees with effective radiation protection programs)

2

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

b Collective doses indicate the sum of all the doses associated with a facilityrsquos operation and can be used to estimate a facilityrsquos control of occupational doses

Note on collective doses

1 The Radiation Protection Regulations do not set limits on collective doses however the CNSC recommends that licensee radiation protection programs should aim to reduce collective doses These values can indicate a facilityrsquos radiological detriment and help assess whether a facility is operating in accordance with the ALARA principle

c Distribution of effective doses shows the ranges in which effective doses are concentrated

Effective dose calculations By definition effective doses cannot be measured precisely but they can be approximated in order to determine radiation exposure and to assess the associated risks Section 13 of the Radiation Protection Regulations defines the dose calculation methods used to determine effective doses as expressed in millisieverts (mSv) which are based on measurable quantities in the operational environment

Effective radiation doses are made up of various components of which the most common (in Canada) are as follows

bull photons and neutrons from sources outside the body bull radon progeny radon gas long-lived radioactive dust (uranium dust) and tritium that are

taken into the body

The effective doses reported to the NDR represent the sum of their applicable components For example the effective dose to a worker who received radiation doses from both neutrons and tritium would be the sum of these two quantities

Note on average dose values

1 Average values for each dose type (for example tritium) are based on the total collective dose for that type divided by the number of all the workers monitored for any dose type

3

yrenfi R

erev

Ri

dnilB

noid N

orD

SM

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

10 Facility-Wide Comparisons of Average Effective Doses This section presents comparisons of average effective doses at all CNSC-licensed nuclear facilities included in this report for each year within the 2001ndash07 reporting period

bull Figures 11ndash17 present averages based on non-zero (positive) results (Section 11)bull Figures 18ndash114 present averages based on all monitoring results (Section 12)

Notes on facility-wide comparisons of average effective doses

1 Each facility type is represented by a different colour bull nuclear power plants ndash green bull uranium mines and mills ndash purple bull uranium refineries ndash yellow bull fuel fabrication facilities ndash orange bull research and radioisotope facilities ndash blue bull tritium light source production facilities ndash red

2 See Sections 21ndash26 for facility-specific data depicted in Figures 11ndash114

11 Average Effective Doses Based on Non-Zero Results at All Selected Facilities Figures 11ndash17 show average effective doses based on non-zero results for each year from 2001 to 2007 for all the facilities presented in this document

Figure 11 Average Effective Doses at All Selected F acilities for the Year 2001 (Based o n N on-Zero R esults)

4

35

3

25

2

15

1

05

0

) Sv

(me

osD

Bruc

e N

ucle

ar G

ener

atin

g St

atio

ns snotita

Sgntiarene Graelc

Nu

gnirekciP

notita

Sgntiarene Graelc

Nu

ntognilr

Da

notita

Sgntiarene Graelc

Nu

2-ylltineG

notita

Sgntiarene Graelc

Nu

uaerpet LnioP

notiarep Oeka

ff L

uC

l

notiarep Oeka

LnaeC

lc

M

rev R

iru

thrAcM

notiarep Oeka

LyeK

notiarep Oeka

LragC

i

notiarep Oeka

it L

bbR

a

tyilica Fnoisrevn

Co

ept H

oroP

setiilica Fleu

Fraelc N

ucitrcel

ElareneG

tyilical Feu

Fraelc N

uc

teacriZ

Cha

lk R

iver

Lab

orat

orie

s an

d W

hite

shel

lLa

bora

torie

s

tyilica Fnose

Mtyisrev

Uni

-irT

dtearoproc

Inecruo SdleihS

c In)adan

Ca

(seigolonhce T

RB

S

4

y

s n

Dos

e (m

Sv)

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4

35

3

25

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15

1

05

0

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 12 Average Effective Doses at All Selected Facilities for the Year 2002 (Based on Non-Zero Results)

4

35

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15

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Figure 13 Average Effective Doses at All Selected Facilities for the Year 2003 (Based on Non-Zero Results)

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Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 14 Average Effective Doses at All Selected Facilities for the Year 2004 (Based on Non-Zero Results)

4

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Figure 15 Average Effective Doses at All Selected Facilities for the Year 2005 (Based on Non-Zero Results)

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Figure 17 Average Effective Doses at All Selected Facilities for the Year 2007 (Based on Non-Zero Results)

4

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Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 16 Average Effective Doses at All Selected Facilities for the Year 2006 (Based on Non-Zero Results)

4

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Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

12 Average Effective Doses Based on All Monitoring Results at All Selected Facilities Figures 18ndash114 show average effective doses based on all the monitoring results for each year from 2001 to 2007 for every facility listed in this document

Figure 18 Average Effective Doses at All Selected F acilities for the Year 2001 (Based o n A ll Monitoring R esults)

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Figure 110 Average Effective Doses at All Selected F acilities for the Year 2003 (Based o n A ll Monitoring R esults)

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Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 19 Average Effective Doses at All Selected Facilities for the Year 2002 (Based on All Monitoring Results)

4

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Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 111 Average Effective Doses at All Selected F acilities for the Year 2004 (Based o n A ll Monitoring R esults)

4

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Figure 112 Average Effective Doses at All Selected F acilities for the Year 2005 (Based o n A ll Monitoring R esults)

4

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Figure 114 Average Effective Doses at All Selected F acilities for the Year 2007 (Based o n A ll Monitoring R esults)

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Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 113 Average Effective Doses at All Selected Facilities for the Year 2006 (Based on All Monitoring Results)

4

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11

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

20 Facility-Specific Overview of Occupational Doses This section presents data for the following types of facilities

bull nuclear power plants (Section 21) bull uranium mines and mills (Section 22) bull uranium refineries (Section 23) bull fuel fabrication facilities (Section 24) bull research and radioisotope production facilities (Section 25) bull tritium production facilities (Section 26)

21 Nuclear Power Plants This section presents dose information for the following nuclear power plants

bull Bruce A and Bruce B Nuclear Generating Stations (Section 211) bull Pickering Nuclear Generating Stations (Section 212) bull Darlington Nuclear Generating Station Section 213) bull Gentilly-2 Nuclear Generating Station (Section 214) bull Point Lepreau Generating Station (Section 215)

Graphs in this section indicate the following data for each nuclear power plant from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for nuclear power plants

1 Effective doses are composed of the following reported components bull doses from photons (labeled on the charts as ldquoexternalrdquo) bull neutron doses bull tritium doses

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of photon neutron and tritium doses Intakes of other radionuclides (for example Iodine-131 or Carbon-14) occasionally occur but these radionuclides are not included here because the associated collective dose is very small For this reason certain collective dose values in this report may be slightly lower than the sum of their respective components as listed

12

1 2 3 4 5 6 70 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

211 Bruce Nuclear Generating Stations

Bruce Power owns and operates the Bruce Nuclear Generating Stations located near Kincardine Ontario on the shore of Lake Huron

bull Bruce A consists of four nuclear reactors (units 1ndash4) and began operating in 1976 bull Bruce B has four nuclear reactors (units 5ndash8) and started operating in 1984

As part of its extensive recovery program in 1997 the sitersquos previous operator Ontario Hydro (now Ontario Power Generation) temporarily shut down all Bruce A reactors and maintained them in a guaranteed shutdown state Units 3 and 4 were later returned to service (in October 2003 and January 2004) while Units 1 and 2 remained in a guaranteed shutdown state

Figures 21ndash24 present dose information for the Bruce Nuclear Generating Stations from 2001 to 2007 Graphs do not distinguish between doses received at Bruce A versus Bruce B

Fig 21 Average Dose Trends for Bruce Nuclear Generating Stati on (Based o n N on-Zero R esults)

Dos

e (m

Sv)

4

35

3

25

2

15

1

05

0

Tritium Neutron External Effective

Year

13

Neutrons External Tritium

0 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 21 2 3 4 5 6 7

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

0

2

4

6

8

1

2

4

0

0

0

0

1

1

Figure 22 Average Dose Trends for Bruce Nuclear Generating Stati on (Based o n A ll Monitoring R esults)

16

)S

v(m

e os

D

Tritium Neutrons External Effective

Year

Figure 23 Collective Dose Trends for Bruce Nuclear Generating Stati on

8000

7000

6000

5000

4000

3000

2000

1000

0

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Year

14

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 24 Distribution of Effective Doses Among All Workers at Bruce Nuclear Generating Station

6000

5000

4000

3000

2000

1000

0 9 0 0

1-50 0 0 1 0 0 0 0 00 5 0 0 0

0-000

000 1-1 1-1 1-20 1-3 3gt0 0 0 05 0 5 01 1 2

Num

ber o

f Wor

kers

Dose Range (mSv)

15

1 2 3 4 5 6 7 0 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

212 Pickering Nuclear Generating Stations

Located in Pickering Ontario the Pickering Nuclear Generating Stations are owned and operated by Ontario Power Generation Two generating stations are located within one enclosure

bull Pickering A consists of four nuclear reactors (units 1 to 4) that began operating in 1971 bull Pickering B consists of four nuclear reactors (units 5 to 8) that began operating in 1982

As part of its extensive recovery program Ontario Hydro (now Ontario Power Generation) temporarily shut down all Pickering A reactors in 1997 and maintained them in a guaranteed shutdown state Unit 4 was restarted in September 2003 and Unit 1 was restarted in March 2005 Units 2 and 3 remain in a guaranteed shutdown state

Figures 25ndash28 present dose information for the Pickering Nuclear Generating Stations from 2001 to 2007 Graphs do not distinguish between doses received at Pickering A versus those received at Pickering B

Figure 25 Average Dose Trends for Pickering N uclear Generating Stati on (Based o n N on-Zero R esults)

25

2

15

1

05

0

)S

v(m

e os

D

Tritium Neutrons External Effective

Year

16

Tritium Neutrons External Effective

Neutrons External Tritium

1 2 3 4 5 6 70 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

1 2 3 4 5 6 7 0 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 26 Average Dose Trends for Pickering N uclear Generating Stati on (Based o n A ll Monitoring R esults)

12

1

08

06

04

02

0

Year

Figure 27 Collective Dose Trends for Pickering N uclear Generating Stati on

12000

10000

8000

6000

4000

2000

0

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

)

Sv

(me

osD

Year

17

2001 2002 2003 2004 2005 2006 2007

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 28 Distribution o f Effective Doses Among A ll Workers at Pickering Nuclear Generating Stati on

6000

5000

4000

3000

2000

1000

0

Num

ber o

f Wor

kers

Dose Range (mSv)

18

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

213 Darlington Nuclear Generating Station

Owned and operated by Ontario Power Generation the Darlington Nuclear Generating Station has four nuclear reactors the first of which began operating in 1989 The facility is located near Bowmanville on the shore of Lake Ontario

Figures 29ndash212 present dose information for the Darlington Nuclear Generating Station from 2001 to 2007

Figure 29 Average Dose Trends for Darlington N uclear Generating Stati on (Non- Zero R esults Only)

)S

v(m

e os

D

250

200

150

100

050

000

Year

19

Tritium Neutrons External Effective

Neutrons External Tritium

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 210 Average Dose Trends for Darlington N uclear Generating Stati on (All Monitoring R esults)

090

080

070

060

050

040

030

020

010

000

)S

v(m

e os

D

Year

Figure 211 Collective Dose Trends for Darlington N uclear Generating Stati on

4500

4000

3500

3000

2500

2000

1500

1000

500

0

)vSm-nosrep (es

Do

eiv

llect

Co

Year

20

2001 2002 2003 2004 2005 2006 2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 212 Distribution o f Effective Doses Among A ll Workers at Darlington Nuclear Generating Stati on

0

500

1000

1500

2000

2500

3000

3500

ers

ork

W of

be

r um

N

Dose Range (mSv)

21

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

214 Gentilly-2 Nuclear Generating Station

The Gentilly-2 Nuclear Generating Station owned and operated by Hydro-Queacutebec has a single reactor that began operating in 1982 The facility is located on the south shore of the St Lawrence River near Trois-Riviegraveres Queacutebec

Figures 213ndash216 present dose information for the Gentilly-2 Nuclear Generating Station from 2001 to 2007

Figure 213 Average Dose Trends for Gentilly-2 Nuclear Generating Stati on (Based o n N on-Zero R esults)

0

05

1

15

2

25

3

35

4

45

)S

v(m

e os

D

Year

22

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 214 Average Dose Trends for Gentilly-2 Nuclear Generating Stati on (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

)S

v(m

e os

D

Year

Figure 215 Collective Dose Trends for Gentilly-2 Nuclear Generating Stati on

0

500

1000

1500

2000

2500

3000

3500

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Neutrons

External

Tritium

Year

23

000-0

009

001-5

00

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 216 Distribution of Effective Doses Among All Workers at Gentilly-2 Nuclear Generating Station

2500

2000

1500

1000

500

0

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

24

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

215 Point Lepreau Nuclear Generating Station

The Point Lepreau Nuclear Generating Station has one reactor that began operating in 1982 Owned and operated by New Brunswick Power Nuclear the station is located in Point Lepreau New Brunswick about 40 km west of Saint John on the shores of the Bay of Fundy

Figures 217ndash220 present dose information for the Point Lepreau Nuclear Generating Station from 2001 to 2007

Figure 217 Average Dose Trends for Point Lepreau N uclear Generating Stati on (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

)S

v(m

e os

D

Tritium Neutron External Effective

Year

25

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 218 Average Dose Trends for Point Lepreau N uclear Generating Stati on (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

)S

v(m

e os

D

Tritium Neutrons External Effective

Year

Figure 219 Collective Dose Trends for Point Lepreau N uclear Generating Station

0

200

400

600

800

1000

1200

1400

1600

1800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Neutrons

External

Tritium

Year

26

0

1400

1200

1000

800

600

400

200

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 220 Distribution of Effective Doses Among All Workers at Point Lepreau Nuclear Generating Station

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

27

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

22 Uranium Mines and Mills This section presents dose information for mine and mill sites in the following regions

bull Cluff Lake (Section 221) bull McClean Lake (Section 222) bull McArthur River (Section 223) bull Key Lake (Section 224) bull Cigar Lake (Section 225) bull Rabbit Lake (Section 226)

Graphs indicate the following data for each site from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for uranium mines and mills

1 Effective doses are composed of the following reported components bull doses from photons (labelled on the charts as ldquoexternalrdquo) bull doses from radon progeny bull doses from long-lived radioactive dust bull doses from radon gas (in some cases)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of photon radon progeny long-lived radioactive dust and radon gas doses

3 The NDR lists radon progeny in working level months (WLM) For this report radon progeny exposures were converted4 to doses expressed in mSv

221 Cluff Lake Operation

The Cluff Lake mining facilities operated by AREVA Resources Canada Inc are located in northwestern Saskatchewan Work began in 1980 and ended in 2002 with the site now being decommissioned The site consisted of three open-pit and two underground mines a mill and a tailings management facility During 2005 and 2006 most of the infrastructure was removed and the affected areas were remediated

Figures 221ndash224 present dose information for the Cluff Lake operation from 2001 to 2007

4 Doses were converted using the International Commission on Radiation Protection (ICRP)rsquos conversion convention of 1 WLM = 5 mSv This convention was established in the ICRP publication Protection against Radon at Home and at Work (ICRP 65)

28

Long-lived radioactive dust Radon progeny External Effective

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 221 Average Dose Trends for the Cluff Lake Operation (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

Year

Figure 222 Average Dose Trends for the Cluff Lake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

200

Long-lived radioactive dust Radon progeny External Effective

)S

v(m

e os

D)

Sv

(me

osD

Year

29

600

500

400

300

200

100

0

External Radon progeny Long-lived radioactive dust

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 223 Collective Dose Trends for the Cluff Lake Operation s

erkor

of W

ber

Num

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Year

Figure 224 Distribution o f Effective Doses Among A ll Workers at the Cluff Lake Operation

0

20

40

60

80

100

120

140

160

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

30

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

222 McClean Lake Operation

AREVA Resources Canada Inc runs the McClean Lake mining operation in northeastern Saskatchewan It comprises open pit mines a mill and a tailings management facility Mining began in 1995 while milling started in 1999

Figures 225ndash228 present dose information for the McClean Lake operation from 2001 to 2007

Figure 225 Average Dose Trends for the McClean L ake Operation (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

31

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 226 Average Dose Trends for the McClean L ake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 227 Collective Dose Trends for the McClean L ake Operation

0

100

200

300

400

500

600

700

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External

Radon progeny

Long-lived radioactive dust

Year

32

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 228 Distribution o f Effective Doses Among A ll Workers at the McClean Lake Operation

0

100

200

300

400

500

600

700

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

33

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

223 McArthur River Operation

Cameco Corporation operates the McArthur River underground mine in north-central Saskatchewan Ore from the mine which began production in 1999 is processed at the Key Lake Mill located 80 km south of McArthur River

Figures 229ndash232 present dose information for the McArthur River operation from 2001 to 2007

Figure 229 Average Dose Trends for the McArthur River Operation (Based o n N on-Zero R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

34

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 230 Average Dose Trends for the McArthur River Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

Figure 231 Collective Dose Trends for the McArthur River Operation

0

200

400

600

800

1000

1200

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Radon gas External Radon progeny Long-lived radioactive dust

Year

35

00

0-000

9

001-5

00

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 232 Distribution o f Effective Doses Among A ll Workers at the McArthur River Operation

0

100

200

300

400

500

600

700

800

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

36

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

224 Key Lake Operation

Cameco Corporation operates mining facilities in Key Lake located in north-central Saskatchewan The Key Lake operation includes two mined-out open pit mines (used for tailings management) a mill and two dry tailings management facilities Mining began in 1983 and ceased in 1997 the mill continued to process ore from the McArthur River mine during the reporting period

Figures 233ndash236 present dose information for the Key Lake operation from 2001 to 2007

Figure 233 Average Dose Trends for the Key Lake Operation (Based o n N on-Zero R esults)

00

20

40

60

80

00

20

40

60

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

37

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

00

20

40

60

80

00

20

40

60

Figure 234 Average Dose Trends for the Key Lake Operation (Based o n A ll Monitoring R esults)

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 235 Collective Dose Trends for the Key Lake Operation

0

100

200

300

400

500

600

700

800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External Radon progeny Long-lived radioactive dust

Year

38

00

0-000

9

001-5

0

501-1

000

gt 1001

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 236 Distribution o f Effective Doses Among A ll Workers at the Key Lake Operation

0

200

400

600

800

1000

1200

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose Range (mSv)

39

se

(mS

v)o

D

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

225 Cigar Lake Operation

Cameco Corporation manages the Cigar Lake underground mine located in northern Saskatchewan at the southern end of Waterbury Lake The mine was under construction at the time of this reportrsquos publication Test mining in ore was carried out in 1991 1992 and 2000

Figures 237ndash240 present dose information for the Cigar Lake operation from

Figure 2 37 Average D ose T rends fo r th e C igar L ake O peration (Based on Non-Zero Results)

2001 to 2007

Year

000

005

010

015

020

025

Long-lived radioactive dust Radon Progeny External Effective

40

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 238 Average Dose Trends for the Cigar Lake Operation (Based on All Monitoring Results)

000

005

010

015

020

025

030

035

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny

External

Effective

Year

Figure 239 Collective Dose Trends for the Cigar Lake Operation

0

50

100

150

200

250

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

External Radon progeny Long-lived radioactive dust

Year

41

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 240 Distribution of Effective Doses Among All Workers at the Cigar Lake Operation

0

200

400

600

800

1000

1200

1400

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

42

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

226 Rabbit Lake Operation

Cameco Corporation owns and operates mining facilities in Rabbit Lake located in north-eastern Saskatchewan Facilities include an underground mine four mined-out open-pit mines a mill and two tailings management facilities Mining and milling began in 1975

Figures 241ndash244 present dose information for the Rabbit Lake operation from 2001 to 2007

Figure 241 Average Dose Trends for the Rabbit Lake Operation (Based on Non-Zero Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

43

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 242 Average Dose Trends for the Rabbit Lake Operation (Based on All Monitoring Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

Figure 243 Collective Dose Trends for the Rabbit Lake Operation

0

200

400

600

800

1000

1200

1400

1600

1800

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Radon gas External Radon progeny Long-lived radioactive dust

Year

44

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

gt300

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 244 Distribution of Effective Doses Among All Workers at the Rabbit Lake Operation

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

900

800

700

600

500

400

300

200

100

0

Dose (mSv)

45

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

23 Uranium Refineries This section presents data for the following two facilities

bull a uranium refining facility in Blind River (Section 231) bull a uranium conversion facility in Port Hope (Section 232)

Graphs indicate the following average doses at each facility from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Note on data for uranium refineries

1 Doses from photons from external sources are measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay and lung counting Historically while these internal doses have been measured they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

231 Blind River Refinery

Cameco Corporation owns and is licensed to operate a uranium refinery in Blind River Ontario The facility which began operating in 1983 converts uranium ore concentrate to uranium trioxide The uranium trioxide is shipped to Camecorsquos uranium conversion facility in Port Hope Ontario where it is processed into uranium dioxide (for use in the fabrication of fuel for nuclear reactors in Canada) or uranium hexafluoride (exported for enrichment and fabrication into fuel for nuclear power reactors around the world)

Figures 245ndash248 present dose information for the Blind River refinery from 2001 to 2007

46

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 245 Average Dose Trends for the Blind River Refinery (Based on Non-Zero Results)

0

05

1

15

2

25

Year

Figure 246 Average Dose Trends for the Blind River Refinery (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

47

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 247 Collective Dose Trends for the Blind River Refinery

0

50

100

150

200

250

300 C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 248 Distribution of Effective Doses Among All Workers at the Blind River Refinery

0

20

40

60

80

100

120

140

160

180

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

48

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

232 Port Hope Conversion Facility

Cameco Corporation owns and is licensed to operate a uranium conversion facility in Port Hope Ontario The facility processes uranium trioxide received from the refinery in Blind River into uranium dioxide and uranium hexafluoride

Figures 249ndash252 present dose information for the Port Hope uranium conversion facility from 2001 to 2007

Figure 249 Average Dose Trends for the Port Hope Conversion Facility (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

49

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 250 Average Dose Trends for the Port Hope Conversion Facility (Based on All Monitoring Results)

0

01

02

03

04

05

06

07

08

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 251 Collective Dose Trends for the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

50

000-0

009

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 252 Distribution of Effective Doses Among All Workers at the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

400

450

500

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

51

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

24 Fuel Fabrication Facilities This section presents data for three nuclear fuel fabrication facilities

bull Two facilities owned and operated by General Electric Canada Inc (Section 241) bull One facility in Port Hope operated by Zircatec Precision Industries (Section 242)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average doses

Notes on data for fuel fabrication facilities

1 Effective doses for the three facilities are composed of the following reported components bull dose from photons (labelled on the charts as ldquoexternalrdquo) bull doses from internal intakes of uranium dust (long-lived radioactive dust) from

uranium in air concentrations (for General Electricrsquos Toronto facility only)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components photon doses and doses from long-lived radioactive dust

241 General Electric Nuclear Fuel Facilities

General Electric Canada Inc operates two nuclear fuel facilities in Ontario

bull At the Toronto facility uranium dioxide pellets are produced from natural or depleted uranium dioxide powder

bull At the Peterborough facility uranium dioxide fuel bundles are created from the pellets produced at the Toronto facility

Figures 253ndash256 present dose information for General Electric Canada Incrsquos fuel fabrication facilities from 2001 to 2007 Graphs do not distinguish between the doses received at the Peterborough facility versus those at the Toronto facility

52

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 253 Average Dose Trends for the General Electric Fuel Facility (Based on Non-Zero Results Only)

0

05

1

15

2

25

3

35

Long Lived Radioactive Dust External Effective

Year

Figure 254 Average Dose Trends for the General Electric Fuel Facility (Based on All Monitoring Results)

0

05

1

15

2

25

3

Long Lived Radioactive Dust External Effective

Year

Dos

e (m

Sv)

Dos

e (m

Sv)

53

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 255 Collective Dose Trends for the General Electric Fuel Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Long Lived Radioactive Dust External

Year

Figure 256 Distribution of Effective Doses among all Workers at the General Electric Fuel Facility

0

10

20

30

40

50

60

70

80

90

100

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

54

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

242 Zircatec Nuclear Fuel Facility

Zircatec Precision Industries Inc operates a nuclear fuel facility in Port Hope Ontario where it makes fuel pellets from uranium dioxide powder received from Port Hopersquos uranium conversion facility The nuclear fuel facility also manufactures fuel bundles for nuclear reactors in Canada

Notes on data for the Zircatec nuclear fuel facility

1 Graphs indicate the following data bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of average effective doses

2 Doses from photons from external sources were measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay Historically although these internal doses have been measured and submitted to the CNSC they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

Figures 257ndash260 present dose information for the Zircatec nuclear fuel facility from 2001 to 2007

Figure 257 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on Non-Zero Results)

0

05

1

15

2

25

3

35

Effe

ctiv

e D

ose

(mS

v)

Year

55

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 258 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

18

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 259 Collective Dose Trends for the Zircatec Nuclear Fuel Facility

0

50

100

150

200

250

300

350

400

450

500

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

56

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 260 Distribution of Effective Doses Among All Workers at the Zircatec Nuclear Fuel Facility

300

Num

ber o

f Wor

kers

250

200

150

100

50

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

57

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

25 Research and Radioisotope Production Facilities This section presents dose information for the following research and radioisotope production facilities from 2001 to 2007

bull Chalk River Laboratories and Whiteshell Laboratories (Section 251) bull A radioisotope production facility operated by MDS Nordion (Section 252) bull The Tri-University Meson Facility (TRIUMF) (Section 253)

Note on data for research and radioisotope production facilities

1 Graphs indicate the following data for each facility bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of effective doses

251 Chalk River Laboratories and Whiteshell Laboratories

Atomic Energy of Canada Limited (AECL) owns and is licensed to operate Chalk River Laboratories and Whiteshell Laboratories

Situated in Renfrew County on the south shore of the Ottawa River the Chalk River Laboratories site hosts the National Research Universal Reactor along with numerous other facilities occupying some 160 buildings in an area of approximately 40 km2 Activities consist of radioisotope production for nuclear medicine testing and development of structural materials in support of power reactor operations fuel fabrication research and radioactive waste management and storage

The Whiteshell Laboratories site is located approximately 10 km west of Pinawa Manitoba and 100 km northeast of Winnipeg on the east bank of the Winnipeg River AECL established the laboratories for nuclear research and testing during the early 1960s and has since discontinued operations which are being decommissioned under a licence from the CNSC

Figures 261ndash264 present dose information for Chalk River Laboratories and Whiteshell Laboratories from 2001 to 2007

Notes on data for Chalk River Laboratories and Whiteshell Laboratories

1 Effective doses are composed of the following reported components bull external doses5 (from both photon and neutron doses) bull tritium doses

Due to issues with AECLrsquos in-house dosimetry management system neutron doses were not reported separately to the NDR during the reporting period As a result external doses from photons and neutrons were totaled The reporting discrepancy has since been rectified

58

5

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of external (photon and neutron) and tritium doses Intakes of other radionuclides occasionally occur and these radionuclides are not included here because their associated doses are very small For this reason certain collective doses in this report may have values slightly lower than the sum of their respective components as listed

Figure 261 Average Dose Trends for Chalk River and Whiteshell Laboratories (Non-Zero Results Only)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Tritium External Effective

Year

59

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 262 Average Dose Trends for Chalk River and Whiteshell Laboratories (All Monitoring Results)

000

020

040

060

080

100

120

Dos

e (m

Sv)

Tritium External Effective

Year

Figure 263 Collective Dose Trends for Chalk River and Whiteshell Laboratories

0

500

1000

1500

2000

2500

3000

3500

Col

lect

ive

Dos

e (p

erso

n- m

Sv)

External Tritium

Year

60

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 264 Distribution of Effective Doses Among All Workers at Chalk River and Whiteshell Laboratories

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

3500

3000

2500

2000

1500

1000

500

Dose (mSv)

61

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

252 MDS Nordion (Nuclear Substance Processing Facility and Canadian Irradiation Centre)

MDS Nordion owns and operates a nuclear substance processing facility in Ottawa Ontario where it processes unsealed radioisotopes and manufactures sealed radiation sources In operation since the early 1970s the facility was purchased by Nordion International in 1991

In cooperation with the Universiteacute du Queacutebecrsquos Institut Armand-Frappier MDS Nordion also operates the Canadian Irradiation Centre which conducts various irradiation services which include training testing and development The centre is located in Laval Quebec on the Universiteacute du Queacutebec campus

Figures 265ndash268 present dose information for MDS Nordionrsquos Ottawa nuclear substance processing facility and for the Canadian Irradiation Centre from 2001 to 2007

Notes on data for MDS Nordionrsquos nuclear substance processing facility and the Canadian Irradiation Centre

1 Doses from photons from external sources were measured and reported to the NDR MDS Nordion also has a routine thyroid monitoring program very occasionally small recordable doses of radiation have occurred from thyroid uptake of iodine The resulting doses have not been historically submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided

Figure 265 Average Dose Trends for MDS Nordion (Based on Non-Zero Results)

0

05

1

15

2

25

Effe

ctiv

e D

ose

(mS

v)

Year

62

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 266 Average Dose Trends for MDS Nordion (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

Figure 267 Collective Dose Trends for MDS Nordion

0

100

200

300

400

500

600

700

800

Year

63

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 268 Distribution of Effective Doses Among All Workers at MDS Nordion

0

5 0

1 0 0

1 5 0

2 0 0

2 5 0

3 0 0

3 5 0

4 0 0

4 5 0

5 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

64

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

253 Tri-University Meson Facility

The Tri-University Meson facility (TRIUMF) is situated in Vancouver on the campus of the University of British Columbia TRIUMF which began operating in the early 1970s with one cyclotron now has two cyclotrons and associated laboratories for research and radioisotope production The laboratory provides research facilities for Canadian and international users and also produces radioisotopes which are used by medical facilities and by a commercial organization (MDS Nordion) MDS Nordion staff also work at the TRIUMF site however MDS Nordion oversees this work and has its own radiation protection program

Figures 269ndash272 present dose information for the TRIUMF facility from 2001 to 2007 Please note that data sets do not distinguish between doses received by TRIUMF staff and MDS Nordion staff who work on the site as the data for these two groups was submitted collectively to the NDR for the reporting period shown Future data for each group will be submitted separately to the NDR

Note on data for TRIUMF

1 Effective doses are composed of the following reported components bull doses from photons (labeled as ldquoexternalrdquo in the charts) bull neutron doses

Figure 269 Average Dose Trends for TRIUMF (Non-Zero Results Only)

000

020

040

060

080

100

120

140

160

Dos

e (m

Sv)

Neutrons External Effective

Year

65

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 8: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

b Collective doses indicate the sum of all the doses associated with a facilityrsquos operation and can be used to estimate a facilityrsquos control of occupational doses

Note on collective doses

1 The Radiation Protection Regulations do not set limits on collective doses however the CNSC recommends that licensee radiation protection programs should aim to reduce collective doses These values can indicate a facilityrsquos radiological detriment and help assess whether a facility is operating in accordance with the ALARA principle

c Distribution of effective doses shows the ranges in which effective doses are concentrated

Effective dose calculations By definition effective doses cannot be measured precisely but they can be approximated in order to determine radiation exposure and to assess the associated risks Section 13 of the Radiation Protection Regulations defines the dose calculation methods used to determine effective doses as expressed in millisieverts (mSv) which are based on measurable quantities in the operational environment

Effective radiation doses are made up of various components of which the most common (in Canada) are as follows

bull photons and neutrons from sources outside the body bull radon progeny radon gas long-lived radioactive dust (uranium dust) and tritium that are

taken into the body

The effective doses reported to the NDR represent the sum of their applicable components For example the effective dose to a worker who received radiation doses from both neutrons and tritium would be the sum of these two quantities

Note on average dose values

1 Average values for each dose type (for example tritium) are based on the total collective dose for that type divided by the number of all the workers monitored for any dose type

3

yrenfi R

erev

Ri

dnilB

noid N

orD

SM

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

10 Facility-Wide Comparisons of Average Effective Doses This section presents comparisons of average effective doses at all CNSC-licensed nuclear facilities included in this report for each year within the 2001ndash07 reporting period

bull Figures 11ndash17 present averages based on non-zero (positive) results (Section 11)bull Figures 18ndash114 present averages based on all monitoring results (Section 12)

Notes on facility-wide comparisons of average effective doses

1 Each facility type is represented by a different colour bull nuclear power plants ndash green bull uranium mines and mills ndash purple bull uranium refineries ndash yellow bull fuel fabrication facilities ndash orange bull research and radioisotope facilities ndash blue bull tritium light source production facilities ndash red

2 See Sections 21ndash26 for facility-specific data depicted in Figures 11ndash114

11 Average Effective Doses Based on Non-Zero Results at All Selected Facilities Figures 11ndash17 show average effective doses based on non-zero results for each year from 2001 to 2007 for all the facilities presented in this document

Figure 11 Average Effective Doses at All Selected F acilities for the Year 2001 (Based o n N on-Zero R esults)

4

35

3

25

2

15

1

05

0

) Sv

(me

osD

Bruc

e N

ucle

ar G

ener

atin

g St

atio

ns snotita

Sgntiarene Graelc

Nu

gnirekciP

notita

Sgntiarene Graelc

Nu

ntognilr

Da

notita

Sgntiarene Graelc

Nu

2-ylltineG

notita

Sgntiarene Graelc

Nu

uaerpet LnioP

notiarep Oeka

ff L

uC

l

notiarep Oeka

LnaeC

lc

M

rev R

iru

thrAcM

notiarep Oeka

LyeK

notiarep Oeka

LragC

i

notiarep Oeka

it L

bbR

a

tyilica Fnoisrevn

Co

ept H

oroP

setiilica Fleu

Fraelc N

ucitrcel

ElareneG

tyilical Feu

Fraelc N

uc

teacriZ

Cha

lk R

iver

Lab

orat

orie

s an

d W

hite

shel

lLa

bora

torie

s

tyilica Fnose

Mtyisrev

Uni

-irT

dtearoproc

Inecruo SdleihS

c In)adan

Ca

(seigolonhce T

RB

S

4

y

s n

Dos

e (m

Sv)

) Sv

(me

osD

4

35

3

25

2

15

1

05

0

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 12 Average Effective Doses at All Selected Facilities for the Year 2002 (Based on Non-Zero Results)

4

35

3

25

2

15

1

05

0

Bruc

e N

ucle

ar G

ener

atin

g St

atio

nsBr

uce

Nuc

lear

Gen

erat

ing

Stat

ions

Pick

erin

g N

ucle

ar G

ener

atin

g St

atio

n

Dar

lingt

on N

ucle

ar G

ener

atin

g St

atio

n

Gen

tilly

-2 N

ucle

ar G

ener

atin

g St

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Figure 13 Average Effective Doses at All Selected Facilities for the Year 2003 (Based on Non-Zero Results)

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Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 14 Average Effective Doses at All Selected Facilities for the Year 2004 (Based on Non-Zero Results)

4

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Figure 15 Average Effective Doses at All Selected Facilities for the Year 2005 (Based on Non-Zero Results)

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Figure 17 Average Effective Doses at All Selected Facilities for the Year 2007 (Based on Non-Zero Results)

4

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Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 16 Average Effective Doses at All Selected Facilities for the Year 2006 (Based on Non-Zero Results)

4

35

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Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

12 Average Effective Doses Based on All Monitoring Results at All Selected Facilities Figures 18ndash114 show average effective doses based on all the monitoring results for each year from 2001 to 2007 for every facility listed in this document

Figure 18 Average Effective Doses at All Selected F acilities for the Year 2001 (Based o n A ll Monitoring R esults)

8

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Figure 110 Average Effective Doses at All Selected F acilities for the Year 2003 (Based o n A ll Monitoring R esults)

4

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Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 19 Average Effective Doses at All Selected Facilities for the Year 2002 (Based on All Monitoring Results)

4

35

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Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 111 Average Effective Doses at All Selected F acilities for the Year 2004 (Based o n A ll Monitoring R esults)

4

35

3

25

2

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Figure 112 Average Effective Doses at All Selected F acilities for the Year 2005 (Based o n A ll Monitoring R esults)

4

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4

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Figure 114 Average Effective Doses at All Selected F acilities for the Year 2007 (Based o n A ll Monitoring R esults)

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Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 113 Average Effective Doses at All Selected Facilities for the Year 2006 (Based on All Monitoring Results)

4

35

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11

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

20 Facility-Specific Overview of Occupational Doses This section presents data for the following types of facilities

bull nuclear power plants (Section 21) bull uranium mines and mills (Section 22) bull uranium refineries (Section 23) bull fuel fabrication facilities (Section 24) bull research and radioisotope production facilities (Section 25) bull tritium production facilities (Section 26)

21 Nuclear Power Plants This section presents dose information for the following nuclear power plants

bull Bruce A and Bruce B Nuclear Generating Stations (Section 211) bull Pickering Nuclear Generating Stations (Section 212) bull Darlington Nuclear Generating Station Section 213) bull Gentilly-2 Nuclear Generating Station (Section 214) bull Point Lepreau Generating Station (Section 215)

Graphs in this section indicate the following data for each nuclear power plant from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for nuclear power plants

1 Effective doses are composed of the following reported components bull doses from photons (labeled on the charts as ldquoexternalrdquo) bull neutron doses bull tritium doses

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of photon neutron and tritium doses Intakes of other radionuclides (for example Iodine-131 or Carbon-14) occasionally occur but these radionuclides are not included here because the associated collective dose is very small For this reason certain collective dose values in this report may be slightly lower than the sum of their respective components as listed

12

1 2 3 4 5 6 70 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

211 Bruce Nuclear Generating Stations

Bruce Power owns and operates the Bruce Nuclear Generating Stations located near Kincardine Ontario on the shore of Lake Huron

bull Bruce A consists of four nuclear reactors (units 1ndash4) and began operating in 1976 bull Bruce B has four nuclear reactors (units 5ndash8) and started operating in 1984

As part of its extensive recovery program in 1997 the sitersquos previous operator Ontario Hydro (now Ontario Power Generation) temporarily shut down all Bruce A reactors and maintained them in a guaranteed shutdown state Units 3 and 4 were later returned to service (in October 2003 and January 2004) while Units 1 and 2 remained in a guaranteed shutdown state

Figures 21ndash24 present dose information for the Bruce Nuclear Generating Stations from 2001 to 2007 Graphs do not distinguish between doses received at Bruce A versus Bruce B

Fig 21 Average Dose Trends for Bruce Nuclear Generating Stati on (Based o n N on-Zero R esults)

Dos

e (m

Sv)

4

35

3

25

2

15

1

05

0

Tritium Neutron External Effective

Year

13

Neutrons External Tritium

0 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 21 2 3 4 5 6 7

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

0

2

4

6

8

1

2

4

0

0

0

0

1

1

Figure 22 Average Dose Trends for Bruce Nuclear Generating Stati on (Based o n A ll Monitoring R esults)

16

)S

v(m

e os

D

Tritium Neutrons External Effective

Year

Figure 23 Collective Dose Trends for Bruce Nuclear Generating Stati on

8000

7000

6000

5000

4000

3000

2000

1000

0

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Year

14

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 24 Distribution of Effective Doses Among All Workers at Bruce Nuclear Generating Station

6000

5000

4000

3000

2000

1000

0 9 0 0

1-50 0 0 1 0 0 0 0 00 5 0 0 0

0-000

000 1-1 1-1 1-20 1-3 3gt0 0 0 05 0 5 01 1 2

Num

ber o

f Wor

kers

Dose Range (mSv)

15

1 2 3 4 5 6 7 0 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

212 Pickering Nuclear Generating Stations

Located in Pickering Ontario the Pickering Nuclear Generating Stations are owned and operated by Ontario Power Generation Two generating stations are located within one enclosure

bull Pickering A consists of four nuclear reactors (units 1 to 4) that began operating in 1971 bull Pickering B consists of four nuclear reactors (units 5 to 8) that began operating in 1982

As part of its extensive recovery program Ontario Hydro (now Ontario Power Generation) temporarily shut down all Pickering A reactors in 1997 and maintained them in a guaranteed shutdown state Unit 4 was restarted in September 2003 and Unit 1 was restarted in March 2005 Units 2 and 3 remain in a guaranteed shutdown state

Figures 25ndash28 present dose information for the Pickering Nuclear Generating Stations from 2001 to 2007 Graphs do not distinguish between doses received at Pickering A versus those received at Pickering B

Figure 25 Average Dose Trends for Pickering N uclear Generating Stati on (Based o n N on-Zero R esults)

25

2

15

1

05

0

)S

v(m

e os

D

Tritium Neutrons External Effective

Year

16

Tritium Neutrons External Effective

Neutrons External Tritium

1 2 3 4 5 6 70 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

1 2 3 4 5 6 7 0 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 26 Average Dose Trends for Pickering N uclear Generating Stati on (Based o n A ll Monitoring R esults)

12

1

08

06

04

02

0

Year

Figure 27 Collective Dose Trends for Pickering N uclear Generating Stati on

12000

10000

8000

6000

4000

2000

0

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

)

Sv

(me

osD

Year

17

2001 2002 2003 2004 2005 2006 2007

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 28 Distribution o f Effective Doses Among A ll Workers at Pickering Nuclear Generating Stati on

6000

5000

4000

3000

2000

1000

0

Num

ber o

f Wor

kers

Dose Range (mSv)

18

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

213 Darlington Nuclear Generating Station

Owned and operated by Ontario Power Generation the Darlington Nuclear Generating Station has four nuclear reactors the first of which began operating in 1989 The facility is located near Bowmanville on the shore of Lake Ontario

Figures 29ndash212 present dose information for the Darlington Nuclear Generating Station from 2001 to 2007

Figure 29 Average Dose Trends for Darlington N uclear Generating Stati on (Non- Zero R esults Only)

)S

v(m

e os

D

250

200

150

100

050

000

Year

19

Tritium Neutrons External Effective

Neutrons External Tritium

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 210 Average Dose Trends for Darlington N uclear Generating Stati on (All Monitoring R esults)

090

080

070

060

050

040

030

020

010

000

)S

v(m

e os

D

Year

Figure 211 Collective Dose Trends for Darlington N uclear Generating Stati on

4500

4000

3500

3000

2500

2000

1500

1000

500

0

)vSm-nosrep (es

Do

eiv

llect

Co

Year

20

2001 2002 2003 2004 2005 2006 2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 212 Distribution o f Effective Doses Among A ll Workers at Darlington Nuclear Generating Stati on

0

500

1000

1500

2000

2500

3000

3500

ers

ork

W of

be

r um

N

Dose Range (mSv)

21

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

214 Gentilly-2 Nuclear Generating Station

The Gentilly-2 Nuclear Generating Station owned and operated by Hydro-Queacutebec has a single reactor that began operating in 1982 The facility is located on the south shore of the St Lawrence River near Trois-Riviegraveres Queacutebec

Figures 213ndash216 present dose information for the Gentilly-2 Nuclear Generating Station from 2001 to 2007

Figure 213 Average Dose Trends for Gentilly-2 Nuclear Generating Stati on (Based o n N on-Zero R esults)

0

05

1

15

2

25

3

35

4

45

)S

v(m

e os

D

Year

22

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 214 Average Dose Trends for Gentilly-2 Nuclear Generating Stati on (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

)S

v(m

e os

D

Year

Figure 215 Collective Dose Trends for Gentilly-2 Nuclear Generating Stati on

0

500

1000

1500

2000

2500

3000

3500

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Neutrons

External

Tritium

Year

23

000-0

009

001-5

00

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 216 Distribution of Effective Doses Among All Workers at Gentilly-2 Nuclear Generating Station

2500

2000

1500

1000

500

0

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

24

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

215 Point Lepreau Nuclear Generating Station

The Point Lepreau Nuclear Generating Station has one reactor that began operating in 1982 Owned and operated by New Brunswick Power Nuclear the station is located in Point Lepreau New Brunswick about 40 km west of Saint John on the shores of the Bay of Fundy

Figures 217ndash220 present dose information for the Point Lepreau Nuclear Generating Station from 2001 to 2007

Figure 217 Average Dose Trends for Point Lepreau N uclear Generating Stati on (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

)S

v(m

e os

D

Tritium Neutron External Effective

Year

25

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 218 Average Dose Trends for Point Lepreau N uclear Generating Stati on (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

)S

v(m

e os

D

Tritium Neutrons External Effective

Year

Figure 219 Collective Dose Trends for Point Lepreau N uclear Generating Station

0

200

400

600

800

1000

1200

1400

1600

1800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Neutrons

External

Tritium

Year

26

0

1400

1200

1000

800

600

400

200

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 220 Distribution of Effective Doses Among All Workers at Point Lepreau Nuclear Generating Station

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

27

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

22 Uranium Mines and Mills This section presents dose information for mine and mill sites in the following regions

bull Cluff Lake (Section 221) bull McClean Lake (Section 222) bull McArthur River (Section 223) bull Key Lake (Section 224) bull Cigar Lake (Section 225) bull Rabbit Lake (Section 226)

Graphs indicate the following data for each site from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for uranium mines and mills

1 Effective doses are composed of the following reported components bull doses from photons (labelled on the charts as ldquoexternalrdquo) bull doses from radon progeny bull doses from long-lived radioactive dust bull doses from radon gas (in some cases)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of photon radon progeny long-lived radioactive dust and radon gas doses

3 The NDR lists radon progeny in working level months (WLM) For this report radon progeny exposures were converted4 to doses expressed in mSv

221 Cluff Lake Operation

The Cluff Lake mining facilities operated by AREVA Resources Canada Inc are located in northwestern Saskatchewan Work began in 1980 and ended in 2002 with the site now being decommissioned The site consisted of three open-pit and two underground mines a mill and a tailings management facility During 2005 and 2006 most of the infrastructure was removed and the affected areas were remediated

Figures 221ndash224 present dose information for the Cluff Lake operation from 2001 to 2007

4 Doses were converted using the International Commission on Radiation Protection (ICRP)rsquos conversion convention of 1 WLM = 5 mSv This convention was established in the ICRP publication Protection against Radon at Home and at Work (ICRP 65)

28

Long-lived radioactive dust Radon progeny External Effective

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 221 Average Dose Trends for the Cluff Lake Operation (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

Year

Figure 222 Average Dose Trends for the Cluff Lake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

200

Long-lived radioactive dust Radon progeny External Effective

)S

v(m

e os

D)

Sv

(me

osD

Year

29

600

500

400

300

200

100

0

External Radon progeny Long-lived radioactive dust

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 223 Collective Dose Trends for the Cluff Lake Operation s

erkor

of W

ber

Num

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Year

Figure 224 Distribution o f Effective Doses Among A ll Workers at the Cluff Lake Operation

0

20

40

60

80

100

120

140

160

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

30

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

222 McClean Lake Operation

AREVA Resources Canada Inc runs the McClean Lake mining operation in northeastern Saskatchewan It comprises open pit mines a mill and a tailings management facility Mining began in 1995 while milling started in 1999

Figures 225ndash228 present dose information for the McClean Lake operation from 2001 to 2007

Figure 225 Average Dose Trends for the McClean L ake Operation (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

31

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 226 Average Dose Trends for the McClean L ake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 227 Collective Dose Trends for the McClean L ake Operation

0

100

200

300

400

500

600

700

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External

Radon progeny

Long-lived radioactive dust

Year

32

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 228 Distribution o f Effective Doses Among A ll Workers at the McClean Lake Operation

0

100

200

300

400

500

600

700

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

33

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

223 McArthur River Operation

Cameco Corporation operates the McArthur River underground mine in north-central Saskatchewan Ore from the mine which began production in 1999 is processed at the Key Lake Mill located 80 km south of McArthur River

Figures 229ndash232 present dose information for the McArthur River operation from 2001 to 2007

Figure 229 Average Dose Trends for the McArthur River Operation (Based o n N on-Zero R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

34

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 230 Average Dose Trends for the McArthur River Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

Figure 231 Collective Dose Trends for the McArthur River Operation

0

200

400

600

800

1000

1200

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Radon gas External Radon progeny Long-lived radioactive dust

Year

35

00

0-000

9

001-5

00

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 232 Distribution o f Effective Doses Among A ll Workers at the McArthur River Operation

0

100

200

300

400

500

600

700

800

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

36

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

224 Key Lake Operation

Cameco Corporation operates mining facilities in Key Lake located in north-central Saskatchewan The Key Lake operation includes two mined-out open pit mines (used for tailings management) a mill and two dry tailings management facilities Mining began in 1983 and ceased in 1997 the mill continued to process ore from the McArthur River mine during the reporting period

Figures 233ndash236 present dose information for the Key Lake operation from 2001 to 2007

Figure 233 Average Dose Trends for the Key Lake Operation (Based o n N on-Zero R esults)

00

20

40

60

80

00

20

40

60

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

37

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

00

20

40

60

80

00

20

40

60

Figure 234 Average Dose Trends for the Key Lake Operation (Based o n A ll Monitoring R esults)

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 235 Collective Dose Trends for the Key Lake Operation

0

100

200

300

400

500

600

700

800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External Radon progeny Long-lived radioactive dust

Year

38

00

0-000

9

001-5

0

501-1

000

gt 1001

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 236 Distribution o f Effective Doses Among A ll Workers at the Key Lake Operation

0

200

400

600

800

1000

1200

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose Range (mSv)

39

se

(mS

v)o

D

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

225 Cigar Lake Operation

Cameco Corporation manages the Cigar Lake underground mine located in northern Saskatchewan at the southern end of Waterbury Lake The mine was under construction at the time of this reportrsquos publication Test mining in ore was carried out in 1991 1992 and 2000

Figures 237ndash240 present dose information for the Cigar Lake operation from

Figure 2 37 Average D ose T rends fo r th e C igar L ake O peration (Based on Non-Zero Results)

2001 to 2007

Year

000

005

010

015

020

025

Long-lived radioactive dust Radon Progeny External Effective

40

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 238 Average Dose Trends for the Cigar Lake Operation (Based on All Monitoring Results)

000

005

010

015

020

025

030

035

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny

External

Effective

Year

Figure 239 Collective Dose Trends for the Cigar Lake Operation

0

50

100

150

200

250

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

External Radon progeny Long-lived radioactive dust

Year

41

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 240 Distribution of Effective Doses Among All Workers at the Cigar Lake Operation

0

200

400

600

800

1000

1200

1400

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

42

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

226 Rabbit Lake Operation

Cameco Corporation owns and operates mining facilities in Rabbit Lake located in north-eastern Saskatchewan Facilities include an underground mine four mined-out open-pit mines a mill and two tailings management facilities Mining and milling began in 1975

Figures 241ndash244 present dose information for the Rabbit Lake operation from 2001 to 2007

Figure 241 Average Dose Trends for the Rabbit Lake Operation (Based on Non-Zero Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

43

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 242 Average Dose Trends for the Rabbit Lake Operation (Based on All Monitoring Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

Figure 243 Collective Dose Trends for the Rabbit Lake Operation

0

200

400

600

800

1000

1200

1400

1600

1800

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Radon gas External Radon progeny Long-lived radioactive dust

Year

44

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

gt300

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 244 Distribution of Effective Doses Among All Workers at the Rabbit Lake Operation

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

900

800

700

600

500

400

300

200

100

0

Dose (mSv)

45

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

23 Uranium Refineries This section presents data for the following two facilities

bull a uranium refining facility in Blind River (Section 231) bull a uranium conversion facility in Port Hope (Section 232)

Graphs indicate the following average doses at each facility from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Note on data for uranium refineries

1 Doses from photons from external sources are measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay and lung counting Historically while these internal doses have been measured they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

231 Blind River Refinery

Cameco Corporation owns and is licensed to operate a uranium refinery in Blind River Ontario The facility which began operating in 1983 converts uranium ore concentrate to uranium trioxide The uranium trioxide is shipped to Camecorsquos uranium conversion facility in Port Hope Ontario where it is processed into uranium dioxide (for use in the fabrication of fuel for nuclear reactors in Canada) or uranium hexafluoride (exported for enrichment and fabrication into fuel for nuclear power reactors around the world)

Figures 245ndash248 present dose information for the Blind River refinery from 2001 to 2007

46

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 245 Average Dose Trends for the Blind River Refinery (Based on Non-Zero Results)

0

05

1

15

2

25

Year

Figure 246 Average Dose Trends for the Blind River Refinery (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

47

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 247 Collective Dose Trends for the Blind River Refinery

0

50

100

150

200

250

300 C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 248 Distribution of Effective Doses Among All Workers at the Blind River Refinery

0

20

40

60

80

100

120

140

160

180

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

48

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

232 Port Hope Conversion Facility

Cameco Corporation owns and is licensed to operate a uranium conversion facility in Port Hope Ontario The facility processes uranium trioxide received from the refinery in Blind River into uranium dioxide and uranium hexafluoride

Figures 249ndash252 present dose information for the Port Hope uranium conversion facility from 2001 to 2007

Figure 249 Average Dose Trends for the Port Hope Conversion Facility (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

49

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 250 Average Dose Trends for the Port Hope Conversion Facility (Based on All Monitoring Results)

0

01

02

03

04

05

06

07

08

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 251 Collective Dose Trends for the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

50

000-0

009

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 252 Distribution of Effective Doses Among All Workers at the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

400

450

500

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

51

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

24 Fuel Fabrication Facilities This section presents data for three nuclear fuel fabrication facilities

bull Two facilities owned and operated by General Electric Canada Inc (Section 241) bull One facility in Port Hope operated by Zircatec Precision Industries (Section 242)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average doses

Notes on data for fuel fabrication facilities

1 Effective doses for the three facilities are composed of the following reported components bull dose from photons (labelled on the charts as ldquoexternalrdquo) bull doses from internal intakes of uranium dust (long-lived radioactive dust) from

uranium in air concentrations (for General Electricrsquos Toronto facility only)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components photon doses and doses from long-lived radioactive dust

241 General Electric Nuclear Fuel Facilities

General Electric Canada Inc operates two nuclear fuel facilities in Ontario

bull At the Toronto facility uranium dioxide pellets are produced from natural or depleted uranium dioxide powder

bull At the Peterborough facility uranium dioxide fuel bundles are created from the pellets produced at the Toronto facility

Figures 253ndash256 present dose information for General Electric Canada Incrsquos fuel fabrication facilities from 2001 to 2007 Graphs do not distinguish between the doses received at the Peterborough facility versus those at the Toronto facility

52

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 253 Average Dose Trends for the General Electric Fuel Facility (Based on Non-Zero Results Only)

0

05

1

15

2

25

3

35

Long Lived Radioactive Dust External Effective

Year

Figure 254 Average Dose Trends for the General Electric Fuel Facility (Based on All Monitoring Results)

0

05

1

15

2

25

3

Long Lived Radioactive Dust External Effective

Year

Dos

e (m

Sv)

Dos

e (m

Sv)

53

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 255 Collective Dose Trends for the General Electric Fuel Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Long Lived Radioactive Dust External

Year

Figure 256 Distribution of Effective Doses among all Workers at the General Electric Fuel Facility

0

10

20

30

40

50

60

70

80

90

100

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

54

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

242 Zircatec Nuclear Fuel Facility

Zircatec Precision Industries Inc operates a nuclear fuel facility in Port Hope Ontario where it makes fuel pellets from uranium dioxide powder received from Port Hopersquos uranium conversion facility The nuclear fuel facility also manufactures fuel bundles for nuclear reactors in Canada

Notes on data for the Zircatec nuclear fuel facility

1 Graphs indicate the following data bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of average effective doses

2 Doses from photons from external sources were measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay Historically although these internal doses have been measured and submitted to the CNSC they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

Figures 257ndash260 present dose information for the Zircatec nuclear fuel facility from 2001 to 2007

Figure 257 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on Non-Zero Results)

0

05

1

15

2

25

3

35

Effe

ctiv

e D

ose

(mS

v)

Year

55

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 258 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

18

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 259 Collective Dose Trends for the Zircatec Nuclear Fuel Facility

0

50

100

150

200

250

300

350

400

450

500

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

56

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 260 Distribution of Effective Doses Among All Workers at the Zircatec Nuclear Fuel Facility

300

Num

ber o

f Wor

kers

250

200

150

100

50

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

57

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

25 Research and Radioisotope Production Facilities This section presents dose information for the following research and radioisotope production facilities from 2001 to 2007

bull Chalk River Laboratories and Whiteshell Laboratories (Section 251) bull A radioisotope production facility operated by MDS Nordion (Section 252) bull The Tri-University Meson Facility (TRIUMF) (Section 253)

Note on data for research and radioisotope production facilities

1 Graphs indicate the following data for each facility bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of effective doses

251 Chalk River Laboratories and Whiteshell Laboratories

Atomic Energy of Canada Limited (AECL) owns and is licensed to operate Chalk River Laboratories and Whiteshell Laboratories

Situated in Renfrew County on the south shore of the Ottawa River the Chalk River Laboratories site hosts the National Research Universal Reactor along with numerous other facilities occupying some 160 buildings in an area of approximately 40 km2 Activities consist of radioisotope production for nuclear medicine testing and development of structural materials in support of power reactor operations fuel fabrication research and radioactive waste management and storage

The Whiteshell Laboratories site is located approximately 10 km west of Pinawa Manitoba and 100 km northeast of Winnipeg on the east bank of the Winnipeg River AECL established the laboratories for nuclear research and testing during the early 1960s and has since discontinued operations which are being decommissioned under a licence from the CNSC

Figures 261ndash264 present dose information for Chalk River Laboratories and Whiteshell Laboratories from 2001 to 2007

Notes on data for Chalk River Laboratories and Whiteshell Laboratories

1 Effective doses are composed of the following reported components bull external doses5 (from both photon and neutron doses) bull tritium doses

Due to issues with AECLrsquos in-house dosimetry management system neutron doses were not reported separately to the NDR during the reporting period As a result external doses from photons and neutrons were totaled The reporting discrepancy has since been rectified

58

5

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of external (photon and neutron) and tritium doses Intakes of other radionuclides occasionally occur and these radionuclides are not included here because their associated doses are very small For this reason certain collective doses in this report may have values slightly lower than the sum of their respective components as listed

Figure 261 Average Dose Trends for Chalk River and Whiteshell Laboratories (Non-Zero Results Only)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Tritium External Effective

Year

59

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 262 Average Dose Trends for Chalk River and Whiteshell Laboratories (All Monitoring Results)

000

020

040

060

080

100

120

Dos

e (m

Sv)

Tritium External Effective

Year

Figure 263 Collective Dose Trends for Chalk River and Whiteshell Laboratories

0

500

1000

1500

2000

2500

3000

3500

Col

lect

ive

Dos

e (p

erso

n- m

Sv)

External Tritium

Year

60

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 264 Distribution of Effective Doses Among All Workers at Chalk River and Whiteshell Laboratories

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

3500

3000

2500

2000

1500

1000

500

Dose (mSv)

61

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

252 MDS Nordion (Nuclear Substance Processing Facility and Canadian Irradiation Centre)

MDS Nordion owns and operates a nuclear substance processing facility in Ottawa Ontario where it processes unsealed radioisotopes and manufactures sealed radiation sources In operation since the early 1970s the facility was purchased by Nordion International in 1991

In cooperation with the Universiteacute du Queacutebecrsquos Institut Armand-Frappier MDS Nordion also operates the Canadian Irradiation Centre which conducts various irradiation services which include training testing and development The centre is located in Laval Quebec on the Universiteacute du Queacutebec campus

Figures 265ndash268 present dose information for MDS Nordionrsquos Ottawa nuclear substance processing facility and for the Canadian Irradiation Centre from 2001 to 2007

Notes on data for MDS Nordionrsquos nuclear substance processing facility and the Canadian Irradiation Centre

1 Doses from photons from external sources were measured and reported to the NDR MDS Nordion also has a routine thyroid monitoring program very occasionally small recordable doses of radiation have occurred from thyroid uptake of iodine The resulting doses have not been historically submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided

Figure 265 Average Dose Trends for MDS Nordion (Based on Non-Zero Results)

0

05

1

15

2

25

Effe

ctiv

e D

ose

(mS

v)

Year

62

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 266 Average Dose Trends for MDS Nordion (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

Figure 267 Collective Dose Trends for MDS Nordion

0

100

200

300

400

500

600

700

800

Year

63

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 268 Distribution of Effective Doses Among All Workers at MDS Nordion

0

5 0

1 0 0

1 5 0

2 0 0

2 5 0

3 0 0

3 5 0

4 0 0

4 5 0

5 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

64

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

253 Tri-University Meson Facility

The Tri-University Meson facility (TRIUMF) is situated in Vancouver on the campus of the University of British Columbia TRIUMF which began operating in the early 1970s with one cyclotron now has two cyclotrons and associated laboratories for research and radioisotope production The laboratory provides research facilities for Canadian and international users and also produces radioisotopes which are used by medical facilities and by a commercial organization (MDS Nordion) MDS Nordion staff also work at the TRIUMF site however MDS Nordion oversees this work and has its own radiation protection program

Figures 269ndash272 present dose information for the TRIUMF facility from 2001 to 2007 Please note that data sets do not distinguish between doses received by TRIUMF staff and MDS Nordion staff who work on the site as the data for these two groups was submitted collectively to the NDR for the reporting period shown Future data for each group will be submitted separately to the NDR

Note on data for TRIUMF

1 Effective doses are composed of the following reported components bull doses from photons (labeled as ldquoexternalrdquo in the charts) bull neutron doses

Figure 269 Average Dose Trends for TRIUMF (Non-Zero Results Only)

000

020

040

060

080

100

120

140

160

Dos

e (m

Sv)

Neutrons External Effective

Year

65

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 9: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

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Ri

dnilB

noid N

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SM

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

10 Facility-Wide Comparisons of Average Effective Doses This section presents comparisons of average effective doses at all CNSC-licensed nuclear facilities included in this report for each year within the 2001ndash07 reporting period

bull Figures 11ndash17 present averages based on non-zero (positive) results (Section 11)bull Figures 18ndash114 present averages based on all monitoring results (Section 12)

Notes on facility-wide comparisons of average effective doses

1 Each facility type is represented by a different colour bull nuclear power plants ndash green bull uranium mines and mills ndash purple bull uranium refineries ndash yellow bull fuel fabrication facilities ndash orange bull research and radioisotope facilities ndash blue bull tritium light source production facilities ndash red

2 See Sections 21ndash26 for facility-specific data depicted in Figures 11ndash114

11 Average Effective Doses Based on Non-Zero Results at All Selected Facilities Figures 11ndash17 show average effective doses based on non-zero results for each year from 2001 to 2007 for all the facilities presented in this document

Figure 11 Average Effective Doses at All Selected F acilities for the Year 2001 (Based o n N on-Zero R esults)

4

35

3

25

2

15

1

05

0

) Sv

(me

osD

Bruc

e N

ucle

ar G

ener

atin

g St

atio

ns snotita

Sgntiarene Graelc

Nu

gnirekciP

notita

Sgntiarene Graelc

Nu

ntognilr

Da

notita

Sgntiarene Graelc

Nu

2-ylltineG

notita

Sgntiarene Graelc

Nu

uaerpet LnioP

notiarep Oeka

ff L

uC

l

notiarep Oeka

LnaeC

lc

M

rev R

iru

thrAcM

notiarep Oeka

LyeK

notiarep Oeka

LragC

i

notiarep Oeka

it L

bbR

a

tyilica Fnoisrevn

Co

ept H

oroP

setiilica Fleu

Fraelc N

ucitrcel

ElareneG

tyilical Feu

Fraelc N

uc

teacriZ

Cha

lk R

iver

Lab

orat

orie

s an

d W

hite

shel

lLa

bora

torie

s

tyilica Fnose

Mtyisrev

Uni

-irT

dtearoproc

Inecruo SdleihS

c In)adan

Ca

(seigolonhce T

RB

S

4

y

s n

Dos

e (m

Sv)

) Sv

(me

osD

4

35

3

25

2

15

1

05

0

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 12 Average Effective Doses at All Selected Facilities for the Year 2002 (Based on Non-Zero Results)

4

35

3

25

2

15

1

05

0

Bruc

e N

ucle

ar G

ener

atin

g St

atio

nsBr

uce

Nuc

lear

Gen

erat

ing

Stat

ions

Pick

erin

g N

ucle

ar G

ener

atin

g St

atio

n

Dar

lingt

on N

ucle

ar G

ener

atin

g St

atio

n

Gen

tilly

-2 N

ucle

ar G

ener

atin

g St

atio

n

Poin

t Lep

reau

Nuc

lear

Gen

erat

ing

Stat

ion

Clu

ff La

ke O

pera

tion

McC

lean

Lak

e O

pera

tio

McA

rthur

Riv

er

Key

Lake

Ope

ratio

n

Cig

ar L

ake

Ope

ratio

n

Rab

bit L

ake

Ope

ratio

n

Blin

d R

iver

Ref

iner

y

Port

Hop

e C

onve

rsio

n Fa

cilit

y

Gen

eral

Ele

ctric

Nuc

lear

Fue

l Fac

ilitie

s

Zirc

atec

Nuc

lear

Fue

l Fac

ility llehs

teih Wdn

a ses ie rir toto ara or bo ab La

Lrev R

ikla

Ch

MD

S N

ordi

on

Tri- U

nive

rsity

Mes

on F

acilit

y

Figure 13 Average Effective Doses at All Selected Facilities for the Year 2003 (Based on Non-Zero Results)

Pick

erin

g N

ucle

ar G

ener

atin

g St

atio

ns

Dar

lingt

on N

ucle

ar G

ener

atin

g St

atio

n

Gen

tilly

-2 N

ucle

ar G

ener

atin

g St

atio

n

Poin

t Lep

reau

Nuc

lear

Gen

erat

ing

Stat

ion

Clu

ff La

ke O

pera

tion

McC

lean

Lak

e O

pera

tion

McA

rthur

Riv

er

Key

Lake

Ope

ratio

n

Cig

ar L

ake

Ope

rat io

n

Rab

bit L

ake

Ope

ratio

n

Blin

d R

iver

Ref

iner

y

Port

Hop

e C

onve

rsio

n Fa

cilit

y

Gen

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Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 14 Average Effective Doses at All Selected Facilities for the Year 2004 (Based on Non-Zero Results)

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Figure 17 Average Effective Doses at All Selected Facilities for the Year 2007 (Based on Non-Zero Results)

4

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Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 16 Average Effective Doses at All Selected Facilities for the Year 2006 (Based on Non-Zero Results)

4

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Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

12 Average Effective Doses Based on All Monitoring Results at All Selected Facilities Figures 18ndash114 show average effective doses based on all the monitoring results for each year from 2001 to 2007 for every facility listed in this document

Figure 18 Average Effective Doses at All Selected F acilities for the Year 2001 (Based o n A ll Monitoring R esults)

8

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Figure 110 Average Effective Doses at All Selected F acilities for the Year 2003 (Based o n A ll Monitoring R esults)

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Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 19 Average Effective Doses at All Selected Facilities for the Year 2002 (Based on All Monitoring Results)

4

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Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 111 Average Effective Doses at All Selected F acilities for the Year 2004 (Based o n A ll Monitoring R esults)

4

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Figure 112 Average Effective Doses at All Selected F acilities for the Year 2005 (Based o n A ll Monitoring R esults)

4

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Figure 114 Average Effective Doses at All Selected F acilities for the Year 2007 (Based o n A ll Monitoring R esults)

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Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 113 Average Effective Doses at All Selected Facilities for the Year 2006 (Based on All Monitoring Results)

4

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Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

20 Facility-Specific Overview of Occupational Doses This section presents data for the following types of facilities

bull nuclear power plants (Section 21) bull uranium mines and mills (Section 22) bull uranium refineries (Section 23) bull fuel fabrication facilities (Section 24) bull research and radioisotope production facilities (Section 25) bull tritium production facilities (Section 26)

21 Nuclear Power Plants This section presents dose information for the following nuclear power plants

bull Bruce A and Bruce B Nuclear Generating Stations (Section 211) bull Pickering Nuclear Generating Stations (Section 212) bull Darlington Nuclear Generating Station Section 213) bull Gentilly-2 Nuclear Generating Station (Section 214) bull Point Lepreau Generating Station (Section 215)

Graphs in this section indicate the following data for each nuclear power plant from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for nuclear power plants

1 Effective doses are composed of the following reported components bull doses from photons (labeled on the charts as ldquoexternalrdquo) bull neutron doses bull tritium doses

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of photon neutron and tritium doses Intakes of other radionuclides (for example Iodine-131 or Carbon-14) occasionally occur but these radionuclides are not included here because the associated collective dose is very small For this reason certain collective dose values in this report may be slightly lower than the sum of their respective components as listed

12

1 2 3 4 5 6 70 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

211 Bruce Nuclear Generating Stations

Bruce Power owns and operates the Bruce Nuclear Generating Stations located near Kincardine Ontario on the shore of Lake Huron

bull Bruce A consists of four nuclear reactors (units 1ndash4) and began operating in 1976 bull Bruce B has four nuclear reactors (units 5ndash8) and started operating in 1984

As part of its extensive recovery program in 1997 the sitersquos previous operator Ontario Hydro (now Ontario Power Generation) temporarily shut down all Bruce A reactors and maintained them in a guaranteed shutdown state Units 3 and 4 were later returned to service (in October 2003 and January 2004) while Units 1 and 2 remained in a guaranteed shutdown state

Figures 21ndash24 present dose information for the Bruce Nuclear Generating Stations from 2001 to 2007 Graphs do not distinguish between doses received at Bruce A versus Bruce B

Fig 21 Average Dose Trends for Bruce Nuclear Generating Stati on (Based o n N on-Zero R esults)

Dos

e (m

Sv)

4

35

3

25

2

15

1

05

0

Tritium Neutron External Effective

Year

13

Neutrons External Tritium

0 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 21 2 3 4 5 6 7

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

0

2

4

6

8

1

2

4

0

0

0

0

1

1

Figure 22 Average Dose Trends for Bruce Nuclear Generating Stati on (Based o n A ll Monitoring R esults)

16

)S

v(m

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D

Tritium Neutrons External Effective

Year

Figure 23 Collective Dose Trends for Bruce Nuclear Generating Stati on

8000

7000

6000

5000

4000

3000

2000

1000

0

)S

von

-m(p

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De

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C

Year

14

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 24 Distribution of Effective Doses Among All Workers at Bruce Nuclear Generating Station

6000

5000

4000

3000

2000

1000

0 9 0 0

1-50 0 0 1 0 0 0 0 00 5 0 0 0

0-000

000 1-1 1-1 1-20 1-3 3gt0 0 0 05 0 5 01 1 2

Num

ber o

f Wor

kers

Dose Range (mSv)

15

1 2 3 4 5 6 7 0 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

212 Pickering Nuclear Generating Stations

Located in Pickering Ontario the Pickering Nuclear Generating Stations are owned and operated by Ontario Power Generation Two generating stations are located within one enclosure

bull Pickering A consists of four nuclear reactors (units 1 to 4) that began operating in 1971 bull Pickering B consists of four nuclear reactors (units 5 to 8) that began operating in 1982

As part of its extensive recovery program Ontario Hydro (now Ontario Power Generation) temporarily shut down all Pickering A reactors in 1997 and maintained them in a guaranteed shutdown state Unit 4 was restarted in September 2003 and Unit 1 was restarted in March 2005 Units 2 and 3 remain in a guaranteed shutdown state

Figures 25ndash28 present dose information for the Pickering Nuclear Generating Stations from 2001 to 2007 Graphs do not distinguish between doses received at Pickering A versus those received at Pickering B

Figure 25 Average Dose Trends for Pickering N uclear Generating Stati on (Based o n N on-Zero R esults)

25

2

15

1

05

0

)S

v(m

e os

D

Tritium Neutrons External Effective

Year

16

Tritium Neutrons External Effective

Neutrons External Tritium

1 2 3 4 5 6 70 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

1 2 3 4 5 6 7 0 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 26 Average Dose Trends for Pickering N uclear Generating Stati on (Based o n A ll Monitoring R esults)

12

1

08

06

04

02

0

Year

Figure 27 Collective Dose Trends for Pickering N uclear Generating Stati on

12000

10000

8000

6000

4000

2000

0

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

)

Sv

(me

osD

Year

17

2001 2002 2003 2004 2005 2006 2007

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 28 Distribution o f Effective Doses Among A ll Workers at Pickering Nuclear Generating Stati on

6000

5000

4000

3000

2000

1000

0

Num

ber o

f Wor

kers

Dose Range (mSv)

18

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

213 Darlington Nuclear Generating Station

Owned and operated by Ontario Power Generation the Darlington Nuclear Generating Station has four nuclear reactors the first of which began operating in 1989 The facility is located near Bowmanville on the shore of Lake Ontario

Figures 29ndash212 present dose information for the Darlington Nuclear Generating Station from 2001 to 2007

Figure 29 Average Dose Trends for Darlington N uclear Generating Stati on (Non- Zero R esults Only)

)S

v(m

e os

D

250

200

150

100

050

000

Year

19

Tritium Neutrons External Effective

Neutrons External Tritium

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 210 Average Dose Trends for Darlington N uclear Generating Stati on (All Monitoring R esults)

090

080

070

060

050

040

030

020

010

000

)S

v(m

e os

D

Year

Figure 211 Collective Dose Trends for Darlington N uclear Generating Stati on

4500

4000

3500

3000

2500

2000

1500

1000

500

0

)vSm-nosrep (es

Do

eiv

llect

Co

Year

20

2001 2002 2003 2004 2005 2006 2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 212 Distribution o f Effective Doses Among A ll Workers at Darlington Nuclear Generating Stati on

0

500

1000

1500

2000

2500

3000

3500

ers

ork

W of

be

r um

N

Dose Range (mSv)

21

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

214 Gentilly-2 Nuclear Generating Station

The Gentilly-2 Nuclear Generating Station owned and operated by Hydro-Queacutebec has a single reactor that began operating in 1982 The facility is located on the south shore of the St Lawrence River near Trois-Riviegraveres Queacutebec

Figures 213ndash216 present dose information for the Gentilly-2 Nuclear Generating Station from 2001 to 2007

Figure 213 Average Dose Trends for Gentilly-2 Nuclear Generating Stati on (Based o n N on-Zero R esults)

0

05

1

15

2

25

3

35

4

45

)S

v(m

e os

D

Year

22

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 214 Average Dose Trends for Gentilly-2 Nuclear Generating Stati on (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

)S

v(m

e os

D

Year

Figure 215 Collective Dose Trends for Gentilly-2 Nuclear Generating Stati on

0

500

1000

1500

2000

2500

3000

3500

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Neutrons

External

Tritium

Year

23

000-0

009

001-5

00

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 216 Distribution of Effective Doses Among All Workers at Gentilly-2 Nuclear Generating Station

2500

2000

1500

1000

500

0

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

24

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

215 Point Lepreau Nuclear Generating Station

The Point Lepreau Nuclear Generating Station has one reactor that began operating in 1982 Owned and operated by New Brunswick Power Nuclear the station is located in Point Lepreau New Brunswick about 40 km west of Saint John on the shores of the Bay of Fundy

Figures 217ndash220 present dose information for the Point Lepreau Nuclear Generating Station from 2001 to 2007

Figure 217 Average Dose Trends for Point Lepreau N uclear Generating Stati on (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

)S

v(m

e os

D

Tritium Neutron External Effective

Year

25

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 218 Average Dose Trends for Point Lepreau N uclear Generating Stati on (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

)S

v(m

e os

D

Tritium Neutrons External Effective

Year

Figure 219 Collective Dose Trends for Point Lepreau N uclear Generating Station

0

200

400

600

800

1000

1200

1400

1600

1800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Neutrons

External

Tritium

Year

26

0

1400

1200

1000

800

600

400

200

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 220 Distribution of Effective Doses Among All Workers at Point Lepreau Nuclear Generating Station

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

27

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

22 Uranium Mines and Mills This section presents dose information for mine and mill sites in the following regions

bull Cluff Lake (Section 221) bull McClean Lake (Section 222) bull McArthur River (Section 223) bull Key Lake (Section 224) bull Cigar Lake (Section 225) bull Rabbit Lake (Section 226)

Graphs indicate the following data for each site from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for uranium mines and mills

1 Effective doses are composed of the following reported components bull doses from photons (labelled on the charts as ldquoexternalrdquo) bull doses from radon progeny bull doses from long-lived radioactive dust bull doses from radon gas (in some cases)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of photon radon progeny long-lived radioactive dust and radon gas doses

3 The NDR lists radon progeny in working level months (WLM) For this report radon progeny exposures were converted4 to doses expressed in mSv

221 Cluff Lake Operation

The Cluff Lake mining facilities operated by AREVA Resources Canada Inc are located in northwestern Saskatchewan Work began in 1980 and ended in 2002 with the site now being decommissioned The site consisted of three open-pit and two underground mines a mill and a tailings management facility During 2005 and 2006 most of the infrastructure was removed and the affected areas were remediated

Figures 221ndash224 present dose information for the Cluff Lake operation from 2001 to 2007

4 Doses were converted using the International Commission on Radiation Protection (ICRP)rsquos conversion convention of 1 WLM = 5 mSv This convention was established in the ICRP publication Protection against Radon at Home and at Work (ICRP 65)

28

Long-lived radioactive dust Radon progeny External Effective

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 221 Average Dose Trends for the Cluff Lake Operation (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

Year

Figure 222 Average Dose Trends for the Cluff Lake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

200

Long-lived radioactive dust Radon progeny External Effective

)S

v(m

e os

D)

Sv

(me

osD

Year

29

600

500

400

300

200

100

0

External Radon progeny Long-lived radioactive dust

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 223 Collective Dose Trends for the Cluff Lake Operation s

erkor

of W

ber

Num

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Year

Figure 224 Distribution o f Effective Doses Among A ll Workers at the Cluff Lake Operation

0

20

40

60

80

100

120

140

160

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

30

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

222 McClean Lake Operation

AREVA Resources Canada Inc runs the McClean Lake mining operation in northeastern Saskatchewan It comprises open pit mines a mill and a tailings management facility Mining began in 1995 while milling started in 1999

Figures 225ndash228 present dose information for the McClean Lake operation from 2001 to 2007

Figure 225 Average Dose Trends for the McClean L ake Operation (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

31

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 226 Average Dose Trends for the McClean L ake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 227 Collective Dose Trends for the McClean L ake Operation

0

100

200

300

400

500

600

700

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External

Radon progeny

Long-lived radioactive dust

Year

32

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 228 Distribution o f Effective Doses Among A ll Workers at the McClean Lake Operation

0

100

200

300

400

500

600

700

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

33

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

223 McArthur River Operation

Cameco Corporation operates the McArthur River underground mine in north-central Saskatchewan Ore from the mine which began production in 1999 is processed at the Key Lake Mill located 80 km south of McArthur River

Figures 229ndash232 present dose information for the McArthur River operation from 2001 to 2007

Figure 229 Average Dose Trends for the McArthur River Operation (Based o n N on-Zero R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

34

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 230 Average Dose Trends for the McArthur River Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

Figure 231 Collective Dose Trends for the McArthur River Operation

0

200

400

600

800

1000

1200

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Radon gas External Radon progeny Long-lived radioactive dust

Year

35

00

0-000

9

001-5

00

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 232 Distribution o f Effective Doses Among A ll Workers at the McArthur River Operation

0

100

200

300

400

500

600

700

800

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

36

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

224 Key Lake Operation

Cameco Corporation operates mining facilities in Key Lake located in north-central Saskatchewan The Key Lake operation includes two mined-out open pit mines (used for tailings management) a mill and two dry tailings management facilities Mining began in 1983 and ceased in 1997 the mill continued to process ore from the McArthur River mine during the reporting period

Figures 233ndash236 present dose information for the Key Lake operation from 2001 to 2007

Figure 233 Average Dose Trends for the Key Lake Operation (Based o n N on-Zero R esults)

00

20

40

60

80

00

20

40

60

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

37

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

00

20

40

60

80

00

20

40

60

Figure 234 Average Dose Trends for the Key Lake Operation (Based o n A ll Monitoring R esults)

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 235 Collective Dose Trends for the Key Lake Operation

0

100

200

300

400

500

600

700

800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External Radon progeny Long-lived radioactive dust

Year

38

00

0-000

9

001-5

0

501-1

000

gt 1001

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 236 Distribution o f Effective Doses Among A ll Workers at the Key Lake Operation

0

200

400

600

800

1000

1200

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose Range (mSv)

39

se

(mS

v)o

D

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

225 Cigar Lake Operation

Cameco Corporation manages the Cigar Lake underground mine located in northern Saskatchewan at the southern end of Waterbury Lake The mine was under construction at the time of this reportrsquos publication Test mining in ore was carried out in 1991 1992 and 2000

Figures 237ndash240 present dose information for the Cigar Lake operation from

Figure 2 37 Average D ose T rends fo r th e C igar L ake O peration (Based on Non-Zero Results)

2001 to 2007

Year

000

005

010

015

020

025

Long-lived radioactive dust Radon Progeny External Effective

40

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 238 Average Dose Trends for the Cigar Lake Operation (Based on All Monitoring Results)

000

005

010

015

020

025

030

035

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny

External

Effective

Year

Figure 239 Collective Dose Trends for the Cigar Lake Operation

0

50

100

150

200

250

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

External Radon progeny Long-lived radioactive dust

Year

41

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 240 Distribution of Effective Doses Among All Workers at the Cigar Lake Operation

0

200

400

600

800

1000

1200

1400

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

42

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

226 Rabbit Lake Operation

Cameco Corporation owns and operates mining facilities in Rabbit Lake located in north-eastern Saskatchewan Facilities include an underground mine four mined-out open-pit mines a mill and two tailings management facilities Mining and milling began in 1975

Figures 241ndash244 present dose information for the Rabbit Lake operation from 2001 to 2007

Figure 241 Average Dose Trends for the Rabbit Lake Operation (Based on Non-Zero Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

43

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 242 Average Dose Trends for the Rabbit Lake Operation (Based on All Monitoring Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

Figure 243 Collective Dose Trends for the Rabbit Lake Operation

0

200

400

600

800

1000

1200

1400

1600

1800

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Radon gas External Radon progeny Long-lived radioactive dust

Year

44

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

gt300

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 244 Distribution of Effective Doses Among All Workers at the Rabbit Lake Operation

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

900

800

700

600

500

400

300

200

100

0

Dose (mSv)

45

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

23 Uranium Refineries This section presents data for the following two facilities

bull a uranium refining facility in Blind River (Section 231) bull a uranium conversion facility in Port Hope (Section 232)

Graphs indicate the following average doses at each facility from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Note on data for uranium refineries

1 Doses from photons from external sources are measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay and lung counting Historically while these internal doses have been measured they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

231 Blind River Refinery

Cameco Corporation owns and is licensed to operate a uranium refinery in Blind River Ontario The facility which began operating in 1983 converts uranium ore concentrate to uranium trioxide The uranium trioxide is shipped to Camecorsquos uranium conversion facility in Port Hope Ontario where it is processed into uranium dioxide (for use in the fabrication of fuel for nuclear reactors in Canada) or uranium hexafluoride (exported for enrichment and fabrication into fuel for nuclear power reactors around the world)

Figures 245ndash248 present dose information for the Blind River refinery from 2001 to 2007

46

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 245 Average Dose Trends for the Blind River Refinery (Based on Non-Zero Results)

0

05

1

15

2

25

Year

Figure 246 Average Dose Trends for the Blind River Refinery (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

47

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 247 Collective Dose Trends for the Blind River Refinery

0

50

100

150

200

250

300 C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 248 Distribution of Effective Doses Among All Workers at the Blind River Refinery

0

20

40

60

80

100

120

140

160

180

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

48

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

232 Port Hope Conversion Facility

Cameco Corporation owns and is licensed to operate a uranium conversion facility in Port Hope Ontario The facility processes uranium trioxide received from the refinery in Blind River into uranium dioxide and uranium hexafluoride

Figures 249ndash252 present dose information for the Port Hope uranium conversion facility from 2001 to 2007

Figure 249 Average Dose Trends for the Port Hope Conversion Facility (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

49

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 250 Average Dose Trends for the Port Hope Conversion Facility (Based on All Monitoring Results)

0

01

02

03

04

05

06

07

08

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 251 Collective Dose Trends for the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

50

000-0

009

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 252 Distribution of Effective Doses Among All Workers at the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

400

450

500

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

51

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

24 Fuel Fabrication Facilities This section presents data for three nuclear fuel fabrication facilities

bull Two facilities owned and operated by General Electric Canada Inc (Section 241) bull One facility in Port Hope operated by Zircatec Precision Industries (Section 242)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average doses

Notes on data for fuel fabrication facilities

1 Effective doses for the three facilities are composed of the following reported components bull dose from photons (labelled on the charts as ldquoexternalrdquo) bull doses from internal intakes of uranium dust (long-lived radioactive dust) from

uranium in air concentrations (for General Electricrsquos Toronto facility only)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components photon doses and doses from long-lived radioactive dust

241 General Electric Nuclear Fuel Facilities

General Electric Canada Inc operates two nuclear fuel facilities in Ontario

bull At the Toronto facility uranium dioxide pellets are produced from natural or depleted uranium dioxide powder

bull At the Peterborough facility uranium dioxide fuel bundles are created from the pellets produced at the Toronto facility

Figures 253ndash256 present dose information for General Electric Canada Incrsquos fuel fabrication facilities from 2001 to 2007 Graphs do not distinguish between the doses received at the Peterborough facility versus those at the Toronto facility

52

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 253 Average Dose Trends for the General Electric Fuel Facility (Based on Non-Zero Results Only)

0

05

1

15

2

25

3

35

Long Lived Radioactive Dust External Effective

Year

Figure 254 Average Dose Trends for the General Electric Fuel Facility (Based on All Monitoring Results)

0

05

1

15

2

25

3

Long Lived Radioactive Dust External Effective

Year

Dos

e (m

Sv)

Dos

e (m

Sv)

53

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 255 Collective Dose Trends for the General Electric Fuel Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Long Lived Radioactive Dust External

Year

Figure 256 Distribution of Effective Doses among all Workers at the General Electric Fuel Facility

0

10

20

30

40

50

60

70

80

90

100

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

54

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

242 Zircatec Nuclear Fuel Facility

Zircatec Precision Industries Inc operates a nuclear fuel facility in Port Hope Ontario where it makes fuel pellets from uranium dioxide powder received from Port Hopersquos uranium conversion facility The nuclear fuel facility also manufactures fuel bundles for nuclear reactors in Canada

Notes on data for the Zircatec nuclear fuel facility

1 Graphs indicate the following data bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of average effective doses

2 Doses from photons from external sources were measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay Historically although these internal doses have been measured and submitted to the CNSC they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

Figures 257ndash260 present dose information for the Zircatec nuclear fuel facility from 2001 to 2007

Figure 257 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on Non-Zero Results)

0

05

1

15

2

25

3

35

Effe

ctiv

e D

ose

(mS

v)

Year

55

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 258 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

18

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 259 Collective Dose Trends for the Zircatec Nuclear Fuel Facility

0

50

100

150

200

250

300

350

400

450

500

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

56

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 260 Distribution of Effective Doses Among All Workers at the Zircatec Nuclear Fuel Facility

300

Num

ber o

f Wor

kers

250

200

150

100

50

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

57

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

25 Research and Radioisotope Production Facilities This section presents dose information for the following research and radioisotope production facilities from 2001 to 2007

bull Chalk River Laboratories and Whiteshell Laboratories (Section 251) bull A radioisotope production facility operated by MDS Nordion (Section 252) bull The Tri-University Meson Facility (TRIUMF) (Section 253)

Note on data for research and radioisotope production facilities

1 Graphs indicate the following data for each facility bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of effective doses

251 Chalk River Laboratories and Whiteshell Laboratories

Atomic Energy of Canada Limited (AECL) owns and is licensed to operate Chalk River Laboratories and Whiteshell Laboratories

Situated in Renfrew County on the south shore of the Ottawa River the Chalk River Laboratories site hosts the National Research Universal Reactor along with numerous other facilities occupying some 160 buildings in an area of approximately 40 km2 Activities consist of radioisotope production for nuclear medicine testing and development of structural materials in support of power reactor operations fuel fabrication research and radioactive waste management and storage

The Whiteshell Laboratories site is located approximately 10 km west of Pinawa Manitoba and 100 km northeast of Winnipeg on the east bank of the Winnipeg River AECL established the laboratories for nuclear research and testing during the early 1960s and has since discontinued operations which are being decommissioned under a licence from the CNSC

Figures 261ndash264 present dose information for Chalk River Laboratories and Whiteshell Laboratories from 2001 to 2007

Notes on data for Chalk River Laboratories and Whiteshell Laboratories

1 Effective doses are composed of the following reported components bull external doses5 (from both photon and neutron doses) bull tritium doses

Due to issues with AECLrsquos in-house dosimetry management system neutron doses were not reported separately to the NDR during the reporting period As a result external doses from photons and neutrons were totaled The reporting discrepancy has since been rectified

58

5

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of external (photon and neutron) and tritium doses Intakes of other radionuclides occasionally occur and these radionuclides are not included here because their associated doses are very small For this reason certain collective doses in this report may have values slightly lower than the sum of their respective components as listed

Figure 261 Average Dose Trends for Chalk River and Whiteshell Laboratories (Non-Zero Results Only)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Tritium External Effective

Year

59

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 262 Average Dose Trends for Chalk River and Whiteshell Laboratories (All Monitoring Results)

000

020

040

060

080

100

120

Dos

e (m

Sv)

Tritium External Effective

Year

Figure 263 Collective Dose Trends for Chalk River and Whiteshell Laboratories

0

500

1000

1500

2000

2500

3000

3500

Col

lect

ive

Dos

e (p

erso

n- m

Sv)

External Tritium

Year

60

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 264 Distribution of Effective Doses Among All Workers at Chalk River and Whiteshell Laboratories

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

3500

3000

2500

2000

1500

1000

500

Dose (mSv)

61

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

252 MDS Nordion (Nuclear Substance Processing Facility and Canadian Irradiation Centre)

MDS Nordion owns and operates a nuclear substance processing facility in Ottawa Ontario where it processes unsealed radioisotopes and manufactures sealed radiation sources In operation since the early 1970s the facility was purchased by Nordion International in 1991

In cooperation with the Universiteacute du Queacutebecrsquos Institut Armand-Frappier MDS Nordion also operates the Canadian Irradiation Centre which conducts various irradiation services which include training testing and development The centre is located in Laval Quebec on the Universiteacute du Queacutebec campus

Figures 265ndash268 present dose information for MDS Nordionrsquos Ottawa nuclear substance processing facility and for the Canadian Irradiation Centre from 2001 to 2007

Notes on data for MDS Nordionrsquos nuclear substance processing facility and the Canadian Irradiation Centre

1 Doses from photons from external sources were measured and reported to the NDR MDS Nordion also has a routine thyroid monitoring program very occasionally small recordable doses of radiation have occurred from thyroid uptake of iodine The resulting doses have not been historically submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided

Figure 265 Average Dose Trends for MDS Nordion (Based on Non-Zero Results)

0

05

1

15

2

25

Effe

ctiv

e D

ose

(mS

v)

Year

62

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 266 Average Dose Trends for MDS Nordion (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

Figure 267 Collective Dose Trends for MDS Nordion

0

100

200

300

400

500

600

700

800

Year

63

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 268 Distribution of Effective Doses Among All Workers at MDS Nordion

0

5 0

1 0 0

1 5 0

2 0 0

2 5 0

3 0 0

3 5 0

4 0 0

4 5 0

5 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

64

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

253 Tri-University Meson Facility

The Tri-University Meson facility (TRIUMF) is situated in Vancouver on the campus of the University of British Columbia TRIUMF which began operating in the early 1970s with one cyclotron now has two cyclotrons and associated laboratories for research and radioisotope production The laboratory provides research facilities for Canadian and international users and also produces radioisotopes which are used by medical facilities and by a commercial organization (MDS Nordion) MDS Nordion staff also work at the TRIUMF site however MDS Nordion oversees this work and has its own radiation protection program

Figures 269ndash272 present dose information for the TRIUMF facility from 2001 to 2007 Please note that data sets do not distinguish between doses received by TRIUMF staff and MDS Nordion staff who work on the site as the data for these two groups was submitted collectively to the NDR for the reporting period shown Future data for each group will be submitted separately to the NDR

Note on data for TRIUMF

1 Effective doses are composed of the following reported components bull doses from photons (labeled as ldquoexternalrdquo in the charts) bull neutron doses

Figure 269 Average Dose Trends for TRIUMF (Non-Zero Results Only)

000

020

040

060

080

100

120

140

160

Dos

e (m

Sv)

Neutrons External Effective

Year

65

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 10: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

y

s n

Dos

e (m

Sv)

) Sv

(me

osD

4

35

3

25

2

15

1

05

0

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 12 Average Effective Doses at All Selected Facilities for the Year 2002 (Based on Non-Zero Results)

4

35

3

25

2

15

1

05

0

Bruc

e N

ucle

ar G

ener

atin

g St

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Nuc

lear

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Stat

ions

Pick

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g N

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ar G

ener

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atio

n

Dar

lingt

on N

ucle

ar G

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g St

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tilly

-2 N

ucle

ar G

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Poin

t Lep

reau

Nuc

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Gen

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ion

Clu

ff La

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tion

McC

lean

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e O

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McA

rthur

Riv

er

Key

Lake

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ratio

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Cig

ar L

ake

Ope

ratio

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iver

Ref

iner

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Port

Hop

e C

onve

rsio

n Fa

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y

Gen

eral

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ctric

Nuc

lear

Fue

l Fac

ilitie

s

Zirc

atec

Nuc

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Fue

l Fac

ility llehs

teih Wdn

a ses ie rir toto ara or bo ab La

Lrev R

ikla

Ch

MD

S N

ordi

on

Tri- U

nive

rsity

Mes

on F

acilit

y

Figure 13 Average Effective Doses at All Selected Facilities for the Year 2003 (Based on Non-Zero Results)

Pick

erin

g N

ucle

ar G

ener

atin

g St

atio

ns

Dar

lingt

on N

ucle

ar G

ener

atin

g St

atio

n

Gen

tilly

-2 N

ucle

ar G

ener

atin

g St

atio

n

Poin

t Lep

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Nuc

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Clu

ff La

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McA

rthur

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er

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Lake

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ake

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iver

Ref

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Port

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n Fa

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y

Gen

eral

Ele

ctric

Nuc

lear

Fue

l Fac

ilitie

s

Zirc

atec

Nuc

lear

Fue

l Fac

ilit

llehsteih

Wdn a ses ie rir to

to ara or bo ab La Lrev

Ri

klaC

h

MD

S N

ord i

on

Tri-U

nive

rsity

Mes

on F

acilit

y

Shie

ld S

ourc

e In

corp

orat

edSh

ield

Sou

rce

Inco

rpor

ated

SRB

Tech

nolo

gies

(Can

ada)

Inc

SR

B Te

chno

logi

es (C

anad

a) In

c

5

n

2

1

35

3

5

2

5

1

Dos

e (m

Sv)

) Sv

(me

osD

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 14 Average Effective Doses at All Selected Facilities for the Year 2004 (Based on Non-Zero Results)

4

05

0

Figure 15 Average Effective Doses at All Selected Facilities for the Year 2005 (Based on Non-Zero Results)

4

35

3

25

2

15

1

05

0

Bruc

e N

ucle

ar G

ener

atin

g St

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uce

Nuc

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Gen

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Stat

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Pick

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Dar

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Gen

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-2 N

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Poin

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McA

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Lake

Ope

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Cig

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Ref

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Port

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n Fa

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y

Gen

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Ele

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Nuc

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Fue

l Fac

ilitie

s

Zirc

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Nuc

lear

Fue

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teih Wdn

a ses ie rir toto ara or bo ab La

Lrev R

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Ch

MD

S N

ordi

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Tri-U

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Mes

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Pick

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Dar

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McA

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Lake

Ope

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n

Cig

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ake

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Blin

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Ref

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Port

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y

Gen

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Ele

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Nuc

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Fue

l Fac

ilitie

s

Zirc

atec

Nuc

lear

Fue

l Fac

ility llehs

teih Wdn

a ses ie rir toto ara or bo ab La

Lrev R

ikla

Ch

MD

S N

ordi

on

Tri-U

niv e

rsity

Mes

on F

acilit

y

Shie

ld S

ourc

e In

corp

orat

edSh

ield

Sou

rce

Inco

rpor

ated

SRB

Tech

nolo

gies

(Can

ada)

Inc

SR

B Te

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logi

es (C

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a) In

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ty

Dos

e (m

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) v

Sm( e so

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e N

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ucle

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n Fa

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klaC

h

MD

S N

ordi

on

Tri-U

nive

rsity

Mes

on F

acilit

y

Figure 17 Average Effective Doses at All Selected Facilities for the Year 2007 (Based on Non-Zero Results)

4

35

3

25

2

15

1

05

0

Bru

ce N

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C

MD

S N

ordi

on

Tri-U

nive

rsity

Mes

on F

acili

ty

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 16 Average Effective Doses at All Selected Facilities for the Year 2006 (Based on Non-Zero Results)

4

35

3

25

2

15

1

05

0

Shie

ld S

ourc

e In

corp

orat

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corp

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SRB

Tech

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(Can

ada)

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orD

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snotita

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4

35

3

25

2

15

1

05

0

Dos

e (m

Sv)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

12 Average Effective Doses Based on All Monitoring Results at All Selected Facilities Figures 18ndash114 show average effective doses based on all the monitoring results for each year from 2001 to 2007 for every facility listed in this document

Figure 18 Average Effective Doses at All Selected F acilities for the Year 2001 (Based o n A ll Monitoring R esults)

8

r

Dos

e (m

Sv)

)

Sv

(me

osD

Bruc

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ar G

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Lrev R

ikl a

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Tri-U

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rsity

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on F

acilit

y

Figure 110 Average Effective Doses at All Selected F acilities for the Year 2003 (Based o n A ll Monitoring R esults)

4

35

3

25

2

15

1

05

0

Bruc

e N

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ilitie

s

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lear

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l Fac

ility llehs

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a ses ie rir toto ara or bo ab La

Lrev R

ikla

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MD

S N

o rdi

on

Tri-U

nive

r sity

Mes

on F

acilit

y

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 19 Average Effective Doses at All Selected Facilities for the Year 2002 (Based on All Monitoring Results)

4

35

3

25

2

15

1

05

0

Shie

ld S

ourc

e In

corp

orat

edSh

ield

Sou

rce

Inco

rpor

ated

c In)adan

Ca

(seigolonhce T

RB

SSR

B Te

chno

logi

es (C

anad

a) In

c

9

Dos

e (m

Sv)

)

Sv

(me

osD

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 111 Average Effective Doses at All Selected F acilities for the Year 2004 (Based o n A ll Monitoring R esults)

4

35

3

25

2

15

1

05

0

Bruc

e N

ucle

ar G

ener

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atio

ns

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erin

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Nuc

lear

Fue

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Lre v R

ikla

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MD

S N

ordi

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T ri-U

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Mes

on F

acilit

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Figure 112 Average Effective Doses at All Selected F acilities for the Year 2005 (Based o n A ll Monitoring R esults)

4

35

3

25

2

15

1

05

0

Bruc

e N

ucle

ar G

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Mes

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(Can

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10

r s s n n n n n n n n ty s ty l l ty de y n cn n o o o o o o o o r i il e e o ivo o ti l h lti ti ti ti ti ti ti ti i i

Ri i tee

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o nti O O th O l orti i e cn r O O un ti se e A e e e e s Wti ti a a a u d er k k kc k k v r F DS

a a r r e n In Ca

r r e a a M a re e a a Ri F M e (n L r s Me e n n L v a

L n e a c sa en n e e e ff L

y t L s r en lr d ty

G

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P

) S

v(m

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D

4

35

3

25

2

15

1

05

0

) vS

m( e soD

Figure 114 Average Effective Doses at All Selected F acilities for the Year 2007 (Based o n A ll Monitoring R esults)

Bru

ce N

ucle

ar G

ener

atin

g S

tatio

ns

Pic

kerin

g N

ucle

ar G

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tatio

ns

Dar

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tatio

n

Gen

tilly

-2 N

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Poi

nt L

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au N

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ar G

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tatio

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Clu

ff La

ke O

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Lak

e O

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McA

rthur

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ake

Ope

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bit L

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d R

iver

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n Fa

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eral

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Rk lah

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MD

S N

ordi

on

Tri-U

nive

rsity

Mes

on F

acili

ty

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 113 Average Effective Doses at All Selected Facilities for the Year 2006 (Based on All Monitoring Results)

4

35

3

25

2

15

1

05

0

Shi

eld

Sou

rce

Inco

rpor

ated

SR

B T

echn

olog

ies

(Can

ada)

Inc

11

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

20 Facility-Specific Overview of Occupational Doses This section presents data for the following types of facilities

bull nuclear power plants (Section 21) bull uranium mines and mills (Section 22) bull uranium refineries (Section 23) bull fuel fabrication facilities (Section 24) bull research and radioisotope production facilities (Section 25) bull tritium production facilities (Section 26)

21 Nuclear Power Plants This section presents dose information for the following nuclear power plants

bull Bruce A and Bruce B Nuclear Generating Stations (Section 211) bull Pickering Nuclear Generating Stations (Section 212) bull Darlington Nuclear Generating Station Section 213) bull Gentilly-2 Nuclear Generating Station (Section 214) bull Point Lepreau Generating Station (Section 215)

Graphs in this section indicate the following data for each nuclear power plant from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for nuclear power plants

1 Effective doses are composed of the following reported components bull doses from photons (labeled on the charts as ldquoexternalrdquo) bull neutron doses bull tritium doses

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of photon neutron and tritium doses Intakes of other radionuclides (for example Iodine-131 or Carbon-14) occasionally occur but these radionuclides are not included here because the associated collective dose is very small For this reason certain collective dose values in this report may be slightly lower than the sum of their respective components as listed

12

1 2 3 4 5 6 70 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

211 Bruce Nuclear Generating Stations

Bruce Power owns and operates the Bruce Nuclear Generating Stations located near Kincardine Ontario on the shore of Lake Huron

bull Bruce A consists of four nuclear reactors (units 1ndash4) and began operating in 1976 bull Bruce B has four nuclear reactors (units 5ndash8) and started operating in 1984

As part of its extensive recovery program in 1997 the sitersquos previous operator Ontario Hydro (now Ontario Power Generation) temporarily shut down all Bruce A reactors and maintained them in a guaranteed shutdown state Units 3 and 4 were later returned to service (in October 2003 and January 2004) while Units 1 and 2 remained in a guaranteed shutdown state

Figures 21ndash24 present dose information for the Bruce Nuclear Generating Stations from 2001 to 2007 Graphs do not distinguish between doses received at Bruce A versus Bruce B

Fig 21 Average Dose Trends for Bruce Nuclear Generating Stati on (Based o n N on-Zero R esults)

Dos

e (m

Sv)

4

35

3

25

2

15

1

05

0

Tritium Neutron External Effective

Year

13

Neutrons External Tritium

0 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 21 2 3 4 5 6 7

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

0

2

4

6

8

1

2

4

0

0

0

0

1

1

Figure 22 Average Dose Trends for Bruce Nuclear Generating Stati on (Based o n A ll Monitoring R esults)

16

)S

v(m

e os

D

Tritium Neutrons External Effective

Year

Figure 23 Collective Dose Trends for Bruce Nuclear Generating Stati on

8000

7000

6000

5000

4000

3000

2000

1000

0

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Year

14

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 24 Distribution of Effective Doses Among All Workers at Bruce Nuclear Generating Station

6000

5000

4000

3000

2000

1000

0 9 0 0

1-50 0 0 1 0 0 0 0 00 5 0 0 0

0-000

000 1-1 1-1 1-20 1-3 3gt0 0 0 05 0 5 01 1 2

Num

ber o

f Wor

kers

Dose Range (mSv)

15

1 2 3 4 5 6 7 0 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

212 Pickering Nuclear Generating Stations

Located in Pickering Ontario the Pickering Nuclear Generating Stations are owned and operated by Ontario Power Generation Two generating stations are located within one enclosure

bull Pickering A consists of four nuclear reactors (units 1 to 4) that began operating in 1971 bull Pickering B consists of four nuclear reactors (units 5 to 8) that began operating in 1982

As part of its extensive recovery program Ontario Hydro (now Ontario Power Generation) temporarily shut down all Pickering A reactors in 1997 and maintained them in a guaranteed shutdown state Unit 4 was restarted in September 2003 and Unit 1 was restarted in March 2005 Units 2 and 3 remain in a guaranteed shutdown state

Figures 25ndash28 present dose information for the Pickering Nuclear Generating Stations from 2001 to 2007 Graphs do not distinguish between doses received at Pickering A versus those received at Pickering B

Figure 25 Average Dose Trends for Pickering N uclear Generating Stati on (Based o n N on-Zero R esults)

25

2

15

1

05

0

)S

v(m

e os

D

Tritium Neutrons External Effective

Year

16

Tritium Neutrons External Effective

Neutrons External Tritium

1 2 3 4 5 6 70 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

1 2 3 4 5 6 7 0 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 26 Average Dose Trends for Pickering N uclear Generating Stati on (Based o n A ll Monitoring R esults)

12

1

08

06

04

02

0

Year

Figure 27 Collective Dose Trends for Pickering N uclear Generating Stati on

12000

10000

8000

6000

4000

2000

0

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

)

Sv

(me

osD

Year

17

2001 2002 2003 2004 2005 2006 2007

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 28 Distribution o f Effective Doses Among A ll Workers at Pickering Nuclear Generating Stati on

6000

5000

4000

3000

2000

1000

0

Num

ber o

f Wor

kers

Dose Range (mSv)

18

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

213 Darlington Nuclear Generating Station

Owned and operated by Ontario Power Generation the Darlington Nuclear Generating Station has four nuclear reactors the first of which began operating in 1989 The facility is located near Bowmanville on the shore of Lake Ontario

Figures 29ndash212 present dose information for the Darlington Nuclear Generating Station from 2001 to 2007

Figure 29 Average Dose Trends for Darlington N uclear Generating Stati on (Non- Zero R esults Only)

)S

v(m

e os

D

250

200

150

100

050

000

Year

19

Tritium Neutrons External Effective

Neutrons External Tritium

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 210 Average Dose Trends for Darlington N uclear Generating Stati on (All Monitoring R esults)

090

080

070

060

050

040

030

020

010

000

)S

v(m

e os

D

Year

Figure 211 Collective Dose Trends for Darlington N uclear Generating Stati on

4500

4000

3500

3000

2500

2000

1500

1000

500

0

)vSm-nosrep (es

Do

eiv

llect

Co

Year

20

2001 2002 2003 2004 2005 2006 2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 212 Distribution o f Effective Doses Among A ll Workers at Darlington Nuclear Generating Stati on

0

500

1000

1500

2000

2500

3000

3500

ers

ork

W of

be

r um

N

Dose Range (mSv)

21

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

214 Gentilly-2 Nuclear Generating Station

The Gentilly-2 Nuclear Generating Station owned and operated by Hydro-Queacutebec has a single reactor that began operating in 1982 The facility is located on the south shore of the St Lawrence River near Trois-Riviegraveres Queacutebec

Figures 213ndash216 present dose information for the Gentilly-2 Nuclear Generating Station from 2001 to 2007

Figure 213 Average Dose Trends for Gentilly-2 Nuclear Generating Stati on (Based o n N on-Zero R esults)

0

05

1

15

2

25

3

35

4

45

)S

v(m

e os

D

Year

22

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 214 Average Dose Trends for Gentilly-2 Nuclear Generating Stati on (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

)S

v(m

e os

D

Year

Figure 215 Collective Dose Trends for Gentilly-2 Nuclear Generating Stati on

0

500

1000

1500

2000

2500

3000

3500

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Neutrons

External

Tritium

Year

23

000-0

009

001-5

00

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 216 Distribution of Effective Doses Among All Workers at Gentilly-2 Nuclear Generating Station

2500

2000

1500

1000

500

0

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

24

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

215 Point Lepreau Nuclear Generating Station

The Point Lepreau Nuclear Generating Station has one reactor that began operating in 1982 Owned and operated by New Brunswick Power Nuclear the station is located in Point Lepreau New Brunswick about 40 km west of Saint John on the shores of the Bay of Fundy

Figures 217ndash220 present dose information for the Point Lepreau Nuclear Generating Station from 2001 to 2007

Figure 217 Average Dose Trends for Point Lepreau N uclear Generating Stati on (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

)S

v(m

e os

D

Tritium Neutron External Effective

Year

25

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 218 Average Dose Trends for Point Lepreau N uclear Generating Stati on (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

)S

v(m

e os

D

Tritium Neutrons External Effective

Year

Figure 219 Collective Dose Trends for Point Lepreau N uclear Generating Station

0

200

400

600

800

1000

1200

1400

1600

1800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Neutrons

External

Tritium

Year

26

0

1400

1200

1000

800

600

400

200

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 220 Distribution of Effective Doses Among All Workers at Point Lepreau Nuclear Generating Station

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

27

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

22 Uranium Mines and Mills This section presents dose information for mine and mill sites in the following regions

bull Cluff Lake (Section 221) bull McClean Lake (Section 222) bull McArthur River (Section 223) bull Key Lake (Section 224) bull Cigar Lake (Section 225) bull Rabbit Lake (Section 226)

Graphs indicate the following data for each site from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for uranium mines and mills

1 Effective doses are composed of the following reported components bull doses from photons (labelled on the charts as ldquoexternalrdquo) bull doses from radon progeny bull doses from long-lived radioactive dust bull doses from radon gas (in some cases)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of photon radon progeny long-lived radioactive dust and radon gas doses

3 The NDR lists radon progeny in working level months (WLM) For this report radon progeny exposures were converted4 to doses expressed in mSv

221 Cluff Lake Operation

The Cluff Lake mining facilities operated by AREVA Resources Canada Inc are located in northwestern Saskatchewan Work began in 1980 and ended in 2002 with the site now being decommissioned The site consisted of three open-pit and two underground mines a mill and a tailings management facility During 2005 and 2006 most of the infrastructure was removed and the affected areas were remediated

Figures 221ndash224 present dose information for the Cluff Lake operation from 2001 to 2007

4 Doses were converted using the International Commission on Radiation Protection (ICRP)rsquos conversion convention of 1 WLM = 5 mSv This convention was established in the ICRP publication Protection against Radon at Home and at Work (ICRP 65)

28

Long-lived radioactive dust Radon progeny External Effective

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 221 Average Dose Trends for the Cluff Lake Operation (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

Year

Figure 222 Average Dose Trends for the Cluff Lake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

200

Long-lived radioactive dust Radon progeny External Effective

)S

v(m

e os

D)

Sv

(me

osD

Year

29

600

500

400

300

200

100

0

External Radon progeny Long-lived radioactive dust

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 223 Collective Dose Trends for the Cluff Lake Operation s

erkor

of W

ber

Num

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Year

Figure 224 Distribution o f Effective Doses Among A ll Workers at the Cluff Lake Operation

0

20

40

60

80

100

120

140

160

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

30

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

222 McClean Lake Operation

AREVA Resources Canada Inc runs the McClean Lake mining operation in northeastern Saskatchewan It comprises open pit mines a mill and a tailings management facility Mining began in 1995 while milling started in 1999

Figures 225ndash228 present dose information for the McClean Lake operation from 2001 to 2007

Figure 225 Average Dose Trends for the McClean L ake Operation (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

31

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 226 Average Dose Trends for the McClean L ake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 227 Collective Dose Trends for the McClean L ake Operation

0

100

200

300

400

500

600

700

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External

Radon progeny

Long-lived radioactive dust

Year

32

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 228 Distribution o f Effective Doses Among A ll Workers at the McClean Lake Operation

0

100

200

300

400

500

600

700

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

33

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

223 McArthur River Operation

Cameco Corporation operates the McArthur River underground mine in north-central Saskatchewan Ore from the mine which began production in 1999 is processed at the Key Lake Mill located 80 km south of McArthur River

Figures 229ndash232 present dose information for the McArthur River operation from 2001 to 2007

Figure 229 Average Dose Trends for the McArthur River Operation (Based o n N on-Zero R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

34

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 230 Average Dose Trends for the McArthur River Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

Figure 231 Collective Dose Trends for the McArthur River Operation

0

200

400

600

800

1000

1200

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Radon gas External Radon progeny Long-lived radioactive dust

Year

35

00

0-000

9

001-5

00

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 232 Distribution o f Effective Doses Among A ll Workers at the McArthur River Operation

0

100

200

300

400

500

600

700

800

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

36

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

224 Key Lake Operation

Cameco Corporation operates mining facilities in Key Lake located in north-central Saskatchewan The Key Lake operation includes two mined-out open pit mines (used for tailings management) a mill and two dry tailings management facilities Mining began in 1983 and ceased in 1997 the mill continued to process ore from the McArthur River mine during the reporting period

Figures 233ndash236 present dose information for the Key Lake operation from 2001 to 2007

Figure 233 Average Dose Trends for the Key Lake Operation (Based o n N on-Zero R esults)

00

20

40

60

80

00

20

40

60

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

37

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

00

20

40

60

80

00

20

40

60

Figure 234 Average Dose Trends for the Key Lake Operation (Based o n A ll Monitoring R esults)

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 235 Collective Dose Trends for the Key Lake Operation

0

100

200

300

400

500

600

700

800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External Radon progeny Long-lived radioactive dust

Year

38

00

0-000

9

001-5

0

501-1

000

gt 1001

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 236 Distribution o f Effective Doses Among A ll Workers at the Key Lake Operation

0

200

400

600

800

1000

1200

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose Range (mSv)

39

se

(mS

v)o

D

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

225 Cigar Lake Operation

Cameco Corporation manages the Cigar Lake underground mine located in northern Saskatchewan at the southern end of Waterbury Lake The mine was under construction at the time of this reportrsquos publication Test mining in ore was carried out in 1991 1992 and 2000

Figures 237ndash240 present dose information for the Cigar Lake operation from

Figure 2 37 Average D ose T rends fo r th e C igar L ake O peration (Based on Non-Zero Results)

2001 to 2007

Year

000

005

010

015

020

025

Long-lived radioactive dust Radon Progeny External Effective

40

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 238 Average Dose Trends for the Cigar Lake Operation (Based on All Monitoring Results)

000

005

010

015

020

025

030

035

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny

External

Effective

Year

Figure 239 Collective Dose Trends for the Cigar Lake Operation

0

50

100

150

200

250

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

External Radon progeny Long-lived radioactive dust

Year

41

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 240 Distribution of Effective Doses Among All Workers at the Cigar Lake Operation

0

200

400

600

800

1000

1200

1400

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

42

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

226 Rabbit Lake Operation

Cameco Corporation owns and operates mining facilities in Rabbit Lake located in north-eastern Saskatchewan Facilities include an underground mine four mined-out open-pit mines a mill and two tailings management facilities Mining and milling began in 1975

Figures 241ndash244 present dose information for the Rabbit Lake operation from 2001 to 2007

Figure 241 Average Dose Trends for the Rabbit Lake Operation (Based on Non-Zero Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

43

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 242 Average Dose Trends for the Rabbit Lake Operation (Based on All Monitoring Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

Figure 243 Collective Dose Trends for the Rabbit Lake Operation

0

200

400

600

800

1000

1200

1400

1600

1800

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Radon gas External Radon progeny Long-lived radioactive dust

Year

44

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

gt300

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 244 Distribution of Effective Doses Among All Workers at the Rabbit Lake Operation

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

900

800

700

600

500

400

300

200

100

0

Dose (mSv)

45

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

23 Uranium Refineries This section presents data for the following two facilities

bull a uranium refining facility in Blind River (Section 231) bull a uranium conversion facility in Port Hope (Section 232)

Graphs indicate the following average doses at each facility from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Note on data for uranium refineries

1 Doses from photons from external sources are measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay and lung counting Historically while these internal doses have been measured they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

231 Blind River Refinery

Cameco Corporation owns and is licensed to operate a uranium refinery in Blind River Ontario The facility which began operating in 1983 converts uranium ore concentrate to uranium trioxide The uranium trioxide is shipped to Camecorsquos uranium conversion facility in Port Hope Ontario where it is processed into uranium dioxide (for use in the fabrication of fuel for nuclear reactors in Canada) or uranium hexafluoride (exported for enrichment and fabrication into fuel for nuclear power reactors around the world)

Figures 245ndash248 present dose information for the Blind River refinery from 2001 to 2007

46

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 245 Average Dose Trends for the Blind River Refinery (Based on Non-Zero Results)

0

05

1

15

2

25

Year

Figure 246 Average Dose Trends for the Blind River Refinery (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

47

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 247 Collective Dose Trends for the Blind River Refinery

0

50

100

150

200

250

300 C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 248 Distribution of Effective Doses Among All Workers at the Blind River Refinery

0

20

40

60

80

100

120

140

160

180

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

48

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

232 Port Hope Conversion Facility

Cameco Corporation owns and is licensed to operate a uranium conversion facility in Port Hope Ontario The facility processes uranium trioxide received from the refinery in Blind River into uranium dioxide and uranium hexafluoride

Figures 249ndash252 present dose information for the Port Hope uranium conversion facility from 2001 to 2007

Figure 249 Average Dose Trends for the Port Hope Conversion Facility (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

49

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 250 Average Dose Trends for the Port Hope Conversion Facility (Based on All Monitoring Results)

0

01

02

03

04

05

06

07

08

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 251 Collective Dose Trends for the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

50

000-0

009

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 252 Distribution of Effective Doses Among All Workers at the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

400

450

500

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

51

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

24 Fuel Fabrication Facilities This section presents data for three nuclear fuel fabrication facilities

bull Two facilities owned and operated by General Electric Canada Inc (Section 241) bull One facility in Port Hope operated by Zircatec Precision Industries (Section 242)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average doses

Notes on data for fuel fabrication facilities

1 Effective doses for the three facilities are composed of the following reported components bull dose from photons (labelled on the charts as ldquoexternalrdquo) bull doses from internal intakes of uranium dust (long-lived radioactive dust) from

uranium in air concentrations (for General Electricrsquos Toronto facility only)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components photon doses and doses from long-lived radioactive dust

241 General Electric Nuclear Fuel Facilities

General Electric Canada Inc operates two nuclear fuel facilities in Ontario

bull At the Toronto facility uranium dioxide pellets are produced from natural or depleted uranium dioxide powder

bull At the Peterborough facility uranium dioxide fuel bundles are created from the pellets produced at the Toronto facility

Figures 253ndash256 present dose information for General Electric Canada Incrsquos fuel fabrication facilities from 2001 to 2007 Graphs do not distinguish between the doses received at the Peterborough facility versus those at the Toronto facility

52

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 253 Average Dose Trends for the General Electric Fuel Facility (Based on Non-Zero Results Only)

0

05

1

15

2

25

3

35

Long Lived Radioactive Dust External Effective

Year

Figure 254 Average Dose Trends for the General Electric Fuel Facility (Based on All Monitoring Results)

0

05

1

15

2

25

3

Long Lived Radioactive Dust External Effective

Year

Dos

e (m

Sv)

Dos

e (m

Sv)

53

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 255 Collective Dose Trends for the General Electric Fuel Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Long Lived Radioactive Dust External

Year

Figure 256 Distribution of Effective Doses among all Workers at the General Electric Fuel Facility

0

10

20

30

40

50

60

70

80

90

100

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

54

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

242 Zircatec Nuclear Fuel Facility

Zircatec Precision Industries Inc operates a nuclear fuel facility in Port Hope Ontario where it makes fuel pellets from uranium dioxide powder received from Port Hopersquos uranium conversion facility The nuclear fuel facility also manufactures fuel bundles for nuclear reactors in Canada

Notes on data for the Zircatec nuclear fuel facility

1 Graphs indicate the following data bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of average effective doses

2 Doses from photons from external sources were measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay Historically although these internal doses have been measured and submitted to the CNSC they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

Figures 257ndash260 present dose information for the Zircatec nuclear fuel facility from 2001 to 2007

Figure 257 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on Non-Zero Results)

0

05

1

15

2

25

3

35

Effe

ctiv

e D

ose

(mS

v)

Year

55

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 258 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

18

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 259 Collective Dose Trends for the Zircatec Nuclear Fuel Facility

0

50

100

150

200

250

300

350

400

450

500

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

56

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 260 Distribution of Effective Doses Among All Workers at the Zircatec Nuclear Fuel Facility

300

Num

ber o

f Wor

kers

250

200

150

100

50

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

57

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

25 Research and Radioisotope Production Facilities This section presents dose information for the following research and radioisotope production facilities from 2001 to 2007

bull Chalk River Laboratories and Whiteshell Laboratories (Section 251) bull A radioisotope production facility operated by MDS Nordion (Section 252) bull The Tri-University Meson Facility (TRIUMF) (Section 253)

Note on data for research and radioisotope production facilities

1 Graphs indicate the following data for each facility bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of effective doses

251 Chalk River Laboratories and Whiteshell Laboratories

Atomic Energy of Canada Limited (AECL) owns and is licensed to operate Chalk River Laboratories and Whiteshell Laboratories

Situated in Renfrew County on the south shore of the Ottawa River the Chalk River Laboratories site hosts the National Research Universal Reactor along with numerous other facilities occupying some 160 buildings in an area of approximately 40 km2 Activities consist of radioisotope production for nuclear medicine testing and development of structural materials in support of power reactor operations fuel fabrication research and radioactive waste management and storage

The Whiteshell Laboratories site is located approximately 10 km west of Pinawa Manitoba and 100 km northeast of Winnipeg on the east bank of the Winnipeg River AECL established the laboratories for nuclear research and testing during the early 1960s and has since discontinued operations which are being decommissioned under a licence from the CNSC

Figures 261ndash264 present dose information for Chalk River Laboratories and Whiteshell Laboratories from 2001 to 2007

Notes on data for Chalk River Laboratories and Whiteshell Laboratories

1 Effective doses are composed of the following reported components bull external doses5 (from both photon and neutron doses) bull tritium doses

Due to issues with AECLrsquos in-house dosimetry management system neutron doses were not reported separately to the NDR during the reporting period As a result external doses from photons and neutrons were totaled The reporting discrepancy has since been rectified

58

5

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of external (photon and neutron) and tritium doses Intakes of other radionuclides occasionally occur and these radionuclides are not included here because their associated doses are very small For this reason certain collective doses in this report may have values slightly lower than the sum of their respective components as listed

Figure 261 Average Dose Trends for Chalk River and Whiteshell Laboratories (Non-Zero Results Only)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Tritium External Effective

Year

59

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 262 Average Dose Trends for Chalk River and Whiteshell Laboratories (All Monitoring Results)

000

020

040

060

080

100

120

Dos

e (m

Sv)

Tritium External Effective

Year

Figure 263 Collective Dose Trends for Chalk River and Whiteshell Laboratories

0

500

1000

1500

2000

2500

3000

3500

Col

lect

ive

Dos

e (p

erso

n- m

Sv)

External Tritium

Year

60

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 264 Distribution of Effective Doses Among All Workers at Chalk River and Whiteshell Laboratories

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

3500

3000

2500

2000

1500

1000

500

Dose (mSv)

61

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

252 MDS Nordion (Nuclear Substance Processing Facility and Canadian Irradiation Centre)

MDS Nordion owns and operates a nuclear substance processing facility in Ottawa Ontario where it processes unsealed radioisotopes and manufactures sealed radiation sources In operation since the early 1970s the facility was purchased by Nordion International in 1991

In cooperation with the Universiteacute du Queacutebecrsquos Institut Armand-Frappier MDS Nordion also operates the Canadian Irradiation Centre which conducts various irradiation services which include training testing and development The centre is located in Laval Quebec on the Universiteacute du Queacutebec campus

Figures 265ndash268 present dose information for MDS Nordionrsquos Ottawa nuclear substance processing facility and for the Canadian Irradiation Centre from 2001 to 2007

Notes on data for MDS Nordionrsquos nuclear substance processing facility and the Canadian Irradiation Centre

1 Doses from photons from external sources were measured and reported to the NDR MDS Nordion also has a routine thyroid monitoring program very occasionally small recordable doses of radiation have occurred from thyroid uptake of iodine The resulting doses have not been historically submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided

Figure 265 Average Dose Trends for MDS Nordion (Based on Non-Zero Results)

0

05

1

15

2

25

Effe

ctiv

e D

ose

(mS

v)

Year

62

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 266 Average Dose Trends for MDS Nordion (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

Figure 267 Collective Dose Trends for MDS Nordion

0

100

200

300

400

500

600

700

800

Year

63

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 268 Distribution of Effective Doses Among All Workers at MDS Nordion

0

5 0

1 0 0

1 5 0

2 0 0

2 5 0

3 0 0

3 5 0

4 0 0

4 5 0

5 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

64

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

253 Tri-University Meson Facility

The Tri-University Meson facility (TRIUMF) is situated in Vancouver on the campus of the University of British Columbia TRIUMF which began operating in the early 1970s with one cyclotron now has two cyclotrons and associated laboratories for research and radioisotope production The laboratory provides research facilities for Canadian and international users and also produces radioisotopes which are used by medical facilities and by a commercial organization (MDS Nordion) MDS Nordion staff also work at the TRIUMF site however MDS Nordion oversees this work and has its own radiation protection program

Figures 269ndash272 present dose information for the TRIUMF facility from 2001 to 2007 Please note that data sets do not distinguish between doses received by TRIUMF staff and MDS Nordion staff who work on the site as the data for these two groups was submitted collectively to the NDR for the reporting period shown Future data for each group will be submitted separately to the NDR

Note on data for TRIUMF

1 Effective doses are composed of the following reported components bull doses from photons (labeled as ldquoexternalrdquo in the charts) bull neutron doses

Figure 269 Average Dose Trends for TRIUMF (Non-Zero Results Only)

000

020

040

060

080

100

120

140

160

Dos

e (m

Sv)

Neutrons External Effective

Year

65

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 11: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

n

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35

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Dos

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Sv)

) Sv

(me

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Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 14 Average Effective Doses at All Selected Facilities for the Year 2004 (Based on Non-Zero Results)

4

05

0

Figure 15 Average Effective Doses at All Selected Facilities for the Year 2005 (Based on Non-Zero Results)

4

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S N

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Mes

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corp

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ield

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Tech

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(Can

ada)

Inc

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B Te

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c

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ty

Dos

e (m

Sv)

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e N

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ff La

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McA

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Ope

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n

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Nuc

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Fue

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Wdn a ses ie rir to

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klaC

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MD

S N

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Tri-U

nive

rsity

Mes

on F

acilit

y

Figure 17 Average Effective Doses at All Selected Facilities for the Year 2007 (Based on Non-Zero Results)

4

35

3

25

2

15

1

05

0

Bru

ce N

ucle

ar G

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atin

g S

tatio

ns

Pic

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g N

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ff La

ke O

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Lak

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Lak

e O

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d R

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Ref

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t Hop

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Gen

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ctric

Nuc

lear

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l Fac

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l Fac

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W d na s s ee iri oro tat ra or bo ab LaLr evi

Rk la h

C

MD

S N

ordi

on

Tri-U

nive

rsity

Mes

on F

acili

ty

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 16 Average Effective Doses at All Selected Facilities for the Year 2006 (Based on Non-Zero Results)

4

35

3

25

2

15

1

05

0

Shie

ld S

ourc

e In

corp

orat

edS

hiel

d S

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e In

corp

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ed

SRB

Tech

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(Can

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s (C

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a) In

c

7

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Sgntiarene Graelc

Nu

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snotita

Sgntiarene Graelc

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(seigolonhce T

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4

35

3

25

2

15

1

05

0

Dos

e (m

Sv)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

12 Average Effective Doses Based on All Monitoring Results at All Selected Facilities Figures 18ndash114 show average effective doses based on all the monitoring results for each year from 2001 to 2007 for every facility listed in this document

Figure 18 Average Effective Doses at All Selected F acilities for the Year 2001 (Based o n A ll Monitoring R esults)

8

r

Dos

e (m

Sv)

)

Sv

(me

osD

Bruc

e N

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ar G

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g St

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ff La

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S N

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Tri-U

n ive

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Mes

on F

acilit

y

Figure 110 Average Effective Doses at All Selected F acilities for the Year 2003 (Based o n A ll Monitoring R esults)

4

35

3

25

2

15

1

05

0

Bruc

e N

ucle

ar G

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ctric

Nuc

lear

Fue

l Fac

ilitie

s

Zirc

atec

Nuc

lear

Fue

l Fac

ility llehs

teih Wdn

a ses ie rir toto ara or bo ab La

Lrev R

ikla

Ch

MD

S N

o rdi

on

Tri-U

nive

r sity

Mes

on F

acilit

y

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 19 Average Effective Doses at All Selected Facilities for the Year 2002 (Based on All Monitoring Results)

4

35

3

25

2

15

1

05

0

Shie

ld S

ourc

e In

corp

orat

edSh

ield

Sou

rce

Inco

rpor

ated

c In)adan

Ca

(seigolonhce T

RB

SSR

B Te

chno

logi

es (C

anad

a) In

c

9

Dos

e (m

Sv)

)

Sv

(me

osD

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 111 Average Effective Doses at All Selected F acilities for the Year 2004 (Based o n A ll Monitoring R esults)

4

35

3

25

2

15

1

05

0

Bruc

e N

ucle

ar G

ener

atin

g St

atio

ns

Pick

erin

g N

ucle

ar G

ener

atin

g St

atio

ns

Dar

lingt

on N

ucle

ar G

ener

atin

g St

atio

n

Gen

tilly

-2 N

ucle

ar G

ener

atin

g St

atio

n

Poin

t Lep

reau

Nuc

lear

Gen

erat

ing

Stat

ion

Clu

ff La

ke O

pera

tion

McC

lean

Lak

e O

pera

tion

McA

rthur

Riv

er

Key

Lake

Ope

ratio

n

Cig

ar L

ake

Ope

ratio

n

Rab

bit L

ake

Ope

ratio

n

Blin

d R

iver

Ref

iner

y

Port

Hop

e C

onve

rsio

n Fa

cilit

y

Gen

eral

Ele

ctric

Nuc

lear

Fue

l Fac

ilitie

s

Zirc

atec

Nuc

lear

Fue

l Fac

ility llehs

teih Wdn

a ses ie rir toto ara or bo ab La

Lre v R

ikla

Ch

MD

S N

ordi

on

T ri-U

nive

rsity

Mes

on F

acilit

y

Figure 112 Average Effective Doses at All Selected F acilities for the Year 2005 (Based o n A ll Monitoring R esults)

4

35

3

25

2

15

1

05

0

Bruc

e N

ucle

ar G

ener

atin

g St

atio

ns

Pick

erin

g N

ucle

ar G

ener

atin

g St

atio

ns

Dar

lingt

on N

ucle

ar G

ener

atin

g St

atio

n

Gen

tilly

-2 N

ucle

ar G

ener

atin

g St

atio

n

Poin

t Lep

reau

Nuc

lear

Gen

erat

ing

Stat

ion

Clu

ff La

ke O

pera

tion

McC

lean

Lak

e O

pera

tion

McA

rthur

Riv

er

Key

Lake

Ope

ratio

n

Cig

ar L

ake

Ope

ratio

n

Rab

bit L

ake

Ope

ratio

n

Blin

d R

iver

Ref

iner

y

Port

Hop

e C

onve

rsio

n Fa

cilit

y

Gen

eral

Ele

ctric

Nuc

lear

Fue

l Fac

ilitie

s

Zirc

atec

Nuc

lear

Fue

l Fac

ility llehs

teih Wdn

a ses ie rir toto ara or bo ab La

Lrev R

ikl a

Ch

MD

S N

ordi

on

Tri-U

n ive

rsity

Mes

on F

acilit

y

Shie

ld S

ourc

e In

corp

orat

edSh

ield

Sou

rce

Inco

rpor

ated

SRB

Tech

nolo

gies

(Can

ada)

Inc

SR

B Te

chno

logi

es (C

anad

a) In

c

10

r s s n n n n n n n n ty s ty l l ty de y n cn n o o o o o o o o r i il e e o ivo o ti l h lti ti ti ti ti ti ti ti i i

Ri i tee

ta c c iil c ati ti ta ta a a a a a n i s d Inr ata r )r r r r ata a

S

fi cr te S S F F

Nor F o ae e e e e

S S au p p p i p dp p hg g g n F l n r ae og g n n n Re

o nti O O th O l orti i e cn r O O un ti se e A e e e e s Wti ti a a a u d er k k kc k k v r F DS

a a r r e n In Ca

r r e a a M a re e a a Ri F M e (n L r s Me e n n L v a

L n e a c sa en n e e e ff L

y t L s r en lr d ty

G

i

Co e c ie G a il e r i ue G nu a e b

G G g i s

K b toCl c

Nu i ge l r r o or r r C

i B

Nu to e

Cl er a a Sa Ra a lr a vp r oa ce e ae i

t Ho doe l te ll c r bl c M cc Un ne lc o e hlc c

Nu

Nu

Nu i a ab i ctr

Nu

Nu - hc L i er c a rri So en 2 u l Z L T TPe gc to ayn g l E

r- el RB

u i l e vrr atir Sn pe r

B i nk l e er Ri

e

Da t L n kc li G e aP ni Go C

h

P

) S

v(m

e os

D

4

35

3

25

2

15

1

05

0

) vS

m( e soD

Figure 114 Average Effective Doses at All Selected F acilities for the Year 2007 (Based o n A ll Monitoring R esults)

Bru

ce N

ucle

ar G

ener

atin

g S

tatio

ns

Pic

kerin

g N

ucle

ar G

ener

atin

g S

tatio

ns

Dar

lingt

on N

ucle

ar G

ener

atin

g S

tatio

n

Gen

tilly

-2 N

ucle

ar G

ener

atin

g S

tatio

n

Poi

nt L

epre

au N

ucle

ar G

ener

atin

g S

tatio

n

Clu

ff La

ke O

pera

tion

McC

lean

Lak

e O

pera

tion

McA

rthur

Riv

er

Key

Lak

e O

pera

tion

Cig

ar L

ake

Ope

ratio

n

Rab

bit L

ake

Ope

ratio

n

Blin

d R

iver

Ref

iner

y

Por

t Hop

e C

onve

rsio

n Fa

cilit

y

Gen

eral

Ele

ctric

Nuc

lear

Fue

l Fac

ilitie

s

Zirc

atec

Nuc

lear

Fue

l Fac

ility llehsetih

W d na s s ee iri oro tat ra or bo ab La Lr evi

Rk lah

C

MD

S N

ordi

on

Tri-U

nive

rsity

Mes

on F

acili

ty

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 113 Average Effective Doses at All Selected Facilities for the Year 2006 (Based on All Monitoring Results)

4

35

3

25

2

15

1

05

0

Shi

eld

Sou

rce

Inco

rpor

ated

SR

B T

echn

olog

ies

(Can

ada)

Inc

11

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

20 Facility-Specific Overview of Occupational Doses This section presents data for the following types of facilities

bull nuclear power plants (Section 21) bull uranium mines and mills (Section 22) bull uranium refineries (Section 23) bull fuel fabrication facilities (Section 24) bull research and radioisotope production facilities (Section 25) bull tritium production facilities (Section 26)

21 Nuclear Power Plants This section presents dose information for the following nuclear power plants

bull Bruce A and Bruce B Nuclear Generating Stations (Section 211) bull Pickering Nuclear Generating Stations (Section 212) bull Darlington Nuclear Generating Station Section 213) bull Gentilly-2 Nuclear Generating Station (Section 214) bull Point Lepreau Generating Station (Section 215)

Graphs in this section indicate the following data for each nuclear power plant from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for nuclear power plants

1 Effective doses are composed of the following reported components bull doses from photons (labeled on the charts as ldquoexternalrdquo) bull neutron doses bull tritium doses

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of photon neutron and tritium doses Intakes of other radionuclides (for example Iodine-131 or Carbon-14) occasionally occur but these radionuclides are not included here because the associated collective dose is very small For this reason certain collective dose values in this report may be slightly lower than the sum of their respective components as listed

12

1 2 3 4 5 6 70 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

211 Bruce Nuclear Generating Stations

Bruce Power owns and operates the Bruce Nuclear Generating Stations located near Kincardine Ontario on the shore of Lake Huron

bull Bruce A consists of four nuclear reactors (units 1ndash4) and began operating in 1976 bull Bruce B has four nuclear reactors (units 5ndash8) and started operating in 1984

As part of its extensive recovery program in 1997 the sitersquos previous operator Ontario Hydro (now Ontario Power Generation) temporarily shut down all Bruce A reactors and maintained them in a guaranteed shutdown state Units 3 and 4 were later returned to service (in October 2003 and January 2004) while Units 1 and 2 remained in a guaranteed shutdown state

Figures 21ndash24 present dose information for the Bruce Nuclear Generating Stations from 2001 to 2007 Graphs do not distinguish between doses received at Bruce A versus Bruce B

Fig 21 Average Dose Trends for Bruce Nuclear Generating Stati on (Based o n N on-Zero R esults)

Dos

e (m

Sv)

4

35

3

25

2

15

1

05

0

Tritium Neutron External Effective

Year

13

Neutrons External Tritium

0 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 21 2 3 4 5 6 7

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

0

2

4

6

8

1

2

4

0

0

0

0

1

1

Figure 22 Average Dose Trends for Bruce Nuclear Generating Stati on (Based o n A ll Monitoring R esults)

16

)S

v(m

e os

D

Tritium Neutrons External Effective

Year

Figure 23 Collective Dose Trends for Bruce Nuclear Generating Stati on

8000

7000

6000

5000

4000

3000

2000

1000

0

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Year

14

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 24 Distribution of Effective Doses Among All Workers at Bruce Nuclear Generating Station

6000

5000

4000

3000

2000

1000

0 9 0 0

1-50 0 0 1 0 0 0 0 00 5 0 0 0

0-000

000 1-1 1-1 1-20 1-3 3gt0 0 0 05 0 5 01 1 2

Num

ber o

f Wor

kers

Dose Range (mSv)

15

1 2 3 4 5 6 7 0 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

212 Pickering Nuclear Generating Stations

Located in Pickering Ontario the Pickering Nuclear Generating Stations are owned and operated by Ontario Power Generation Two generating stations are located within one enclosure

bull Pickering A consists of four nuclear reactors (units 1 to 4) that began operating in 1971 bull Pickering B consists of four nuclear reactors (units 5 to 8) that began operating in 1982

As part of its extensive recovery program Ontario Hydro (now Ontario Power Generation) temporarily shut down all Pickering A reactors in 1997 and maintained them in a guaranteed shutdown state Unit 4 was restarted in September 2003 and Unit 1 was restarted in March 2005 Units 2 and 3 remain in a guaranteed shutdown state

Figures 25ndash28 present dose information for the Pickering Nuclear Generating Stations from 2001 to 2007 Graphs do not distinguish between doses received at Pickering A versus those received at Pickering B

Figure 25 Average Dose Trends for Pickering N uclear Generating Stati on (Based o n N on-Zero R esults)

25

2

15

1

05

0

)S

v(m

e os

D

Tritium Neutrons External Effective

Year

16

Tritium Neutrons External Effective

Neutrons External Tritium

1 2 3 4 5 6 70 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

1 2 3 4 5 6 7 0 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 26 Average Dose Trends for Pickering N uclear Generating Stati on (Based o n A ll Monitoring R esults)

12

1

08

06

04

02

0

Year

Figure 27 Collective Dose Trends for Pickering N uclear Generating Stati on

12000

10000

8000

6000

4000

2000

0

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

)

Sv

(me

osD

Year

17

2001 2002 2003 2004 2005 2006 2007

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 28 Distribution o f Effective Doses Among A ll Workers at Pickering Nuclear Generating Stati on

6000

5000

4000

3000

2000

1000

0

Num

ber o

f Wor

kers

Dose Range (mSv)

18

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

213 Darlington Nuclear Generating Station

Owned and operated by Ontario Power Generation the Darlington Nuclear Generating Station has four nuclear reactors the first of which began operating in 1989 The facility is located near Bowmanville on the shore of Lake Ontario

Figures 29ndash212 present dose information for the Darlington Nuclear Generating Station from 2001 to 2007

Figure 29 Average Dose Trends for Darlington N uclear Generating Stati on (Non- Zero R esults Only)

)S

v(m

e os

D

250

200

150

100

050

000

Year

19

Tritium Neutrons External Effective

Neutrons External Tritium

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 210 Average Dose Trends for Darlington N uclear Generating Stati on (All Monitoring R esults)

090

080

070

060

050

040

030

020

010

000

)S

v(m

e os

D

Year

Figure 211 Collective Dose Trends for Darlington N uclear Generating Stati on

4500

4000

3500

3000

2500

2000

1500

1000

500

0

)vSm-nosrep (es

Do

eiv

llect

Co

Year

20

2001 2002 2003 2004 2005 2006 2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 212 Distribution o f Effective Doses Among A ll Workers at Darlington Nuclear Generating Stati on

0

500

1000

1500

2000

2500

3000

3500

ers

ork

W of

be

r um

N

Dose Range (mSv)

21

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

214 Gentilly-2 Nuclear Generating Station

The Gentilly-2 Nuclear Generating Station owned and operated by Hydro-Queacutebec has a single reactor that began operating in 1982 The facility is located on the south shore of the St Lawrence River near Trois-Riviegraveres Queacutebec

Figures 213ndash216 present dose information for the Gentilly-2 Nuclear Generating Station from 2001 to 2007

Figure 213 Average Dose Trends for Gentilly-2 Nuclear Generating Stati on (Based o n N on-Zero R esults)

0

05

1

15

2

25

3

35

4

45

)S

v(m

e os

D

Year

22

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 214 Average Dose Trends for Gentilly-2 Nuclear Generating Stati on (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

)S

v(m

e os

D

Year

Figure 215 Collective Dose Trends for Gentilly-2 Nuclear Generating Stati on

0

500

1000

1500

2000

2500

3000

3500

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Neutrons

External

Tritium

Year

23

000-0

009

001-5

00

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 216 Distribution of Effective Doses Among All Workers at Gentilly-2 Nuclear Generating Station

2500

2000

1500

1000

500

0

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

24

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

215 Point Lepreau Nuclear Generating Station

The Point Lepreau Nuclear Generating Station has one reactor that began operating in 1982 Owned and operated by New Brunswick Power Nuclear the station is located in Point Lepreau New Brunswick about 40 km west of Saint John on the shores of the Bay of Fundy

Figures 217ndash220 present dose information for the Point Lepreau Nuclear Generating Station from 2001 to 2007

Figure 217 Average Dose Trends for Point Lepreau N uclear Generating Stati on (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

)S

v(m

e os

D

Tritium Neutron External Effective

Year

25

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 218 Average Dose Trends for Point Lepreau N uclear Generating Stati on (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

)S

v(m

e os

D

Tritium Neutrons External Effective

Year

Figure 219 Collective Dose Trends for Point Lepreau N uclear Generating Station

0

200

400

600

800

1000

1200

1400

1600

1800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Neutrons

External

Tritium

Year

26

0

1400

1200

1000

800

600

400

200

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 220 Distribution of Effective Doses Among All Workers at Point Lepreau Nuclear Generating Station

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

27

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

22 Uranium Mines and Mills This section presents dose information for mine and mill sites in the following regions

bull Cluff Lake (Section 221) bull McClean Lake (Section 222) bull McArthur River (Section 223) bull Key Lake (Section 224) bull Cigar Lake (Section 225) bull Rabbit Lake (Section 226)

Graphs indicate the following data for each site from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for uranium mines and mills

1 Effective doses are composed of the following reported components bull doses from photons (labelled on the charts as ldquoexternalrdquo) bull doses from radon progeny bull doses from long-lived radioactive dust bull doses from radon gas (in some cases)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of photon radon progeny long-lived radioactive dust and radon gas doses

3 The NDR lists radon progeny in working level months (WLM) For this report radon progeny exposures were converted4 to doses expressed in mSv

221 Cluff Lake Operation

The Cluff Lake mining facilities operated by AREVA Resources Canada Inc are located in northwestern Saskatchewan Work began in 1980 and ended in 2002 with the site now being decommissioned The site consisted of three open-pit and two underground mines a mill and a tailings management facility During 2005 and 2006 most of the infrastructure was removed and the affected areas were remediated

Figures 221ndash224 present dose information for the Cluff Lake operation from 2001 to 2007

4 Doses were converted using the International Commission on Radiation Protection (ICRP)rsquos conversion convention of 1 WLM = 5 mSv This convention was established in the ICRP publication Protection against Radon at Home and at Work (ICRP 65)

28

Long-lived radioactive dust Radon progeny External Effective

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 221 Average Dose Trends for the Cluff Lake Operation (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

Year

Figure 222 Average Dose Trends for the Cluff Lake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

200

Long-lived radioactive dust Radon progeny External Effective

)S

v(m

e os

D)

Sv

(me

osD

Year

29

600

500

400

300

200

100

0

External Radon progeny Long-lived radioactive dust

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 223 Collective Dose Trends for the Cluff Lake Operation s

erkor

of W

ber

Num

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Year

Figure 224 Distribution o f Effective Doses Among A ll Workers at the Cluff Lake Operation

0

20

40

60

80

100

120

140

160

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

30

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

222 McClean Lake Operation

AREVA Resources Canada Inc runs the McClean Lake mining operation in northeastern Saskatchewan It comprises open pit mines a mill and a tailings management facility Mining began in 1995 while milling started in 1999

Figures 225ndash228 present dose information for the McClean Lake operation from 2001 to 2007

Figure 225 Average Dose Trends for the McClean L ake Operation (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

31

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 226 Average Dose Trends for the McClean L ake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 227 Collective Dose Trends for the McClean L ake Operation

0

100

200

300

400

500

600

700

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External

Radon progeny

Long-lived radioactive dust

Year

32

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 228 Distribution o f Effective Doses Among A ll Workers at the McClean Lake Operation

0

100

200

300

400

500

600

700

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

33

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

223 McArthur River Operation

Cameco Corporation operates the McArthur River underground mine in north-central Saskatchewan Ore from the mine which began production in 1999 is processed at the Key Lake Mill located 80 km south of McArthur River

Figures 229ndash232 present dose information for the McArthur River operation from 2001 to 2007

Figure 229 Average Dose Trends for the McArthur River Operation (Based o n N on-Zero R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

34

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 230 Average Dose Trends for the McArthur River Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

Figure 231 Collective Dose Trends for the McArthur River Operation

0

200

400

600

800

1000

1200

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Radon gas External Radon progeny Long-lived radioactive dust

Year

35

00

0-000

9

001-5

00

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 232 Distribution o f Effective Doses Among A ll Workers at the McArthur River Operation

0

100

200

300

400

500

600

700

800

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

36

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

224 Key Lake Operation

Cameco Corporation operates mining facilities in Key Lake located in north-central Saskatchewan The Key Lake operation includes two mined-out open pit mines (used for tailings management) a mill and two dry tailings management facilities Mining began in 1983 and ceased in 1997 the mill continued to process ore from the McArthur River mine during the reporting period

Figures 233ndash236 present dose information for the Key Lake operation from 2001 to 2007

Figure 233 Average Dose Trends for the Key Lake Operation (Based o n N on-Zero R esults)

00

20

40

60

80

00

20

40

60

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

37

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

00

20

40

60

80

00

20

40

60

Figure 234 Average Dose Trends for the Key Lake Operation (Based o n A ll Monitoring R esults)

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 235 Collective Dose Trends for the Key Lake Operation

0

100

200

300

400

500

600

700

800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External Radon progeny Long-lived radioactive dust

Year

38

00

0-000

9

001-5

0

501-1

000

gt 1001

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 236 Distribution o f Effective Doses Among A ll Workers at the Key Lake Operation

0

200

400

600

800

1000

1200

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose Range (mSv)

39

se

(mS

v)o

D

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

225 Cigar Lake Operation

Cameco Corporation manages the Cigar Lake underground mine located in northern Saskatchewan at the southern end of Waterbury Lake The mine was under construction at the time of this reportrsquos publication Test mining in ore was carried out in 1991 1992 and 2000

Figures 237ndash240 present dose information for the Cigar Lake operation from

Figure 2 37 Average D ose T rends fo r th e C igar L ake O peration (Based on Non-Zero Results)

2001 to 2007

Year

000

005

010

015

020

025

Long-lived radioactive dust Radon Progeny External Effective

40

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 238 Average Dose Trends for the Cigar Lake Operation (Based on All Monitoring Results)

000

005

010

015

020

025

030

035

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny

External

Effective

Year

Figure 239 Collective Dose Trends for the Cigar Lake Operation

0

50

100

150

200

250

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

External Radon progeny Long-lived radioactive dust

Year

41

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 240 Distribution of Effective Doses Among All Workers at the Cigar Lake Operation

0

200

400

600

800

1000

1200

1400

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

42

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

226 Rabbit Lake Operation

Cameco Corporation owns and operates mining facilities in Rabbit Lake located in north-eastern Saskatchewan Facilities include an underground mine four mined-out open-pit mines a mill and two tailings management facilities Mining and milling began in 1975

Figures 241ndash244 present dose information for the Rabbit Lake operation from 2001 to 2007

Figure 241 Average Dose Trends for the Rabbit Lake Operation (Based on Non-Zero Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

43

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 242 Average Dose Trends for the Rabbit Lake Operation (Based on All Monitoring Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

Figure 243 Collective Dose Trends for the Rabbit Lake Operation

0

200

400

600

800

1000

1200

1400

1600

1800

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Radon gas External Radon progeny Long-lived radioactive dust

Year

44

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

gt300

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 244 Distribution of Effective Doses Among All Workers at the Rabbit Lake Operation

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

900

800

700

600

500

400

300

200

100

0

Dose (mSv)

45

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

23 Uranium Refineries This section presents data for the following two facilities

bull a uranium refining facility in Blind River (Section 231) bull a uranium conversion facility in Port Hope (Section 232)

Graphs indicate the following average doses at each facility from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Note on data for uranium refineries

1 Doses from photons from external sources are measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay and lung counting Historically while these internal doses have been measured they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

231 Blind River Refinery

Cameco Corporation owns and is licensed to operate a uranium refinery in Blind River Ontario The facility which began operating in 1983 converts uranium ore concentrate to uranium trioxide The uranium trioxide is shipped to Camecorsquos uranium conversion facility in Port Hope Ontario where it is processed into uranium dioxide (for use in the fabrication of fuel for nuclear reactors in Canada) or uranium hexafluoride (exported for enrichment and fabrication into fuel for nuclear power reactors around the world)

Figures 245ndash248 present dose information for the Blind River refinery from 2001 to 2007

46

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 245 Average Dose Trends for the Blind River Refinery (Based on Non-Zero Results)

0

05

1

15

2

25

Year

Figure 246 Average Dose Trends for the Blind River Refinery (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

47

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 247 Collective Dose Trends for the Blind River Refinery

0

50

100

150

200

250

300 C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 248 Distribution of Effective Doses Among All Workers at the Blind River Refinery

0

20

40

60

80

100

120

140

160

180

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

48

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

232 Port Hope Conversion Facility

Cameco Corporation owns and is licensed to operate a uranium conversion facility in Port Hope Ontario The facility processes uranium trioxide received from the refinery in Blind River into uranium dioxide and uranium hexafluoride

Figures 249ndash252 present dose information for the Port Hope uranium conversion facility from 2001 to 2007

Figure 249 Average Dose Trends for the Port Hope Conversion Facility (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

49

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 250 Average Dose Trends for the Port Hope Conversion Facility (Based on All Monitoring Results)

0

01

02

03

04

05

06

07

08

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 251 Collective Dose Trends for the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

50

000-0

009

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 252 Distribution of Effective Doses Among All Workers at the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

400

450

500

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

51

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

24 Fuel Fabrication Facilities This section presents data for three nuclear fuel fabrication facilities

bull Two facilities owned and operated by General Electric Canada Inc (Section 241) bull One facility in Port Hope operated by Zircatec Precision Industries (Section 242)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average doses

Notes on data for fuel fabrication facilities

1 Effective doses for the three facilities are composed of the following reported components bull dose from photons (labelled on the charts as ldquoexternalrdquo) bull doses from internal intakes of uranium dust (long-lived radioactive dust) from

uranium in air concentrations (for General Electricrsquos Toronto facility only)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components photon doses and doses from long-lived radioactive dust

241 General Electric Nuclear Fuel Facilities

General Electric Canada Inc operates two nuclear fuel facilities in Ontario

bull At the Toronto facility uranium dioxide pellets are produced from natural or depleted uranium dioxide powder

bull At the Peterborough facility uranium dioxide fuel bundles are created from the pellets produced at the Toronto facility

Figures 253ndash256 present dose information for General Electric Canada Incrsquos fuel fabrication facilities from 2001 to 2007 Graphs do not distinguish between the doses received at the Peterborough facility versus those at the Toronto facility

52

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 253 Average Dose Trends for the General Electric Fuel Facility (Based on Non-Zero Results Only)

0

05

1

15

2

25

3

35

Long Lived Radioactive Dust External Effective

Year

Figure 254 Average Dose Trends for the General Electric Fuel Facility (Based on All Monitoring Results)

0

05

1

15

2

25

3

Long Lived Radioactive Dust External Effective

Year

Dos

e (m

Sv)

Dos

e (m

Sv)

53

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 255 Collective Dose Trends for the General Electric Fuel Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Long Lived Radioactive Dust External

Year

Figure 256 Distribution of Effective Doses among all Workers at the General Electric Fuel Facility

0

10

20

30

40

50

60

70

80

90

100

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

54

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

242 Zircatec Nuclear Fuel Facility

Zircatec Precision Industries Inc operates a nuclear fuel facility in Port Hope Ontario where it makes fuel pellets from uranium dioxide powder received from Port Hopersquos uranium conversion facility The nuclear fuel facility also manufactures fuel bundles for nuclear reactors in Canada

Notes on data for the Zircatec nuclear fuel facility

1 Graphs indicate the following data bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of average effective doses

2 Doses from photons from external sources were measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay Historically although these internal doses have been measured and submitted to the CNSC they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

Figures 257ndash260 present dose information for the Zircatec nuclear fuel facility from 2001 to 2007

Figure 257 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on Non-Zero Results)

0

05

1

15

2

25

3

35

Effe

ctiv

e D

ose

(mS

v)

Year

55

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 258 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

18

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 259 Collective Dose Trends for the Zircatec Nuclear Fuel Facility

0

50

100

150

200

250

300

350

400

450

500

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

56

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 260 Distribution of Effective Doses Among All Workers at the Zircatec Nuclear Fuel Facility

300

Num

ber o

f Wor

kers

250

200

150

100

50

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

57

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

25 Research and Radioisotope Production Facilities This section presents dose information for the following research and radioisotope production facilities from 2001 to 2007

bull Chalk River Laboratories and Whiteshell Laboratories (Section 251) bull A radioisotope production facility operated by MDS Nordion (Section 252) bull The Tri-University Meson Facility (TRIUMF) (Section 253)

Note on data for research and radioisotope production facilities

1 Graphs indicate the following data for each facility bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of effective doses

251 Chalk River Laboratories and Whiteshell Laboratories

Atomic Energy of Canada Limited (AECL) owns and is licensed to operate Chalk River Laboratories and Whiteshell Laboratories

Situated in Renfrew County on the south shore of the Ottawa River the Chalk River Laboratories site hosts the National Research Universal Reactor along with numerous other facilities occupying some 160 buildings in an area of approximately 40 km2 Activities consist of radioisotope production for nuclear medicine testing and development of structural materials in support of power reactor operations fuel fabrication research and radioactive waste management and storage

The Whiteshell Laboratories site is located approximately 10 km west of Pinawa Manitoba and 100 km northeast of Winnipeg on the east bank of the Winnipeg River AECL established the laboratories for nuclear research and testing during the early 1960s and has since discontinued operations which are being decommissioned under a licence from the CNSC

Figures 261ndash264 present dose information for Chalk River Laboratories and Whiteshell Laboratories from 2001 to 2007

Notes on data for Chalk River Laboratories and Whiteshell Laboratories

1 Effective doses are composed of the following reported components bull external doses5 (from both photon and neutron doses) bull tritium doses

Due to issues with AECLrsquos in-house dosimetry management system neutron doses were not reported separately to the NDR during the reporting period As a result external doses from photons and neutrons were totaled The reporting discrepancy has since been rectified

58

5

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of external (photon and neutron) and tritium doses Intakes of other radionuclides occasionally occur and these radionuclides are not included here because their associated doses are very small For this reason certain collective doses in this report may have values slightly lower than the sum of their respective components as listed

Figure 261 Average Dose Trends for Chalk River and Whiteshell Laboratories (Non-Zero Results Only)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Tritium External Effective

Year

59

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 262 Average Dose Trends for Chalk River and Whiteshell Laboratories (All Monitoring Results)

000

020

040

060

080

100

120

Dos

e (m

Sv)

Tritium External Effective

Year

Figure 263 Collective Dose Trends for Chalk River and Whiteshell Laboratories

0

500

1000

1500

2000

2500

3000

3500

Col

lect

ive

Dos

e (p

erso

n- m

Sv)

External Tritium

Year

60

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 264 Distribution of Effective Doses Among All Workers at Chalk River and Whiteshell Laboratories

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

3500

3000

2500

2000

1500

1000

500

Dose (mSv)

61

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

252 MDS Nordion (Nuclear Substance Processing Facility and Canadian Irradiation Centre)

MDS Nordion owns and operates a nuclear substance processing facility in Ottawa Ontario where it processes unsealed radioisotopes and manufactures sealed radiation sources In operation since the early 1970s the facility was purchased by Nordion International in 1991

In cooperation with the Universiteacute du Queacutebecrsquos Institut Armand-Frappier MDS Nordion also operates the Canadian Irradiation Centre which conducts various irradiation services which include training testing and development The centre is located in Laval Quebec on the Universiteacute du Queacutebec campus

Figures 265ndash268 present dose information for MDS Nordionrsquos Ottawa nuclear substance processing facility and for the Canadian Irradiation Centre from 2001 to 2007

Notes on data for MDS Nordionrsquos nuclear substance processing facility and the Canadian Irradiation Centre

1 Doses from photons from external sources were measured and reported to the NDR MDS Nordion also has a routine thyroid monitoring program very occasionally small recordable doses of radiation have occurred from thyroid uptake of iodine The resulting doses have not been historically submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided

Figure 265 Average Dose Trends for MDS Nordion (Based on Non-Zero Results)

0

05

1

15

2

25

Effe

ctiv

e D

ose

(mS

v)

Year

62

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 266 Average Dose Trends for MDS Nordion (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

Figure 267 Collective Dose Trends for MDS Nordion

0

100

200

300

400

500

600

700

800

Year

63

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 268 Distribution of Effective Doses Among All Workers at MDS Nordion

0

5 0

1 0 0

1 5 0

2 0 0

2 5 0

3 0 0

3 5 0

4 0 0

4 5 0

5 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

64

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

253 Tri-University Meson Facility

The Tri-University Meson facility (TRIUMF) is situated in Vancouver on the campus of the University of British Columbia TRIUMF which began operating in the early 1970s with one cyclotron now has two cyclotrons and associated laboratories for research and radioisotope production The laboratory provides research facilities for Canadian and international users and also produces radioisotopes which are used by medical facilities and by a commercial organization (MDS Nordion) MDS Nordion staff also work at the TRIUMF site however MDS Nordion oversees this work and has its own radiation protection program

Figures 269ndash272 present dose information for the TRIUMF facility from 2001 to 2007 Please note that data sets do not distinguish between doses received by TRIUMF staff and MDS Nordion staff who work on the site as the data for these two groups was submitted collectively to the NDR for the reporting period shown Future data for each group will be submitted separately to the NDR

Note on data for TRIUMF

1 Effective doses are composed of the following reported components bull doses from photons (labeled as ldquoexternalrdquo in the charts) bull neutron doses

Figure 269 Average Dose Trends for TRIUMF (Non-Zero Results Only)

000

020

040

060

080

100

120

140

160

Dos

e (m

Sv)

Neutrons External Effective

Year

65

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 12: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

ty

Dos

e (m

Sv)

) v

Sm( e so

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e N

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iver

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klaC

h

MD

S N

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on

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nive

rsity

Mes

on F

acilit

y

Figure 17 Average Effective Doses at All Selected Facilities for the Year 2007 (Based on Non-Zero Results)

4

35

3

25

2

15

1

05

0

Bru

ce N

ucle

ar G

ener

atin

g S

tatio

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ff La

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C

MD

S N

ordi

on

Tri-U

nive

rsity

Mes

on F

acili

ty

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 16 Average Effective Doses at All Selected Facilities for the Year 2006 (Based on Non-Zero Results)

4

35

3

25

2

15

1

05

0

Shie

ld S

ourc

e In

corp

orat

edS

hiel

d S

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e In

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ed

SRB

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(Can

ada)

Inc

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s (C

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a) In

c

7

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4

35

3

25

2

15

1

05

0

Dos

e (m

Sv)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

12 Average Effective Doses Based on All Monitoring Results at All Selected Facilities Figures 18ndash114 show average effective doses based on all the monitoring results for each year from 2001 to 2007 for every facility listed in this document

Figure 18 Average Effective Doses at All Selected F acilities for the Year 2001 (Based o n A ll Monitoring R esults)

8

r

Dos

e (m

Sv)

)

Sv

(me

osD

Bruc

e N

ucle

ar G

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Pick

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MD

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n ive

rsity

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on F

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Figure 110 Average Effective Doses at All Selected F acilities for the Year 2003 (Based o n A ll Monitoring R esults)

4

35

3

25

2

15

1

05

0

Bruc

e N

ucle

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erin

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MD

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nive

r sity

Mes

on F

acilit

y

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 19 Average Effective Doses at All Selected Facilities for the Year 2002 (Based on All Monitoring Results)

4

35

3

25

2

15

1

05

0

Shie

ld S

ourc

e In

corp

orat

edSh

ield

Sou

rce

Inco

rpor

ated

c In)adan

Ca

(seigolonhce T

RB

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B Te

chno

logi

es (C

anad

a) In

c

9

Dos

e (m

Sv)

)

Sv

(me

osD

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 111 Average Effective Doses at All Selected F acilities for the Year 2004 (Based o n A ll Monitoring R esults)

4

35

3

25

2

15

1

05

0

Bruc

e N

ucle

ar G

ener

atin

g St

atio

ns

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erin

g N

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n

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t Lep

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ff La

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tion

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McA

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er

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ctric

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l Fac

ilitie

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lear

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Lre v R

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MD

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on F

acilit

y

Figure 112 Average Effective Doses at All Selected F acilities for the Year 2005 (Based o n A ll Monitoring R esults)

4

35

3

25

2

15

1

05

0

Bruc

e N

ucle

ar G

ener

atin

g St

atio

ns

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erin

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ff La

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eral

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l Fac

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on F

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ld S

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rce

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ada)

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B Te

chno

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es (C

anad

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10

r s s n n n n n n n n ty s ty l l ty de y n cn n o o o o o o o o r i il e e o ivo o ti l h lti ti ti ti ti ti ti ti i i

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fi cr te S S F F

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S S au p p p i p dp p hg g g n F l n r ae og g n n n Re

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a a r r e n In Ca

r r e a a M a re e a a Ri F M e (n L r s Me e n n L v a

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y t L s r en lr d ty

G

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) S

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D

4

35

3

25

2

15

1

05

0

) vS

m( e soD

Figure 114 Average Effective Doses at All Selected F acilities for the Year 2007 (Based o n A ll Monitoring R esults)

Bru

ce N

ucle

ar G

ener

atin

g S

tatio

ns

Pic

kerin

g N

ucle

ar G

ener

atin

g S

tatio

ns

Dar

lingt

on N

ucle

ar G

ener

atin

g S

tatio

n

Gen

tilly

-2 N

ucle

ar G

ener

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g S

tatio

n

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nt L

epre

au N

ucle

ar G

ener

atin

g S

tatio

n

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ff La

ke O

pera

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lean

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e O

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McA

rthur

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er

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Lak

e O

pera

tion

Cig

ar L

ake

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ratio

n

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bit L

ake

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ratio

n

Blin

d R

iver

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iner

y

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t Hop

e C

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n Fa

cilit

y

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eral

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ctric

Nuc

lear

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l Fac

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l Fac

ility llehsetih

W d na s s ee iri oro tat ra or bo ab La Lr evi

Rk lah

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MD

S N

ordi

on

Tri-U

nive

rsity

Mes

on F

acili

ty

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 113 Average Effective Doses at All Selected Facilities for the Year 2006 (Based on All Monitoring Results)

4

35

3

25

2

15

1

05

0

Shi

eld

Sou

rce

Inco

rpor

ated

SR

B T

echn

olog

ies

(Can

ada)

Inc

11

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

20 Facility-Specific Overview of Occupational Doses This section presents data for the following types of facilities

bull nuclear power plants (Section 21) bull uranium mines and mills (Section 22) bull uranium refineries (Section 23) bull fuel fabrication facilities (Section 24) bull research and radioisotope production facilities (Section 25) bull tritium production facilities (Section 26)

21 Nuclear Power Plants This section presents dose information for the following nuclear power plants

bull Bruce A and Bruce B Nuclear Generating Stations (Section 211) bull Pickering Nuclear Generating Stations (Section 212) bull Darlington Nuclear Generating Station Section 213) bull Gentilly-2 Nuclear Generating Station (Section 214) bull Point Lepreau Generating Station (Section 215)

Graphs in this section indicate the following data for each nuclear power plant from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for nuclear power plants

1 Effective doses are composed of the following reported components bull doses from photons (labeled on the charts as ldquoexternalrdquo) bull neutron doses bull tritium doses

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of photon neutron and tritium doses Intakes of other radionuclides (for example Iodine-131 or Carbon-14) occasionally occur but these radionuclides are not included here because the associated collective dose is very small For this reason certain collective dose values in this report may be slightly lower than the sum of their respective components as listed

12

1 2 3 4 5 6 70 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

211 Bruce Nuclear Generating Stations

Bruce Power owns and operates the Bruce Nuclear Generating Stations located near Kincardine Ontario on the shore of Lake Huron

bull Bruce A consists of four nuclear reactors (units 1ndash4) and began operating in 1976 bull Bruce B has four nuclear reactors (units 5ndash8) and started operating in 1984

As part of its extensive recovery program in 1997 the sitersquos previous operator Ontario Hydro (now Ontario Power Generation) temporarily shut down all Bruce A reactors and maintained them in a guaranteed shutdown state Units 3 and 4 were later returned to service (in October 2003 and January 2004) while Units 1 and 2 remained in a guaranteed shutdown state

Figures 21ndash24 present dose information for the Bruce Nuclear Generating Stations from 2001 to 2007 Graphs do not distinguish between doses received at Bruce A versus Bruce B

Fig 21 Average Dose Trends for Bruce Nuclear Generating Stati on (Based o n N on-Zero R esults)

Dos

e (m

Sv)

4

35

3

25

2

15

1

05

0

Tritium Neutron External Effective

Year

13

Neutrons External Tritium

0 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 21 2 3 4 5 6 7

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

0

2

4

6

8

1

2

4

0

0

0

0

1

1

Figure 22 Average Dose Trends for Bruce Nuclear Generating Stati on (Based o n A ll Monitoring R esults)

16

)S

v(m

e os

D

Tritium Neutrons External Effective

Year

Figure 23 Collective Dose Trends for Bruce Nuclear Generating Stati on

8000

7000

6000

5000

4000

3000

2000

1000

0

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Year

14

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 24 Distribution of Effective Doses Among All Workers at Bruce Nuclear Generating Station

6000

5000

4000

3000

2000

1000

0 9 0 0

1-50 0 0 1 0 0 0 0 00 5 0 0 0

0-000

000 1-1 1-1 1-20 1-3 3gt0 0 0 05 0 5 01 1 2

Num

ber o

f Wor

kers

Dose Range (mSv)

15

1 2 3 4 5 6 7 0 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

212 Pickering Nuclear Generating Stations

Located in Pickering Ontario the Pickering Nuclear Generating Stations are owned and operated by Ontario Power Generation Two generating stations are located within one enclosure

bull Pickering A consists of four nuclear reactors (units 1 to 4) that began operating in 1971 bull Pickering B consists of four nuclear reactors (units 5 to 8) that began operating in 1982

As part of its extensive recovery program Ontario Hydro (now Ontario Power Generation) temporarily shut down all Pickering A reactors in 1997 and maintained them in a guaranteed shutdown state Unit 4 was restarted in September 2003 and Unit 1 was restarted in March 2005 Units 2 and 3 remain in a guaranteed shutdown state

Figures 25ndash28 present dose information for the Pickering Nuclear Generating Stations from 2001 to 2007 Graphs do not distinguish between doses received at Pickering A versus those received at Pickering B

Figure 25 Average Dose Trends for Pickering N uclear Generating Stati on (Based o n N on-Zero R esults)

25

2

15

1

05

0

)S

v(m

e os

D

Tritium Neutrons External Effective

Year

16

Tritium Neutrons External Effective

Neutrons External Tritium

1 2 3 4 5 6 70 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

1 2 3 4 5 6 7 0 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 26 Average Dose Trends for Pickering N uclear Generating Stati on (Based o n A ll Monitoring R esults)

12

1

08

06

04

02

0

Year

Figure 27 Collective Dose Trends for Pickering N uclear Generating Stati on

12000

10000

8000

6000

4000

2000

0

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

)

Sv

(me

osD

Year

17

2001 2002 2003 2004 2005 2006 2007

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 28 Distribution o f Effective Doses Among A ll Workers at Pickering Nuclear Generating Stati on

6000

5000

4000

3000

2000

1000

0

Num

ber o

f Wor

kers

Dose Range (mSv)

18

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

213 Darlington Nuclear Generating Station

Owned and operated by Ontario Power Generation the Darlington Nuclear Generating Station has four nuclear reactors the first of which began operating in 1989 The facility is located near Bowmanville on the shore of Lake Ontario

Figures 29ndash212 present dose information for the Darlington Nuclear Generating Station from 2001 to 2007

Figure 29 Average Dose Trends for Darlington N uclear Generating Stati on (Non- Zero R esults Only)

)S

v(m

e os

D

250

200

150

100

050

000

Year

19

Tritium Neutrons External Effective

Neutrons External Tritium

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 210 Average Dose Trends for Darlington N uclear Generating Stati on (All Monitoring R esults)

090

080

070

060

050

040

030

020

010

000

)S

v(m

e os

D

Year

Figure 211 Collective Dose Trends for Darlington N uclear Generating Stati on

4500

4000

3500

3000

2500

2000

1500

1000

500

0

)vSm-nosrep (es

Do

eiv

llect

Co

Year

20

2001 2002 2003 2004 2005 2006 2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 212 Distribution o f Effective Doses Among A ll Workers at Darlington Nuclear Generating Stati on

0

500

1000

1500

2000

2500

3000

3500

ers

ork

W of

be

r um

N

Dose Range (mSv)

21

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

214 Gentilly-2 Nuclear Generating Station

The Gentilly-2 Nuclear Generating Station owned and operated by Hydro-Queacutebec has a single reactor that began operating in 1982 The facility is located on the south shore of the St Lawrence River near Trois-Riviegraveres Queacutebec

Figures 213ndash216 present dose information for the Gentilly-2 Nuclear Generating Station from 2001 to 2007

Figure 213 Average Dose Trends for Gentilly-2 Nuclear Generating Stati on (Based o n N on-Zero R esults)

0

05

1

15

2

25

3

35

4

45

)S

v(m

e os

D

Year

22

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 214 Average Dose Trends for Gentilly-2 Nuclear Generating Stati on (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

)S

v(m

e os

D

Year

Figure 215 Collective Dose Trends for Gentilly-2 Nuclear Generating Stati on

0

500

1000

1500

2000

2500

3000

3500

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Neutrons

External

Tritium

Year

23

000-0

009

001-5

00

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 216 Distribution of Effective Doses Among All Workers at Gentilly-2 Nuclear Generating Station

2500

2000

1500

1000

500

0

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

24

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

215 Point Lepreau Nuclear Generating Station

The Point Lepreau Nuclear Generating Station has one reactor that began operating in 1982 Owned and operated by New Brunswick Power Nuclear the station is located in Point Lepreau New Brunswick about 40 km west of Saint John on the shores of the Bay of Fundy

Figures 217ndash220 present dose information for the Point Lepreau Nuclear Generating Station from 2001 to 2007

Figure 217 Average Dose Trends for Point Lepreau N uclear Generating Stati on (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

)S

v(m

e os

D

Tritium Neutron External Effective

Year

25

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 218 Average Dose Trends for Point Lepreau N uclear Generating Stati on (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

)S

v(m

e os

D

Tritium Neutrons External Effective

Year

Figure 219 Collective Dose Trends for Point Lepreau N uclear Generating Station

0

200

400

600

800

1000

1200

1400

1600

1800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Neutrons

External

Tritium

Year

26

0

1400

1200

1000

800

600

400

200

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 220 Distribution of Effective Doses Among All Workers at Point Lepreau Nuclear Generating Station

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

27

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

22 Uranium Mines and Mills This section presents dose information for mine and mill sites in the following regions

bull Cluff Lake (Section 221) bull McClean Lake (Section 222) bull McArthur River (Section 223) bull Key Lake (Section 224) bull Cigar Lake (Section 225) bull Rabbit Lake (Section 226)

Graphs indicate the following data for each site from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for uranium mines and mills

1 Effective doses are composed of the following reported components bull doses from photons (labelled on the charts as ldquoexternalrdquo) bull doses from radon progeny bull doses from long-lived radioactive dust bull doses from radon gas (in some cases)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of photon radon progeny long-lived radioactive dust and radon gas doses

3 The NDR lists radon progeny in working level months (WLM) For this report radon progeny exposures were converted4 to doses expressed in mSv

221 Cluff Lake Operation

The Cluff Lake mining facilities operated by AREVA Resources Canada Inc are located in northwestern Saskatchewan Work began in 1980 and ended in 2002 with the site now being decommissioned The site consisted of three open-pit and two underground mines a mill and a tailings management facility During 2005 and 2006 most of the infrastructure was removed and the affected areas were remediated

Figures 221ndash224 present dose information for the Cluff Lake operation from 2001 to 2007

4 Doses were converted using the International Commission on Radiation Protection (ICRP)rsquos conversion convention of 1 WLM = 5 mSv This convention was established in the ICRP publication Protection against Radon at Home and at Work (ICRP 65)

28

Long-lived radioactive dust Radon progeny External Effective

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 221 Average Dose Trends for the Cluff Lake Operation (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

Year

Figure 222 Average Dose Trends for the Cluff Lake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

200

Long-lived radioactive dust Radon progeny External Effective

)S

v(m

e os

D)

Sv

(me

osD

Year

29

600

500

400

300

200

100

0

External Radon progeny Long-lived radioactive dust

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 223 Collective Dose Trends for the Cluff Lake Operation s

erkor

of W

ber

Num

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Year

Figure 224 Distribution o f Effective Doses Among A ll Workers at the Cluff Lake Operation

0

20

40

60

80

100

120

140

160

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

30

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

222 McClean Lake Operation

AREVA Resources Canada Inc runs the McClean Lake mining operation in northeastern Saskatchewan It comprises open pit mines a mill and a tailings management facility Mining began in 1995 while milling started in 1999

Figures 225ndash228 present dose information for the McClean Lake operation from 2001 to 2007

Figure 225 Average Dose Trends for the McClean L ake Operation (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

31

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 226 Average Dose Trends for the McClean L ake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 227 Collective Dose Trends for the McClean L ake Operation

0

100

200

300

400

500

600

700

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External

Radon progeny

Long-lived radioactive dust

Year

32

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 228 Distribution o f Effective Doses Among A ll Workers at the McClean Lake Operation

0

100

200

300

400

500

600

700

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

33

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

223 McArthur River Operation

Cameco Corporation operates the McArthur River underground mine in north-central Saskatchewan Ore from the mine which began production in 1999 is processed at the Key Lake Mill located 80 km south of McArthur River

Figures 229ndash232 present dose information for the McArthur River operation from 2001 to 2007

Figure 229 Average Dose Trends for the McArthur River Operation (Based o n N on-Zero R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

34

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 230 Average Dose Trends for the McArthur River Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

Figure 231 Collective Dose Trends for the McArthur River Operation

0

200

400

600

800

1000

1200

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Radon gas External Radon progeny Long-lived radioactive dust

Year

35

00

0-000

9

001-5

00

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 232 Distribution o f Effective Doses Among A ll Workers at the McArthur River Operation

0

100

200

300

400

500

600

700

800

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

36

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

224 Key Lake Operation

Cameco Corporation operates mining facilities in Key Lake located in north-central Saskatchewan The Key Lake operation includes two mined-out open pit mines (used for tailings management) a mill and two dry tailings management facilities Mining began in 1983 and ceased in 1997 the mill continued to process ore from the McArthur River mine during the reporting period

Figures 233ndash236 present dose information for the Key Lake operation from 2001 to 2007

Figure 233 Average Dose Trends for the Key Lake Operation (Based o n N on-Zero R esults)

00

20

40

60

80

00

20

40

60

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

37

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

00

20

40

60

80

00

20

40

60

Figure 234 Average Dose Trends for the Key Lake Operation (Based o n A ll Monitoring R esults)

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 235 Collective Dose Trends for the Key Lake Operation

0

100

200

300

400

500

600

700

800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External Radon progeny Long-lived radioactive dust

Year

38

00

0-000

9

001-5

0

501-1

000

gt 1001

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 236 Distribution o f Effective Doses Among A ll Workers at the Key Lake Operation

0

200

400

600

800

1000

1200

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose Range (mSv)

39

se

(mS

v)o

D

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

225 Cigar Lake Operation

Cameco Corporation manages the Cigar Lake underground mine located in northern Saskatchewan at the southern end of Waterbury Lake The mine was under construction at the time of this reportrsquos publication Test mining in ore was carried out in 1991 1992 and 2000

Figures 237ndash240 present dose information for the Cigar Lake operation from

Figure 2 37 Average D ose T rends fo r th e C igar L ake O peration (Based on Non-Zero Results)

2001 to 2007

Year

000

005

010

015

020

025

Long-lived radioactive dust Radon Progeny External Effective

40

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 238 Average Dose Trends for the Cigar Lake Operation (Based on All Monitoring Results)

000

005

010

015

020

025

030

035

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny

External

Effective

Year

Figure 239 Collective Dose Trends for the Cigar Lake Operation

0

50

100

150

200

250

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

External Radon progeny Long-lived radioactive dust

Year

41

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 240 Distribution of Effective Doses Among All Workers at the Cigar Lake Operation

0

200

400

600

800

1000

1200

1400

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

42

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

226 Rabbit Lake Operation

Cameco Corporation owns and operates mining facilities in Rabbit Lake located in north-eastern Saskatchewan Facilities include an underground mine four mined-out open-pit mines a mill and two tailings management facilities Mining and milling began in 1975

Figures 241ndash244 present dose information for the Rabbit Lake operation from 2001 to 2007

Figure 241 Average Dose Trends for the Rabbit Lake Operation (Based on Non-Zero Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

43

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 242 Average Dose Trends for the Rabbit Lake Operation (Based on All Monitoring Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

Figure 243 Collective Dose Trends for the Rabbit Lake Operation

0

200

400

600

800

1000

1200

1400

1600

1800

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Radon gas External Radon progeny Long-lived radioactive dust

Year

44

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

gt300

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 244 Distribution of Effective Doses Among All Workers at the Rabbit Lake Operation

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

900

800

700

600

500

400

300

200

100

0

Dose (mSv)

45

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

23 Uranium Refineries This section presents data for the following two facilities

bull a uranium refining facility in Blind River (Section 231) bull a uranium conversion facility in Port Hope (Section 232)

Graphs indicate the following average doses at each facility from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Note on data for uranium refineries

1 Doses from photons from external sources are measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay and lung counting Historically while these internal doses have been measured they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

231 Blind River Refinery

Cameco Corporation owns and is licensed to operate a uranium refinery in Blind River Ontario The facility which began operating in 1983 converts uranium ore concentrate to uranium trioxide The uranium trioxide is shipped to Camecorsquos uranium conversion facility in Port Hope Ontario where it is processed into uranium dioxide (for use in the fabrication of fuel for nuclear reactors in Canada) or uranium hexafluoride (exported for enrichment and fabrication into fuel for nuclear power reactors around the world)

Figures 245ndash248 present dose information for the Blind River refinery from 2001 to 2007

46

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 245 Average Dose Trends for the Blind River Refinery (Based on Non-Zero Results)

0

05

1

15

2

25

Year

Figure 246 Average Dose Trends for the Blind River Refinery (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

47

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 247 Collective Dose Trends for the Blind River Refinery

0

50

100

150

200

250

300 C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 248 Distribution of Effective Doses Among All Workers at the Blind River Refinery

0

20

40

60

80

100

120

140

160

180

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

48

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

232 Port Hope Conversion Facility

Cameco Corporation owns and is licensed to operate a uranium conversion facility in Port Hope Ontario The facility processes uranium trioxide received from the refinery in Blind River into uranium dioxide and uranium hexafluoride

Figures 249ndash252 present dose information for the Port Hope uranium conversion facility from 2001 to 2007

Figure 249 Average Dose Trends for the Port Hope Conversion Facility (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

49

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 250 Average Dose Trends for the Port Hope Conversion Facility (Based on All Monitoring Results)

0

01

02

03

04

05

06

07

08

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 251 Collective Dose Trends for the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

50

000-0

009

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 252 Distribution of Effective Doses Among All Workers at the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

400

450

500

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

51

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

24 Fuel Fabrication Facilities This section presents data for three nuclear fuel fabrication facilities

bull Two facilities owned and operated by General Electric Canada Inc (Section 241) bull One facility in Port Hope operated by Zircatec Precision Industries (Section 242)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average doses

Notes on data for fuel fabrication facilities

1 Effective doses for the three facilities are composed of the following reported components bull dose from photons (labelled on the charts as ldquoexternalrdquo) bull doses from internal intakes of uranium dust (long-lived radioactive dust) from

uranium in air concentrations (for General Electricrsquos Toronto facility only)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components photon doses and doses from long-lived radioactive dust

241 General Electric Nuclear Fuel Facilities

General Electric Canada Inc operates two nuclear fuel facilities in Ontario

bull At the Toronto facility uranium dioxide pellets are produced from natural or depleted uranium dioxide powder

bull At the Peterborough facility uranium dioxide fuel bundles are created from the pellets produced at the Toronto facility

Figures 253ndash256 present dose information for General Electric Canada Incrsquos fuel fabrication facilities from 2001 to 2007 Graphs do not distinguish between the doses received at the Peterborough facility versus those at the Toronto facility

52

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 253 Average Dose Trends for the General Electric Fuel Facility (Based on Non-Zero Results Only)

0

05

1

15

2

25

3

35

Long Lived Radioactive Dust External Effective

Year

Figure 254 Average Dose Trends for the General Electric Fuel Facility (Based on All Monitoring Results)

0

05

1

15

2

25

3

Long Lived Radioactive Dust External Effective

Year

Dos

e (m

Sv)

Dos

e (m

Sv)

53

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 255 Collective Dose Trends for the General Electric Fuel Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Long Lived Radioactive Dust External

Year

Figure 256 Distribution of Effective Doses among all Workers at the General Electric Fuel Facility

0

10

20

30

40

50

60

70

80

90

100

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

54

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

242 Zircatec Nuclear Fuel Facility

Zircatec Precision Industries Inc operates a nuclear fuel facility in Port Hope Ontario where it makes fuel pellets from uranium dioxide powder received from Port Hopersquos uranium conversion facility The nuclear fuel facility also manufactures fuel bundles for nuclear reactors in Canada

Notes on data for the Zircatec nuclear fuel facility

1 Graphs indicate the following data bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of average effective doses

2 Doses from photons from external sources were measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay Historically although these internal doses have been measured and submitted to the CNSC they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

Figures 257ndash260 present dose information for the Zircatec nuclear fuel facility from 2001 to 2007

Figure 257 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on Non-Zero Results)

0

05

1

15

2

25

3

35

Effe

ctiv

e D

ose

(mS

v)

Year

55

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 258 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

18

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 259 Collective Dose Trends for the Zircatec Nuclear Fuel Facility

0

50

100

150

200

250

300

350

400

450

500

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

56

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 260 Distribution of Effective Doses Among All Workers at the Zircatec Nuclear Fuel Facility

300

Num

ber o

f Wor

kers

250

200

150

100

50

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

57

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

25 Research and Radioisotope Production Facilities This section presents dose information for the following research and radioisotope production facilities from 2001 to 2007

bull Chalk River Laboratories and Whiteshell Laboratories (Section 251) bull A radioisotope production facility operated by MDS Nordion (Section 252) bull The Tri-University Meson Facility (TRIUMF) (Section 253)

Note on data for research and radioisotope production facilities

1 Graphs indicate the following data for each facility bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of effective doses

251 Chalk River Laboratories and Whiteshell Laboratories

Atomic Energy of Canada Limited (AECL) owns and is licensed to operate Chalk River Laboratories and Whiteshell Laboratories

Situated in Renfrew County on the south shore of the Ottawa River the Chalk River Laboratories site hosts the National Research Universal Reactor along with numerous other facilities occupying some 160 buildings in an area of approximately 40 km2 Activities consist of radioisotope production for nuclear medicine testing and development of structural materials in support of power reactor operations fuel fabrication research and radioactive waste management and storage

The Whiteshell Laboratories site is located approximately 10 km west of Pinawa Manitoba and 100 km northeast of Winnipeg on the east bank of the Winnipeg River AECL established the laboratories for nuclear research and testing during the early 1960s and has since discontinued operations which are being decommissioned under a licence from the CNSC

Figures 261ndash264 present dose information for Chalk River Laboratories and Whiteshell Laboratories from 2001 to 2007

Notes on data for Chalk River Laboratories and Whiteshell Laboratories

1 Effective doses are composed of the following reported components bull external doses5 (from both photon and neutron doses) bull tritium doses

Due to issues with AECLrsquos in-house dosimetry management system neutron doses were not reported separately to the NDR during the reporting period As a result external doses from photons and neutrons were totaled The reporting discrepancy has since been rectified

58

5

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of external (photon and neutron) and tritium doses Intakes of other radionuclides occasionally occur and these radionuclides are not included here because their associated doses are very small For this reason certain collective doses in this report may have values slightly lower than the sum of their respective components as listed

Figure 261 Average Dose Trends for Chalk River and Whiteshell Laboratories (Non-Zero Results Only)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Tritium External Effective

Year

59

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 262 Average Dose Trends for Chalk River and Whiteshell Laboratories (All Monitoring Results)

000

020

040

060

080

100

120

Dos

e (m

Sv)

Tritium External Effective

Year

Figure 263 Collective Dose Trends for Chalk River and Whiteshell Laboratories

0

500

1000

1500

2000

2500

3000

3500

Col

lect

ive

Dos

e (p

erso

n- m

Sv)

External Tritium

Year

60

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 264 Distribution of Effective Doses Among All Workers at Chalk River and Whiteshell Laboratories

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

3500

3000

2500

2000

1500

1000

500

Dose (mSv)

61

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

252 MDS Nordion (Nuclear Substance Processing Facility and Canadian Irradiation Centre)

MDS Nordion owns and operates a nuclear substance processing facility in Ottawa Ontario where it processes unsealed radioisotopes and manufactures sealed radiation sources In operation since the early 1970s the facility was purchased by Nordion International in 1991

In cooperation with the Universiteacute du Queacutebecrsquos Institut Armand-Frappier MDS Nordion also operates the Canadian Irradiation Centre which conducts various irradiation services which include training testing and development The centre is located in Laval Quebec on the Universiteacute du Queacutebec campus

Figures 265ndash268 present dose information for MDS Nordionrsquos Ottawa nuclear substance processing facility and for the Canadian Irradiation Centre from 2001 to 2007

Notes on data for MDS Nordionrsquos nuclear substance processing facility and the Canadian Irradiation Centre

1 Doses from photons from external sources were measured and reported to the NDR MDS Nordion also has a routine thyroid monitoring program very occasionally small recordable doses of radiation have occurred from thyroid uptake of iodine The resulting doses have not been historically submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided

Figure 265 Average Dose Trends for MDS Nordion (Based on Non-Zero Results)

0

05

1

15

2

25

Effe

ctiv

e D

ose

(mS

v)

Year

62

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 266 Average Dose Trends for MDS Nordion (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

Figure 267 Collective Dose Trends for MDS Nordion

0

100

200

300

400

500

600

700

800

Year

63

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 268 Distribution of Effective Doses Among All Workers at MDS Nordion

0

5 0

1 0 0

1 5 0

2 0 0

2 5 0

3 0 0

3 5 0

4 0 0

4 5 0

5 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

64

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

253 Tri-University Meson Facility

The Tri-University Meson facility (TRIUMF) is situated in Vancouver on the campus of the University of British Columbia TRIUMF which began operating in the early 1970s with one cyclotron now has two cyclotrons and associated laboratories for research and radioisotope production The laboratory provides research facilities for Canadian and international users and also produces radioisotopes which are used by medical facilities and by a commercial organization (MDS Nordion) MDS Nordion staff also work at the TRIUMF site however MDS Nordion oversees this work and has its own radiation protection program

Figures 269ndash272 present dose information for the TRIUMF facility from 2001 to 2007 Please note that data sets do not distinguish between doses received by TRIUMF staff and MDS Nordion staff who work on the site as the data for these two groups was submitted collectively to the NDR for the reporting period shown Future data for each group will be submitted separately to the NDR

Note on data for TRIUMF

1 Effective doses are composed of the following reported components bull doses from photons (labeled as ldquoexternalrdquo in the charts) bull neutron doses

Figure 269 Average Dose Trends for TRIUMF (Non-Zero Results Only)

000

020

040

060

080

100

120

140

160

Dos

e (m

Sv)

Neutrons External Effective

Year

65

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 13: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

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Dos

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Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

12 Average Effective Doses Based on All Monitoring Results at All Selected Facilities Figures 18ndash114 show average effective doses based on all the monitoring results for each year from 2001 to 2007 for every facility listed in this document

Figure 18 Average Effective Doses at All Selected F acilities for the Year 2001 (Based o n A ll Monitoring R esults)

8

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Ch

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Mes

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Figure 110 Average Effective Doses at All Selected F acilities for the Year 2003 (Based o n A ll Monitoring R esults)

4

35

3

25

2

15

1

05

0

Bruc

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ucle

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Ch

MD

S N

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Tri-U

nive

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Mes

on F

acilit

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Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 19 Average Effective Doses at All Selected Facilities for the Year 2002 (Based on All Monitoring Results)

4

35

3

25

2

15

1

05

0

Shie

ld S

ourc

e In

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Ca

(seigolonhce T

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logi

es (C

anad

a) In

c

9

Dos

e (m

Sv)

)

Sv

(me

osD

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 111 Average Effective Doses at All Selected F acilities for the Year 2004 (Based o n A ll Monitoring R esults)

4

35

3

25

2

15

1

05

0

Bruc

e N

ucle

ar G

ener

atin

g St

atio

ns

Pick

erin

g N

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ar G

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Dar

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ar G

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tilly

-2 N

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ff La

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pera

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McC

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Lak

e O

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tion

McA

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Riv

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Key

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Ope

ratio

n

Cig

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ratio

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n

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d R

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Ref

iner

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Port

Hop

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onve

rsio

n Fa

cilit

y

Gen

eral

Ele

ctric

Nuc

lear

Fue

l Fac

ilitie

s

Zirc

atec

Nuc

lear

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l Fac

ility llehs

teih Wdn

a ses ie rir toto ara or bo ab La

Lre v R

ikla

Ch

MD

S N

ordi

on

T ri-U

nive

rsity

Mes

on F

acilit

y

Figure 112 Average Effective Doses at All Selected F acilities for the Year 2005 (Based o n A ll Monitoring R esults)

4

35

3

25

2

15

1

05

0

Bruc

e N

ucle

ar G

ener

atin

g St

atio

ns

Pick

erin

g N

ucle

ar G

ener

atin

g St

atio

ns

Dar

lingt

on N

ucle

ar G

ener

atin

g St

atio

n

Gen

tilly

-2 N

ucle

ar G

ener

atin

g St

atio

n

Poin

t Lep

reau

Nuc

lear

Gen

erat

ing

Stat

ion

Clu

ff La

ke O

pera

tion

McC

lean

Lak

e O

pera

tion

McA

rthur

Riv

er

Key

Lake

Ope

ratio

n

Cig

ar L

ake

Ope

ratio

n

Rab

bit L

ake

Ope

ratio

n

Blin

d R

iver

Ref

iner

y

Port

Hop

e C

onve

rsio

n Fa

cilit

y

Gen

eral

Ele

ctric

Nuc

lear

Fue

l Fac

ilitie

s

Zirc

atec

Nuc

lear

Fue

l Fac

ility llehs

teih Wdn

a ses ie rir toto ara or bo ab La

Lrev R

ikl a

Ch

MD

S N

ordi

on

Tri-U

n ive

rsity

Mes

on F

acilit

y

Shie

ld S

ourc

e In

corp

orat

edSh

ield

Sou

rce

Inco

rpor

ated

SRB

Tech

nolo

gies

(Can

ada)

Inc

SR

B Te

chno

logi

es (C

anad

a) In

c

10

r s s n n n n n n n n ty s ty l l ty de y n cn n o o o o o o o o r i il e e o ivo o ti l h lti ti ti ti ti ti ti ti i i

Ri i tee

ta c c iil c ati ti ta ta a a a a a n i s d Inr ata r )r r r r ata a

S

fi cr te S S F F

Nor F o ae e e e e

S S au p p p i p dp p hg g g n F l n r ae og g n n n Re

o nti O O th O l orti i e cn r O O un ti se e A e e e e s Wti ti a a a u d er k k kc k k v r F DS

a a r r e n In Ca

r r e a a M a re e a a Ri F M e (n L r s Me e n n L v a

L n e a c sa en n e e e ff L

y t L s r en lr d ty

G

i

Co e c ie G a il e r i ue G nu a e b

G G g i s

K b toCl c

Nu i ge l r r o or r r C

i B

Nu to e

Cl er a a Sa Ra a lr a vp r oa ce e ae i

t Ho doe l te ll c r bl c M cc Un ne lc o e hlc c

Nu

Nu

Nu i a ab i ctr

Nu

Nu - hc L i er c a rri So en 2 u l Z L T TPe gc to ayn g l E

r- el RB

u i l e vrr atir Sn pe r

B i nk l e er Ri

e

Da t L n kc li G e aP ni Go C

h

P

) S

v(m

e os

D

4

35

3

25

2

15

1

05

0

) vS

m( e soD

Figure 114 Average Effective Doses at All Selected F acilities for the Year 2007 (Based o n A ll Monitoring R esults)

Bru

ce N

ucle

ar G

ener

atin

g S

tatio

ns

Pic

kerin

g N

ucle

ar G

ener

atin

g S

tatio

ns

Dar

lingt

on N

ucle

ar G

ener

atin

g S

tatio

n

Gen

tilly

-2 N

ucle

ar G

ener

atin

g S

tatio

n

Poi

nt L

epre

au N

ucle

ar G

ener

atin

g S

tatio

n

Clu

ff La

ke O

pera

tion

McC

lean

Lak

e O

pera

tion

McA

rthur

Riv

er

Key

Lak

e O

pera

tion

Cig

ar L

ake

Ope

ratio

n

Rab

bit L

ake

Ope

ratio

n

Blin

d R

iver

Ref

iner

y

Por

t Hop

e C

onve

rsio

n Fa

cilit

y

Gen

eral

Ele

ctric

Nuc

lear

Fue

l Fac

ilitie

s

Zirc

atec

Nuc

lear

Fue

l Fac

ility llehsetih

W d na s s ee iri oro tat ra or bo ab La Lr evi

Rk lah

C

MD

S N

ordi

on

Tri-U

nive

rsity

Mes

on F

acili

ty

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 113 Average Effective Doses at All Selected Facilities for the Year 2006 (Based on All Monitoring Results)

4

35

3

25

2

15

1

05

0

Shi

eld

Sou

rce

Inco

rpor

ated

SR

B T

echn

olog

ies

(Can

ada)

Inc

11

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

20 Facility-Specific Overview of Occupational Doses This section presents data for the following types of facilities

bull nuclear power plants (Section 21) bull uranium mines and mills (Section 22) bull uranium refineries (Section 23) bull fuel fabrication facilities (Section 24) bull research and radioisotope production facilities (Section 25) bull tritium production facilities (Section 26)

21 Nuclear Power Plants This section presents dose information for the following nuclear power plants

bull Bruce A and Bruce B Nuclear Generating Stations (Section 211) bull Pickering Nuclear Generating Stations (Section 212) bull Darlington Nuclear Generating Station Section 213) bull Gentilly-2 Nuclear Generating Station (Section 214) bull Point Lepreau Generating Station (Section 215)

Graphs in this section indicate the following data for each nuclear power plant from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for nuclear power plants

1 Effective doses are composed of the following reported components bull doses from photons (labeled on the charts as ldquoexternalrdquo) bull neutron doses bull tritium doses

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of photon neutron and tritium doses Intakes of other radionuclides (for example Iodine-131 or Carbon-14) occasionally occur but these radionuclides are not included here because the associated collective dose is very small For this reason certain collective dose values in this report may be slightly lower than the sum of their respective components as listed

12

1 2 3 4 5 6 70 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

211 Bruce Nuclear Generating Stations

Bruce Power owns and operates the Bruce Nuclear Generating Stations located near Kincardine Ontario on the shore of Lake Huron

bull Bruce A consists of four nuclear reactors (units 1ndash4) and began operating in 1976 bull Bruce B has four nuclear reactors (units 5ndash8) and started operating in 1984

As part of its extensive recovery program in 1997 the sitersquos previous operator Ontario Hydro (now Ontario Power Generation) temporarily shut down all Bruce A reactors and maintained them in a guaranteed shutdown state Units 3 and 4 were later returned to service (in October 2003 and January 2004) while Units 1 and 2 remained in a guaranteed shutdown state

Figures 21ndash24 present dose information for the Bruce Nuclear Generating Stations from 2001 to 2007 Graphs do not distinguish between doses received at Bruce A versus Bruce B

Fig 21 Average Dose Trends for Bruce Nuclear Generating Stati on (Based o n N on-Zero R esults)

Dos

e (m

Sv)

4

35

3

25

2

15

1

05

0

Tritium Neutron External Effective

Year

13

Neutrons External Tritium

0 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 21 2 3 4 5 6 7

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

0

2

4

6

8

1

2

4

0

0

0

0

1

1

Figure 22 Average Dose Trends for Bruce Nuclear Generating Stati on (Based o n A ll Monitoring R esults)

16

)S

v(m

e os

D

Tritium Neutrons External Effective

Year

Figure 23 Collective Dose Trends for Bruce Nuclear Generating Stati on

8000

7000

6000

5000

4000

3000

2000

1000

0

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Year

14

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 24 Distribution of Effective Doses Among All Workers at Bruce Nuclear Generating Station

6000

5000

4000

3000

2000

1000

0 9 0 0

1-50 0 0 1 0 0 0 0 00 5 0 0 0

0-000

000 1-1 1-1 1-20 1-3 3gt0 0 0 05 0 5 01 1 2

Num

ber o

f Wor

kers

Dose Range (mSv)

15

1 2 3 4 5 6 7 0 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

212 Pickering Nuclear Generating Stations

Located in Pickering Ontario the Pickering Nuclear Generating Stations are owned and operated by Ontario Power Generation Two generating stations are located within one enclosure

bull Pickering A consists of four nuclear reactors (units 1 to 4) that began operating in 1971 bull Pickering B consists of four nuclear reactors (units 5 to 8) that began operating in 1982

As part of its extensive recovery program Ontario Hydro (now Ontario Power Generation) temporarily shut down all Pickering A reactors in 1997 and maintained them in a guaranteed shutdown state Unit 4 was restarted in September 2003 and Unit 1 was restarted in March 2005 Units 2 and 3 remain in a guaranteed shutdown state

Figures 25ndash28 present dose information for the Pickering Nuclear Generating Stations from 2001 to 2007 Graphs do not distinguish between doses received at Pickering A versus those received at Pickering B

Figure 25 Average Dose Trends for Pickering N uclear Generating Stati on (Based o n N on-Zero R esults)

25

2

15

1

05

0

)S

v(m

e os

D

Tritium Neutrons External Effective

Year

16

Tritium Neutrons External Effective

Neutrons External Tritium

1 2 3 4 5 6 70 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

1 2 3 4 5 6 7 0 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 26 Average Dose Trends for Pickering N uclear Generating Stati on (Based o n A ll Monitoring R esults)

12

1

08

06

04

02

0

Year

Figure 27 Collective Dose Trends for Pickering N uclear Generating Stati on

12000

10000

8000

6000

4000

2000

0

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

)

Sv

(me

osD

Year

17

2001 2002 2003 2004 2005 2006 2007

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 28 Distribution o f Effective Doses Among A ll Workers at Pickering Nuclear Generating Stati on

6000

5000

4000

3000

2000

1000

0

Num

ber o

f Wor

kers

Dose Range (mSv)

18

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

213 Darlington Nuclear Generating Station

Owned and operated by Ontario Power Generation the Darlington Nuclear Generating Station has four nuclear reactors the first of which began operating in 1989 The facility is located near Bowmanville on the shore of Lake Ontario

Figures 29ndash212 present dose information for the Darlington Nuclear Generating Station from 2001 to 2007

Figure 29 Average Dose Trends for Darlington N uclear Generating Stati on (Non- Zero R esults Only)

)S

v(m

e os

D

250

200

150

100

050

000

Year

19

Tritium Neutrons External Effective

Neutrons External Tritium

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 210 Average Dose Trends for Darlington N uclear Generating Stati on (All Monitoring R esults)

090

080

070

060

050

040

030

020

010

000

)S

v(m

e os

D

Year

Figure 211 Collective Dose Trends for Darlington N uclear Generating Stati on

4500

4000

3500

3000

2500

2000

1500

1000

500

0

)vSm-nosrep (es

Do

eiv

llect

Co

Year

20

2001 2002 2003 2004 2005 2006 2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 212 Distribution o f Effective Doses Among A ll Workers at Darlington Nuclear Generating Stati on

0

500

1000

1500

2000

2500

3000

3500

ers

ork

W of

be

r um

N

Dose Range (mSv)

21

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

214 Gentilly-2 Nuclear Generating Station

The Gentilly-2 Nuclear Generating Station owned and operated by Hydro-Queacutebec has a single reactor that began operating in 1982 The facility is located on the south shore of the St Lawrence River near Trois-Riviegraveres Queacutebec

Figures 213ndash216 present dose information for the Gentilly-2 Nuclear Generating Station from 2001 to 2007

Figure 213 Average Dose Trends for Gentilly-2 Nuclear Generating Stati on (Based o n N on-Zero R esults)

0

05

1

15

2

25

3

35

4

45

)S

v(m

e os

D

Year

22

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 214 Average Dose Trends for Gentilly-2 Nuclear Generating Stati on (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

)S

v(m

e os

D

Year

Figure 215 Collective Dose Trends for Gentilly-2 Nuclear Generating Stati on

0

500

1000

1500

2000

2500

3000

3500

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Neutrons

External

Tritium

Year

23

000-0

009

001-5

00

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 216 Distribution of Effective Doses Among All Workers at Gentilly-2 Nuclear Generating Station

2500

2000

1500

1000

500

0

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

24

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

215 Point Lepreau Nuclear Generating Station

The Point Lepreau Nuclear Generating Station has one reactor that began operating in 1982 Owned and operated by New Brunswick Power Nuclear the station is located in Point Lepreau New Brunswick about 40 km west of Saint John on the shores of the Bay of Fundy

Figures 217ndash220 present dose information for the Point Lepreau Nuclear Generating Station from 2001 to 2007

Figure 217 Average Dose Trends for Point Lepreau N uclear Generating Stati on (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

)S

v(m

e os

D

Tritium Neutron External Effective

Year

25

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 218 Average Dose Trends for Point Lepreau N uclear Generating Stati on (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

)S

v(m

e os

D

Tritium Neutrons External Effective

Year

Figure 219 Collective Dose Trends for Point Lepreau N uclear Generating Station

0

200

400

600

800

1000

1200

1400

1600

1800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Neutrons

External

Tritium

Year

26

0

1400

1200

1000

800

600

400

200

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 220 Distribution of Effective Doses Among All Workers at Point Lepreau Nuclear Generating Station

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

27

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

22 Uranium Mines and Mills This section presents dose information for mine and mill sites in the following regions

bull Cluff Lake (Section 221) bull McClean Lake (Section 222) bull McArthur River (Section 223) bull Key Lake (Section 224) bull Cigar Lake (Section 225) bull Rabbit Lake (Section 226)

Graphs indicate the following data for each site from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for uranium mines and mills

1 Effective doses are composed of the following reported components bull doses from photons (labelled on the charts as ldquoexternalrdquo) bull doses from radon progeny bull doses from long-lived radioactive dust bull doses from radon gas (in some cases)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of photon radon progeny long-lived radioactive dust and radon gas doses

3 The NDR lists radon progeny in working level months (WLM) For this report radon progeny exposures were converted4 to doses expressed in mSv

221 Cluff Lake Operation

The Cluff Lake mining facilities operated by AREVA Resources Canada Inc are located in northwestern Saskatchewan Work began in 1980 and ended in 2002 with the site now being decommissioned The site consisted of three open-pit and two underground mines a mill and a tailings management facility During 2005 and 2006 most of the infrastructure was removed and the affected areas were remediated

Figures 221ndash224 present dose information for the Cluff Lake operation from 2001 to 2007

4 Doses were converted using the International Commission on Radiation Protection (ICRP)rsquos conversion convention of 1 WLM = 5 mSv This convention was established in the ICRP publication Protection against Radon at Home and at Work (ICRP 65)

28

Long-lived radioactive dust Radon progeny External Effective

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 221 Average Dose Trends for the Cluff Lake Operation (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

Year

Figure 222 Average Dose Trends for the Cluff Lake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

200

Long-lived radioactive dust Radon progeny External Effective

)S

v(m

e os

D)

Sv

(me

osD

Year

29

600

500

400

300

200

100

0

External Radon progeny Long-lived radioactive dust

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 223 Collective Dose Trends for the Cluff Lake Operation s

erkor

of W

ber

Num

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Year

Figure 224 Distribution o f Effective Doses Among A ll Workers at the Cluff Lake Operation

0

20

40

60

80

100

120

140

160

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

30

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

222 McClean Lake Operation

AREVA Resources Canada Inc runs the McClean Lake mining operation in northeastern Saskatchewan It comprises open pit mines a mill and a tailings management facility Mining began in 1995 while milling started in 1999

Figures 225ndash228 present dose information for the McClean Lake operation from 2001 to 2007

Figure 225 Average Dose Trends for the McClean L ake Operation (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

31

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 226 Average Dose Trends for the McClean L ake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 227 Collective Dose Trends for the McClean L ake Operation

0

100

200

300

400

500

600

700

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External

Radon progeny

Long-lived radioactive dust

Year

32

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 228 Distribution o f Effective Doses Among A ll Workers at the McClean Lake Operation

0

100

200

300

400

500

600

700

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

33

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

223 McArthur River Operation

Cameco Corporation operates the McArthur River underground mine in north-central Saskatchewan Ore from the mine which began production in 1999 is processed at the Key Lake Mill located 80 km south of McArthur River

Figures 229ndash232 present dose information for the McArthur River operation from 2001 to 2007

Figure 229 Average Dose Trends for the McArthur River Operation (Based o n N on-Zero R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

34

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 230 Average Dose Trends for the McArthur River Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

Figure 231 Collective Dose Trends for the McArthur River Operation

0

200

400

600

800

1000

1200

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Radon gas External Radon progeny Long-lived radioactive dust

Year

35

00

0-000

9

001-5

00

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 232 Distribution o f Effective Doses Among A ll Workers at the McArthur River Operation

0

100

200

300

400

500

600

700

800

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

36

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

224 Key Lake Operation

Cameco Corporation operates mining facilities in Key Lake located in north-central Saskatchewan The Key Lake operation includes two mined-out open pit mines (used for tailings management) a mill and two dry tailings management facilities Mining began in 1983 and ceased in 1997 the mill continued to process ore from the McArthur River mine during the reporting period

Figures 233ndash236 present dose information for the Key Lake operation from 2001 to 2007

Figure 233 Average Dose Trends for the Key Lake Operation (Based o n N on-Zero R esults)

00

20

40

60

80

00

20

40

60

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

37

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

00

20

40

60

80

00

20

40

60

Figure 234 Average Dose Trends for the Key Lake Operation (Based o n A ll Monitoring R esults)

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 235 Collective Dose Trends for the Key Lake Operation

0

100

200

300

400

500

600

700

800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External Radon progeny Long-lived radioactive dust

Year

38

00

0-000

9

001-5

0

501-1

000

gt 1001

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 236 Distribution o f Effective Doses Among A ll Workers at the Key Lake Operation

0

200

400

600

800

1000

1200

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose Range (mSv)

39

se

(mS

v)o

D

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

225 Cigar Lake Operation

Cameco Corporation manages the Cigar Lake underground mine located in northern Saskatchewan at the southern end of Waterbury Lake The mine was under construction at the time of this reportrsquos publication Test mining in ore was carried out in 1991 1992 and 2000

Figures 237ndash240 present dose information for the Cigar Lake operation from

Figure 2 37 Average D ose T rends fo r th e C igar L ake O peration (Based on Non-Zero Results)

2001 to 2007

Year

000

005

010

015

020

025

Long-lived radioactive dust Radon Progeny External Effective

40

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 238 Average Dose Trends for the Cigar Lake Operation (Based on All Monitoring Results)

000

005

010

015

020

025

030

035

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny

External

Effective

Year

Figure 239 Collective Dose Trends for the Cigar Lake Operation

0

50

100

150

200

250

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

External Radon progeny Long-lived radioactive dust

Year

41

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 240 Distribution of Effective Doses Among All Workers at the Cigar Lake Operation

0

200

400

600

800

1000

1200

1400

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

42

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

226 Rabbit Lake Operation

Cameco Corporation owns and operates mining facilities in Rabbit Lake located in north-eastern Saskatchewan Facilities include an underground mine four mined-out open-pit mines a mill and two tailings management facilities Mining and milling began in 1975

Figures 241ndash244 present dose information for the Rabbit Lake operation from 2001 to 2007

Figure 241 Average Dose Trends for the Rabbit Lake Operation (Based on Non-Zero Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

43

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 242 Average Dose Trends for the Rabbit Lake Operation (Based on All Monitoring Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

Figure 243 Collective Dose Trends for the Rabbit Lake Operation

0

200

400

600

800

1000

1200

1400

1600

1800

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Radon gas External Radon progeny Long-lived radioactive dust

Year

44

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

gt300

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 244 Distribution of Effective Doses Among All Workers at the Rabbit Lake Operation

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

900

800

700

600

500

400

300

200

100

0

Dose (mSv)

45

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

23 Uranium Refineries This section presents data for the following two facilities

bull a uranium refining facility in Blind River (Section 231) bull a uranium conversion facility in Port Hope (Section 232)

Graphs indicate the following average doses at each facility from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Note on data for uranium refineries

1 Doses from photons from external sources are measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay and lung counting Historically while these internal doses have been measured they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

231 Blind River Refinery

Cameco Corporation owns and is licensed to operate a uranium refinery in Blind River Ontario The facility which began operating in 1983 converts uranium ore concentrate to uranium trioxide The uranium trioxide is shipped to Camecorsquos uranium conversion facility in Port Hope Ontario where it is processed into uranium dioxide (for use in the fabrication of fuel for nuclear reactors in Canada) or uranium hexafluoride (exported for enrichment and fabrication into fuel for nuclear power reactors around the world)

Figures 245ndash248 present dose information for the Blind River refinery from 2001 to 2007

46

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 245 Average Dose Trends for the Blind River Refinery (Based on Non-Zero Results)

0

05

1

15

2

25

Year

Figure 246 Average Dose Trends for the Blind River Refinery (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

47

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 247 Collective Dose Trends for the Blind River Refinery

0

50

100

150

200

250

300 C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 248 Distribution of Effective Doses Among All Workers at the Blind River Refinery

0

20

40

60

80

100

120

140

160

180

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

48

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

232 Port Hope Conversion Facility

Cameco Corporation owns and is licensed to operate a uranium conversion facility in Port Hope Ontario The facility processes uranium trioxide received from the refinery in Blind River into uranium dioxide and uranium hexafluoride

Figures 249ndash252 present dose information for the Port Hope uranium conversion facility from 2001 to 2007

Figure 249 Average Dose Trends for the Port Hope Conversion Facility (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

49

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 250 Average Dose Trends for the Port Hope Conversion Facility (Based on All Monitoring Results)

0

01

02

03

04

05

06

07

08

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 251 Collective Dose Trends for the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

50

000-0

009

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 252 Distribution of Effective Doses Among All Workers at the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

400

450

500

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

51

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

24 Fuel Fabrication Facilities This section presents data for three nuclear fuel fabrication facilities

bull Two facilities owned and operated by General Electric Canada Inc (Section 241) bull One facility in Port Hope operated by Zircatec Precision Industries (Section 242)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average doses

Notes on data for fuel fabrication facilities

1 Effective doses for the three facilities are composed of the following reported components bull dose from photons (labelled on the charts as ldquoexternalrdquo) bull doses from internal intakes of uranium dust (long-lived radioactive dust) from

uranium in air concentrations (for General Electricrsquos Toronto facility only)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components photon doses and doses from long-lived radioactive dust

241 General Electric Nuclear Fuel Facilities

General Electric Canada Inc operates two nuclear fuel facilities in Ontario

bull At the Toronto facility uranium dioxide pellets are produced from natural or depleted uranium dioxide powder

bull At the Peterborough facility uranium dioxide fuel bundles are created from the pellets produced at the Toronto facility

Figures 253ndash256 present dose information for General Electric Canada Incrsquos fuel fabrication facilities from 2001 to 2007 Graphs do not distinguish between the doses received at the Peterborough facility versus those at the Toronto facility

52

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 253 Average Dose Trends for the General Electric Fuel Facility (Based on Non-Zero Results Only)

0

05

1

15

2

25

3

35

Long Lived Radioactive Dust External Effective

Year

Figure 254 Average Dose Trends for the General Electric Fuel Facility (Based on All Monitoring Results)

0

05

1

15

2

25

3

Long Lived Radioactive Dust External Effective

Year

Dos

e (m

Sv)

Dos

e (m

Sv)

53

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 255 Collective Dose Trends for the General Electric Fuel Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Long Lived Radioactive Dust External

Year

Figure 256 Distribution of Effective Doses among all Workers at the General Electric Fuel Facility

0

10

20

30

40

50

60

70

80

90

100

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

54

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

242 Zircatec Nuclear Fuel Facility

Zircatec Precision Industries Inc operates a nuclear fuel facility in Port Hope Ontario where it makes fuel pellets from uranium dioxide powder received from Port Hopersquos uranium conversion facility The nuclear fuel facility also manufactures fuel bundles for nuclear reactors in Canada

Notes on data for the Zircatec nuclear fuel facility

1 Graphs indicate the following data bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of average effective doses

2 Doses from photons from external sources were measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay Historically although these internal doses have been measured and submitted to the CNSC they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

Figures 257ndash260 present dose information for the Zircatec nuclear fuel facility from 2001 to 2007

Figure 257 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on Non-Zero Results)

0

05

1

15

2

25

3

35

Effe

ctiv

e D

ose

(mS

v)

Year

55

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 258 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

18

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 259 Collective Dose Trends for the Zircatec Nuclear Fuel Facility

0

50

100

150

200

250

300

350

400

450

500

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

56

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 260 Distribution of Effective Doses Among All Workers at the Zircatec Nuclear Fuel Facility

300

Num

ber o

f Wor

kers

250

200

150

100

50

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

57

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

25 Research and Radioisotope Production Facilities This section presents dose information for the following research and radioisotope production facilities from 2001 to 2007

bull Chalk River Laboratories and Whiteshell Laboratories (Section 251) bull A radioisotope production facility operated by MDS Nordion (Section 252) bull The Tri-University Meson Facility (TRIUMF) (Section 253)

Note on data for research and radioisotope production facilities

1 Graphs indicate the following data for each facility bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of effective doses

251 Chalk River Laboratories and Whiteshell Laboratories

Atomic Energy of Canada Limited (AECL) owns and is licensed to operate Chalk River Laboratories and Whiteshell Laboratories

Situated in Renfrew County on the south shore of the Ottawa River the Chalk River Laboratories site hosts the National Research Universal Reactor along with numerous other facilities occupying some 160 buildings in an area of approximately 40 km2 Activities consist of radioisotope production for nuclear medicine testing and development of structural materials in support of power reactor operations fuel fabrication research and radioactive waste management and storage

The Whiteshell Laboratories site is located approximately 10 km west of Pinawa Manitoba and 100 km northeast of Winnipeg on the east bank of the Winnipeg River AECL established the laboratories for nuclear research and testing during the early 1960s and has since discontinued operations which are being decommissioned under a licence from the CNSC

Figures 261ndash264 present dose information for Chalk River Laboratories and Whiteshell Laboratories from 2001 to 2007

Notes on data for Chalk River Laboratories and Whiteshell Laboratories

1 Effective doses are composed of the following reported components bull external doses5 (from both photon and neutron doses) bull tritium doses

Due to issues with AECLrsquos in-house dosimetry management system neutron doses were not reported separately to the NDR during the reporting period As a result external doses from photons and neutrons were totaled The reporting discrepancy has since been rectified

58

5

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of external (photon and neutron) and tritium doses Intakes of other radionuclides occasionally occur and these radionuclides are not included here because their associated doses are very small For this reason certain collective doses in this report may have values slightly lower than the sum of their respective components as listed

Figure 261 Average Dose Trends for Chalk River and Whiteshell Laboratories (Non-Zero Results Only)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Tritium External Effective

Year

59

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 262 Average Dose Trends for Chalk River and Whiteshell Laboratories (All Monitoring Results)

000

020

040

060

080

100

120

Dos

e (m

Sv)

Tritium External Effective

Year

Figure 263 Collective Dose Trends for Chalk River and Whiteshell Laboratories

0

500

1000

1500

2000

2500

3000

3500

Col

lect

ive

Dos

e (p

erso

n- m

Sv)

External Tritium

Year

60

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 264 Distribution of Effective Doses Among All Workers at Chalk River and Whiteshell Laboratories

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

3500

3000

2500

2000

1500

1000

500

Dose (mSv)

61

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

252 MDS Nordion (Nuclear Substance Processing Facility and Canadian Irradiation Centre)

MDS Nordion owns and operates a nuclear substance processing facility in Ottawa Ontario where it processes unsealed radioisotopes and manufactures sealed radiation sources In operation since the early 1970s the facility was purchased by Nordion International in 1991

In cooperation with the Universiteacute du Queacutebecrsquos Institut Armand-Frappier MDS Nordion also operates the Canadian Irradiation Centre which conducts various irradiation services which include training testing and development The centre is located in Laval Quebec on the Universiteacute du Queacutebec campus

Figures 265ndash268 present dose information for MDS Nordionrsquos Ottawa nuclear substance processing facility and for the Canadian Irradiation Centre from 2001 to 2007

Notes on data for MDS Nordionrsquos nuclear substance processing facility and the Canadian Irradiation Centre

1 Doses from photons from external sources were measured and reported to the NDR MDS Nordion also has a routine thyroid monitoring program very occasionally small recordable doses of radiation have occurred from thyroid uptake of iodine The resulting doses have not been historically submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided

Figure 265 Average Dose Trends for MDS Nordion (Based on Non-Zero Results)

0

05

1

15

2

25

Effe

ctiv

e D

ose

(mS

v)

Year

62

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 266 Average Dose Trends for MDS Nordion (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

Figure 267 Collective Dose Trends for MDS Nordion

0

100

200

300

400

500

600

700

800

Year

63

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 268 Distribution of Effective Doses Among All Workers at MDS Nordion

0

5 0

1 0 0

1 5 0

2 0 0

2 5 0

3 0 0

3 5 0

4 0 0

4 5 0

5 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

64

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

253 Tri-University Meson Facility

The Tri-University Meson facility (TRIUMF) is situated in Vancouver on the campus of the University of British Columbia TRIUMF which began operating in the early 1970s with one cyclotron now has two cyclotrons and associated laboratories for research and radioisotope production The laboratory provides research facilities for Canadian and international users and also produces radioisotopes which are used by medical facilities and by a commercial organization (MDS Nordion) MDS Nordion staff also work at the TRIUMF site however MDS Nordion oversees this work and has its own radiation protection program

Figures 269ndash272 present dose information for the TRIUMF facility from 2001 to 2007 Please note that data sets do not distinguish between doses received by TRIUMF staff and MDS Nordion staff who work on the site as the data for these two groups was submitted collectively to the NDR for the reporting period shown Future data for each group will be submitted separately to the NDR

Note on data for TRIUMF

1 Effective doses are composed of the following reported components bull doses from photons (labeled as ldquoexternalrdquo in the charts) bull neutron doses

Figure 269 Average Dose Trends for TRIUMF (Non-Zero Results Only)

000

020

040

060

080

100

120

140

160

Dos

e (m

Sv)

Neutrons External Effective

Year

65

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 14: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

r

Dos

e (m

Sv)

)

Sv

(me

osD

Bruc

e N

ucle

ar G

ener

atin

g St

atio

ns

Pick

erin

g N

ucle

ar G

ener

atin

g St

atio

ns

Dar

lingt

on N

ucle

ar G

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-2 N

ucle

ar G

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n

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t Lep

reau

Nuc

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erat

ing

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ion

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ff La

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e O

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rthur

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e

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ratio

n

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ar L

ake

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ratio

n

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bit L

ake

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d R

iver

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iner

y

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e C

onve

rsio

n Fa

cilit

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eral

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ctric

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l Fac

ilitie

s

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atec

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lear

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l Fac

ility llehs

teih Wdn

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Lrev R

ikl a

Ch

MD

S N

ordi

on

Tri-U

n ive

rsity

Mes

on F

acilit

y

Figure 110 Average Effective Doses at All Selected F acilities for the Year 2003 (Based o n A ll Monitoring R esults)

4

35

3

25

2

15

1

05

0

Bruc

e N

ucle

ar G

ener

atin

g St

atio

ns

Pick

erin

g N

ucle

ar G

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g St

atio

ns

Dar

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on N

ucle

ar G

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n

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tilly

-2 N

ucle

ar G

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n

Poin

t Lep

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Nuc

lear

Gen

erat

ing

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ion

Clu

ff La

ke O

pera

tion

McC

lean

Lak

e O

pera

tion

McA

rthur

Riv

er

Key

Lake

Ope

ratio

n

Cig

ar L

ake

Ope

ratio

n

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bit L

ake

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ratio

n

Blin

d R

iver

Ref

iner

y

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e C

onve

rsio

n Fa

cilit

y

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eral

Ele

ctric

Nuc

lear

Fue

l Fac

ilitie

s

Zirc

atec

Nuc

lear

Fue

l Fac

ility llehs

teih Wdn

a ses ie rir toto ara or bo ab La

Lrev R

ikla

Ch

MD

S N

o rdi

on

Tri-U

nive

r sity

Mes

on F

acilit

y

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 19 Average Effective Doses at All Selected Facilities for the Year 2002 (Based on All Monitoring Results)

4

35

3

25

2

15

1

05

0

Shie

ld S

ourc

e In

corp

orat

edSh

ield

Sou

rce

Inco

rpor

ated

c In)adan

Ca

(seigolonhce T

RB

SSR

B Te

chno

logi

es (C

anad

a) In

c

9

Dos

e (m

Sv)

)

Sv

(me

osD

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 111 Average Effective Doses at All Selected F acilities for the Year 2004 (Based o n A ll Monitoring R esults)

4

35

3

25

2

15

1

05

0

Bruc

e N

ucle

ar G

ener

atin

g St

atio

ns

Pick

erin

g N

ucle

ar G

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atin

g St

atio

ns

Dar

lingt

on N

ucle

ar G

ener

atin

g St

atio

n

Gen

tilly

-2 N

ucle

ar G

ener

atin

g St

atio

n

Poin

t Lep

reau

Nuc

lear

Gen

erat

ing

Stat

ion

Clu

ff La

ke O

pera

tion

McC

lean

Lak

e O

pera

tion

McA

rthur

Riv

er

Key

Lake

Ope

ratio

n

Cig

ar L

ake

Ope

ratio

n

Rab

bit L

ake

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n

Blin

d R

iver

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iner

y

Port

Hop

e C

onve

rsio

n Fa

cilit

y

Gen

eral

Ele

ctric

Nuc

lear

Fue

l Fac

ilitie

s

Zirc

atec

Nuc

lear

Fue

l Fac

ility llehs

teih Wdn

a ses ie rir toto ara or bo ab La

Lre v R

ikla

Ch

MD

S N

ordi

on

T ri-U

nive

rsity

Mes

on F

acilit

y

Figure 112 Average Effective Doses at All Selected F acilities for the Year 2005 (Based o n A ll Monitoring R esults)

4

35

3

25

2

15

1

05

0

Bruc

e N

ucle

ar G

ener

atin

g St

atio

ns

Pick

erin

g N

ucle

ar G

ener

atin

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ns

Dar

lingt

on N

ucle

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tilly

-2 N

ucle

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t Lep

reau

Nuc

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ion

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ff La

ke O

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e O

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er

Key

Lake

Ope

ratio

n

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ar L

ake

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ratio

n

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bit L

ake

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ratio

n

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d R

iver

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iner

y

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e C

onve

rsio

n Fa

cilit

y

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eral

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ctric

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lear

Fue

l Fac

ilitie

s

Zirc

atec

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lear

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l Fac

ility llehs

teih Wdn

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Lrev R

ikl a

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MD

S N

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Tri-U

n ive

rsity

Mes

on F

acilit

y

Shie

ld S

ourc

e In

corp

orat

edSh

ield

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rce

Inco

rpor

ated

SRB

Tech

nolo

gies

(Can

ada)

Inc

SR

B Te

chno

logi

es (C

anad

a) In

c

10

r s s n n n n n n n n ty s ty l l ty de y n cn n o o o o o o o o r i il e e o ivo o ti l h lti ti ti ti ti ti ti ti i i

Ri i tee

ta c c iil c ati ti ta ta a a a a a n i s d Inr ata r )r r r r ata a

S

fi cr te S S F F

Nor F o ae e e e e

S S au p p p i p dp p hg g g n F l n r ae og g n n n Re

o nti O O th O l orti i e cn r O O un ti se e A e e e e s Wti ti a a a u d er k k kc k k v r F DS

a a r r e n In Ca

r r e a a M a re e a a Ri F M e (n L r s Me e n n L v a

L n e a c sa en n e e e ff L

y t L s r en lr d ty

G

i

Co e c ie G a il e r i ue G nu a e b

G G g i s

K b toCl c

Nu i ge l r r o or r r C

i B

Nu to e

Cl er a a Sa Ra a lr a vp r oa ce e ae i

t Ho doe l te ll c r bl c M cc Un ne lc o e hlc c

Nu

Nu

Nu i a ab i ctr

Nu

Nu - hc L i er c a rri So en 2 u l Z L T TPe gc to ayn g l E

r- el RB

u i l e vrr atir Sn pe r

B i nk l e er Ri

e

Da t L n kc li G e aP ni Go C

h

P

) S

v(m

e os

D

4

35

3

25

2

15

1

05

0

) vS

m( e soD

Figure 114 Average Effective Doses at All Selected F acilities for the Year 2007 (Based o n A ll Monitoring R esults)

Bru

ce N

ucle

ar G

ener

atin

g S

tatio

ns

Pic

kerin

g N

ucle

ar G

ener

atin

g S

tatio

ns

Dar

lingt

on N

ucle

ar G

ener

atin

g S

tatio

n

Gen

tilly

-2 N

ucle

ar G

ener

atin

g S

tatio

n

Poi

nt L

epre

au N

ucle

ar G

ener

atin

g S

tatio

n

Clu

ff La

ke O

pera

tion

McC

lean

Lak

e O

pera

tion

McA

rthur

Riv

er

Key

Lak

e O

pera

tion

Cig

ar L

ake

Ope

ratio

n

Rab

bit L

ake

Ope

ratio

n

Blin

d R

iver

Ref

iner

y

Por

t Hop

e C

onve

rsio

n Fa

cilit

y

Gen

eral

Ele

ctric

Nuc

lear

Fue

l Fac

ilitie

s

Zirc

atec

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lear

Fue

l Fac

ility llehsetih

W d na s s ee iri oro tat ra or bo ab La Lr evi

Rk lah

C

MD

S N

ordi

on

Tri-U

nive

rsity

Mes

on F

acili

ty

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 113 Average Effective Doses at All Selected Facilities for the Year 2006 (Based on All Monitoring Results)

4

35

3

25

2

15

1

05

0

Shi

eld

Sou

rce

Inco

rpor

ated

SR

B T

echn

olog

ies

(Can

ada)

Inc

11

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

20 Facility-Specific Overview of Occupational Doses This section presents data for the following types of facilities

bull nuclear power plants (Section 21) bull uranium mines and mills (Section 22) bull uranium refineries (Section 23) bull fuel fabrication facilities (Section 24) bull research and radioisotope production facilities (Section 25) bull tritium production facilities (Section 26)

21 Nuclear Power Plants This section presents dose information for the following nuclear power plants

bull Bruce A and Bruce B Nuclear Generating Stations (Section 211) bull Pickering Nuclear Generating Stations (Section 212) bull Darlington Nuclear Generating Station Section 213) bull Gentilly-2 Nuclear Generating Station (Section 214) bull Point Lepreau Generating Station (Section 215)

Graphs in this section indicate the following data for each nuclear power plant from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for nuclear power plants

1 Effective doses are composed of the following reported components bull doses from photons (labeled on the charts as ldquoexternalrdquo) bull neutron doses bull tritium doses

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of photon neutron and tritium doses Intakes of other radionuclides (for example Iodine-131 or Carbon-14) occasionally occur but these radionuclides are not included here because the associated collective dose is very small For this reason certain collective dose values in this report may be slightly lower than the sum of their respective components as listed

12

1 2 3 4 5 6 70 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

211 Bruce Nuclear Generating Stations

Bruce Power owns and operates the Bruce Nuclear Generating Stations located near Kincardine Ontario on the shore of Lake Huron

bull Bruce A consists of four nuclear reactors (units 1ndash4) and began operating in 1976 bull Bruce B has four nuclear reactors (units 5ndash8) and started operating in 1984

As part of its extensive recovery program in 1997 the sitersquos previous operator Ontario Hydro (now Ontario Power Generation) temporarily shut down all Bruce A reactors and maintained them in a guaranteed shutdown state Units 3 and 4 were later returned to service (in October 2003 and January 2004) while Units 1 and 2 remained in a guaranteed shutdown state

Figures 21ndash24 present dose information for the Bruce Nuclear Generating Stations from 2001 to 2007 Graphs do not distinguish between doses received at Bruce A versus Bruce B

Fig 21 Average Dose Trends for Bruce Nuclear Generating Stati on (Based o n N on-Zero R esults)

Dos

e (m

Sv)

4

35

3

25

2

15

1

05

0

Tritium Neutron External Effective

Year

13

Neutrons External Tritium

0 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 21 2 3 4 5 6 7

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

0

2

4

6

8

1

2

4

0

0

0

0

1

1

Figure 22 Average Dose Trends for Bruce Nuclear Generating Stati on (Based o n A ll Monitoring R esults)

16

)S

v(m

e os

D

Tritium Neutrons External Effective

Year

Figure 23 Collective Dose Trends for Bruce Nuclear Generating Stati on

8000

7000

6000

5000

4000

3000

2000

1000

0

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Year

14

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 24 Distribution of Effective Doses Among All Workers at Bruce Nuclear Generating Station

6000

5000

4000

3000

2000

1000

0 9 0 0

1-50 0 0 1 0 0 0 0 00 5 0 0 0

0-000

000 1-1 1-1 1-20 1-3 3gt0 0 0 05 0 5 01 1 2

Num

ber o

f Wor

kers

Dose Range (mSv)

15

1 2 3 4 5 6 7 0 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

212 Pickering Nuclear Generating Stations

Located in Pickering Ontario the Pickering Nuclear Generating Stations are owned and operated by Ontario Power Generation Two generating stations are located within one enclosure

bull Pickering A consists of four nuclear reactors (units 1 to 4) that began operating in 1971 bull Pickering B consists of four nuclear reactors (units 5 to 8) that began operating in 1982

As part of its extensive recovery program Ontario Hydro (now Ontario Power Generation) temporarily shut down all Pickering A reactors in 1997 and maintained them in a guaranteed shutdown state Unit 4 was restarted in September 2003 and Unit 1 was restarted in March 2005 Units 2 and 3 remain in a guaranteed shutdown state

Figures 25ndash28 present dose information for the Pickering Nuclear Generating Stations from 2001 to 2007 Graphs do not distinguish between doses received at Pickering A versus those received at Pickering B

Figure 25 Average Dose Trends for Pickering N uclear Generating Stati on (Based o n N on-Zero R esults)

25

2

15

1

05

0

)S

v(m

e os

D

Tritium Neutrons External Effective

Year

16

Tritium Neutrons External Effective

Neutrons External Tritium

1 2 3 4 5 6 70 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

1 2 3 4 5 6 7 0 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 26 Average Dose Trends for Pickering N uclear Generating Stati on (Based o n A ll Monitoring R esults)

12

1

08

06

04

02

0

Year

Figure 27 Collective Dose Trends for Pickering N uclear Generating Stati on

12000

10000

8000

6000

4000

2000

0

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

)

Sv

(me

osD

Year

17

2001 2002 2003 2004 2005 2006 2007

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 28 Distribution o f Effective Doses Among A ll Workers at Pickering Nuclear Generating Stati on

6000

5000

4000

3000

2000

1000

0

Num

ber o

f Wor

kers

Dose Range (mSv)

18

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

213 Darlington Nuclear Generating Station

Owned and operated by Ontario Power Generation the Darlington Nuclear Generating Station has four nuclear reactors the first of which began operating in 1989 The facility is located near Bowmanville on the shore of Lake Ontario

Figures 29ndash212 present dose information for the Darlington Nuclear Generating Station from 2001 to 2007

Figure 29 Average Dose Trends for Darlington N uclear Generating Stati on (Non- Zero R esults Only)

)S

v(m

e os

D

250

200

150

100

050

000

Year

19

Tritium Neutrons External Effective

Neutrons External Tritium

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 210 Average Dose Trends for Darlington N uclear Generating Stati on (All Monitoring R esults)

090

080

070

060

050

040

030

020

010

000

)S

v(m

e os

D

Year

Figure 211 Collective Dose Trends for Darlington N uclear Generating Stati on

4500

4000

3500

3000

2500

2000

1500

1000

500

0

)vSm-nosrep (es

Do

eiv

llect

Co

Year

20

2001 2002 2003 2004 2005 2006 2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 212 Distribution o f Effective Doses Among A ll Workers at Darlington Nuclear Generating Stati on

0

500

1000

1500

2000

2500

3000

3500

ers

ork

W of

be

r um

N

Dose Range (mSv)

21

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

214 Gentilly-2 Nuclear Generating Station

The Gentilly-2 Nuclear Generating Station owned and operated by Hydro-Queacutebec has a single reactor that began operating in 1982 The facility is located on the south shore of the St Lawrence River near Trois-Riviegraveres Queacutebec

Figures 213ndash216 present dose information for the Gentilly-2 Nuclear Generating Station from 2001 to 2007

Figure 213 Average Dose Trends for Gentilly-2 Nuclear Generating Stati on (Based o n N on-Zero R esults)

0

05

1

15

2

25

3

35

4

45

)S

v(m

e os

D

Year

22

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 214 Average Dose Trends for Gentilly-2 Nuclear Generating Stati on (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

)S

v(m

e os

D

Year

Figure 215 Collective Dose Trends for Gentilly-2 Nuclear Generating Stati on

0

500

1000

1500

2000

2500

3000

3500

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Neutrons

External

Tritium

Year

23

000-0

009

001-5

00

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 216 Distribution of Effective Doses Among All Workers at Gentilly-2 Nuclear Generating Station

2500

2000

1500

1000

500

0

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

24

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

215 Point Lepreau Nuclear Generating Station

The Point Lepreau Nuclear Generating Station has one reactor that began operating in 1982 Owned and operated by New Brunswick Power Nuclear the station is located in Point Lepreau New Brunswick about 40 km west of Saint John on the shores of the Bay of Fundy

Figures 217ndash220 present dose information for the Point Lepreau Nuclear Generating Station from 2001 to 2007

Figure 217 Average Dose Trends for Point Lepreau N uclear Generating Stati on (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

)S

v(m

e os

D

Tritium Neutron External Effective

Year

25

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 218 Average Dose Trends for Point Lepreau N uclear Generating Stati on (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

)S

v(m

e os

D

Tritium Neutrons External Effective

Year

Figure 219 Collective Dose Trends for Point Lepreau N uclear Generating Station

0

200

400

600

800

1000

1200

1400

1600

1800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Neutrons

External

Tritium

Year

26

0

1400

1200

1000

800

600

400

200

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 220 Distribution of Effective Doses Among All Workers at Point Lepreau Nuclear Generating Station

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

27

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

22 Uranium Mines and Mills This section presents dose information for mine and mill sites in the following regions

bull Cluff Lake (Section 221) bull McClean Lake (Section 222) bull McArthur River (Section 223) bull Key Lake (Section 224) bull Cigar Lake (Section 225) bull Rabbit Lake (Section 226)

Graphs indicate the following data for each site from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for uranium mines and mills

1 Effective doses are composed of the following reported components bull doses from photons (labelled on the charts as ldquoexternalrdquo) bull doses from radon progeny bull doses from long-lived radioactive dust bull doses from radon gas (in some cases)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of photon radon progeny long-lived radioactive dust and radon gas doses

3 The NDR lists radon progeny in working level months (WLM) For this report radon progeny exposures were converted4 to doses expressed in mSv

221 Cluff Lake Operation

The Cluff Lake mining facilities operated by AREVA Resources Canada Inc are located in northwestern Saskatchewan Work began in 1980 and ended in 2002 with the site now being decommissioned The site consisted of three open-pit and two underground mines a mill and a tailings management facility During 2005 and 2006 most of the infrastructure was removed and the affected areas were remediated

Figures 221ndash224 present dose information for the Cluff Lake operation from 2001 to 2007

4 Doses were converted using the International Commission on Radiation Protection (ICRP)rsquos conversion convention of 1 WLM = 5 mSv This convention was established in the ICRP publication Protection against Radon at Home and at Work (ICRP 65)

28

Long-lived radioactive dust Radon progeny External Effective

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 221 Average Dose Trends for the Cluff Lake Operation (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

Year

Figure 222 Average Dose Trends for the Cluff Lake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

200

Long-lived radioactive dust Radon progeny External Effective

)S

v(m

e os

D)

Sv

(me

osD

Year

29

600

500

400

300

200

100

0

External Radon progeny Long-lived radioactive dust

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 223 Collective Dose Trends for the Cluff Lake Operation s

erkor

of W

ber

Num

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Year

Figure 224 Distribution o f Effective Doses Among A ll Workers at the Cluff Lake Operation

0

20

40

60

80

100

120

140

160

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

30

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

222 McClean Lake Operation

AREVA Resources Canada Inc runs the McClean Lake mining operation in northeastern Saskatchewan It comprises open pit mines a mill and a tailings management facility Mining began in 1995 while milling started in 1999

Figures 225ndash228 present dose information for the McClean Lake operation from 2001 to 2007

Figure 225 Average Dose Trends for the McClean L ake Operation (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

31

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 226 Average Dose Trends for the McClean L ake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 227 Collective Dose Trends for the McClean L ake Operation

0

100

200

300

400

500

600

700

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External

Radon progeny

Long-lived radioactive dust

Year

32

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 228 Distribution o f Effective Doses Among A ll Workers at the McClean Lake Operation

0

100

200

300

400

500

600

700

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

33

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

223 McArthur River Operation

Cameco Corporation operates the McArthur River underground mine in north-central Saskatchewan Ore from the mine which began production in 1999 is processed at the Key Lake Mill located 80 km south of McArthur River

Figures 229ndash232 present dose information for the McArthur River operation from 2001 to 2007

Figure 229 Average Dose Trends for the McArthur River Operation (Based o n N on-Zero R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

34

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 230 Average Dose Trends for the McArthur River Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

Figure 231 Collective Dose Trends for the McArthur River Operation

0

200

400

600

800

1000

1200

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Radon gas External Radon progeny Long-lived radioactive dust

Year

35

00

0-000

9

001-5

00

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 232 Distribution o f Effective Doses Among A ll Workers at the McArthur River Operation

0

100

200

300

400

500

600

700

800

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

36

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

224 Key Lake Operation

Cameco Corporation operates mining facilities in Key Lake located in north-central Saskatchewan The Key Lake operation includes two mined-out open pit mines (used for tailings management) a mill and two dry tailings management facilities Mining began in 1983 and ceased in 1997 the mill continued to process ore from the McArthur River mine during the reporting period

Figures 233ndash236 present dose information for the Key Lake operation from 2001 to 2007

Figure 233 Average Dose Trends for the Key Lake Operation (Based o n N on-Zero R esults)

00

20

40

60

80

00

20

40

60

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

37

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

00

20

40

60

80

00

20

40

60

Figure 234 Average Dose Trends for the Key Lake Operation (Based o n A ll Monitoring R esults)

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 235 Collective Dose Trends for the Key Lake Operation

0

100

200

300

400

500

600

700

800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External Radon progeny Long-lived radioactive dust

Year

38

00

0-000

9

001-5

0

501-1

000

gt 1001

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 236 Distribution o f Effective Doses Among A ll Workers at the Key Lake Operation

0

200

400

600

800

1000

1200

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose Range (mSv)

39

se

(mS

v)o

D

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

225 Cigar Lake Operation

Cameco Corporation manages the Cigar Lake underground mine located in northern Saskatchewan at the southern end of Waterbury Lake The mine was under construction at the time of this reportrsquos publication Test mining in ore was carried out in 1991 1992 and 2000

Figures 237ndash240 present dose information for the Cigar Lake operation from

Figure 2 37 Average D ose T rends fo r th e C igar L ake O peration (Based on Non-Zero Results)

2001 to 2007

Year

000

005

010

015

020

025

Long-lived radioactive dust Radon Progeny External Effective

40

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 238 Average Dose Trends for the Cigar Lake Operation (Based on All Monitoring Results)

000

005

010

015

020

025

030

035

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny

External

Effective

Year

Figure 239 Collective Dose Trends for the Cigar Lake Operation

0

50

100

150

200

250

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

External Radon progeny Long-lived radioactive dust

Year

41

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 240 Distribution of Effective Doses Among All Workers at the Cigar Lake Operation

0

200

400

600

800

1000

1200

1400

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

42

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

226 Rabbit Lake Operation

Cameco Corporation owns and operates mining facilities in Rabbit Lake located in north-eastern Saskatchewan Facilities include an underground mine four mined-out open-pit mines a mill and two tailings management facilities Mining and milling began in 1975

Figures 241ndash244 present dose information for the Rabbit Lake operation from 2001 to 2007

Figure 241 Average Dose Trends for the Rabbit Lake Operation (Based on Non-Zero Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

43

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 242 Average Dose Trends for the Rabbit Lake Operation (Based on All Monitoring Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

Figure 243 Collective Dose Trends for the Rabbit Lake Operation

0

200

400

600

800

1000

1200

1400

1600

1800

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Radon gas External Radon progeny Long-lived radioactive dust

Year

44

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

gt300

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 244 Distribution of Effective Doses Among All Workers at the Rabbit Lake Operation

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

900

800

700

600

500

400

300

200

100

0

Dose (mSv)

45

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

23 Uranium Refineries This section presents data for the following two facilities

bull a uranium refining facility in Blind River (Section 231) bull a uranium conversion facility in Port Hope (Section 232)

Graphs indicate the following average doses at each facility from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Note on data for uranium refineries

1 Doses from photons from external sources are measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay and lung counting Historically while these internal doses have been measured they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

231 Blind River Refinery

Cameco Corporation owns and is licensed to operate a uranium refinery in Blind River Ontario The facility which began operating in 1983 converts uranium ore concentrate to uranium trioxide The uranium trioxide is shipped to Camecorsquos uranium conversion facility in Port Hope Ontario where it is processed into uranium dioxide (for use in the fabrication of fuel for nuclear reactors in Canada) or uranium hexafluoride (exported for enrichment and fabrication into fuel for nuclear power reactors around the world)

Figures 245ndash248 present dose information for the Blind River refinery from 2001 to 2007

46

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 245 Average Dose Trends for the Blind River Refinery (Based on Non-Zero Results)

0

05

1

15

2

25

Year

Figure 246 Average Dose Trends for the Blind River Refinery (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

47

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 247 Collective Dose Trends for the Blind River Refinery

0

50

100

150

200

250

300 C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 248 Distribution of Effective Doses Among All Workers at the Blind River Refinery

0

20

40

60

80

100

120

140

160

180

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

48

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

232 Port Hope Conversion Facility

Cameco Corporation owns and is licensed to operate a uranium conversion facility in Port Hope Ontario The facility processes uranium trioxide received from the refinery in Blind River into uranium dioxide and uranium hexafluoride

Figures 249ndash252 present dose information for the Port Hope uranium conversion facility from 2001 to 2007

Figure 249 Average Dose Trends for the Port Hope Conversion Facility (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

49

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 250 Average Dose Trends for the Port Hope Conversion Facility (Based on All Monitoring Results)

0

01

02

03

04

05

06

07

08

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 251 Collective Dose Trends for the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

50

000-0

009

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 252 Distribution of Effective Doses Among All Workers at the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

400

450

500

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

51

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

24 Fuel Fabrication Facilities This section presents data for three nuclear fuel fabrication facilities

bull Two facilities owned and operated by General Electric Canada Inc (Section 241) bull One facility in Port Hope operated by Zircatec Precision Industries (Section 242)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average doses

Notes on data for fuel fabrication facilities

1 Effective doses for the three facilities are composed of the following reported components bull dose from photons (labelled on the charts as ldquoexternalrdquo) bull doses from internal intakes of uranium dust (long-lived radioactive dust) from

uranium in air concentrations (for General Electricrsquos Toronto facility only)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components photon doses and doses from long-lived radioactive dust

241 General Electric Nuclear Fuel Facilities

General Electric Canada Inc operates two nuclear fuel facilities in Ontario

bull At the Toronto facility uranium dioxide pellets are produced from natural or depleted uranium dioxide powder

bull At the Peterborough facility uranium dioxide fuel bundles are created from the pellets produced at the Toronto facility

Figures 253ndash256 present dose information for General Electric Canada Incrsquos fuel fabrication facilities from 2001 to 2007 Graphs do not distinguish between the doses received at the Peterborough facility versus those at the Toronto facility

52

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 253 Average Dose Trends for the General Electric Fuel Facility (Based on Non-Zero Results Only)

0

05

1

15

2

25

3

35

Long Lived Radioactive Dust External Effective

Year

Figure 254 Average Dose Trends for the General Electric Fuel Facility (Based on All Monitoring Results)

0

05

1

15

2

25

3

Long Lived Radioactive Dust External Effective

Year

Dos

e (m

Sv)

Dos

e (m

Sv)

53

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 255 Collective Dose Trends for the General Electric Fuel Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Long Lived Radioactive Dust External

Year

Figure 256 Distribution of Effective Doses among all Workers at the General Electric Fuel Facility

0

10

20

30

40

50

60

70

80

90

100

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

54

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

242 Zircatec Nuclear Fuel Facility

Zircatec Precision Industries Inc operates a nuclear fuel facility in Port Hope Ontario where it makes fuel pellets from uranium dioxide powder received from Port Hopersquos uranium conversion facility The nuclear fuel facility also manufactures fuel bundles for nuclear reactors in Canada

Notes on data for the Zircatec nuclear fuel facility

1 Graphs indicate the following data bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of average effective doses

2 Doses from photons from external sources were measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay Historically although these internal doses have been measured and submitted to the CNSC they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

Figures 257ndash260 present dose information for the Zircatec nuclear fuel facility from 2001 to 2007

Figure 257 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on Non-Zero Results)

0

05

1

15

2

25

3

35

Effe

ctiv

e D

ose

(mS

v)

Year

55

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 258 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

18

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 259 Collective Dose Trends for the Zircatec Nuclear Fuel Facility

0

50

100

150

200

250

300

350

400

450

500

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

56

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 260 Distribution of Effective Doses Among All Workers at the Zircatec Nuclear Fuel Facility

300

Num

ber o

f Wor

kers

250

200

150

100

50

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

57

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

25 Research and Radioisotope Production Facilities This section presents dose information for the following research and radioisotope production facilities from 2001 to 2007

bull Chalk River Laboratories and Whiteshell Laboratories (Section 251) bull A radioisotope production facility operated by MDS Nordion (Section 252) bull The Tri-University Meson Facility (TRIUMF) (Section 253)

Note on data for research and radioisotope production facilities

1 Graphs indicate the following data for each facility bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of effective doses

251 Chalk River Laboratories and Whiteshell Laboratories

Atomic Energy of Canada Limited (AECL) owns and is licensed to operate Chalk River Laboratories and Whiteshell Laboratories

Situated in Renfrew County on the south shore of the Ottawa River the Chalk River Laboratories site hosts the National Research Universal Reactor along with numerous other facilities occupying some 160 buildings in an area of approximately 40 km2 Activities consist of radioisotope production for nuclear medicine testing and development of structural materials in support of power reactor operations fuel fabrication research and radioactive waste management and storage

The Whiteshell Laboratories site is located approximately 10 km west of Pinawa Manitoba and 100 km northeast of Winnipeg on the east bank of the Winnipeg River AECL established the laboratories for nuclear research and testing during the early 1960s and has since discontinued operations which are being decommissioned under a licence from the CNSC

Figures 261ndash264 present dose information for Chalk River Laboratories and Whiteshell Laboratories from 2001 to 2007

Notes on data for Chalk River Laboratories and Whiteshell Laboratories

1 Effective doses are composed of the following reported components bull external doses5 (from both photon and neutron doses) bull tritium doses

Due to issues with AECLrsquos in-house dosimetry management system neutron doses were not reported separately to the NDR during the reporting period As a result external doses from photons and neutrons were totaled The reporting discrepancy has since been rectified

58

5

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of external (photon and neutron) and tritium doses Intakes of other radionuclides occasionally occur and these radionuclides are not included here because their associated doses are very small For this reason certain collective doses in this report may have values slightly lower than the sum of their respective components as listed

Figure 261 Average Dose Trends for Chalk River and Whiteshell Laboratories (Non-Zero Results Only)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Tritium External Effective

Year

59

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 262 Average Dose Trends for Chalk River and Whiteshell Laboratories (All Monitoring Results)

000

020

040

060

080

100

120

Dos

e (m

Sv)

Tritium External Effective

Year

Figure 263 Collective Dose Trends for Chalk River and Whiteshell Laboratories

0

500

1000

1500

2000

2500

3000

3500

Col

lect

ive

Dos

e (p

erso

n- m

Sv)

External Tritium

Year

60

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 264 Distribution of Effective Doses Among All Workers at Chalk River and Whiteshell Laboratories

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

3500

3000

2500

2000

1500

1000

500

Dose (mSv)

61

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

252 MDS Nordion (Nuclear Substance Processing Facility and Canadian Irradiation Centre)

MDS Nordion owns and operates a nuclear substance processing facility in Ottawa Ontario where it processes unsealed radioisotopes and manufactures sealed radiation sources In operation since the early 1970s the facility was purchased by Nordion International in 1991

In cooperation with the Universiteacute du Queacutebecrsquos Institut Armand-Frappier MDS Nordion also operates the Canadian Irradiation Centre which conducts various irradiation services which include training testing and development The centre is located in Laval Quebec on the Universiteacute du Queacutebec campus

Figures 265ndash268 present dose information for MDS Nordionrsquos Ottawa nuclear substance processing facility and for the Canadian Irradiation Centre from 2001 to 2007

Notes on data for MDS Nordionrsquos nuclear substance processing facility and the Canadian Irradiation Centre

1 Doses from photons from external sources were measured and reported to the NDR MDS Nordion also has a routine thyroid monitoring program very occasionally small recordable doses of radiation have occurred from thyroid uptake of iodine The resulting doses have not been historically submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided

Figure 265 Average Dose Trends for MDS Nordion (Based on Non-Zero Results)

0

05

1

15

2

25

Effe

ctiv

e D

ose

(mS

v)

Year

62

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 266 Average Dose Trends for MDS Nordion (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

Figure 267 Collective Dose Trends for MDS Nordion

0

100

200

300

400

500

600

700

800

Year

63

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 268 Distribution of Effective Doses Among All Workers at MDS Nordion

0

5 0

1 0 0

1 5 0

2 0 0

2 5 0

3 0 0

3 5 0

4 0 0

4 5 0

5 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

64

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

253 Tri-University Meson Facility

The Tri-University Meson facility (TRIUMF) is situated in Vancouver on the campus of the University of British Columbia TRIUMF which began operating in the early 1970s with one cyclotron now has two cyclotrons and associated laboratories for research and radioisotope production The laboratory provides research facilities for Canadian and international users and also produces radioisotopes which are used by medical facilities and by a commercial organization (MDS Nordion) MDS Nordion staff also work at the TRIUMF site however MDS Nordion oversees this work and has its own radiation protection program

Figures 269ndash272 present dose information for the TRIUMF facility from 2001 to 2007 Please note that data sets do not distinguish between doses received by TRIUMF staff and MDS Nordion staff who work on the site as the data for these two groups was submitted collectively to the NDR for the reporting period shown Future data for each group will be submitted separately to the NDR

Note on data for TRIUMF

1 Effective doses are composed of the following reported components bull doses from photons (labeled as ldquoexternalrdquo in the charts) bull neutron doses

Figure 269 Average Dose Trends for TRIUMF (Non-Zero Results Only)

000

020

040

060

080

100

120

140

160

Dos

e (m

Sv)

Neutrons External Effective

Year

65

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 15: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

Dos

e (m

Sv)

)

Sv

(me

osD

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 111 Average Effective Doses at All Selected F acilities for the Year 2004 (Based o n A ll Monitoring R esults)

4

35

3

25

2

15

1

05

0

Bruc

e N

ucle

ar G

ener

atin

g St

atio

ns

Pick

erin

g N

ucle

ar G

ener

atin

g St

atio

ns

Dar

lingt

on N

ucle

ar G

ener

atin

g St

atio

n

Gen

tilly

-2 N

ucle

ar G

ener

atin

g St

atio

n

Poin

t Lep

reau

Nuc

lear

Gen

erat

ing

Stat

ion

Clu

ff La

ke O

pera

tion

McC

lean

Lak

e O

pera

tion

McA

rthur

Riv

er

Key

Lake

Ope

ratio

n

Cig

ar L

ake

Ope

ratio

n

Rab

bit L

ake

Ope

ratio

n

Blin

d R

iver

Ref

iner

y

Port

Hop

e C

onve

rsio

n Fa

cilit

y

Gen

eral

Ele

ctric

Nuc

lear

Fue

l Fac

ilitie

s

Zirc

atec

Nuc

lear

Fue

l Fac

ility llehs

teih Wdn

a ses ie rir toto ara or bo ab La

Lre v R

ikla

Ch

MD

S N

ordi

on

T ri-U

nive

rsity

Mes

on F

acilit

y

Figure 112 Average Effective Doses at All Selected F acilities for the Year 2005 (Based o n A ll Monitoring R esults)

4

35

3

25

2

15

1

05

0

Bruc

e N

ucle

ar G

ener

atin

g St

atio

ns

Pick

erin

g N

ucle

ar G

ener

atin

g St

atio

ns

Dar

lingt

on N

ucle

ar G

ener

atin

g St

atio

n

Gen

tilly

-2 N

ucle

ar G

ener

atin

g St

atio

n

Poin

t Lep

reau

Nuc

lear

Gen

erat

ing

Stat

ion

Clu

ff La

ke O

pera

tion

McC

lean

Lak

e O

pera

tion

McA

rthur

Riv

er

Key

Lake

Ope

ratio

n

Cig

ar L

ake

Ope

ratio

n

Rab

bit L

ake

Ope

ratio

n

Blin

d R

iver

Ref

iner

y

Port

Hop

e C

onve

rsio

n Fa

cilit

y

Gen

eral

Ele

ctric

Nuc

lear

Fue

l Fac

ilitie

s

Zirc

atec

Nuc

lear

Fue

l Fac

ility llehs

teih Wdn

a ses ie rir toto ara or bo ab La

Lrev R

ikl a

Ch

MD

S N

ordi

on

Tri-U

n ive

rsity

Mes

on F

acilit

y

Shie

ld S

ourc

e In

corp

orat

edSh

ield

Sou

rce

Inco

rpor

ated

SRB

Tech

nolo

gies

(Can

ada)

Inc

SR

B Te

chno

logi

es (C

anad

a) In

c

10

r s s n n n n n n n n ty s ty l l ty de y n cn n o o o o o o o o r i il e e o ivo o ti l h lti ti ti ti ti ti ti ti i i

Ri i tee

ta c c iil c ati ti ta ta a a a a a n i s d Inr ata r )r r r r ata a

S

fi cr te S S F F

Nor F o ae e e e e

S S au p p p i p dp p hg g g n F l n r ae og g n n n Re

o nti O O th O l orti i e cn r O O un ti se e A e e e e s Wti ti a a a u d er k k kc k k v r F DS

a a r r e n In Ca

r r e a a M a re e a a Ri F M e (n L r s Me e n n L v a

L n e a c sa en n e e e ff L

y t L s r en lr d ty

G

i

Co e c ie G a il e r i ue G nu a e b

G G g i s

K b toCl c

Nu i ge l r r o or r r C

i B

Nu to e

Cl er a a Sa Ra a lr a vp r oa ce e ae i

t Ho doe l te ll c r bl c M cc Un ne lc o e hlc c

Nu

Nu

Nu i a ab i ctr

Nu

Nu - hc L i er c a rri So en 2 u l Z L T TPe gc to ayn g l E

r- el RB

u i l e vrr atir Sn pe r

B i nk l e er Ri

e

Da t L n kc li G e aP ni Go C

h

P

) S

v(m

e os

D

4

35

3

25

2

15

1

05

0

) vS

m( e soD

Figure 114 Average Effective Doses at All Selected F acilities for the Year 2007 (Based o n A ll Monitoring R esults)

Bru

ce N

ucle

ar G

ener

atin

g S

tatio

ns

Pic

kerin

g N

ucle

ar G

ener

atin

g S

tatio

ns

Dar

lingt

on N

ucle

ar G

ener

atin

g S

tatio

n

Gen

tilly

-2 N

ucle

ar G

ener

atin

g S

tatio

n

Poi

nt L

epre

au N

ucle

ar G

ener

atin

g S

tatio

n

Clu

ff La

ke O

pera

tion

McC

lean

Lak

e O

pera

tion

McA

rthur

Riv

er

Key

Lak

e O

pera

tion

Cig

ar L

ake

Ope

ratio

n

Rab

bit L

ake

Ope

ratio

n

Blin

d R

iver

Ref

iner

y

Por

t Hop

e C

onve

rsio

n Fa

cilit

y

Gen

eral

Ele

ctric

Nuc

lear

Fue

l Fac

ilitie

s

Zirc

atec

Nuc

lear

Fue

l Fac

ility llehsetih

W d na s s ee iri oro tat ra or bo ab La Lr evi

Rk lah

C

MD

S N

ordi

on

Tri-U

nive

rsity

Mes

on F

acili

ty

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 113 Average Effective Doses at All Selected Facilities for the Year 2006 (Based on All Monitoring Results)

4

35

3

25

2

15

1

05

0

Shi

eld

Sou

rce

Inco

rpor

ated

SR

B T

echn

olog

ies

(Can

ada)

Inc

11

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

20 Facility-Specific Overview of Occupational Doses This section presents data for the following types of facilities

bull nuclear power plants (Section 21) bull uranium mines and mills (Section 22) bull uranium refineries (Section 23) bull fuel fabrication facilities (Section 24) bull research and radioisotope production facilities (Section 25) bull tritium production facilities (Section 26)

21 Nuclear Power Plants This section presents dose information for the following nuclear power plants

bull Bruce A and Bruce B Nuclear Generating Stations (Section 211) bull Pickering Nuclear Generating Stations (Section 212) bull Darlington Nuclear Generating Station Section 213) bull Gentilly-2 Nuclear Generating Station (Section 214) bull Point Lepreau Generating Station (Section 215)

Graphs in this section indicate the following data for each nuclear power plant from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for nuclear power plants

1 Effective doses are composed of the following reported components bull doses from photons (labeled on the charts as ldquoexternalrdquo) bull neutron doses bull tritium doses

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of photon neutron and tritium doses Intakes of other radionuclides (for example Iodine-131 or Carbon-14) occasionally occur but these radionuclides are not included here because the associated collective dose is very small For this reason certain collective dose values in this report may be slightly lower than the sum of their respective components as listed

12

1 2 3 4 5 6 70 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

211 Bruce Nuclear Generating Stations

Bruce Power owns and operates the Bruce Nuclear Generating Stations located near Kincardine Ontario on the shore of Lake Huron

bull Bruce A consists of four nuclear reactors (units 1ndash4) and began operating in 1976 bull Bruce B has four nuclear reactors (units 5ndash8) and started operating in 1984

As part of its extensive recovery program in 1997 the sitersquos previous operator Ontario Hydro (now Ontario Power Generation) temporarily shut down all Bruce A reactors and maintained them in a guaranteed shutdown state Units 3 and 4 were later returned to service (in October 2003 and January 2004) while Units 1 and 2 remained in a guaranteed shutdown state

Figures 21ndash24 present dose information for the Bruce Nuclear Generating Stations from 2001 to 2007 Graphs do not distinguish between doses received at Bruce A versus Bruce B

Fig 21 Average Dose Trends for Bruce Nuclear Generating Stati on (Based o n N on-Zero R esults)

Dos

e (m

Sv)

4

35

3

25

2

15

1

05

0

Tritium Neutron External Effective

Year

13

Neutrons External Tritium

0 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 21 2 3 4 5 6 7

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

0

2

4

6

8

1

2

4

0

0

0

0

1

1

Figure 22 Average Dose Trends for Bruce Nuclear Generating Stati on (Based o n A ll Monitoring R esults)

16

)S

v(m

e os

D

Tritium Neutrons External Effective

Year

Figure 23 Collective Dose Trends for Bruce Nuclear Generating Stati on

8000

7000

6000

5000

4000

3000

2000

1000

0

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Year

14

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 24 Distribution of Effective Doses Among All Workers at Bruce Nuclear Generating Station

6000

5000

4000

3000

2000

1000

0 9 0 0

1-50 0 0 1 0 0 0 0 00 5 0 0 0

0-000

000 1-1 1-1 1-20 1-3 3gt0 0 0 05 0 5 01 1 2

Num

ber o

f Wor

kers

Dose Range (mSv)

15

1 2 3 4 5 6 7 0 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

212 Pickering Nuclear Generating Stations

Located in Pickering Ontario the Pickering Nuclear Generating Stations are owned and operated by Ontario Power Generation Two generating stations are located within one enclosure

bull Pickering A consists of four nuclear reactors (units 1 to 4) that began operating in 1971 bull Pickering B consists of four nuclear reactors (units 5 to 8) that began operating in 1982

As part of its extensive recovery program Ontario Hydro (now Ontario Power Generation) temporarily shut down all Pickering A reactors in 1997 and maintained them in a guaranteed shutdown state Unit 4 was restarted in September 2003 and Unit 1 was restarted in March 2005 Units 2 and 3 remain in a guaranteed shutdown state

Figures 25ndash28 present dose information for the Pickering Nuclear Generating Stations from 2001 to 2007 Graphs do not distinguish between doses received at Pickering A versus those received at Pickering B

Figure 25 Average Dose Trends for Pickering N uclear Generating Stati on (Based o n N on-Zero R esults)

25

2

15

1

05

0

)S

v(m

e os

D

Tritium Neutrons External Effective

Year

16

Tritium Neutrons External Effective

Neutrons External Tritium

1 2 3 4 5 6 70 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

1 2 3 4 5 6 7 0 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 26 Average Dose Trends for Pickering N uclear Generating Stati on (Based o n A ll Monitoring R esults)

12

1

08

06

04

02

0

Year

Figure 27 Collective Dose Trends for Pickering N uclear Generating Stati on

12000

10000

8000

6000

4000

2000

0

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

)

Sv

(me

osD

Year

17

2001 2002 2003 2004 2005 2006 2007

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 28 Distribution o f Effective Doses Among A ll Workers at Pickering Nuclear Generating Stati on

6000

5000

4000

3000

2000

1000

0

Num

ber o

f Wor

kers

Dose Range (mSv)

18

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

213 Darlington Nuclear Generating Station

Owned and operated by Ontario Power Generation the Darlington Nuclear Generating Station has four nuclear reactors the first of which began operating in 1989 The facility is located near Bowmanville on the shore of Lake Ontario

Figures 29ndash212 present dose information for the Darlington Nuclear Generating Station from 2001 to 2007

Figure 29 Average Dose Trends for Darlington N uclear Generating Stati on (Non- Zero R esults Only)

)S

v(m

e os

D

250

200

150

100

050

000

Year

19

Tritium Neutrons External Effective

Neutrons External Tritium

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 210 Average Dose Trends for Darlington N uclear Generating Stati on (All Monitoring R esults)

090

080

070

060

050

040

030

020

010

000

)S

v(m

e os

D

Year

Figure 211 Collective Dose Trends for Darlington N uclear Generating Stati on

4500

4000

3500

3000

2500

2000

1500

1000

500

0

)vSm-nosrep (es

Do

eiv

llect

Co

Year

20

2001 2002 2003 2004 2005 2006 2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 212 Distribution o f Effective Doses Among A ll Workers at Darlington Nuclear Generating Stati on

0

500

1000

1500

2000

2500

3000

3500

ers

ork

W of

be

r um

N

Dose Range (mSv)

21

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

214 Gentilly-2 Nuclear Generating Station

The Gentilly-2 Nuclear Generating Station owned and operated by Hydro-Queacutebec has a single reactor that began operating in 1982 The facility is located on the south shore of the St Lawrence River near Trois-Riviegraveres Queacutebec

Figures 213ndash216 present dose information for the Gentilly-2 Nuclear Generating Station from 2001 to 2007

Figure 213 Average Dose Trends for Gentilly-2 Nuclear Generating Stati on (Based o n N on-Zero R esults)

0

05

1

15

2

25

3

35

4

45

)S

v(m

e os

D

Year

22

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 214 Average Dose Trends for Gentilly-2 Nuclear Generating Stati on (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

)S

v(m

e os

D

Year

Figure 215 Collective Dose Trends for Gentilly-2 Nuclear Generating Stati on

0

500

1000

1500

2000

2500

3000

3500

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Neutrons

External

Tritium

Year

23

000-0

009

001-5

00

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 216 Distribution of Effective Doses Among All Workers at Gentilly-2 Nuclear Generating Station

2500

2000

1500

1000

500

0

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

24

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

215 Point Lepreau Nuclear Generating Station

The Point Lepreau Nuclear Generating Station has one reactor that began operating in 1982 Owned and operated by New Brunswick Power Nuclear the station is located in Point Lepreau New Brunswick about 40 km west of Saint John on the shores of the Bay of Fundy

Figures 217ndash220 present dose information for the Point Lepreau Nuclear Generating Station from 2001 to 2007

Figure 217 Average Dose Trends for Point Lepreau N uclear Generating Stati on (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

)S

v(m

e os

D

Tritium Neutron External Effective

Year

25

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 218 Average Dose Trends for Point Lepreau N uclear Generating Stati on (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

)S

v(m

e os

D

Tritium Neutrons External Effective

Year

Figure 219 Collective Dose Trends for Point Lepreau N uclear Generating Station

0

200

400

600

800

1000

1200

1400

1600

1800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Neutrons

External

Tritium

Year

26

0

1400

1200

1000

800

600

400

200

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 220 Distribution of Effective Doses Among All Workers at Point Lepreau Nuclear Generating Station

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

27

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

22 Uranium Mines and Mills This section presents dose information for mine and mill sites in the following regions

bull Cluff Lake (Section 221) bull McClean Lake (Section 222) bull McArthur River (Section 223) bull Key Lake (Section 224) bull Cigar Lake (Section 225) bull Rabbit Lake (Section 226)

Graphs indicate the following data for each site from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for uranium mines and mills

1 Effective doses are composed of the following reported components bull doses from photons (labelled on the charts as ldquoexternalrdquo) bull doses from radon progeny bull doses from long-lived radioactive dust bull doses from radon gas (in some cases)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of photon radon progeny long-lived radioactive dust and radon gas doses

3 The NDR lists radon progeny in working level months (WLM) For this report radon progeny exposures were converted4 to doses expressed in mSv

221 Cluff Lake Operation

The Cluff Lake mining facilities operated by AREVA Resources Canada Inc are located in northwestern Saskatchewan Work began in 1980 and ended in 2002 with the site now being decommissioned The site consisted of three open-pit and two underground mines a mill and a tailings management facility During 2005 and 2006 most of the infrastructure was removed and the affected areas were remediated

Figures 221ndash224 present dose information for the Cluff Lake operation from 2001 to 2007

4 Doses were converted using the International Commission on Radiation Protection (ICRP)rsquos conversion convention of 1 WLM = 5 mSv This convention was established in the ICRP publication Protection against Radon at Home and at Work (ICRP 65)

28

Long-lived radioactive dust Radon progeny External Effective

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 221 Average Dose Trends for the Cluff Lake Operation (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

Year

Figure 222 Average Dose Trends for the Cluff Lake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

200

Long-lived radioactive dust Radon progeny External Effective

)S

v(m

e os

D)

Sv

(me

osD

Year

29

600

500

400

300

200

100

0

External Radon progeny Long-lived radioactive dust

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 223 Collective Dose Trends for the Cluff Lake Operation s

erkor

of W

ber

Num

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Year

Figure 224 Distribution o f Effective Doses Among A ll Workers at the Cluff Lake Operation

0

20

40

60

80

100

120

140

160

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

30

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

222 McClean Lake Operation

AREVA Resources Canada Inc runs the McClean Lake mining operation in northeastern Saskatchewan It comprises open pit mines a mill and a tailings management facility Mining began in 1995 while milling started in 1999

Figures 225ndash228 present dose information for the McClean Lake operation from 2001 to 2007

Figure 225 Average Dose Trends for the McClean L ake Operation (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

31

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 226 Average Dose Trends for the McClean L ake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 227 Collective Dose Trends for the McClean L ake Operation

0

100

200

300

400

500

600

700

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External

Radon progeny

Long-lived radioactive dust

Year

32

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 228 Distribution o f Effective Doses Among A ll Workers at the McClean Lake Operation

0

100

200

300

400

500

600

700

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

33

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

223 McArthur River Operation

Cameco Corporation operates the McArthur River underground mine in north-central Saskatchewan Ore from the mine which began production in 1999 is processed at the Key Lake Mill located 80 km south of McArthur River

Figures 229ndash232 present dose information for the McArthur River operation from 2001 to 2007

Figure 229 Average Dose Trends for the McArthur River Operation (Based o n N on-Zero R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

34

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 230 Average Dose Trends for the McArthur River Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

Figure 231 Collective Dose Trends for the McArthur River Operation

0

200

400

600

800

1000

1200

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Radon gas External Radon progeny Long-lived radioactive dust

Year

35

00

0-000

9

001-5

00

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 232 Distribution o f Effective Doses Among A ll Workers at the McArthur River Operation

0

100

200

300

400

500

600

700

800

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

36

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

224 Key Lake Operation

Cameco Corporation operates mining facilities in Key Lake located in north-central Saskatchewan The Key Lake operation includes two mined-out open pit mines (used for tailings management) a mill and two dry tailings management facilities Mining began in 1983 and ceased in 1997 the mill continued to process ore from the McArthur River mine during the reporting period

Figures 233ndash236 present dose information for the Key Lake operation from 2001 to 2007

Figure 233 Average Dose Trends for the Key Lake Operation (Based o n N on-Zero R esults)

00

20

40

60

80

00

20

40

60

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

37

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

00

20

40

60

80

00

20

40

60

Figure 234 Average Dose Trends for the Key Lake Operation (Based o n A ll Monitoring R esults)

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 235 Collective Dose Trends for the Key Lake Operation

0

100

200

300

400

500

600

700

800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External Radon progeny Long-lived radioactive dust

Year

38

00

0-000

9

001-5

0

501-1

000

gt 1001

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 236 Distribution o f Effective Doses Among A ll Workers at the Key Lake Operation

0

200

400

600

800

1000

1200

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose Range (mSv)

39

se

(mS

v)o

D

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

225 Cigar Lake Operation

Cameco Corporation manages the Cigar Lake underground mine located in northern Saskatchewan at the southern end of Waterbury Lake The mine was under construction at the time of this reportrsquos publication Test mining in ore was carried out in 1991 1992 and 2000

Figures 237ndash240 present dose information for the Cigar Lake operation from

Figure 2 37 Average D ose T rends fo r th e C igar L ake O peration (Based on Non-Zero Results)

2001 to 2007

Year

000

005

010

015

020

025

Long-lived radioactive dust Radon Progeny External Effective

40

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 238 Average Dose Trends for the Cigar Lake Operation (Based on All Monitoring Results)

000

005

010

015

020

025

030

035

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny

External

Effective

Year

Figure 239 Collective Dose Trends for the Cigar Lake Operation

0

50

100

150

200

250

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

External Radon progeny Long-lived radioactive dust

Year

41

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 240 Distribution of Effective Doses Among All Workers at the Cigar Lake Operation

0

200

400

600

800

1000

1200

1400

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

42

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

226 Rabbit Lake Operation

Cameco Corporation owns and operates mining facilities in Rabbit Lake located in north-eastern Saskatchewan Facilities include an underground mine four mined-out open-pit mines a mill and two tailings management facilities Mining and milling began in 1975

Figures 241ndash244 present dose information for the Rabbit Lake operation from 2001 to 2007

Figure 241 Average Dose Trends for the Rabbit Lake Operation (Based on Non-Zero Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

43

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 242 Average Dose Trends for the Rabbit Lake Operation (Based on All Monitoring Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

Figure 243 Collective Dose Trends for the Rabbit Lake Operation

0

200

400

600

800

1000

1200

1400

1600

1800

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Radon gas External Radon progeny Long-lived radioactive dust

Year

44

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

gt300

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 244 Distribution of Effective Doses Among All Workers at the Rabbit Lake Operation

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

900

800

700

600

500

400

300

200

100

0

Dose (mSv)

45

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

23 Uranium Refineries This section presents data for the following two facilities

bull a uranium refining facility in Blind River (Section 231) bull a uranium conversion facility in Port Hope (Section 232)

Graphs indicate the following average doses at each facility from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Note on data for uranium refineries

1 Doses from photons from external sources are measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay and lung counting Historically while these internal doses have been measured they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

231 Blind River Refinery

Cameco Corporation owns and is licensed to operate a uranium refinery in Blind River Ontario The facility which began operating in 1983 converts uranium ore concentrate to uranium trioxide The uranium trioxide is shipped to Camecorsquos uranium conversion facility in Port Hope Ontario where it is processed into uranium dioxide (for use in the fabrication of fuel for nuclear reactors in Canada) or uranium hexafluoride (exported for enrichment and fabrication into fuel for nuclear power reactors around the world)

Figures 245ndash248 present dose information for the Blind River refinery from 2001 to 2007

46

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 245 Average Dose Trends for the Blind River Refinery (Based on Non-Zero Results)

0

05

1

15

2

25

Year

Figure 246 Average Dose Trends for the Blind River Refinery (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

47

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 247 Collective Dose Trends for the Blind River Refinery

0

50

100

150

200

250

300 C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 248 Distribution of Effective Doses Among All Workers at the Blind River Refinery

0

20

40

60

80

100

120

140

160

180

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

48

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

232 Port Hope Conversion Facility

Cameco Corporation owns and is licensed to operate a uranium conversion facility in Port Hope Ontario The facility processes uranium trioxide received from the refinery in Blind River into uranium dioxide and uranium hexafluoride

Figures 249ndash252 present dose information for the Port Hope uranium conversion facility from 2001 to 2007

Figure 249 Average Dose Trends for the Port Hope Conversion Facility (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

49

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 250 Average Dose Trends for the Port Hope Conversion Facility (Based on All Monitoring Results)

0

01

02

03

04

05

06

07

08

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 251 Collective Dose Trends for the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

50

000-0

009

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 252 Distribution of Effective Doses Among All Workers at the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

400

450

500

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

51

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

24 Fuel Fabrication Facilities This section presents data for three nuclear fuel fabrication facilities

bull Two facilities owned and operated by General Electric Canada Inc (Section 241) bull One facility in Port Hope operated by Zircatec Precision Industries (Section 242)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average doses

Notes on data for fuel fabrication facilities

1 Effective doses for the three facilities are composed of the following reported components bull dose from photons (labelled on the charts as ldquoexternalrdquo) bull doses from internal intakes of uranium dust (long-lived radioactive dust) from

uranium in air concentrations (for General Electricrsquos Toronto facility only)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components photon doses and doses from long-lived radioactive dust

241 General Electric Nuclear Fuel Facilities

General Electric Canada Inc operates two nuclear fuel facilities in Ontario

bull At the Toronto facility uranium dioxide pellets are produced from natural or depleted uranium dioxide powder

bull At the Peterborough facility uranium dioxide fuel bundles are created from the pellets produced at the Toronto facility

Figures 253ndash256 present dose information for General Electric Canada Incrsquos fuel fabrication facilities from 2001 to 2007 Graphs do not distinguish between the doses received at the Peterborough facility versus those at the Toronto facility

52

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 253 Average Dose Trends for the General Electric Fuel Facility (Based on Non-Zero Results Only)

0

05

1

15

2

25

3

35

Long Lived Radioactive Dust External Effective

Year

Figure 254 Average Dose Trends for the General Electric Fuel Facility (Based on All Monitoring Results)

0

05

1

15

2

25

3

Long Lived Radioactive Dust External Effective

Year

Dos

e (m

Sv)

Dos

e (m

Sv)

53

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 255 Collective Dose Trends for the General Electric Fuel Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Long Lived Radioactive Dust External

Year

Figure 256 Distribution of Effective Doses among all Workers at the General Electric Fuel Facility

0

10

20

30

40

50

60

70

80

90

100

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

54

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

242 Zircatec Nuclear Fuel Facility

Zircatec Precision Industries Inc operates a nuclear fuel facility in Port Hope Ontario where it makes fuel pellets from uranium dioxide powder received from Port Hopersquos uranium conversion facility The nuclear fuel facility also manufactures fuel bundles for nuclear reactors in Canada

Notes on data for the Zircatec nuclear fuel facility

1 Graphs indicate the following data bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of average effective doses

2 Doses from photons from external sources were measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay Historically although these internal doses have been measured and submitted to the CNSC they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

Figures 257ndash260 present dose information for the Zircatec nuclear fuel facility from 2001 to 2007

Figure 257 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on Non-Zero Results)

0

05

1

15

2

25

3

35

Effe

ctiv

e D

ose

(mS

v)

Year

55

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 258 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

18

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 259 Collective Dose Trends for the Zircatec Nuclear Fuel Facility

0

50

100

150

200

250

300

350

400

450

500

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

56

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 260 Distribution of Effective Doses Among All Workers at the Zircatec Nuclear Fuel Facility

300

Num

ber o

f Wor

kers

250

200

150

100

50

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

57

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

25 Research and Radioisotope Production Facilities This section presents dose information for the following research and radioisotope production facilities from 2001 to 2007

bull Chalk River Laboratories and Whiteshell Laboratories (Section 251) bull A radioisotope production facility operated by MDS Nordion (Section 252) bull The Tri-University Meson Facility (TRIUMF) (Section 253)

Note on data for research and radioisotope production facilities

1 Graphs indicate the following data for each facility bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of effective doses

251 Chalk River Laboratories and Whiteshell Laboratories

Atomic Energy of Canada Limited (AECL) owns and is licensed to operate Chalk River Laboratories and Whiteshell Laboratories

Situated in Renfrew County on the south shore of the Ottawa River the Chalk River Laboratories site hosts the National Research Universal Reactor along with numerous other facilities occupying some 160 buildings in an area of approximately 40 km2 Activities consist of radioisotope production for nuclear medicine testing and development of structural materials in support of power reactor operations fuel fabrication research and radioactive waste management and storage

The Whiteshell Laboratories site is located approximately 10 km west of Pinawa Manitoba and 100 km northeast of Winnipeg on the east bank of the Winnipeg River AECL established the laboratories for nuclear research and testing during the early 1960s and has since discontinued operations which are being decommissioned under a licence from the CNSC

Figures 261ndash264 present dose information for Chalk River Laboratories and Whiteshell Laboratories from 2001 to 2007

Notes on data for Chalk River Laboratories and Whiteshell Laboratories

1 Effective doses are composed of the following reported components bull external doses5 (from both photon and neutron doses) bull tritium doses

Due to issues with AECLrsquos in-house dosimetry management system neutron doses were not reported separately to the NDR during the reporting period As a result external doses from photons and neutrons were totaled The reporting discrepancy has since been rectified

58

5

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of external (photon and neutron) and tritium doses Intakes of other radionuclides occasionally occur and these radionuclides are not included here because their associated doses are very small For this reason certain collective doses in this report may have values slightly lower than the sum of their respective components as listed

Figure 261 Average Dose Trends for Chalk River and Whiteshell Laboratories (Non-Zero Results Only)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Tritium External Effective

Year

59

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 262 Average Dose Trends for Chalk River and Whiteshell Laboratories (All Monitoring Results)

000

020

040

060

080

100

120

Dos

e (m

Sv)

Tritium External Effective

Year

Figure 263 Collective Dose Trends for Chalk River and Whiteshell Laboratories

0

500

1000

1500

2000

2500

3000

3500

Col

lect

ive

Dos

e (p

erso

n- m

Sv)

External Tritium

Year

60

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 264 Distribution of Effective Doses Among All Workers at Chalk River and Whiteshell Laboratories

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

3500

3000

2500

2000

1500

1000

500

Dose (mSv)

61

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

252 MDS Nordion (Nuclear Substance Processing Facility and Canadian Irradiation Centre)

MDS Nordion owns and operates a nuclear substance processing facility in Ottawa Ontario where it processes unsealed radioisotopes and manufactures sealed radiation sources In operation since the early 1970s the facility was purchased by Nordion International in 1991

In cooperation with the Universiteacute du Queacutebecrsquos Institut Armand-Frappier MDS Nordion also operates the Canadian Irradiation Centre which conducts various irradiation services which include training testing and development The centre is located in Laval Quebec on the Universiteacute du Queacutebec campus

Figures 265ndash268 present dose information for MDS Nordionrsquos Ottawa nuclear substance processing facility and for the Canadian Irradiation Centre from 2001 to 2007

Notes on data for MDS Nordionrsquos nuclear substance processing facility and the Canadian Irradiation Centre

1 Doses from photons from external sources were measured and reported to the NDR MDS Nordion also has a routine thyroid monitoring program very occasionally small recordable doses of radiation have occurred from thyroid uptake of iodine The resulting doses have not been historically submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided

Figure 265 Average Dose Trends for MDS Nordion (Based on Non-Zero Results)

0

05

1

15

2

25

Effe

ctiv

e D

ose

(mS

v)

Year

62

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 266 Average Dose Trends for MDS Nordion (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

Figure 267 Collective Dose Trends for MDS Nordion

0

100

200

300

400

500

600

700

800

Year

63

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 268 Distribution of Effective Doses Among All Workers at MDS Nordion

0

5 0

1 0 0

1 5 0

2 0 0

2 5 0

3 0 0

3 5 0

4 0 0

4 5 0

5 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

64

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

253 Tri-University Meson Facility

The Tri-University Meson facility (TRIUMF) is situated in Vancouver on the campus of the University of British Columbia TRIUMF which began operating in the early 1970s with one cyclotron now has two cyclotrons and associated laboratories for research and radioisotope production The laboratory provides research facilities for Canadian and international users and also produces radioisotopes which are used by medical facilities and by a commercial organization (MDS Nordion) MDS Nordion staff also work at the TRIUMF site however MDS Nordion oversees this work and has its own radiation protection program

Figures 269ndash272 present dose information for the TRIUMF facility from 2001 to 2007 Please note that data sets do not distinguish between doses received by TRIUMF staff and MDS Nordion staff who work on the site as the data for these two groups was submitted collectively to the NDR for the reporting period shown Future data for each group will be submitted separately to the NDR

Note on data for TRIUMF

1 Effective doses are composed of the following reported components bull doses from photons (labeled as ldquoexternalrdquo in the charts) bull neutron doses

Figure 269 Average Dose Trends for TRIUMF (Non-Zero Results Only)

000

020

040

060

080

100

120

140

160

Dos

e (m

Sv)

Neutrons External Effective

Year

65

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 16: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

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S

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e

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h

P

) S

v(m

e os

D

4

35

3

25

2

15

1

05

0

) vS

m( e soD

Figure 114 Average Effective Doses at All Selected F acilities for the Year 2007 (Based o n A ll Monitoring R esults)

Bru

ce N

ucle

ar G

ener

atin

g S

tatio

ns

Pic

kerin

g N

ucle

ar G

ener

atin

g S

tatio

ns

Dar

lingt

on N

ucle

ar G

ener

atin

g S

tatio

n

Gen

tilly

-2 N

ucle

ar G

ener

atin

g S

tatio

n

Poi

nt L

epre

au N

ucle

ar G

ener

atin

g S

tatio

n

Clu

ff La

ke O

pera

tion

McC

lean

Lak

e O

pera

tion

McA

rthur

Riv

er

Key

Lak

e O

pera

tion

Cig

ar L

ake

Ope

ratio

n

Rab

bit L

ake

Ope

ratio

n

Blin

d R

iver

Ref

iner

y

Por

t Hop

e C

onve

rsio

n Fa

cilit

y

Gen

eral

Ele

ctric

Nuc

lear

Fue

l Fac

ilitie

s

Zirc

atec

Nuc

lear

Fue

l Fac

ility llehsetih

W d na s s ee iri oro tat ra or bo ab La Lr evi

Rk lah

C

MD

S N

ordi

on

Tri-U

nive

rsity

Mes

on F

acili

ty

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 113 Average Effective Doses at All Selected Facilities for the Year 2006 (Based on All Monitoring Results)

4

35

3

25

2

15

1

05

0

Shi

eld

Sou

rce

Inco

rpor

ated

SR

B T

echn

olog

ies

(Can

ada)

Inc

11

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

20 Facility-Specific Overview of Occupational Doses This section presents data for the following types of facilities

bull nuclear power plants (Section 21) bull uranium mines and mills (Section 22) bull uranium refineries (Section 23) bull fuel fabrication facilities (Section 24) bull research and radioisotope production facilities (Section 25) bull tritium production facilities (Section 26)

21 Nuclear Power Plants This section presents dose information for the following nuclear power plants

bull Bruce A and Bruce B Nuclear Generating Stations (Section 211) bull Pickering Nuclear Generating Stations (Section 212) bull Darlington Nuclear Generating Station Section 213) bull Gentilly-2 Nuclear Generating Station (Section 214) bull Point Lepreau Generating Station (Section 215)

Graphs in this section indicate the following data for each nuclear power plant from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for nuclear power plants

1 Effective doses are composed of the following reported components bull doses from photons (labeled on the charts as ldquoexternalrdquo) bull neutron doses bull tritium doses

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of photon neutron and tritium doses Intakes of other radionuclides (for example Iodine-131 or Carbon-14) occasionally occur but these radionuclides are not included here because the associated collective dose is very small For this reason certain collective dose values in this report may be slightly lower than the sum of their respective components as listed

12

1 2 3 4 5 6 70 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

211 Bruce Nuclear Generating Stations

Bruce Power owns and operates the Bruce Nuclear Generating Stations located near Kincardine Ontario on the shore of Lake Huron

bull Bruce A consists of four nuclear reactors (units 1ndash4) and began operating in 1976 bull Bruce B has four nuclear reactors (units 5ndash8) and started operating in 1984

As part of its extensive recovery program in 1997 the sitersquos previous operator Ontario Hydro (now Ontario Power Generation) temporarily shut down all Bruce A reactors and maintained them in a guaranteed shutdown state Units 3 and 4 were later returned to service (in October 2003 and January 2004) while Units 1 and 2 remained in a guaranteed shutdown state

Figures 21ndash24 present dose information for the Bruce Nuclear Generating Stations from 2001 to 2007 Graphs do not distinguish between doses received at Bruce A versus Bruce B

Fig 21 Average Dose Trends for Bruce Nuclear Generating Stati on (Based o n N on-Zero R esults)

Dos

e (m

Sv)

4

35

3

25

2

15

1

05

0

Tritium Neutron External Effective

Year

13

Neutrons External Tritium

0 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 21 2 3 4 5 6 7

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

0

2

4

6

8

1

2

4

0

0

0

0

1

1

Figure 22 Average Dose Trends for Bruce Nuclear Generating Stati on (Based o n A ll Monitoring R esults)

16

)S

v(m

e os

D

Tritium Neutrons External Effective

Year

Figure 23 Collective Dose Trends for Bruce Nuclear Generating Stati on

8000

7000

6000

5000

4000

3000

2000

1000

0

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Year

14

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 24 Distribution of Effective Doses Among All Workers at Bruce Nuclear Generating Station

6000

5000

4000

3000

2000

1000

0 9 0 0

1-50 0 0 1 0 0 0 0 00 5 0 0 0

0-000

000 1-1 1-1 1-20 1-3 3gt0 0 0 05 0 5 01 1 2

Num

ber o

f Wor

kers

Dose Range (mSv)

15

1 2 3 4 5 6 7 0 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

212 Pickering Nuclear Generating Stations

Located in Pickering Ontario the Pickering Nuclear Generating Stations are owned and operated by Ontario Power Generation Two generating stations are located within one enclosure

bull Pickering A consists of four nuclear reactors (units 1 to 4) that began operating in 1971 bull Pickering B consists of four nuclear reactors (units 5 to 8) that began operating in 1982

As part of its extensive recovery program Ontario Hydro (now Ontario Power Generation) temporarily shut down all Pickering A reactors in 1997 and maintained them in a guaranteed shutdown state Unit 4 was restarted in September 2003 and Unit 1 was restarted in March 2005 Units 2 and 3 remain in a guaranteed shutdown state

Figures 25ndash28 present dose information for the Pickering Nuclear Generating Stations from 2001 to 2007 Graphs do not distinguish between doses received at Pickering A versus those received at Pickering B

Figure 25 Average Dose Trends for Pickering N uclear Generating Stati on (Based o n N on-Zero R esults)

25

2

15

1

05

0

)S

v(m

e os

D

Tritium Neutrons External Effective

Year

16

Tritium Neutrons External Effective

Neutrons External Tritium

1 2 3 4 5 6 70 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

1 2 3 4 5 6 7 0 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 26 Average Dose Trends for Pickering N uclear Generating Stati on (Based o n A ll Monitoring R esults)

12

1

08

06

04

02

0

Year

Figure 27 Collective Dose Trends for Pickering N uclear Generating Stati on

12000

10000

8000

6000

4000

2000

0

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

)

Sv

(me

osD

Year

17

2001 2002 2003 2004 2005 2006 2007

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 28 Distribution o f Effective Doses Among A ll Workers at Pickering Nuclear Generating Stati on

6000

5000

4000

3000

2000

1000

0

Num

ber o

f Wor

kers

Dose Range (mSv)

18

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

213 Darlington Nuclear Generating Station

Owned and operated by Ontario Power Generation the Darlington Nuclear Generating Station has four nuclear reactors the first of which began operating in 1989 The facility is located near Bowmanville on the shore of Lake Ontario

Figures 29ndash212 present dose information for the Darlington Nuclear Generating Station from 2001 to 2007

Figure 29 Average Dose Trends for Darlington N uclear Generating Stati on (Non- Zero R esults Only)

)S

v(m

e os

D

250

200

150

100

050

000

Year

19

Tritium Neutrons External Effective

Neutrons External Tritium

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 210 Average Dose Trends for Darlington N uclear Generating Stati on (All Monitoring R esults)

090

080

070

060

050

040

030

020

010

000

)S

v(m

e os

D

Year

Figure 211 Collective Dose Trends for Darlington N uclear Generating Stati on

4500

4000

3500

3000

2500

2000

1500

1000

500

0

)vSm-nosrep (es

Do

eiv

llect

Co

Year

20

2001 2002 2003 2004 2005 2006 2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 212 Distribution o f Effective Doses Among A ll Workers at Darlington Nuclear Generating Stati on

0

500

1000

1500

2000

2500

3000

3500

ers

ork

W of

be

r um

N

Dose Range (mSv)

21

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

214 Gentilly-2 Nuclear Generating Station

The Gentilly-2 Nuclear Generating Station owned and operated by Hydro-Queacutebec has a single reactor that began operating in 1982 The facility is located on the south shore of the St Lawrence River near Trois-Riviegraveres Queacutebec

Figures 213ndash216 present dose information for the Gentilly-2 Nuclear Generating Station from 2001 to 2007

Figure 213 Average Dose Trends for Gentilly-2 Nuclear Generating Stati on (Based o n N on-Zero R esults)

0

05

1

15

2

25

3

35

4

45

)S

v(m

e os

D

Year

22

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 214 Average Dose Trends for Gentilly-2 Nuclear Generating Stati on (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

)S

v(m

e os

D

Year

Figure 215 Collective Dose Trends for Gentilly-2 Nuclear Generating Stati on

0

500

1000

1500

2000

2500

3000

3500

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Neutrons

External

Tritium

Year

23

000-0

009

001-5

00

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 216 Distribution of Effective Doses Among All Workers at Gentilly-2 Nuclear Generating Station

2500

2000

1500

1000

500

0

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

24

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

215 Point Lepreau Nuclear Generating Station

The Point Lepreau Nuclear Generating Station has one reactor that began operating in 1982 Owned and operated by New Brunswick Power Nuclear the station is located in Point Lepreau New Brunswick about 40 km west of Saint John on the shores of the Bay of Fundy

Figures 217ndash220 present dose information for the Point Lepreau Nuclear Generating Station from 2001 to 2007

Figure 217 Average Dose Trends for Point Lepreau N uclear Generating Stati on (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

)S

v(m

e os

D

Tritium Neutron External Effective

Year

25

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 218 Average Dose Trends for Point Lepreau N uclear Generating Stati on (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

)S

v(m

e os

D

Tritium Neutrons External Effective

Year

Figure 219 Collective Dose Trends for Point Lepreau N uclear Generating Station

0

200

400

600

800

1000

1200

1400

1600

1800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Neutrons

External

Tritium

Year

26

0

1400

1200

1000

800

600

400

200

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 220 Distribution of Effective Doses Among All Workers at Point Lepreau Nuclear Generating Station

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

27

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

22 Uranium Mines and Mills This section presents dose information for mine and mill sites in the following regions

bull Cluff Lake (Section 221) bull McClean Lake (Section 222) bull McArthur River (Section 223) bull Key Lake (Section 224) bull Cigar Lake (Section 225) bull Rabbit Lake (Section 226)

Graphs indicate the following data for each site from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for uranium mines and mills

1 Effective doses are composed of the following reported components bull doses from photons (labelled on the charts as ldquoexternalrdquo) bull doses from radon progeny bull doses from long-lived radioactive dust bull doses from radon gas (in some cases)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of photon radon progeny long-lived radioactive dust and radon gas doses

3 The NDR lists radon progeny in working level months (WLM) For this report radon progeny exposures were converted4 to doses expressed in mSv

221 Cluff Lake Operation

The Cluff Lake mining facilities operated by AREVA Resources Canada Inc are located in northwestern Saskatchewan Work began in 1980 and ended in 2002 with the site now being decommissioned The site consisted of three open-pit and two underground mines a mill and a tailings management facility During 2005 and 2006 most of the infrastructure was removed and the affected areas were remediated

Figures 221ndash224 present dose information for the Cluff Lake operation from 2001 to 2007

4 Doses were converted using the International Commission on Radiation Protection (ICRP)rsquos conversion convention of 1 WLM = 5 mSv This convention was established in the ICRP publication Protection against Radon at Home and at Work (ICRP 65)

28

Long-lived radioactive dust Radon progeny External Effective

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 221 Average Dose Trends for the Cluff Lake Operation (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

Year

Figure 222 Average Dose Trends for the Cluff Lake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

200

Long-lived radioactive dust Radon progeny External Effective

)S

v(m

e os

D)

Sv

(me

osD

Year

29

600

500

400

300

200

100

0

External Radon progeny Long-lived radioactive dust

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 223 Collective Dose Trends for the Cluff Lake Operation s

erkor

of W

ber

Num

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Year

Figure 224 Distribution o f Effective Doses Among A ll Workers at the Cluff Lake Operation

0

20

40

60

80

100

120

140

160

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

30

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

222 McClean Lake Operation

AREVA Resources Canada Inc runs the McClean Lake mining operation in northeastern Saskatchewan It comprises open pit mines a mill and a tailings management facility Mining began in 1995 while milling started in 1999

Figures 225ndash228 present dose information for the McClean Lake operation from 2001 to 2007

Figure 225 Average Dose Trends for the McClean L ake Operation (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

31

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 226 Average Dose Trends for the McClean L ake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 227 Collective Dose Trends for the McClean L ake Operation

0

100

200

300

400

500

600

700

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External

Radon progeny

Long-lived radioactive dust

Year

32

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 228 Distribution o f Effective Doses Among A ll Workers at the McClean Lake Operation

0

100

200

300

400

500

600

700

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

33

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

223 McArthur River Operation

Cameco Corporation operates the McArthur River underground mine in north-central Saskatchewan Ore from the mine which began production in 1999 is processed at the Key Lake Mill located 80 km south of McArthur River

Figures 229ndash232 present dose information for the McArthur River operation from 2001 to 2007

Figure 229 Average Dose Trends for the McArthur River Operation (Based o n N on-Zero R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

34

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 230 Average Dose Trends for the McArthur River Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

Figure 231 Collective Dose Trends for the McArthur River Operation

0

200

400

600

800

1000

1200

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Radon gas External Radon progeny Long-lived radioactive dust

Year

35

00

0-000

9

001-5

00

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 232 Distribution o f Effective Doses Among A ll Workers at the McArthur River Operation

0

100

200

300

400

500

600

700

800

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

36

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

224 Key Lake Operation

Cameco Corporation operates mining facilities in Key Lake located in north-central Saskatchewan The Key Lake operation includes two mined-out open pit mines (used for tailings management) a mill and two dry tailings management facilities Mining began in 1983 and ceased in 1997 the mill continued to process ore from the McArthur River mine during the reporting period

Figures 233ndash236 present dose information for the Key Lake operation from 2001 to 2007

Figure 233 Average Dose Trends for the Key Lake Operation (Based o n N on-Zero R esults)

00

20

40

60

80

00

20

40

60

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

37

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

00

20

40

60

80

00

20

40

60

Figure 234 Average Dose Trends for the Key Lake Operation (Based o n A ll Monitoring R esults)

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 235 Collective Dose Trends for the Key Lake Operation

0

100

200

300

400

500

600

700

800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External Radon progeny Long-lived radioactive dust

Year

38

00

0-000

9

001-5

0

501-1

000

gt 1001

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 236 Distribution o f Effective Doses Among A ll Workers at the Key Lake Operation

0

200

400

600

800

1000

1200

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose Range (mSv)

39

se

(mS

v)o

D

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

225 Cigar Lake Operation

Cameco Corporation manages the Cigar Lake underground mine located in northern Saskatchewan at the southern end of Waterbury Lake The mine was under construction at the time of this reportrsquos publication Test mining in ore was carried out in 1991 1992 and 2000

Figures 237ndash240 present dose information for the Cigar Lake operation from

Figure 2 37 Average D ose T rends fo r th e C igar L ake O peration (Based on Non-Zero Results)

2001 to 2007

Year

000

005

010

015

020

025

Long-lived radioactive dust Radon Progeny External Effective

40

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 238 Average Dose Trends for the Cigar Lake Operation (Based on All Monitoring Results)

000

005

010

015

020

025

030

035

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny

External

Effective

Year

Figure 239 Collective Dose Trends for the Cigar Lake Operation

0

50

100

150

200

250

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

External Radon progeny Long-lived radioactive dust

Year

41

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 240 Distribution of Effective Doses Among All Workers at the Cigar Lake Operation

0

200

400

600

800

1000

1200

1400

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

42

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

226 Rabbit Lake Operation

Cameco Corporation owns and operates mining facilities in Rabbit Lake located in north-eastern Saskatchewan Facilities include an underground mine four mined-out open-pit mines a mill and two tailings management facilities Mining and milling began in 1975

Figures 241ndash244 present dose information for the Rabbit Lake operation from 2001 to 2007

Figure 241 Average Dose Trends for the Rabbit Lake Operation (Based on Non-Zero Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

43

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 242 Average Dose Trends for the Rabbit Lake Operation (Based on All Monitoring Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

Figure 243 Collective Dose Trends for the Rabbit Lake Operation

0

200

400

600

800

1000

1200

1400

1600

1800

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Radon gas External Radon progeny Long-lived radioactive dust

Year

44

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

gt300

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 244 Distribution of Effective Doses Among All Workers at the Rabbit Lake Operation

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

900

800

700

600

500

400

300

200

100

0

Dose (mSv)

45

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

23 Uranium Refineries This section presents data for the following two facilities

bull a uranium refining facility in Blind River (Section 231) bull a uranium conversion facility in Port Hope (Section 232)

Graphs indicate the following average doses at each facility from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Note on data for uranium refineries

1 Doses from photons from external sources are measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay and lung counting Historically while these internal doses have been measured they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

231 Blind River Refinery

Cameco Corporation owns and is licensed to operate a uranium refinery in Blind River Ontario The facility which began operating in 1983 converts uranium ore concentrate to uranium trioxide The uranium trioxide is shipped to Camecorsquos uranium conversion facility in Port Hope Ontario where it is processed into uranium dioxide (for use in the fabrication of fuel for nuclear reactors in Canada) or uranium hexafluoride (exported for enrichment and fabrication into fuel for nuclear power reactors around the world)

Figures 245ndash248 present dose information for the Blind River refinery from 2001 to 2007

46

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 245 Average Dose Trends for the Blind River Refinery (Based on Non-Zero Results)

0

05

1

15

2

25

Year

Figure 246 Average Dose Trends for the Blind River Refinery (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

47

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 247 Collective Dose Trends for the Blind River Refinery

0

50

100

150

200

250

300 C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 248 Distribution of Effective Doses Among All Workers at the Blind River Refinery

0

20

40

60

80

100

120

140

160

180

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

48

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

232 Port Hope Conversion Facility

Cameco Corporation owns and is licensed to operate a uranium conversion facility in Port Hope Ontario The facility processes uranium trioxide received from the refinery in Blind River into uranium dioxide and uranium hexafluoride

Figures 249ndash252 present dose information for the Port Hope uranium conversion facility from 2001 to 2007

Figure 249 Average Dose Trends for the Port Hope Conversion Facility (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

49

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 250 Average Dose Trends for the Port Hope Conversion Facility (Based on All Monitoring Results)

0

01

02

03

04

05

06

07

08

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 251 Collective Dose Trends for the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

50

000-0

009

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 252 Distribution of Effective Doses Among All Workers at the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

400

450

500

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

51

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

24 Fuel Fabrication Facilities This section presents data for three nuclear fuel fabrication facilities

bull Two facilities owned and operated by General Electric Canada Inc (Section 241) bull One facility in Port Hope operated by Zircatec Precision Industries (Section 242)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average doses

Notes on data for fuel fabrication facilities

1 Effective doses for the three facilities are composed of the following reported components bull dose from photons (labelled on the charts as ldquoexternalrdquo) bull doses from internal intakes of uranium dust (long-lived radioactive dust) from

uranium in air concentrations (for General Electricrsquos Toronto facility only)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components photon doses and doses from long-lived radioactive dust

241 General Electric Nuclear Fuel Facilities

General Electric Canada Inc operates two nuclear fuel facilities in Ontario

bull At the Toronto facility uranium dioxide pellets are produced from natural or depleted uranium dioxide powder

bull At the Peterborough facility uranium dioxide fuel bundles are created from the pellets produced at the Toronto facility

Figures 253ndash256 present dose information for General Electric Canada Incrsquos fuel fabrication facilities from 2001 to 2007 Graphs do not distinguish between the doses received at the Peterborough facility versus those at the Toronto facility

52

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 253 Average Dose Trends for the General Electric Fuel Facility (Based on Non-Zero Results Only)

0

05

1

15

2

25

3

35

Long Lived Radioactive Dust External Effective

Year

Figure 254 Average Dose Trends for the General Electric Fuel Facility (Based on All Monitoring Results)

0

05

1

15

2

25

3

Long Lived Radioactive Dust External Effective

Year

Dos

e (m

Sv)

Dos

e (m

Sv)

53

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 255 Collective Dose Trends for the General Electric Fuel Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Long Lived Radioactive Dust External

Year

Figure 256 Distribution of Effective Doses among all Workers at the General Electric Fuel Facility

0

10

20

30

40

50

60

70

80

90

100

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

54

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

242 Zircatec Nuclear Fuel Facility

Zircatec Precision Industries Inc operates a nuclear fuel facility in Port Hope Ontario where it makes fuel pellets from uranium dioxide powder received from Port Hopersquos uranium conversion facility The nuclear fuel facility also manufactures fuel bundles for nuclear reactors in Canada

Notes on data for the Zircatec nuclear fuel facility

1 Graphs indicate the following data bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of average effective doses

2 Doses from photons from external sources were measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay Historically although these internal doses have been measured and submitted to the CNSC they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

Figures 257ndash260 present dose information for the Zircatec nuclear fuel facility from 2001 to 2007

Figure 257 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on Non-Zero Results)

0

05

1

15

2

25

3

35

Effe

ctiv

e D

ose

(mS

v)

Year

55

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 258 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

18

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 259 Collective Dose Trends for the Zircatec Nuclear Fuel Facility

0

50

100

150

200

250

300

350

400

450

500

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

56

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 260 Distribution of Effective Doses Among All Workers at the Zircatec Nuclear Fuel Facility

300

Num

ber o

f Wor

kers

250

200

150

100

50

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

57

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

25 Research and Radioisotope Production Facilities This section presents dose information for the following research and radioisotope production facilities from 2001 to 2007

bull Chalk River Laboratories and Whiteshell Laboratories (Section 251) bull A radioisotope production facility operated by MDS Nordion (Section 252) bull The Tri-University Meson Facility (TRIUMF) (Section 253)

Note on data for research and radioisotope production facilities

1 Graphs indicate the following data for each facility bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of effective doses

251 Chalk River Laboratories and Whiteshell Laboratories

Atomic Energy of Canada Limited (AECL) owns and is licensed to operate Chalk River Laboratories and Whiteshell Laboratories

Situated in Renfrew County on the south shore of the Ottawa River the Chalk River Laboratories site hosts the National Research Universal Reactor along with numerous other facilities occupying some 160 buildings in an area of approximately 40 km2 Activities consist of radioisotope production for nuclear medicine testing and development of structural materials in support of power reactor operations fuel fabrication research and radioactive waste management and storage

The Whiteshell Laboratories site is located approximately 10 km west of Pinawa Manitoba and 100 km northeast of Winnipeg on the east bank of the Winnipeg River AECL established the laboratories for nuclear research and testing during the early 1960s and has since discontinued operations which are being decommissioned under a licence from the CNSC

Figures 261ndash264 present dose information for Chalk River Laboratories and Whiteshell Laboratories from 2001 to 2007

Notes on data for Chalk River Laboratories and Whiteshell Laboratories

1 Effective doses are composed of the following reported components bull external doses5 (from both photon and neutron doses) bull tritium doses

Due to issues with AECLrsquos in-house dosimetry management system neutron doses were not reported separately to the NDR during the reporting period As a result external doses from photons and neutrons were totaled The reporting discrepancy has since been rectified

58

5

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of external (photon and neutron) and tritium doses Intakes of other radionuclides occasionally occur and these radionuclides are not included here because their associated doses are very small For this reason certain collective doses in this report may have values slightly lower than the sum of their respective components as listed

Figure 261 Average Dose Trends for Chalk River and Whiteshell Laboratories (Non-Zero Results Only)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Tritium External Effective

Year

59

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 262 Average Dose Trends for Chalk River and Whiteshell Laboratories (All Monitoring Results)

000

020

040

060

080

100

120

Dos

e (m

Sv)

Tritium External Effective

Year

Figure 263 Collective Dose Trends for Chalk River and Whiteshell Laboratories

0

500

1000

1500

2000

2500

3000

3500

Col

lect

ive

Dos

e (p

erso

n- m

Sv)

External Tritium

Year

60

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 264 Distribution of Effective Doses Among All Workers at Chalk River and Whiteshell Laboratories

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

3500

3000

2500

2000

1500

1000

500

Dose (mSv)

61

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

252 MDS Nordion (Nuclear Substance Processing Facility and Canadian Irradiation Centre)

MDS Nordion owns and operates a nuclear substance processing facility in Ottawa Ontario where it processes unsealed radioisotopes and manufactures sealed radiation sources In operation since the early 1970s the facility was purchased by Nordion International in 1991

In cooperation with the Universiteacute du Queacutebecrsquos Institut Armand-Frappier MDS Nordion also operates the Canadian Irradiation Centre which conducts various irradiation services which include training testing and development The centre is located in Laval Quebec on the Universiteacute du Queacutebec campus

Figures 265ndash268 present dose information for MDS Nordionrsquos Ottawa nuclear substance processing facility and for the Canadian Irradiation Centre from 2001 to 2007

Notes on data for MDS Nordionrsquos nuclear substance processing facility and the Canadian Irradiation Centre

1 Doses from photons from external sources were measured and reported to the NDR MDS Nordion also has a routine thyroid monitoring program very occasionally small recordable doses of radiation have occurred from thyroid uptake of iodine The resulting doses have not been historically submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided

Figure 265 Average Dose Trends for MDS Nordion (Based on Non-Zero Results)

0

05

1

15

2

25

Effe

ctiv

e D

ose

(mS

v)

Year

62

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 266 Average Dose Trends for MDS Nordion (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

Figure 267 Collective Dose Trends for MDS Nordion

0

100

200

300

400

500

600

700

800

Year

63

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 268 Distribution of Effective Doses Among All Workers at MDS Nordion

0

5 0

1 0 0

1 5 0

2 0 0

2 5 0

3 0 0

3 5 0

4 0 0

4 5 0

5 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

64

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

253 Tri-University Meson Facility

The Tri-University Meson facility (TRIUMF) is situated in Vancouver on the campus of the University of British Columbia TRIUMF which began operating in the early 1970s with one cyclotron now has two cyclotrons and associated laboratories for research and radioisotope production The laboratory provides research facilities for Canadian and international users and also produces radioisotopes which are used by medical facilities and by a commercial organization (MDS Nordion) MDS Nordion staff also work at the TRIUMF site however MDS Nordion oversees this work and has its own radiation protection program

Figures 269ndash272 present dose information for the TRIUMF facility from 2001 to 2007 Please note that data sets do not distinguish between doses received by TRIUMF staff and MDS Nordion staff who work on the site as the data for these two groups was submitted collectively to the NDR for the reporting period shown Future data for each group will be submitted separately to the NDR

Note on data for TRIUMF

1 Effective doses are composed of the following reported components bull doses from photons (labeled as ldquoexternalrdquo in the charts) bull neutron doses

Figure 269 Average Dose Trends for TRIUMF (Non-Zero Results Only)

000

020

040

060

080

100

120

140

160

Dos

e (m

Sv)

Neutrons External Effective

Year

65

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 17: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

20 Facility-Specific Overview of Occupational Doses This section presents data for the following types of facilities

bull nuclear power plants (Section 21) bull uranium mines and mills (Section 22) bull uranium refineries (Section 23) bull fuel fabrication facilities (Section 24) bull research and radioisotope production facilities (Section 25) bull tritium production facilities (Section 26)

21 Nuclear Power Plants This section presents dose information for the following nuclear power plants

bull Bruce A and Bruce B Nuclear Generating Stations (Section 211) bull Pickering Nuclear Generating Stations (Section 212) bull Darlington Nuclear Generating Station Section 213) bull Gentilly-2 Nuclear Generating Station (Section 214) bull Point Lepreau Generating Station (Section 215)

Graphs in this section indicate the following data for each nuclear power plant from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for nuclear power plants

1 Effective doses are composed of the following reported components bull doses from photons (labeled on the charts as ldquoexternalrdquo) bull neutron doses bull tritium doses

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of photon neutron and tritium doses Intakes of other radionuclides (for example Iodine-131 or Carbon-14) occasionally occur but these radionuclides are not included here because the associated collective dose is very small For this reason certain collective dose values in this report may be slightly lower than the sum of their respective components as listed

12

1 2 3 4 5 6 70 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

211 Bruce Nuclear Generating Stations

Bruce Power owns and operates the Bruce Nuclear Generating Stations located near Kincardine Ontario on the shore of Lake Huron

bull Bruce A consists of four nuclear reactors (units 1ndash4) and began operating in 1976 bull Bruce B has four nuclear reactors (units 5ndash8) and started operating in 1984

As part of its extensive recovery program in 1997 the sitersquos previous operator Ontario Hydro (now Ontario Power Generation) temporarily shut down all Bruce A reactors and maintained them in a guaranteed shutdown state Units 3 and 4 were later returned to service (in October 2003 and January 2004) while Units 1 and 2 remained in a guaranteed shutdown state

Figures 21ndash24 present dose information for the Bruce Nuclear Generating Stations from 2001 to 2007 Graphs do not distinguish between doses received at Bruce A versus Bruce B

Fig 21 Average Dose Trends for Bruce Nuclear Generating Stati on (Based o n N on-Zero R esults)

Dos

e (m

Sv)

4

35

3

25

2

15

1

05

0

Tritium Neutron External Effective

Year

13

Neutrons External Tritium

0 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 21 2 3 4 5 6 7

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

0

2

4

6

8

1

2

4

0

0

0

0

1

1

Figure 22 Average Dose Trends for Bruce Nuclear Generating Stati on (Based o n A ll Monitoring R esults)

16

)S

v(m

e os

D

Tritium Neutrons External Effective

Year

Figure 23 Collective Dose Trends for Bruce Nuclear Generating Stati on

8000

7000

6000

5000

4000

3000

2000

1000

0

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Year

14

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 24 Distribution of Effective Doses Among All Workers at Bruce Nuclear Generating Station

6000

5000

4000

3000

2000

1000

0 9 0 0

1-50 0 0 1 0 0 0 0 00 5 0 0 0

0-000

000 1-1 1-1 1-20 1-3 3gt0 0 0 05 0 5 01 1 2

Num

ber o

f Wor

kers

Dose Range (mSv)

15

1 2 3 4 5 6 7 0 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

212 Pickering Nuclear Generating Stations

Located in Pickering Ontario the Pickering Nuclear Generating Stations are owned and operated by Ontario Power Generation Two generating stations are located within one enclosure

bull Pickering A consists of four nuclear reactors (units 1 to 4) that began operating in 1971 bull Pickering B consists of four nuclear reactors (units 5 to 8) that began operating in 1982

As part of its extensive recovery program Ontario Hydro (now Ontario Power Generation) temporarily shut down all Pickering A reactors in 1997 and maintained them in a guaranteed shutdown state Unit 4 was restarted in September 2003 and Unit 1 was restarted in March 2005 Units 2 and 3 remain in a guaranteed shutdown state

Figures 25ndash28 present dose information for the Pickering Nuclear Generating Stations from 2001 to 2007 Graphs do not distinguish between doses received at Pickering A versus those received at Pickering B

Figure 25 Average Dose Trends for Pickering N uclear Generating Stati on (Based o n N on-Zero R esults)

25

2

15

1

05

0

)S

v(m

e os

D

Tritium Neutrons External Effective

Year

16

Tritium Neutrons External Effective

Neutrons External Tritium

1 2 3 4 5 6 70 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

1 2 3 4 5 6 7 0 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 26 Average Dose Trends for Pickering N uclear Generating Stati on (Based o n A ll Monitoring R esults)

12

1

08

06

04

02

0

Year

Figure 27 Collective Dose Trends for Pickering N uclear Generating Stati on

12000

10000

8000

6000

4000

2000

0

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

)

Sv

(me

osD

Year

17

2001 2002 2003 2004 2005 2006 2007

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 28 Distribution o f Effective Doses Among A ll Workers at Pickering Nuclear Generating Stati on

6000

5000

4000

3000

2000

1000

0

Num

ber o

f Wor

kers

Dose Range (mSv)

18

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

213 Darlington Nuclear Generating Station

Owned and operated by Ontario Power Generation the Darlington Nuclear Generating Station has four nuclear reactors the first of which began operating in 1989 The facility is located near Bowmanville on the shore of Lake Ontario

Figures 29ndash212 present dose information for the Darlington Nuclear Generating Station from 2001 to 2007

Figure 29 Average Dose Trends for Darlington N uclear Generating Stati on (Non- Zero R esults Only)

)S

v(m

e os

D

250

200

150

100

050

000

Year

19

Tritium Neutrons External Effective

Neutrons External Tritium

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 210 Average Dose Trends for Darlington N uclear Generating Stati on (All Monitoring R esults)

090

080

070

060

050

040

030

020

010

000

)S

v(m

e os

D

Year

Figure 211 Collective Dose Trends for Darlington N uclear Generating Stati on

4500

4000

3500

3000

2500

2000

1500

1000

500

0

)vSm-nosrep (es

Do

eiv

llect

Co

Year

20

2001 2002 2003 2004 2005 2006 2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 212 Distribution o f Effective Doses Among A ll Workers at Darlington Nuclear Generating Stati on

0

500

1000

1500

2000

2500

3000

3500

ers

ork

W of

be

r um

N

Dose Range (mSv)

21

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

214 Gentilly-2 Nuclear Generating Station

The Gentilly-2 Nuclear Generating Station owned and operated by Hydro-Queacutebec has a single reactor that began operating in 1982 The facility is located on the south shore of the St Lawrence River near Trois-Riviegraveres Queacutebec

Figures 213ndash216 present dose information for the Gentilly-2 Nuclear Generating Station from 2001 to 2007

Figure 213 Average Dose Trends for Gentilly-2 Nuclear Generating Stati on (Based o n N on-Zero R esults)

0

05

1

15

2

25

3

35

4

45

)S

v(m

e os

D

Year

22

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 214 Average Dose Trends for Gentilly-2 Nuclear Generating Stati on (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

)S

v(m

e os

D

Year

Figure 215 Collective Dose Trends for Gentilly-2 Nuclear Generating Stati on

0

500

1000

1500

2000

2500

3000

3500

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Neutrons

External

Tritium

Year

23

000-0

009

001-5

00

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 216 Distribution of Effective Doses Among All Workers at Gentilly-2 Nuclear Generating Station

2500

2000

1500

1000

500

0

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

24

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

215 Point Lepreau Nuclear Generating Station

The Point Lepreau Nuclear Generating Station has one reactor that began operating in 1982 Owned and operated by New Brunswick Power Nuclear the station is located in Point Lepreau New Brunswick about 40 km west of Saint John on the shores of the Bay of Fundy

Figures 217ndash220 present dose information for the Point Lepreau Nuclear Generating Station from 2001 to 2007

Figure 217 Average Dose Trends for Point Lepreau N uclear Generating Stati on (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

)S

v(m

e os

D

Tritium Neutron External Effective

Year

25

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 218 Average Dose Trends for Point Lepreau N uclear Generating Stati on (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

)S

v(m

e os

D

Tritium Neutrons External Effective

Year

Figure 219 Collective Dose Trends for Point Lepreau N uclear Generating Station

0

200

400

600

800

1000

1200

1400

1600

1800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Neutrons

External

Tritium

Year

26

0

1400

1200

1000

800

600

400

200

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 220 Distribution of Effective Doses Among All Workers at Point Lepreau Nuclear Generating Station

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

27

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

22 Uranium Mines and Mills This section presents dose information for mine and mill sites in the following regions

bull Cluff Lake (Section 221) bull McClean Lake (Section 222) bull McArthur River (Section 223) bull Key Lake (Section 224) bull Cigar Lake (Section 225) bull Rabbit Lake (Section 226)

Graphs indicate the following data for each site from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for uranium mines and mills

1 Effective doses are composed of the following reported components bull doses from photons (labelled on the charts as ldquoexternalrdquo) bull doses from radon progeny bull doses from long-lived radioactive dust bull doses from radon gas (in some cases)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of photon radon progeny long-lived radioactive dust and radon gas doses

3 The NDR lists radon progeny in working level months (WLM) For this report radon progeny exposures were converted4 to doses expressed in mSv

221 Cluff Lake Operation

The Cluff Lake mining facilities operated by AREVA Resources Canada Inc are located in northwestern Saskatchewan Work began in 1980 and ended in 2002 with the site now being decommissioned The site consisted of three open-pit and two underground mines a mill and a tailings management facility During 2005 and 2006 most of the infrastructure was removed and the affected areas were remediated

Figures 221ndash224 present dose information for the Cluff Lake operation from 2001 to 2007

4 Doses were converted using the International Commission on Radiation Protection (ICRP)rsquos conversion convention of 1 WLM = 5 mSv This convention was established in the ICRP publication Protection against Radon at Home and at Work (ICRP 65)

28

Long-lived radioactive dust Radon progeny External Effective

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 221 Average Dose Trends for the Cluff Lake Operation (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

Year

Figure 222 Average Dose Trends for the Cluff Lake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

200

Long-lived radioactive dust Radon progeny External Effective

)S

v(m

e os

D)

Sv

(me

osD

Year

29

600

500

400

300

200

100

0

External Radon progeny Long-lived radioactive dust

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 223 Collective Dose Trends for the Cluff Lake Operation s

erkor

of W

ber

Num

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Year

Figure 224 Distribution o f Effective Doses Among A ll Workers at the Cluff Lake Operation

0

20

40

60

80

100

120

140

160

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

30

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

222 McClean Lake Operation

AREVA Resources Canada Inc runs the McClean Lake mining operation in northeastern Saskatchewan It comprises open pit mines a mill and a tailings management facility Mining began in 1995 while milling started in 1999

Figures 225ndash228 present dose information for the McClean Lake operation from 2001 to 2007

Figure 225 Average Dose Trends for the McClean L ake Operation (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

31

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 226 Average Dose Trends for the McClean L ake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 227 Collective Dose Trends for the McClean L ake Operation

0

100

200

300

400

500

600

700

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External

Radon progeny

Long-lived radioactive dust

Year

32

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 228 Distribution o f Effective Doses Among A ll Workers at the McClean Lake Operation

0

100

200

300

400

500

600

700

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

33

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

223 McArthur River Operation

Cameco Corporation operates the McArthur River underground mine in north-central Saskatchewan Ore from the mine which began production in 1999 is processed at the Key Lake Mill located 80 km south of McArthur River

Figures 229ndash232 present dose information for the McArthur River operation from 2001 to 2007

Figure 229 Average Dose Trends for the McArthur River Operation (Based o n N on-Zero R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

34

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 230 Average Dose Trends for the McArthur River Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

Figure 231 Collective Dose Trends for the McArthur River Operation

0

200

400

600

800

1000

1200

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Radon gas External Radon progeny Long-lived radioactive dust

Year

35

00

0-000

9

001-5

00

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 232 Distribution o f Effective Doses Among A ll Workers at the McArthur River Operation

0

100

200

300

400

500

600

700

800

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

36

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

224 Key Lake Operation

Cameco Corporation operates mining facilities in Key Lake located in north-central Saskatchewan The Key Lake operation includes two mined-out open pit mines (used for tailings management) a mill and two dry tailings management facilities Mining began in 1983 and ceased in 1997 the mill continued to process ore from the McArthur River mine during the reporting period

Figures 233ndash236 present dose information for the Key Lake operation from 2001 to 2007

Figure 233 Average Dose Trends for the Key Lake Operation (Based o n N on-Zero R esults)

00

20

40

60

80

00

20

40

60

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

37

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

00

20

40

60

80

00

20

40

60

Figure 234 Average Dose Trends for the Key Lake Operation (Based o n A ll Monitoring R esults)

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 235 Collective Dose Trends for the Key Lake Operation

0

100

200

300

400

500

600

700

800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External Radon progeny Long-lived radioactive dust

Year

38

00

0-000

9

001-5

0

501-1

000

gt 1001

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 236 Distribution o f Effective Doses Among A ll Workers at the Key Lake Operation

0

200

400

600

800

1000

1200

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose Range (mSv)

39

se

(mS

v)o

D

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

225 Cigar Lake Operation

Cameco Corporation manages the Cigar Lake underground mine located in northern Saskatchewan at the southern end of Waterbury Lake The mine was under construction at the time of this reportrsquos publication Test mining in ore was carried out in 1991 1992 and 2000

Figures 237ndash240 present dose information for the Cigar Lake operation from

Figure 2 37 Average D ose T rends fo r th e C igar L ake O peration (Based on Non-Zero Results)

2001 to 2007

Year

000

005

010

015

020

025

Long-lived radioactive dust Radon Progeny External Effective

40

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 238 Average Dose Trends for the Cigar Lake Operation (Based on All Monitoring Results)

000

005

010

015

020

025

030

035

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny

External

Effective

Year

Figure 239 Collective Dose Trends for the Cigar Lake Operation

0

50

100

150

200

250

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

External Radon progeny Long-lived radioactive dust

Year

41

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 240 Distribution of Effective Doses Among All Workers at the Cigar Lake Operation

0

200

400

600

800

1000

1200

1400

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

42

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

226 Rabbit Lake Operation

Cameco Corporation owns and operates mining facilities in Rabbit Lake located in north-eastern Saskatchewan Facilities include an underground mine four mined-out open-pit mines a mill and two tailings management facilities Mining and milling began in 1975

Figures 241ndash244 present dose information for the Rabbit Lake operation from 2001 to 2007

Figure 241 Average Dose Trends for the Rabbit Lake Operation (Based on Non-Zero Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

43

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 242 Average Dose Trends for the Rabbit Lake Operation (Based on All Monitoring Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

Figure 243 Collective Dose Trends for the Rabbit Lake Operation

0

200

400

600

800

1000

1200

1400

1600

1800

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Radon gas External Radon progeny Long-lived radioactive dust

Year

44

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

gt300

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 244 Distribution of Effective Doses Among All Workers at the Rabbit Lake Operation

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

900

800

700

600

500

400

300

200

100

0

Dose (mSv)

45

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

23 Uranium Refineries This section presents data for the following two facilities

bull a uranium refining facility in Blind River (Section 231) bull a uranium conversion facility in Port Hope (Section 232)

Graphs indicate the following average doses at each facility from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Note on data for uranium refineries

1 Doses from photons from external sources are measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay and lung counting Historically while these internal doses have been measured they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

231 Blind River Refinery

Cameco Corporation owns and is licensed to operate a uranium refinery in Blind River Ontario The facility which began operating in 1983 converts uranium ore concentrate to uranium trioxide The uranium trioxide is shipped to Camecorsquos uranium conversion facility in Port Hope Ontario where it is processed into uranium dioxide (for use in the fabrication of fuel for nuclear reactors in Canada) or uranium hexafluoride (exported for enrichment and fabrication into fuel for nuclear power reactors around the world)

Figures 245ndash248 present dose information for the Blind River refinery from 2001 to 2007

46

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 245 Average Dose Trends for the Blind River Refinery (Based on Non-Zero Results)

0

05

1

15

2

25

Year

Figure 246 Average Dose Trends for the Blind River Refinery (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

47

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 247 Collective Dose Trends for the Blind River Refinery

0

50

100

150

200

250

300 C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 248 Distribution of Effective Doses Among All Workers at the Blind River Refinery

0

20

40

60

80

100

120

140

160

180

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

48

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

232 Port Hope Conversion Facility

Cameco Corporation owns and is licensed to operate a uranium conversion facility in Port Hope Ontario The facility processes uranium trioxide received from the refinery in Blind River into uranium dioxide and uranium hexafluoride

Figures 249ndash252 present dose information for the Port Hope uranium conversion facility from 2001 to 2007

Figure 249 Average Dose Trends for the Port Hope Conversion Facility (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

49

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 250 Average Dose Trends for the Port Hope Conversion Facility (Based on All Monitoring Results)

0

01

02

03

04

05

06

07

08

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 251 Collective Dose Trends for the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

50

000-0

009

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 252 Distribution of Effective Doses Among All Workers at the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

400

450

500

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

51

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

24 Fuel Fabrication Facilities This section presents data for three nuclear fuel fabrication facilities

bull Two facilities owned and operated by General Electric Canada Inc (Section 241) bull One facility in Port Hope operated by Zircatec Precision Industries (Section 242)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average doses

Notes on data for fuel fabrication facilities

1 Effective doses for the three facilities are composed of the following reported components bull dose from photons (labelled on the charts as ldquoexternalrdquo) bull doses from internal intakes of uranium dust (long-lived radioactive dust) from

uranium in air concentrations (for General Electricrsquos Toronto facility only)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components photon doses and doses from long-lived radioactive dust

241 General Electric Nuclear Fuel Facilities

General Electric Canada Inc operates two nuclear fuel facilities in Ontario

bull At the Toronto facility uranium dioxide pellets are produced from natural or depleted uranium dioxide powder

bull At the Peterborough facility uranium dioxide fuel bundles are created from the pellets produced at the Toronto facility

Figures 253ndash256 present dose information for General Electric Canada Incrsquos fuel fabrication facilities from 2001 to 2007 Graphs do not distinguish between the doses received at the Peterborough facility versus those at the Toronto facility

52

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 253 Average Dose Trends for the General Electric Fuel Facility (Based on Non-Zero Results Only)

0

05

1

15

2

25

3

35

Long Lived Radioactive Dust External Effective

Year

Figure 254 Average Dose Trends for the General Electric Fuel Facility (Based on All Monitoring Results)

0

05

1

15

2

25

3

Long Lived Radioactive Dust External Effective

Year

Dos

e (m

Sv)

Dos

e (m

Sv)

53

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 255 Collective Dose Trends for the General Electric Fuel Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Long Lived Radioactive Dust External

Year

Figure 256 Distribution of Effective Doses among all Workers at the General Electric Fuel Facility

0

10

20

30

40

50

60

70

80

90

100

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

54

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

242 Zircatec Nuclear Fuel Facility

Zircatec Precision Industries Inc operates a nuclear fuel facility in Port Hope Ontario where it makes fuel pellets from uranium dioxide powder received from Port Hopersquos uranium conversion facility The nuclear fuel facility also manufactures fuel bundles for nuclear reactors in Canada

Notes on data for the Zircatec nuclear fuel facility

1 Graphs indicate the following data bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of average effective doses

2 Doses from photons from external sources were measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay Historically although these internal doses have been measured and submitted to the CNSC they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

Figures 257ndash260 present dose information for the Zircatec nuclear fuel facility from 2001 to 2007

Figure 257 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on Non-Zero Results)

0

05

1

15

2

25

3

35

Effe

ctiv

e D

ose

(mS

v)

Year

55

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 258 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

18

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 259 Collective Dose Trends for the Zircatec Nuclear Fuel Facility

0

50

100

150

200

250

300

350

400

450

500

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

56

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 260 Distribution of Effective Doses Among All Workers at the Zircatec Nuclear Fuel Facility

300

Num

ber o

f Wor

kers

250

200

150

100

50

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

57

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

25 Research and Radioisotope Production Facilities This section presents dose information for the following research and radioisotope production facilities from 2001 to 2007

bull Chalk River Laboratories and Whiteshell Laboratories (Section 251) bull A radioisotope production facility operated by MDS Nordion (Section 252) bull The Tri-University Meson Facility (TRIUMF) (Section 253)

Note on data for research and radioisotope production facilities

1 Graphs indicate the following data for each facility bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of effective doses

251 Chalk River Laboratories and Whiteshell Laboratories

Atomic Energy of Canada Limited (AECL) owns and is licensed to operate Chalk River Laboratories and Whiteshell Laboratories

Situated in Renfrew County on the south shore of the Ottawa River the Chalk River Laboratories site hosts the National Research Universal Reactor along with numerous other facilities occupying some 160 buildings in an area of approximately 40 km2 Activities consist of radioisotope production for nuclear medicine testing and development of structural materials in support of power reactor operations fuel fabrication research and radioactive waste management and storage

The Whiteshell Laboratories site is located approximately 10 km west of Pinawa Manitoba and 100 km northeast of Winnipeg on the east bank of the Winnipeg River AECL established the laboratories for nuclear research and testing during the early 1960s and has since discontinued operations which are being decommissioned under a licence from the CNSC

Figures 261ndash264 present dose information for Chalk River Laboratories and Whiteshell Laboratories from 2001 to 2007

Notes on data for Chalk River Laboratories and Whiteshell Laboratories

1 Effective doses are composed of the following reported components bull external doses5 (from both photon and neutron doses) bull tritium doses

Due to issues with AECLrsquos in-house dosimetry management system neutron doses were not reported separately to the NDR during the reporting period As a result external doses from photons and neutrons were totaled The reporting discrepancy has since been rectified

58

5

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of external (photon and neutron) and tritium doses Intakes of other radionuclides occasionally occur and these radionuclides are not included here because their associated doses are very small For this reason certain collective doses in this report may have values slightly lower than the sum of their respective components as listed

Figure 261 Average Dose Trends for Chalk River and Whiteshell Laboratories (Non-Zero Results Only)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Tritium External Effective

Year

59

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 262 Average Dose Trends for Chalk River and Whiteshell Laboratories (All Monitoring Results)

000

020

040

060

080

100

120

Dos

e (m

Sv)

Tritium External Effective

Year

Figure 263 Collective Dose Trends for Chalk River and Whiteshell Laboratories

0

500

1000

1500

2000

2500

3000

3500

Col

lect

ive

Dos

e (p

erso

n- m

Sv)

External Tritium

Year

60

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 264 Distribution of Effective Doses Among All Workers at Chalk River and Whiteshell Laboratories

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

3500

3000

2500

2000

1500

1000

500

Dose (mSv)

61

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

252 MDS Nordion (Nuclear Substance Processing Facility and Canadian Irradiation Centre)

MDS Nordion owns and operates a nuclear substance processing facility in Ottawa Ontario where it processes unsealed radioisotopes and manufactures sealed radiation sources In operation since the early 1970s the facility was purchased by Nordion International in 1991

In cooperation with the Universiteacute du Queacutebecrsquos Institut Armand-Frappier MDS Nordion also operates the Canadian Irradiation Centre which conducts various irradiation services which include training testing and development The centre is located in Laval Quebec on the Universiteacute du Queacutebec campus

Figures 265ndash268 present dose information for MDS Nordionrsquos Ottawa nuclear substance processing facility and for the Canadian Irradiation Centre from 2001 to 2007

Notes on data for MDS Nordionrsquos nuclear substance processing facility and the Canadian Irradiation Centre

1 Doses from photons from external sources were measured and reported to the NDR MDS Nordion also has a routine thyroid monitoring program very occasionally small recordable doses of radiation have occurred from thyroid uptake of iodine The resulting doses have not been historically submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided

Figure 265 Average Dose Trends for MDS Nordion (Based on Non-Zero Results)

0

05

1

15

2

25

Effe

ctiv

e D

ose

(mS

v)

Year

62

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 266 Average Dose Trends for MDS Nordion (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

Figure 267 Collective Dose Trends for MDS Nordion

0

100

200

300

400

500

600

700

800

Year

63

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 268 Distribution of Effective Doses Among All Workers at MDS Nordion

0

5 0

1 0 0

1 5 0

2 0 0

2 5 0

3 0 0

3 5 0

4 0 0

4 5 0

5 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

64

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

253 Tri-University Meson Facility

The Tri-University Meson facility (TRIUMF) is situated in Vancouver on the campus of the University of British Columbia TRIUMF which began operating in the early 1970s with one cyclotron now has two cyclotrons and associated laboratories for research and radioisotope production The laboratory provides research facilities for Canadian and international users and also produces radioisotopes which are used by medical facilities and by a commercial organization (MDS Nordion) MDS Nordion staff also work at the TRIUMF site however MDS Nordion oversees this work and has its own radiation protection program

Figures 269ndash272 present dose information for the TRIUMF facility from 2001 to 2007 Please note that data sets do not distinguish between doses received by TRIUMF staff and MDS Nordion staff who work on the site as the data for these two groups was submitted collectively to the NDR for the reporting period shown Future data for each group will be submitted separately to the NDR

Note on data for TRIUMF

1 Effective doses are composed of the following reported components bull doses from photons (labeled as ldquoexternalrdquo in the charts) bull neutron doses

Figure 269 Average Dose Trends for TRIUMF (Non-Zero Results Only)

000

020

040

060

080

100

120

140

160

Dos

e (m

Sv)

Neutrons External Effective

Year

65

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 18: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

1 2 3 4 5 6 70 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

211 Bruce Nuclear Generating Stations

Bruce Power owns and operates the Bruce Nuclear Generating Stations located near Kincardine Ontario on the shore of Lake Huron

bull Bruce A consists of four nuclear reactors (units 1ndash4) and began operating in 1976 bull Bruce B has four nuclear reactors (units 5ndash8) and started operating in 1984

As part of its extensive recovery program in 1997 the sitersquos previous operator Ontario Hydro (now Ontario Power Generation) temporarily shut down all Bruce A reactors and maintained them in a guaranteed shutdown state Units 3 and 4 were later returned to service (in October 2003 and January 2004) while Units 1 and 2 remained in a guaranteed shutdown state

Figures 21ndash24 present dose information for the Bruce Nuclear Generating Stations from 2001 to 2007 Graphs do not distinguish between doses received at Bruce A versus Bruce B

Fig 21 Average Dose Trends for Bruce Nuclear Generating Stati on (Based o n N on-Zero R esults)

Dos

e (m

Sv)

4

35

3

25

2

15

1

05

0

Tritium Neutron External Effective

Year

13

Neutrons External Tritium

0 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 21 2 3 4 5 6 7

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

0

2

4

6

8

1

2

4

0

0

0

0

1

1

Figure 22 Average Dose Trends for Bruce Nuclear Generating Stati on (Based o n A ll Monitoring R esults)

16

)S

v(m

e os

D

Tritium Neutrons External Effective

Year

Figure 23 Collective Dose Trends for Bruce Nuclear Generating Stati on

8000

7000

6000

5000

4000

3000

2000

1000

0

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Year

14

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 24 Distribution of Effective Doses Among All Workers at Bruce Nuclear Generating Station

6000

5000

4000

3000

2000

1000

0 9 0 0

1-50 0 0 1 0 0 0 0 00 5 0 0 0

0-000

000 1-1 1-1 1-20 1-3 3gt0 0 0 05 0 5 01 1 2

Num

ber o

f Wor

kers

Dose Range (mSv)

15

1 2 3 4 5 6 7 0 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

212 Pickering Nuclear Generating Stations

Located in Pickering Ontario the Pickering Nuclear Generating Stations are owned and operated by Ontario Power Generation Two generating stations are located within one enclosure

bull Pickering A consists of four nuclear reactors (units 1 to 4) that began operating in 1971 bull Pickering B consists of four nuclear reactors (units 5 to 8) that began operating in 1982

As part of its extensive recovery program Ontario Hydro (now Ontario Power Generation) temporarily shut down all Pickering A reactors in 1997 and maintained them in a guaranteed shutdown state Unit 4 was restarted in September 2003 and Unit 1 was restarted in March 2005 Units 2 and 3 remain in a guaranteed shutdown state

Figures 25ndash28 present dose information for the Pickering Nuclear Generating Stations from 2001 to 2007 Graphs do not distinguish between doses received at Pickering A versus those received at Pickering B

Figure 25 Average Dose Trends for Pickering N uclear Generating Stati on (Based o n N on-Zero R esults)

25

2

15

1

05

0

)S

v(m

e os

D

Tritium Neutrons External Effective

Year

16

Tritium Neutrons External Effective

Neutrons External Tritium

1 2 3 4 5 6 70 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

1 2 3 4 5 6 7 0 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 26 Average Dose Trends for Pickering N uclear Generating Stati on (Based o n A ll Monitoring R esults)

12

1

08

06

04

02

0

Year

Figure 27 Collective Dose Trends for Pickering N uclear Generating Stati on

12000

10000

8000

6000

4000

2000

0

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

)

Sv

(me

osD

Year

17

2001 2002 2003 2004 2005 2006 2007

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 28 Distribution o f Effective Doses Among A ll Workers at Pickering Nuclear Generating Stati on

6000

5000

4000

3000

2000

1000

0

Num

ber o

f Wor

kers

Dose Range (mSv)

18

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

213 Darlington Nuclear Generating Station

Owned and operated by Ontario Power Generation the Darlington Nuclear Generating Station has four nuclear reactors the first of which began operating in 1989 The facility is located near Bowmanville on the shore of Lake Ontario

Figures 29ndash212 present dose information for the Darlington Nuclear Generating Station from 2001 to 2007

Figure 29 Average Dose Trends for Darlington N uclear Generating Stati on (Non- Zero R esults Only)

)S

v(m

e os

D

250

200

150

100

050

000

Year

19

Tritium Neutrons External Effective

Neutrons External Tritium

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 210 Average Dose Trends for Darlington N uclear Generating Stati on (All Monitoring R esults)

090

080

070

060

050

040

030

020

010

000

)S

v(m

e os

D

Year

Figure 211 Collective Dose Trends for Darlington N uclear Generating Stati on

4500

4000

3500

3000

2500

2000

1500

1000

500

0

)vSm-nosrep (es

Do

eiv

llect

Co

Year

20

2001 2002 2003 2004 2005 2006 2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 212 Distribution o f Effective Doses Among A ll Workers at Darlington Nuclear Generating Stati on

0

500

1000

1500

2000

2500

3000

3500

ers

ork

W of

be

r um

N

Dose Range (mSv)

21

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

214 Gentilly-2 Nuclear Generating Station

The Gentilly-2 Nuclear Generating Station owned and operated by Hydro-Queacutebec has a single reactor that began operating in 1982 The facility is located on the south shore of the St Lawrence River near Trois-Riviegraveres Queacutebec

Figures 213ndash216 present dose information for the Gentilly-2 Nuclear Generating Station from 2001 to 2007

Figure 213 Average Dose Trends for Gentilly-2 Nuclear Generating Stati on (Based o n N on-Zero R esults)

0

05

1

15

2

25

3

35

4

45

)S

v(m

e os

D

Year

22

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 214 Average Dose Trends for Gentilly-2 Nuclear Generating Stati on (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

)S

v(m

e os

D

Year

Figure 215 Collective Dose Trends for Gentilly-2 Nuclear Generating Stati on

0

500

1000

1500

2000

2500

3000

3500

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Neutrons

External

Tritium

Year

23

000-0

009

001-5

00

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 216 Distribution of Effective Doses Among All Workers at Gentilly-2 Nuclear Generating Station

2500

2000

1500

1000

500

0

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

24

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

215 Point Lepreau Nuclear Generating Station

The Point Lepreau Nuclear Generating Station has one reactor that began operating in 1982 Owned and operated by New Brunswick Power Nuclear the station is located in Point Lepreau New Brunswick about 40 km west of Saint John on the shores of the Bay of Fundy

Figures 217ndash220 present dose information for the Point Lepreau Nuclear Generating Station from 2001 to 2007

Figure 217 Average Dose Trends for Point Lepreau N uclear Generating Stati on (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

)S

v(m

e os

D

Tritium Neutron External Effective

Year

25

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 218 Average Dose Trends for Point Lepreau N uclear Generating Stati on (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

)S

v(m

e os

D

Tritium Neutrons External Effective

Year

Figure 219 Collective Dose Trends for Point Lepreau N uclear Generating Station

0

200

400

600

800

1000

1200

1400

1600

1800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Neutrons

External

Tritium

Year

26

0

1400

1200

1000

800

600

400

200

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 220 Distribution of Effective Doses Among All Workers at Point Lepreau Nuclear Generating Station

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

27

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

22 Uranium Mines and Mills This section presents dose information for mine and mill sites in the following regions

bull Cluff Lake (Section 221) bull McClean Lake (Section 222) bull McArthur River (Section 223) bull Key Lake (Section 224) bull Cigar Lake (Section 225) bull Rabbit Lake (Section 226)

Graphs indicate the following data for each site from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for uranium mines and mills

1 Effective doses are composed of the following reported components bull doses from photons (labelled on the charts as ldquoexternalrdquo) bull doses from radon progeny bull doses from long-lived radioactive dust bull doses from radon gas (in some cases)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of photon radon progeny long-lived radioactive dust and radon gas doses

3 The NDR lists radon progeny in working level months (WLM) For this report radon progeny exposures were converted4 to doses expressed in mSv

221 Cluff Lake Operation

The Cluff Lake mining facilities operated by AREVA Resources Canada Inc are located in northwestern Saskatchewan Work began in 1980 and ended in 2002 with the site now being decommissioned The site consisted of three open-pit and two underground mines a mill and a tailings management facility During 2005 and 2006 most of the infrastructure was removed and the affected areas were remediated

Figures 221ndash224 present dose information for the Cluff Lake operation from 2001 to 2007

4 Doses were converted using the International Commission on Radiation Protection (ICRP)rsquos conversion convention of 1 WLM = 5 mSv This convention was established in the ICRP publication Protection against Radon at Home and at Work (ICRP 65)

28

Long-lived radioactive dust Radon progeny External Effective

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 221 Average Dose Trends for the Cluff Lake Operation (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

Year

Figure 222 Average Dose Trends for the Cluff Lake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

200

Long-lived radioactive dust Radon progeny External Effective

)S

v(m

e os

D)

Sv

(me

osD

Year

29

600

500

400

300

200

100

0

External Radon progeny Long-lived radioactive dust

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 223 Collective Dose Trends for the Cluff Lake Operation s

erkor

of W

ber

Num

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Year

Figure 224 Distribution o f Effective Doses Among A ll Workers at the Cluff Lake Operation

0

20

40

60

80

100

120

140

160

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

30

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

222 McClean Lake Operation

AREVA Resources Canada Inc runs the McClean Lake mining operation in northeastern Saskatchewan It comprises open pit mines a mill and a tailings management facility Mining began in 1995 while milling started in 1999

Figures 225ndash228 present dose information for the McClean Lake operation from 2001 to 2007

Figure 225 Average Dose Trends for the McClean L ake Operation (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

31

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 226 Average Dose Trends for the McClean L ake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 227 Collective Dose Trends for the McClean L ake Operation

0

100

200

300

400

500

600

700

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External

Radon progeny

Long-lived radioactive dust

Year

32

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 228 Distribution o f Effective Doses Among A ll Workers at the McClean Lake Operation

0

100

200

300

400

500

600

700

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

33

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

223 McArthur River Operation

Cameco Corporation operates the McArthur River underground mine in north-central Saskatchewan Ore from the mine which began production in 1999 is processed at the Key Lake Mill located 80 km south of McArthur River

Figures 229ndash232 present dose information for the McArthur River operation from 2001 to 2007

Figure 229 Average Dose Trends for the McArthur River Operation (Based o n N on-Zero R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

34

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 230 Average Dose Trends for the McArthur River Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

Figure 231 Collective Dose Trends for the McArthur River Operation

0

200

400

600

800

1000

1200

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Radon gas External Radon progeny Long-lived radioactive dust

Year

35

00

0-000

9

001-5

00

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 232 Distribution o f Effective Doses Among A ll Workers at the McArthur River Operation

0

100

200

300

400

500

600

700

800

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

36

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

224 Key Lake Operation

Cameco Corporation operates mining facilities in Key Lake located in north-central Saskatchewan The Key Lake operation includes two mined-out open pit mines (used for tailings management) a mill and two dry tailings management facilities Mining began in 1983 and ceased in 1997 the mill continued to process ore from the McArthur River mine during the reporting period

Figures 233ndash236 present dose information for the Key Lake operation from 2001 to 2007

Figure 233 Average Dose Trends for the Key Lake Operation (Based o n N on-Zero R esults)

00

20

40

60

80

00

20

40

60

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

37

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

00

20

40

60

80

00

20

40

60

Figure 234 Average Dose Trends for the Key Lake Operation (Based o n A ll Monitoring R esults)

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 235 Collective Dose Trends for the Key Lake Operation

0

100

200

300

400

500

600

700

800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External Radon progeny Long-lived radioactive dust

Year

38

00

0-000

9

001-5

0

501-1

000

gt 1001

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 236 Distribution o f Effective Doses Among A ll Workers at the Key Lake Operation

0

200

400

600

800

1000

1200

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose Range (mSv)

39

se

(mS

v)o

D

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

225 Cigar Lake Operation

Cameco Corporation manages the Cigar Lake underground mine located in northern Saskatchewan at the southern end of Waterbury Lake The mine was under construction at the time of this reportrsquos publication Test mining in ore was carried out in 1991 1992 and 2000

Figures 237ndash240 present dose information for the Cigar Lake operation from

Figure 2 37 Average D ose T rends fo r th e C igar L ake O peration (Based on Non-Zero Results)

2001 to 2007

Year

000

005

010

015

020

025

Long-lived radioactive dust Radon Progeny External Effective

40

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 238 Average Dose Trends for the Cigar Lake Operation (Based on All Monitoring Results)

000

005

010

015

020

025

030

035

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny

External

Effective

Year

Figure 239 Collective Dose Trends for the Cigar Lake Operation

0

50

100

150

200

250

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

External Radon progeny Long-lived radioactive dust

Year

41

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 240 Distribution of Effective Doses Among All Workers at the Cigar Lake Operation

0

200

400

600

800

1000

1200

1400

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

42

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

226 Rabbit Lake Operation

Cameco Corporation owns and operates mining facilities in Rabbit Lake located in north-eastern Saskatchewan Facilities include an underground mine four mined-out open-pit mines a mill and two tailings management facilities Mining and milling began in 1975

Figures 241ndash244 present dose information for the Rabbit Lake operation from 2001 to 2007

Figure 241 Average Dose Trends for the Rabbit Lake Operation (Based on Non-Zero Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

43

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 242 Average Dose Trends for the Rabbit Lake Operation (Based on All Monitoring Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

Figure 243 Collective Dose Trends for the Rabbit Lake Operation

0

200

400

600

800

1000

1200

1400

1600

1800

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Radon gas External Radon progeny Long-lived radioactive dust

Year

44

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

gt300

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 244 Distribution of Effective Doses Among All Workers at the Rabbit Lake Operation

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

900

800

700

600

500

400

300

200

100

0

Dose (mSv)

45

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

23 Uranium Refineries This section presents data for the following two facilities

bull a uranium refining facility in Blind River (Section 231) bull a uranium conversion facility in Port Hope (Section 232)

Graphs indicate the following average doses at each facility from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Note on data for uranium refineries

1 Doses from photons from external sources are measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay and lung counting Historically while these internal doses have been measured they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

231 Blind River Refinery

Cameco Corporation owns and is licensed to operate a uranium refinery in Blind River Ontario The facility which began operating in 1983 converts uranium ore concentrate to uranium trioxide The uranium trioxide is shipped to Camecorsquos uranium conversion facility in Port Hope Ontario where it is processed into uranium dioxide (for use in the fabrication of fuel for nuclear reactors in Canada) or uranium hexafluoride (exported for enrichment and fabrication into fuel for nuclear power reactors around the world)

Figures 245ndash248 present dose information for the Blind River refinery from 2001 to 2007

46

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 245 Average Dose Trends for the Blind River Refinery (Based on Non-Zero Results)

0

05

1

15

2

25

Year

Figure 246 Average Dose Trends for the Blind River Refinery (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

47

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 247 Collective Dose Trends for the Blind River Refinery

0

50

100

150

200

250

300 C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 248 Distribution of Effective Doses Among All Workers at the Blind River Refinery

0

20

40

60

80

100

120

140

160

180

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

48

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

232 Port Hope Conversion Facility

Cameco Corporation owns and is licensed to operate a uranium conversion facility in Port Hope Ontario The facility processes uranium trioxide received from the refinery in Blind River into uranium dioxide and uranium hexafluoride

Figures 249ndash252 present dose information for the Port Hope uranium conversion facility from 2001 to 2007

Figure 249 Average Dose Trends for the Port Hope Conversion Facility (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

49

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 250 Average Dose Trends for the Port Hope Conversion Facility (Based on All Monitoring Results)

0

01

02

03

04

05

06

07

08

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 251 Collective Dose Trends for the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

50

000-0

009

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 252 Distribution of Effective Doses Among All Workers at the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

400

450

500

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

51

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

24 Fuel Fabrication Facilities This section presents data for three nuclear fuel fabrication facilities

bull Two facilities owned and operated by General Electric Canada Inc (Section 241) bull One facility in Port Hope operated by Zircatec Precision Industries (Section 242)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average doses

Notes on data for fuel fabrication facilities

1 Effective doses for the three facilities are composed of the following reported components bull dose from photons (labelled on the charts as ldquoexternalrdquo) bull doses from internal intakes of uranium dust (long-lived radioactive dust) from

uranium in air concentrations (for General Electricrsquos Toronto facility only)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components photon doses and doses from long-lived radioactive dust

241 General Electric Nuclear Fuel Facilities

General Electric Canada Inc operates two nuclear fuel facilities in Ontario

bull At the Toronto facility uranium dioxide pellets are produced from natural or depleted uranium dioxide powder

bull At the Peterborough facility uranium dioxide fuel bundles are created from the pellets produced at the Toronto facility

Figures 253ndash256 present dose information for General Electric Canada Incrsquos fuel fabrication facilities from 2001 to 2007 Graphs do not distinguish between the doses received at the Peterborough facility versus those at the Toronto facility

52

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 253 Average Dose Trends for the General Electric Fuel Facility (Based on Non-Zero Results Only)

0

05

1

15

2

25

3

35

Long Lived Radioactive Dust External Effective

Year

Figure 254 Average Dose Trends for the General Electric Fuel Facility (Based on All Monitoring Results)

0

05

1

15

2

25

3

Long Lived Radioactive Dust External Effective

Year

Dos

e (m

Sv)

Dos

e (m

Sv)

53

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 255 Collective Dose Trends for the General Electric Fuel Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Long Lived Radioactive Dust External

Year

Figure 256 Distribution of Effective Doses among all Workers at the General Electric Fuel Facility

0

10

20

30

40

50

60

70

80

90

100

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

54

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

242 Zircatec Nuclear Fuel Facility

Zircatec Precision Industries Inc operates a nuclear fuel facility in Port Hope Ontario where it makes fuel pellets from uranium dioxide powder received from Port Hopersquos uranium conversion facility The nuclear fuel facility also manufactures fuel bundles for nuclear reactors in Canada

Notes on data for the Zircatec nuclear fuel facility

1 Graphs indicate the following data bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of average effective doses

2 Doses from photons from external sources were measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay Historically although these internal doses have been measured and submitted to the CNSC they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

Figures 257ndash260 present dose information for the Zircatec nuclear fuel facility from 2001 to 2007

Figure 257 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on Non-Zero Results)

0

05

1

15

2

25

3

35

Effe

ctiv

e D

ose

(mS

v)

Year

55

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 258 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

18

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 259 Collective Dose Trends for the Zircatec Nuclear Fuel Facility

0

50

100

150

200

250

300

350

400

450

500

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

56

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 260 Distribution of Effective Doses Among All Workers at the Zircatec Nuclear Fuel Facility

300

Num

ber o

f Wor

kers

250

200

150

100

50

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

57

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

25 Research and Radioisotope Production Facilities This section presents dose information for the following research and radioisotope production facilities from 2001 to 2007

bull Chalk River Laboratories and Whiteshell Laboratories (Section 251) bull A radioisotope production facility operated by MDS Nordion (Section 252) bull The Tri-University Meson Facility (TRIUMF) (Section 253)

Note on data for research and radioisotope production facilities

1 Graphs indicate the following data for each facility bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of effective doses

251 Chalk River Laboratories and Whiteshell Laboratories

Atomic Energy of Canada Limited (AECL) owns and is licensed to operate Chalk River Laboratories and Whiteshell Laboratories

Situated in Renfrew County on the south shore of the Ottawa River the Chalk River Laboratories site hosts the National Research Universal Reactor along with numerous other facilities occupying some 160 buildings in an area of approximately 40 km2 Activities consist of radioisotope production for nuclear medicine testing and development of structural materials in support of power reactor operations fuel fabrication research and radioactive waste management and storage

The Whiteshell Laboratories site is located approximately 10 km west of Pinawa Manitoba and 100 km northeast of Winnipeg on the east bank of the Winnipeg River AECL established the laboratories for nuclear research and testing during the early 1960s and has since discontinued operations which are being decommissioned under a licence from the CNSC

Figures 261ndash264 present dose information for Chalk River Laboratories and Whiteshell Laboratories from 2001 to 2007

Notes on data for Chalk River Laboratories and Whiteshell Laboratories

1 Effective doses are composed of the following reported components bull external doses5 (from both photon and neutron doses) bull tritium doses

Due to issues with AECLrsquos in-house dosimetry management system neutron doses were not reported separately to the NDR during the reporting period As a result external doses from photons and neutrons were totaled The reporting discrepancy has since been rectified

58

5

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of external (photon and neutron) and tritium doses Intakes of other radionuclides occasionally occur and these radionuclides are not included here because their associated doses are very small For this reason certain collective doses in this report may have values slightly lower than the sum of their respective components as listed

Figure 261 Average Dose Trends for Chalk River and Whiteshell Laboratories (Non-Zero Results Only)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Tritium External Effective

Year

59

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 262 Average Dose Trends for Chalk River and Whiteshell Laboratories (All Monitoring Results)

000

020

040

060

080

100

120

Dos

e (m

Sv)

Tritium External Effective

Year

Figure 263 Collective Dose Trends for Chalk River and Whiteshell Laboratories

0

500

1000

1500

2000

2500

3000

3500

Col

lect

ive

Dos

e (p

erso

n- m

Sv)

External Tritium

Year

60

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 264 Distribution of Effective Doses Among All Workers at Chalk River and Whiteshell Laboratories

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

3500

3000

2500

2000

1500

1000

500

Dose (mSv)

61

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

252 MDS Nordion (Nuclear Substance Processing Facility and Canadian Irradiation Centre)

MDS Nordion owns and operates a nuclear substance processing facility in Ottawa Ontario where it processes unsealed radioisotopes and manufactures sealed radiation sources In operation since the early 1970s the facility was purchased by Nordion International in 1991

In cooperation with the Universiteacute du Queacutebecrsquos Institut Armand-Frappier MDS Nordion also operates the Canadian Irradiation Centre which conducts various irradiation services which include training testing and development The centre is located in Laval Quebec on the Universiteacute du Queacutebec campus

Figures 265ndash268 present dose information for MDS Nordionrsquos Ottawa nuclear substance processing facility and for the Canadian Irradiation Centre from 2001 to 2007

Notes on data for MDS Nordionrsquos nuclear substance processing facility and the Canadian Irradiation Centre

1 Doses from photons from external sources were measured and reported to the NDR MDS Nordion also has a routine thyroid monitoring program very occasionally small recordable doses of radiation have occurred from thyroid uptake of iodine The resulting doses have not been historically submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided

Figure 265 Average Dose Trends for MDS Nordion (Based on Non-Zero Results)

0

05

1

15

2

25

Effe

ctiv

e D

ose

(mS

v)

Year

62

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 266 Average Dose Trends for MDS Nordion (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

Figure 267 Collective Dose Trends for MDS Nordion

0

100

200

300

400

500

600

700

800

Year

63

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 268 Distribution of Effective Doses Among All Workers at MDS Nordion

0

5 0

1 0 0

1 5 0

2 0 0

2 5 0

3 0 0

3 5 0

4 0 0

4 5 0

5 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

64

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

253 Tri-University Meson Facility

The Tri-University Meson facility (TRIUMF) is situated in Vancouver on the campus of the University of British Columbia TRIUMF which began operating in the early 1970s with one cyclotron now has two cyclotrons and associated laboratories for research and radioisotope production The laboratory provides research facilities for Canadian and international users and also produces radioisotopes which are used by medical facilities and by a commercial organization (MDS Nordion) MDS Nordion staff also work at the TRIUMF site however MDS Nordion oversees this work and has its own radiation protection program

Figures 269ndash272 present dose information for the TRIUMF facility from 2001 to 2007 Please note that data sets do not distinguish between doses received by TRIUMF staff and MDS Nordion staff who work on the site as the data for these two groups was submitted collectively to the NDR for the reporting period shown Future data for each group will be submitted separately to the NDR

Note on data for TRIUMF

1 Effective doses are composed of the following reported components bull doses from photons (labeled as ldquoexternalrdquo in the charts) bull neutron doses

Figure 269 Average Dose Trends for TRIUMF (Non-Zero Results Only)

000

020

040

060

080

100

120

140

160

Dos

e (m

Sv)

Neutrons External Effective

Year

65

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 19: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

Neutrons External Tritium

0 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 21 2 3 4 5 6 7

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

0

2

4

6

8

1

2

4

0

0

0

0

1

1

Figure 22 Average Dose Trends for Bruce Nuclear Generating Stati on (Based o n A ll Monitoring R esults)

16

)S

v(m

e os

D

Tritium Neutrons External Effective

Year

Figure 23 Collective Dose Trends for Bruce Nuclear Generating Stati on

8000

7000

6000

5000

4000

3000

2000

1000

0

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Year

14

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 24 Distribution of Effective Doses Among All Workers at Bruce Nuclear Generating Station

6000

5000

4000

3000

2000

1000

0 9 0 0

1-50 0 0 1 0 0 0 0 00 5 0 0 0

0-000

000 1-1 1-1 1-20 1-3 3gt0 0 0 05 0 5 01 1 2

Num

ber o

f Wor

kers

Dose Range (mSv)

15

1 2 3 4 5 6 7 0 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

212 Pickering Nuclear Generating Stations

Located in Pickering Ontario the Pickering Nuclear Generating Stations are owned and operated by Ontario Power Generation Two generating stations are located within one enclosure

bull Pickering A consists of four nuclear reactors (units 1 to 4) that began operating in 1971 bull Pickering B consists of four nuclear reactors (units 5 to 8) that began operating in 1982

As part of its extensive recovery program Ontario Hydro (now Ontario Power Generation) temporarily shut down all Pickering A reactors in 1997 and maintained them in a guaranteed shutdown state Unit 4 was restarted in September 2003 and Unit 1 was restarted in March 2005 Units 2 and 3 remain in a guaranteed shutdown state

Figures 25ndash28 present dose information for the Pickering Nuclear Generating Stations from 2001 to 2007 Graphs do not distinguish between doses received at Pickering A versus those received at Pickering B

Figure 25 Average Dose Trends for Pickering N uclear Generating Stati on (Based o n N on-Zero R esults)

25

2

15

1

05

0

)S

v(m

e os

D

Tritium Neutrons External Effective

Year

16

Tritium Neutrons External Effective

Neutrons External Tritium

1 2 3 4 5 6 70 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

1 2 3 4 5 6 7 0 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 26 Average Dose Trends for Pickering N uclear Generating Stati on (Based o n A ll Monitoring R esults)

12

1

08

06

04

02

0

Year

Figure 27 Collective Dose Trends for Pickering N uclear Generating Stati on

12000

10000

8000

6000

4000

2000

0

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

)

Sv

(me

osD

Year

17

2001 2002 2003 2004 2005 2006 2007

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 28 Distribution o f Effective Doses Among A ll Workers at Pickering Nuclear Generating Stati on

6000

5000

4000

3000

2000

1000

0

Num

ber o

f Wor

kers

Dose Range (mSv)

18

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

213 Darlington Nuclear Generating Station

Owned and operated by Ontario Power Generation the Darlington Nuclear Generating Station has four nuclear reactors the first of which began operating in 1989 The facility is located near Bowmanville on the shore of Lake Ontario

Figures 29ndash212 present dose information for the Darlington Nuclear Generating Station from 2001 to 2007

Figure 29 Average Dose Trends for Darlington N uclear Generating Stati on (Non- Zero R esults Only)

)S

v(m

e os

D

250

200

150

100

050

000

Year

19

Tritium Neutrons External Effective

Neutrons External Tritium

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 210 Average Dose Trends for Darlington N uclear Generating Stati on (All Monitoring R esults)

090

080

070

060

050

040

030

020

010

000

)S

v(m

e os

D

Year

Figure 211 Collective Dose Trends for Darlington N uclear Generating Stati on

4500

4000

3500

3000

2500

2000

1500

1000

500

0

)vSm-nosrep (es

Do

eiv

llect

Co

Year

20

2001 2002 2003 2004 2005 2006 2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 212 Distribution o f Effective Doses Among A ll Workers at Darlington Nuclear Generating Stati on

0

500

1000

1500

2000

2500

3000

3500

ers

ork

W of

be

r um

N

Dose Range (mSv)

21

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

214 Gentilly-2 Nuclear Generating Station

The Gentilly-2 Nuclear Generating Station owned and operated by Hydro-Queacutebec has a single reactor that began operating in 1982 The facility is located on the south shore of the St Lawrence River near Trois-Riviegraveres Queacutebec

Figures 213ndash216 present dose information for the Gentilly-2 Nuclear Generating Station from 2001 to 2007

Figure 213 Average Dose Trends for Gentilly-2 Nuclear Generating Stati on (Based o n N on-Zero R esults)

0

05

1

15

2

25

3

35

4

45

)S

v(m

e os

D

Year

22

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 214 Average Dose Trends for Gentilly-2 Nuclear Generating Stati on (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

)S

v(m

e os

D

Year

Figure 215 Collective Dose Trends for Gentilly-2 Nuclear Generating Stati on

0

500

1000

1500

2000

2500

3000

3500

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Neutrons

External

Tritium

Year

23

000-0

009

001-5

00

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 216 Distribution of Effective Doses Among All Workers at Gentilly-2 Nuclear Generating Station

2500

2000

1500

1000

500

0

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

24

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

215 Point Lepreau Nuclear Generating Station

The Point Lepreau Nuclear Generating Station has one reactor that began operating in 1982 Owned and operated by New Brunswick Power Nuclear the station is located in Point Lepreau New Brunswick about 40 km west of Saint John on the shores of the Bay of Fundy

Figures 217ndash220 present dose information for the Point Lepreau Nuclear Generating Station from 2001 to 2007

Figure 217 Average Dose Trends for Point Lepreau N uclear Generating Stati on (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

)S

v(m

e os

D

Tritium Neutron External Effective

Year

25

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 218 Average Dose Trends for Point Lepreau N uclear Generating Stati on (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

)S

v(m

e os

D

Tritium Neutrons External Effective

Year

Figure 219 Collective Dose Trends for Point Lepreau N uclear Generating Station

0

200

400

600

800

1000

1200

1400

1600

1800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Neutrons

External

Tritium

Year

26

0

1400

1200

1000

800

600

400

200

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 220 Distribution of Effective Doses Among All Workers at Point Lepreau Nuclear Generating Station

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

27

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

22 Uranium Mines and Mills This section presents dose information for mine and mill sites in the following regions

bull Cluff Lake (Section 221) bull McClean Lake (Section 222) bull McArthur River (Section 223) bull Key Lake (Section 224) bull Cigar Lake (Section 225) bull Rabbit Lake (Section 226)

Graphs indicate the following data for each site from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for uranium mines and mills

1 Effective doses are composed of the following reported components bull doses from photons (labelled on the charts as ldquoexternalrdquo) bull doses from radon progeny bull doses from long-lived radioactive dust bull doses from radon gas (in some cases)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of photon radon progeny long-lived radioactive dust and radon gas doses

3 The NDR lists radon progeny in working level months (WLM) For this report radon progeny exposures were converted4 to doses expressed in mSv

221 Cluff Lake Operation

The Cluff Lake mining facilities operated by AREVA Resources Canada Inc are located in northwestern Saskatchewan Work began in 1980 and ended in 2002 with the site now being decommissioned The site consisted of three open-pit and two underground mines a mill and a tailings management facility During 2005 and 2006 most of the infrastructure was removed and the affected areas were remediated

Figures 221ndash224 present dose information for the Cluff Lake operation from 2001 to 2007

4 Doses were converted using the International Commission on Radiation Protection (ICRP)rsquos conversion convention of 1 WLM = 5 mSv This convention was established in the ICRP publication Protection against Radon at Home and at Work (ICRP 65)

28

Long-lived radioactive dust Radon progeny External Effective

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 221 Average Dose Trends for the Cluff Lake Operation (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

Year

Figure 222 Average Dose Trends for the Cluff Lake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

200

Long-lived radioactive dust Radon progeny External Effective

)S

v(m

e os

D)

Sv

(me

osD

Year

29

600

500

400

300

200

100

0

External Radon progeny Long-lived radioactive dust

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 223 Collective Dose Trends for the Cluff Lake Operation s

erkor

of W

ber

Num

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Year

Figure 224 Distribution o f Effective Doses Among A ll Workers at the Cluff Lake Operation

0

20

40

60

80

100

120

140

160

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

30

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

222 McClean Lake Operation

AREVA Resources Canada Inc runs the McClean Lake mining operation in northeastern Saskatchewan It comprises open pit mines a mill and a tailings management facility Mining began in 1995 while milling started in 1999

Figures 225ndash228 present dose information for the McClean Lake operation from 2001 to 2007

Figure 225 Average Dose Trends for the McClean L ake Operation (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

31

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 226 Average Dose Trends for the McClean L ake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 227 Collective Dose Trends for the McClean L ake Operation

0

100

200

300

400

500

600

700

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External

Radon progeny

Long-lived radioactive dust

Year

32

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 228 Distribution o f Effective Doses Among A ll Workers at the McClean Lake Operation

0

100

200

300

400

500

600

700

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

33

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

223 McArthur River Operation

Cameco Corporation operates the McArthur River underground mine in north-central Saskatchewan Ore from the mine which began production in 1999 is processed at the Key Lake Mill located 80 km south of McArthur River

Figures 229ndash232 present dose information for the McArthur River operation from 2001 to 2007

Figure 229 Average Dose Trends for the McArthur River Operation (Based o n N on-Zero R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

34

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 230 Average Dose Trends for the McArthur River Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

Figure 231 Collective Dose Trends for the McArthur River Operation

0

200

400

600

800

1000

1200

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Radon gas External Radon progeny Long-lived radioactive dust

Year

35

00

0-000

9

001-5

00

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 232 Distribution o f Effective Doses Among A ll Workers at the McArthur River Operation

0

100

200

300

400

500

600

700

800

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

36

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

224 Key Lake Operation

Cameco Corporation operates mining facilities in Key Lake located in north-central Saskatchewan The Key Lake operation includes two mined-out open pit mines (used for tailings management) a mill and two dry tailings management facilities Mining began in 1983 and ceased in 1997 the mill continued to process ore from the McArthur River mine during the reporting period

Figures 233ndash236 present dose information for the Key Lake operation from 2001 to 2007

Figure 233 Average Dose Trends for the Key Lake Operation (Based o n N on-Zero R esults)

00

20

40

60

80

00

20

40

60

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

37

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

00

20

40

60

80

00

20

40

60

Figure 234 Average Dose Trends for the Key Lake Operation (Based o n A ll Monitoring R esults)

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 235 Collective Dose Trends for the Key Lake Operation

0

100

200

300

400

500

600

700

800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External Radon progeny Long-lived radioactive dust

Year

38

00

0-000

9

001-5

0

501-1

000

gt 1001

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 236 Distribution o f Effective Doses Among A ll Workers at the Key Lake Operation

0

200

400

600

800

1000

1200

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose Range (mSv)

39

se

(mS

v)o

D

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

225 Cigar Lake Operation

Cameco Corporation manages the Cigar Lake underground mine located in northern Saskatchewan at the southern end of Waterbury Lake The mine was under construction at the time of this reportrsquos publication Test mining in ore was carried out in 1991 1992 and 2000

Figures 237ndash240 present dose information for the Cigar Lake operation from

Figure 2 37 Average D ose T rends fo r th e C igar L ake O peration (Based on Non-Zero Results)

2001 to 2007

Year

000

005

010

015

020

025

Long-lived radioactive dust Radon Progeny External Effective

40

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 238 Average Dose Trends for the Cigar Lake Operation (Based on All Monitoring Results)

000

005

010

015

020

025

030

035

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny

External

Effective

Year

Figure 239 Collective Dose Trends for the Cigar Lake Operation

0

50

100

150

200

250

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

External Radon progeny Long-lived radioactive dust

Year

41

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 240 Distribution of Effective Doses Among All Workers at the Cigar Lake Operation

0

200

400

600

800

1000

1200

1400

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

42

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

226 Rabbit Lake Operation

Cameco Corporation owns and operates mining facilities in Rabbit Lake located in north-eastern Saskatchewan Facilities include an underground mine four mined-out open-pit mines a mill and two tailings management facilities Mining and milling began in 1975

Figures 241ndash244 present dose information for the Rabbit Lake operation from 2001 to 2007

Figure 241 Average Dose Trends for the Rabbit Lake Operation (Based on Non-Zero Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

43

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 242 Average Dose Trends for the Rabbit Lake Operation (Based on All Monitoring Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

Figure 243 Collective Dose Trends for the Rabbit Lake Operation

0

200

400

600

800

1000

1200

1400

1600

1800

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Radon gas External Radon progeny Long-lived radioactive dust

Year

44

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

gt300

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 244 Distribution of Effective Doses Among All Workers at the Rabbit Lake Operation

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

900

800

700

600

500

400

300

200

100

0

Dose (mSv)

45

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

23 Uranium Refineries This section presents data for the following two facilities

bull a uranium refining facility in Blind River (Section 231) bull a uranium conversion facility in Port Hope (Section 232)

Graphs indicate the following average doses at each facility from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Note on data for uranium refineries

1 Doses from photons from external sources are measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay and lung counting Historically while these internal doses have been measured they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

231 Blind River Refinery

Cameco Corporation owns and is licensed to operate a uranium refinery in Blind River Ontario The facility which began operating in 1983 converts uranium ore concentrate to uranium trioxide The uranium trioxide is shipped to Camecorsquos uranium conversion facility in Port Hope Ontario where it is processed into uranium dioxide (for use in the fabrication of fuel for nuclear reactors in Canada) or uranium hexafluoride (exported for enrichment and fabrication into fuel for nuclear power reactors around the world)

Figures 245ndash248 present dose information for the Blind River refinery from 2001 to 2007

46

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 245 Average Dose Trends for the Blind River Refinery (Based on Non-Zero Results)

0

05

1

15

2

25

Year

Figure 246 Average Dose Trends for the Blind River Refinery (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

47

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 247 Collective Dose Trends for the Blind River Refinery

0

50

100

150

200

250

300 C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 248 Distribution of Effective Doses Among All Workers at the Blind River Refinery

0

20

40

60

80

100

120

140

160

180

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

48

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

232 Port Hope Conversion Facility

Cameco Corporation owns and is licensed to operate a uranium conversion facility in Port Hope Ontario The facility processes uranium trioxide received from the refinery in Blind River into uranium dioxide and uranium hexafluoride

Figures 249ndash252 present dose information for the Port Hope uranium conversion facility from 2001 to 2007

Figure 249 Average Dose Trends for the Port Hope Conversion Facility (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

49

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 250 Average Dose Trends for the Port Hope Conversion Facility (Based on All Monitoring Results)

0

01

02

03

04

05

06

07

08

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 251 Collective Dose Trends for the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

50

000-0

009

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 252 Distribution of Effective Doses Among All Workers at the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

400

450

500

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

51

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

24 Fuel Fabrication Facilities This section presents data for three nuclear fuel fabrication facilities

bull Two facilities owned and operated by General Electric Canada Inc (Section 241) bull One facility in Port Hope operated by Zircatec Precision Industries (Section 242)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average doses

Notes on data for fuel fabrication facilities

1 Effective doses for the three facilities are composed of the following reported components bull dose from photons (labelled on the charts as ldquoexternalrdquo) bull doses from internal intakes of uranium dust (long-lived radioactive dust) from

uranium in air concentrations (for General Electricrsquos Toronto facility only)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components photon doses and doses from long-lived radioactive dust

241 General Electric Nuclear Fuel Facilities

General Electric Canada Inc operates two nuclear fuel facilities in Ontario

bull At the Toronto facility uranium dioxide pellets are produced from natural or depleted uranium dioxide powder

bull At the Peterborough facility uranium dioxide fuel bundles are created from the pellets produced at the Toronto facility

Figures 253ndash256 present dose information for General Electric Canada Incrsquos fuel fabrication facilities from 2001 to 2007 Graphs do not distinguish between the doses received at the Peterborough facility versus those at the Toronto facility

52

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 253 Average Dose Trends for the General Electric Fuel Facility (Based on Non-Zero Results Only)

0

05

1

15

2

25

3

35

Long Lived Radioactive Dust External Effective

Year

Figure 254 Average Dose Trends for the General Electric Fuel Facility (Based on All Monitoring Results)

0

05

1

15

2

25

3

Long Lived Radioactive Dust External Effective

Year

Dos

e (m

Sv)

Dos

e (m

Sv)

53

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 255 Collective Dose Trends for the General Electric Fuel Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Long Lived Radioactive Dust External

Year

Figure 256 Distribution of Effective Doses among all Workers at the General Electric Fuel Facility

0

10

20

30

40

50

60

70

80

90

100

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

54

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

242 Zircatec Nuclear Fuel Facility

Zircatec Precision Industries Inc operates a nuclear fuel facility in Port Hope Ontario where it makes fuel pellets from uranium dioxide powder received from Port Hopersquos uranium conversion facility The nuclear fuel facility also manufactures fuel bundles for nuclear reactors in Canada

Notes on data for the Zircatec nuclear fuel facility

1 Graphs indicate the following data bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of average effective doses

2 Doses from photons from external sources were measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay Historically although these internal doses have been measured and submitted to the CNSC they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

Figures 257ndash260 present dose information for the Zircatec nuclear fuel facility from 2001 to 2007

Figure 257 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on Non-Zero Results)

0

05

1

15

2

25

3

35

Effe

ctiv

e D

ose

(mS

v)

Year

55

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 258 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

18

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 259 Collective Dose Trends for the Zircatec Nuclear Fuel Facility

0

50

100

150

200

250

300

350

400

450

500

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

56

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 260 Distribution of Effective Doses Among All Workers at the Zircatec Nuclear Fuel Facility

300

Num

ber o

f Wor

kers

250

200

150

100

50

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

57

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

25 Research and Radioisotope Production Facilities This section presents dose information for the following research and radioisotope production facilities from 2001 to 2007

bull Chalk River Laboratories and Whiteshell Laboratories (Section 251) bull A radioisotope production facility operated by MDS Nordion (Section 252) bull The Tri-University Meson Facility (TRIUMF) (Section 253)

Note on data for research and radioisotope production facilities

1 Graphs indicate the following data for each facility bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of effective doses

251 Chalk River Laboratories and Whiteshell Laboratories

Atomic Energy of Canada Limited (AECL) owns and is licensed to operate Chalk River Laboratories and Whiteshell Laboratories

Situated in Renfrew County on the south shore of the Ottawa River the Chalk River Laboratories site hosts the National Research Universal Reactor along with numerous other facilities occupying some 160 buildings in an area of approximately 40 km2 Activities consist of radioisotope production for nuclear medicine testing and development of structural materials in support of power reactor operations fuel fabrication research and radioactive waste management and storage

The Whiteshell Laboratories site is located approximately 10 km west of Pinawa Manitoba and 100 km northeast of Winnipeg on the east bank of the Winnipeg River AECL established the laboratories for nuclear research and testing during the early 1960s and has since discontinued operations which are being decommissioned under a licence from the CNSC

Figures 261ndash264 present dose information for Chalk River Laboratories and Whiteshell Laboratories from 2001 to 2007

Notes on data for Chalk River Laboratories and Whiteshell Laboratories

1 Effective doses are composed of the following reported components bull external doses5 (from both photon and neutron doses) bull tritium doses

Due to issues with AECLrsquos in-house dosimetry management system neutron doses were not reported separately to the NDR during the reporting period As a result external doses from photons and neutrons were totaled The reporting discrepancy has since been rectified

58

5

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of external (photon and neutron) and tritium doses Intakes of other radionuclides occasionally occur and these radionuclides are not included here because their associated doses are very small For this reason certain collective doses in this report may have values slightly lower than the sum of their respective components as listed

Figure 261 Average Dose Trends for Chalk River and Whiteshell Laboratories (Non-Zero Results Only)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Tritium External Effective

Year

59

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 262 Average Dose Trends for Chalk River and Whiteshell Laboratories (All Monitoring Results)

000

020

040

060

080

100

120

Dos

e (m

Sv)

Tritium External Effective

Year

Figure 263 Collective Dose Trends for Chalk River and Whiteshell Laboratories

0

500

1000

1500

2000

2500

3000

3500

Col

lect

ive

Dos

e (p

erso

n- m

Sv)

External Tritium

Year

60

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 264 Distribution of Effective Doses Among All Workers at Chalk River and Whiteshell Laboratories

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

3500

3000

2500

2000

1500

1000

500

Dose (mSv)

61

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

252 MDS Nordion (Nuclear Substance Processing Facility and Canadian Irradiation Centre)

MDS Nordion owns and operates a nuclear substance processing facility in Ottawa Ontario where it processes unsealed radioisotopes and manufactures sealed radiation sources In operation since the early 1970s the facility was purchased by Nordion International in 1991

In cooperation with the Universiteacute du Queacutebecrsquos Institut Armand-Frappier MDS Nordion also operates the Canadian Irradiation Centre which conducts various irradiation services which include training testing and development The centre is located in Laval Quebec on the Universiteacute du Queacutebec campus

Figures 265ndash268 present dose information for MDS Nordionrsquos Ottawa nuclear substance processing facility and for the Canadian Irradiation Centre from 2001 to 2007

Notes on data for MDS Nordionrsquos nuclear substance processing facility and the Canadian Irradiation Centre

1 Doses from photons from external sources were measured and reported to the NDR MDS Nordion also has a routine thyroid monitoring program very occasionally small recordable doses of radiation have occurred from thyroid uptake of iodine The resulting doses have not been historically submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided

Figure 265 Average Dose Trends for MDS Nordion (Based on Non-Zero Results)

0

05

1

15

2

25

Effe

ctiv

e D

ose

(mS

v)

Year

62

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 266 Average Dose Trends for MDS Nordion (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

Figure 267 Collective Dose Trends for MDS Nordion

0

100

200

300

400

500

600

700

800

Year

63

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 268 Distribution of Effective Doses Among All Workers at MDS Nordion

0

5 0

1 0 0

1 5 0

2 0 0

2 5 0

3 0 0

3 5 0

4 0 0

4 5 0

5 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

64

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

253 Tri-University Meson Facility

The Tri-University Meson facility (TRIUMF) is situated in Vancouver on the campus of the University of British Columbia TRIUMF which began operating in the early 1970s with one cyclotron now has two cyclotrons and associated laboratories for research and radioisotope production The laboratory provides research facilities for Canadian and international users and also produces radioisotopes which are used by medical facilities and by a commercial organization (MDS Nordion) MDS Nordion staff also work at the TRIUMF site however MDS Nordion oversees this work and has its own radiation protection program

Figures 269ndash272 present dose information for the TRIUMF facility from 2001 to 2007 Please note that data sets do not distinguish between doses received by TRIUMF staff and MDS Nordion staff who work on the site as the data for these two groups was submitted collectively to the NDR for the reporting period shown Future data for each group will be submitted separately to the NDR

Note on data for TRIUMF

1 Effective doses are composed of the following reported components bull doses from photons (labeled as ldquoexternalrdquo in the charts) bull neutron doses

Figure 269 Average Dose Trends for TRIUMF (Non-Zero Results Only)

000

020

040

060

080

100

120

140

160

Dos

e (m

Sv)

Neutrons External Effective

Year

65

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 20: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 24 Distribution of Effective Doses Among All Workers at Bruce Nuclear Generating Station

6000

5000

4000

3000

2000

1000

0 9 0 0

1-50 0 0 1 0 0 0 0 00 5 0 0 0

0-000

000 1-1 1-1 1-20 1-3 3gt0 0 0 05 0 5 01 1 2

Num

ber o

f Wor

kers

Dose Range (mSv)

15

1 2 3 4 5 6 7 0 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

212 Pickering Nuclear Generating Stations

Located in Pickering Ontario the Pickering Nuclear Generating Stations are owned and operated by Ontario Power Generation Two generating stations are located within one enclosure

bull Pickering A consists of four nuclear reactors (units 1 to 4) that began operating in 1971 bull Pickering B consists of four nuclear reactors (units 5 to 8) that began operating in 1982

As part of its extensive recovery program Ontario Hydro (now Ontario Power Generation) temporarily shut down all Pickering A reactors in 1997 and maintained them in a guaranteed shutdown state Unit 4 was restarted in September 2003 and Unit 1 was restarted in March 2005 Units 2 and 3 remain in a guaranteed shutdown state

Figures 25ndash28 present dose information for the Pickering Nuclear Generating Stations from 2001 to 2007 Graphs do not distinguish between doses received at Pickering A versus those received at Pickering B

Figure 25 Average Dose Trends for Pickering N uclear Generating Stati on (Based o n N on-Zero R esults)

25

2

15

1

05

0

)S

v(m

e os

D

Tritium Neutrons External Effective

Year

16

Tritium Neutrons External Effective

Neutrons External Tritium

1 2 3 4 5 6 70 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

1 2 3 4 5 6 7 0 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 26 Average Dose Trends for Pickering N uclear Generating Stati on (Based o n A ll Monitoring R esults)

12

1

08

06

04

02

0

Year

Figure 27 Collective Dose Trends for Pickering N uclear Generating Stati on

12000

10000

8000

6000

4000

2000

0

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

)

Sv

(me

osD

Year

17

2001 2002 2003 2004 2005 2006 2007

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 28 Distribution o f Effective Doses Among A ll Workers at Pickering Nuclear Generating Stati on

6000

5000

4000

3000

2000

1000

0

Num

ber o

f Wor

kers

Dose Range (mSv)

18

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

213 Darlington Nuclear Generating Station

Owned and operated by Ontario Power Generation the Darlington Nuclear Generating Station has four nuclear reactors the first of which began operating in 1989 The facility is located near Bowmanville on the shore of Lake Ontario

Figures 29ndash212 present dose information for the Darlington Nuclear Generating Station from 2001 to 2007

Figure 29 Average Dose Trends for Darlington N uclear Generating Stati on (Non- Zero R esults Only)

)S

v(m

e os

D

250

200

150

100

050

000

Year

19

Tritium Neutrons External Effective

Neutrons External Tritium

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 210 Average Dose Trends for Darlington N uclear Generating Stati on (All Monitoring R esults)

090

080

070

060

050

040

030

020

010

000

)S

v(m

e os

D

Year

Figure 211 Collective Dose Trends for Darlington N uclear Generating Stati on

4500

4000

3500

3000

2500

2000

1500

1000

500

0

)vSm-nosrep (es

Do

eiv

llect

Co

Year

20

2001 2002 2003 2004 2005 2006 2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 212 Distribution o f Effective Doses Among A ll Workers at Darlington Nuclear Generating Stati on

0

500

1000

1500

2000

2500

3000

3500

ers

ork

W of

be

r um

N

Dose Range (mSv)

21

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

214 Gentilly-2 Nuclear Generating Station

The Gentilly-2 Nuclear Generating Station owned and operated by Hydro-Queacutebec has a single reactor that began operating in 1982 The facility is located on the south shore of the St Lawrence River near Trois-Riviegraveres Queacutebec

Figures 213ndash216 present dose information for the Gentilly-2 Nuclear Generating Station from 2001 to 2007

Figure 213 Average Dose Trends for Gentilly-2 Nuclear Generating Stati on (Based o n N on-Zero R esults)

0

05

1

15

2

25

3

35

4

45

)S

v(m

e os

D

Year

22

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 214 Average Dose Trends for Gentilly-2 Nuclear Generating Stati on (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

)S

v(m

e os

D

Year

Figure 215 Collective Dose Trends for Gentilly-2 Nuclear Generating Stati on

0

500

1000

1500

2000

2500

3000

3500

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Neutrons

External

Tritium

Year

23

000-0

009

001-5

00

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 216 Distribution of Effective Doses Among All Workers at Gentilly-2 Nuclear Generating Station

2500

2000

1500

1000

500

0

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

24

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

215 Point Lepreau Nuclear Generating Station

The Point Lepreau Nuclear Generating Station has one reactor that began operating in 1982 Owned and operated by New Brunswick Power Nuclear the station is located in Point Lepreau New Brunswick about 40 km west of Saint John on the shores of the Bay of Fundy

Figures 217ndash220 present dose information for the Point Lepreau Nuclear Generating Station from 2001 to 2007

Figure 217 Average Dose Trends for Point Lepreau N uclear Generating Stati on (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

)S

v(m

e os

D

Tritium Neutron External Effective

Year

25

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 218 Average Dose Trends for Point Lepreau N uclear Generating Stati on (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

)S

v(m

e os

D

Tritium Neutrons External Effective

Year

Figure 219 Collective Dose Trends for Point Lepreau N uclear Generating Station

0

200

400

600

800

1000

1200

1400

1600

1800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Neutrons

External

Tritium

Year

26

0

1400

1200

1000

800

600

400

200

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 220 Distribution of Effective Doses Among All Workers at Point Lepreau Nuclear Generating Station

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

27

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

22 Uranium Mines and Mills This section presents dose information for mine and mill sites in the following regions

bull Cluff Lake (Section 221) bull McClean Lake (Section 222) bull McArthur River (Section 223) bull Key Lake (Section 224) bull Cigar Lake (Section 225) bull Rabbit Lake (Section 226)

Graphs indicate the following data for each site from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for uranium mines and mills

1 Effective doses are composed of the following reported components bull doses from photons (labelled on the charts as ldquoexternalrdquo) bull doses from radon progeny bull doses from long-lived radioactive dust bull doses from radon gas (in some cases)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of photon radon progeny long-lived radioactive dust and radon gas doses

3 The NDR lists radon progeny in working level months (WLM) For this report radon progeny exposures were converted4 to doses expressed in mSv

221 Cluff Lake Operation

The Cluff Lake mining facilities operated by AREVA Resources Canada Inc are located in northwestern Saskatchewan Work began in 1980 and ended in 2002 with the site now being decommissioned The site consisted of three open-pit and two underground mines a mill and a tailings management facility During 2005 and 2006 most of the infrastructure was removed and the affected areas were remediated

Figures 221ndash224 present dose information for the Cluff Lake operation from 2001 to 2007

4 Doses were converted using the International Commission on Radiation Protection (ICRP)rsquos conversion convention of 1 WLM = 5 mSv This convention was established in the ICRP publication Protection against Radon at Home and at Work (ICRP 65)

28

Long-lived radioactive dust Radon progeny External Effective

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 221 Average Dose Trends for the Cluff Lake Operation (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

Year

Figure 222 Average Dose Trends for the Cluff Lake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

200

Long-lived radioactive dust Radon progeny External Effective

)S

v(m

e os

D)

Sv

(me

osD

Year

29

600

500

400

300

200

100

0

External Radon progeny Long-lived radioactive dust

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 223 Collective Dose Trends for the Cluff Lake Operation s

erkor

of W

ber

Num

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Year

Figure 224 Distribution o f Effective Doses Among A ll Workers at the Cluff Lake Operation

0

20

40

60

80

100

120

140

160

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

30

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

222 McClean Lake Operation

AREVA Resources Canada Inc runs the McClean Lake mining operation in northeastern Saskatchewan It comprises open pit mines a mill and a tailings management facility Mining began in 1995 while milling started in 1999

Figures 225ndash228 present dose information for the McClean Lake operation from 2001 to 2007

Figure 225 Average Dose Trends for the McClean L ake Operation (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

31

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 226 Average Dose Trends for the McClean L ake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 227 Collective Dose Trends for the McClean L ake Operation

0

100

200

300

400

500

600

700

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External

Radon progeny

Long-lived radioactive dust

Year

32

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 228 Distribution o f Effective Doses Among A ll Workers at the McClean Lake Operation

0

100

200

300

400

500

600

700

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

33

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

223 McArthur River Operation

Cameco Corporation operates the McArthur River underground mine in north-central Saskatchewan Ore from the mine which began production in 1999 is processed at the Key Lake Mill located 80 km south of McArthur River

Figures 229ndash232 present dose information for the McArthur River operation from 2001 to 2007

Figure 229 Average Dose Trends for the McArthur River Operation (Based o n N on-Zero R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

34

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 230 Average Dose Trends for the McArthur River Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

Figure 231 Collective Dose Trends for the McArthur River Operation

0

200

400

600

800

1000

1200

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Radon gas External Radon progeny Long-lived radioactive dust

Year

35

00

0-000

9

001-5

00

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 232 Distribution o f Effective Doses Among A ll Workers at the McArthur River Operation

0

100

200

300

400

500

600

700

800

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

36

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

224 Key Lake Operation

Cameco Corporation operates mining facilities in Key Lake located in north-central Saskatchewan The Key Lake operation includes two mined-out open pit mines (used for tailings management) a mill and two dry tailings management facilities Mining began in 1983 and ceased in 1997 the mill continued to process ore from the McArthur River mine during the reporting period

Figures 233ndash236 present dose information for the Key Lake operation from 2001 to 2007

Figure 233 Average Dose Trends for the Key Lake Operation (Based o n N on-Zero R esults)

00

20

40

60

80

00

20

40

60

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

37

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

00

20

40

60

80

00

20

40

60

Figure 234 Average Dose Trends for the Key Lake Operation (Based o n A ll Monitoring R esults)

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 235 Collective Dose Trends for the Key Lake Operation

0

100

200

300

400

500

600

700

800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External Radon progeny Long-lived radioactive dust

Year

38

00

0-000

9

001-5

0

501-1

000

gt 1001

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 236 Distribution o f Effective Doses Among A ll Workers at the Key Lake Operation

0

200

400

600

800

1000

1200

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose Range (mSv)

39

se

(mS

v)o

D

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

225 Cigar Lake Operation

Cameco Corporation manages the Cigar Lake underground mine located in northern Saskatchewan at the southern end of Waterbury Lake The mine was under construction at the time of this reportrsquos publication Test mining in ore was carried out in 1991 1992 and 2000

Figures 237ndash240 present dose information for the Cigar Lake operation from

Figure 2 37 Average D ose T rends fo r th e C igar L ake O peration (Based on Non-Zero Results)

2001 to 2007

Year

000

005

010

015

020

025

Long-lived radioactive dust Radon Progeny External Effective

40

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 238 Average Dose Trends for the Cigar Lake Operation (Based on All Monitoring Results)

000

005

010

015

020

025

030

035

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny

External

Effective

Year

Figure 239 Collective Dose Trends for the Cigar Lake Operation

0

50

100

150

200

250

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

External Radon progeny Long-lived radioactive dust

Year

41

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 240 Distribution of Effective Doses Among All Workers at the Cigar Lake Operation

0

200

400

600

800

1000

1200

1400

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

42

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

226 Rabbit Lake Operation

Cameco Corporation owns and operates mining facilities in Rabbit Lake located in north-eastern Saskatchewan Facilities include an underground mine four mined-out open-pit mines a mill and two tailings management facilities Mining and milling began in 1975

Figures 241ndash244 present dose information for the Rabbit Lake operation from 2001 to 2007

Figure 241 Average Dose Trends for the Rabbit Lake Operation (Based on Non-Zero Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

43

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 242 Average Dose Trends for the Rabbit Lake Operation (Based on All Monitoring Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

Figure 243 Collective Dose Trends for the Rabbit Lake Operation

0

200

400

600

800

1000

1200

1400

1600

1800

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Radon gas External Radon progeny Long-lived radioactive dust

Year

44

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

gt300

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 244 Distribution of Effective Doses Among All Workers at the Rabbit Lake Operation

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

900

800

700

600

500

400

300

200

100

0

Dose (mSv)

45

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

23 Uranium Refineries This section presents data for the following two facilities

bull a uranium refining facility in Blind River (Section 231) bull a uranium conversion facility in Port Hope (Section 232)

Graphs indicate the following average doses at each facility from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Note on data for uranium refineries

1 Doses from photons from external sources are measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay and lung counting Historically while these internal doses have been measured they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

231 Blind River Refinery

Cameco Corporation owns and is licensed to operate a uranium refinery in Blind River Ontario The facility which began operating in 1983 converts uranium ore concentrate to uranium trioxide The uranium trioxide is shipped to Camecorsquos uranium conversion facility in Port Hope Ontario where it is processed into uranium dioxide (for use in the fabrication of fuel for nuclear reactors in Canada) or uranium hexafluoride (exported for enrichment and fabrication into fuel for nuclear power reactors around the world)

Figures 245ndash248 present dose information for the Blind River refinery from 2001 to 2007

46

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 245 Average Dose Trends for the Blind River Refinery (Based on Non-Zero Results)

0

05

1

15

2

25

Year

Figure 246 Average Dose Trends for the Blind River Refinery (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

47

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 247 Collective Dose Trends for the Blind River Refinery

0

50

100

150

200

250

300 C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 248 Distribution of Effective Doses Among All Workers at the Blind River Refinery

0

20

40

60

80

100

120

140

160

180

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

48

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

232 Port Hope Conversion Facility

Cameco Corporation owns and is licensed to operate a uranium conversion facility in Port Hope Ontario The facility processes uranium trioxide received from the refinery in Blind River into uranium dioxide and uranium hexafluoride

Figures 249ndash252 present dose information for the Port Hope uranium conversion facility from 2001 to 2007

Figure 249 Average Dose Trends for the Port Hope Conversion Facility (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

49

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 250 Average Dose Trends for the Port Hope Conversion Facility (Based on All Monitoring Results)

0

01

02

03

04

05

06

07

08

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 251 Collective Dose Trends for the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

50

000-0

009

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 252 Distribution of Effective Doses Among All Workers at the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

400

450

500

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

51

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

24 Fuel Fabrication Facilities This section presents data for three nuclear fuel fabrication facilities

bull Two facilities owned and operated by General Electric Canada Inc (Section 241) bull One facility in Port Hope operated by Zircatec Precision Industries (Section 242)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average doses

Notes on data for fuel fabrication facilities

1 Effective doses for the three facilities are composed of the following reported components bull dose from photons (labelled on the charts as ldquoexternalrdquo) bull doses from internal intakes of uranium dust (long-lived radioactive dust) from

uranium in air concentrations (for General Electricrsquos Toronto facility only)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components photon doses and doses from long-lived radioactive dust

241 General Electric Nuclear Fuel Facilities

General Electric Canada Inc operates two nuclear fuel facilities in Ontario

bull At the Toronto facility uranium dioxide pellets are produced from natural or depleted uranium dioxide powder

bull At the Peterborough facility uranium dioxide fuel bundles are created from the pellets produced at the Toronto facility

Figures 253ndash256 present dose information for General Electric Canada Incrsquos fuel fabrication facilities from 2001 to 2007 Graphs do not distinguish between the doses received at the Peterborough facility versus those at the Toronto facility

52

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 253 Average Dose Trends for the General Electric Fuel Facility (Based on Non-Zero Results Only)

0

05

1

15

2

25

3

35

Long Lived Radioactive Dust External Effective

Year

Figure 254 Average Dose Trends for the General Electric Fuel Facility (Based on All Monitoring Results)

0

05

1

15

2

25

3

Long Lived Radioactive Dust External Effective

Year

Dos

e (m

Sv)

Dos

e (m

Sv)

53

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 255 Collective Dose Trends for the General Electric Fuel Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Long Lived Radioactive Dust External

Year

Figure 256 Distribution of Effective Doses among all Workers at the General Electric Fuel Facility

0

10

20

30

40

50

60

70

80

90

100

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

54

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

242 Zircatec Nuclear Fuel Facility

Zircatec Precision Industries Inc operates a nuclear fuel facility in Port Hope Ontario where it makes fuel pellets from uranium dioxide powder received from Port Hopersquos uranium conversion facility The nuclear fuel facility also manufactures fuel bundles for nuclear reactors in Canada

Notes on data for the Zircatec nuclear fuel facility

1 Graphs indicate the following data bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of average effective doses

2 Doses from photons from external sources were measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay Historically although these internal doses have been measured and submitted to the CNSC they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

Figures 257ndash260 present dose information for the Zircatec nuclear fuel facility from 2001 to 2007

Figure 257 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on Non-Zero Results)

0

05

1

15

2

25

3

35

Effe

ctiv

e D

ose

(mS

v)

Year

55

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 258 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

18

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 259 Collective Dose Trends for the Zircatec Nuclear Fuel Facility

0

50

100

150

200

250

300

350

400

450

500

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

56

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 260 Distribution of Effective Doses Among All Workers at the Zircatec Nuclear Fuel Facility

300

Num

ber o

f Wor

kers

250

200

150

100

50

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

57

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

25 Research and Radioisotope Production Facilities This section presents dose information for the following research and radioisotope production facilities from 2001 to 2007

bull Chalk River Laboratories and Whiteshell Laboratories (Section 251) bull A radioisotope production facility operated by MDS Nordion (Section 252) bull The Tri-University Meson Facility (TRIUMF) (Section 253)

Note on data for research and radioisotope production facilities

1 Graphs indicate the following data for each facility bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of effective doses

251 Chalk River Laboratories and Whiteshell Laboratories

Atomic Energy of Canada Limited (AECL) owns and is licensed to operate Chalk River Laboratories and Whiteshell Laboratories

Situated in Renfrew County on the south shore of the Ottawa River the Chalk River Laboratories site hosts the National Research Universal Reactor along with numerous other facilities occupying some 160 buildings in an area of approximately 40 km2 Activities consist of radioisotope production for nuclear medicine testing and development of structural materials in support of power reactor operations fuel fabrication research and radioactive waste management and storage

The Whiteshell Laboratories site is located approximately 10 km west of Pinawa Manitoba and 100 km northeast of Winnipeg on the east bank of the Winnipeg River AECL established the laboratories for nuclear research and testing during the early 1960s and has since discontinued operations which are being decommissioned under a licence from the CNSC

Figures 261ndash264 present dose information for Chalk River Laboratories and Whiteshell Laboratories from 2001 to 2007

Notes on data for Chalk River Laboratories and Whiteshell Laboratories

1 Effective doses are composed of the following reported components bull external doses5 (from both photon and neutron doses) bull tritium doses

Due to issues with AECLrsquos in-house dosimetry management system neutron doses were not reported separately to the NDR during the reporting period As a result external doses from photons and neutrons were totaled The reporting discrepancy has since been rectified

58

5

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of external (photon and neutron) and tritium doses Intakes of other radionuclides occasionally occur and these radionuclides are not included here because their associated doses are very small For this reason certain collective doses in this report may have values slightly lower than the sum of their respective components as listed

Figure 261 Average Dose Trends for Chalk River and Whiteshell Laboratories (Non-Zero Results Only)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Tritium External Effective

Year

59

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 262 Average Dose Trends for Chalk River and Whiteshell Laboratories (All Monitoring Results)

000

020

040

060

080

100

120

Dos

e (m

Sv)

Tritium External Effective

Year

Figure 263 Collective Dose Trends for Chalk River and Whiteshell Laboratories

0

500

1000

1500

2000

2500

3000

3500

Col

lect

ive

Dos

e (p

erso

n- m

Sv)

External Tritium

Year

60

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 264 Distribution of Effective Doses Among All Workers at Chalk River and Whiteshell Laboratories

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

3500

3000

2500

2000

1500

1000

500

Dose (mSv)

61

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

252 MDS Nordion (Nuclear Substance Processing Facility and Canadian Irradiation Centre)

MDS Nordion owns and operates a nuclear substance processing facility in Ottawa Ontario where it processes unsealed radioisotopes and manufactures sealed radiation sources In operation since the early 1970s the facility was purchased by Nordion International in 1991

In cooperation with the Universiteacute du Queacutebecrsquos Institut Armand-Frappier MDS Nordion also operates the Canadian Irradiation Centre which conducts various irradiation services which include training testing and development The centre is located in Laval Quebec on the Universiteacute du Queacutebec campus

Figures 265ndash268 present dose information for MDS Nordionrsquos Ottawa nuclear substance processing facility and for the Canadian Irradiation Centre from 2001 to 2007

Notes on data for MDS Nordionrsquos nuclear substance processing facility and the Canadian Irradiation Centre

1 Doses from photons from external sources were measured and reported to the NDR MDS Nordion also has a routine thyroid monitoring program very occasionally small recordable doses of radiation have occurred from thyroid uptake of iodine The resulting doses have not been historically submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided

Figure 265 Average Dose Trends for MDS Nordion (Based on Non-Zero Results)

0

05

1

15

2

25

Effe

ctiv

e D

ose

(mS

v)

Year

62

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 266 Average Dose Trends for MDS Nordion (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

Figure 267 Collective Dose Trends for MDS Nordion

0

100

200

300

400

500

600

700

800

Year

63

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 268 Distribution of Effective Doses Among All Workers at MDS Nordion

0

5 0

1 0 0

1 5 0

2 0 0

2 5 0

3 0 0

3 5 0

4 0 0

4 5 0

5 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

64

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

253 Tri-University Meson Facility

The Tri-University Meson facility (TRIUMF) is situated in Vancouver on the campus of the University of British Columbia TRIUMF which began operating in the early 1970s with one cyclotron now has two cyclotrons and associated laboratories for research and radioisotope production The laboratory provides research facilities for Canadian and international users and also produces radioisotopes which are used by medical facilities and by a commercial organization (MDS Nordion) MDS Nordion staff also work at the TRIUMF site however MDS Nordion oversees this work and has its own radiation protection program

Figures 269ndash272 present dose information for the TRIUMF facility from 2001 to 2007 Please note that data sets do not distinguish between doses received by TRIUMF staff and MDS Nordion staff who work on the site as the data for these two groups was submitted collectively to the NDR for the reporting period shown Future data for each group will be submitted separately to the NDR

Note on data for TRIUMF

1 Effective doses are composed of the following reported components bull doses from photons (labeled as ldquoexternalrdquo in the charts) bull neutron doses

Figure 269 Average Dose Trends for TRIUMF (Non-Zero Results Only)

000

020

040

060

080

100

120

140

160

Dos

e (m

Sv)

Neutrons External Effective

Year

65

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 21: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

1 2 3 4 5 6 7 0 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

212 Pickering Nuclear Generating Stations

Located in Pickering Ontario the Pickering Nuclear Generating Stations are owned and operated by Ontario Power Generation Two generating stations are located within one enclosure

bull Pickering A consists of four nuclear reactors (units 1 to 4) that began operating in 1971 bull Pickering B consists of four nuclear reactors (units 5 to 8) that began operating in 1982

As part of its extensive recovery program Ontario Hydro (now Ontario Power Generation) temporarily shut down all Pickering A reactors in 1997 and maintained them in a guaranteed shutdown state Unit 4 was restarted in September 2003 and Unit 1 was restarted in March 2005 Units 2 and 3 remain in a guaranteed shutdown state

Figures 25ndash28 present dose information for the Pickering Nuclear Generating Stations from 2001 to 2007 Graphs do not distinguish between doses received at Pickering A versus those received at Pickering B

Figure 25 Average Dose Trends for Pickering N uclear Generating Stati on (Based o n N on-Zero R esults)

25

2

15

1

05

0

)S

v(m

e os

D

Tritium Neutrons External Effective

Year

16

Tritium Neutrons External Effective

Neutrons External Tritium

1 2 3 4 5 6 70 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

1 2 3 4 5 6 7 0 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 26 Average Dose Trends for Pickering N uclear Generating Stati on (Based o n A ll Monitoring R esults)

12

1

08

06

04

02

0

Year

Figure 27 Collective Dose Trends for Pickering N uclear Generating Stati on

12000

10000

8000

6000

4000

2000

0

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

)

Sv

(me

osD

Year

17

2001 2002 2003 2004 2005 2006 2007

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 28 Distribution o f Effective Doses Among A ll Workers at Pickering Nuclear Generating Stati on

6000

5000

4000

3000

2000

1000

0

Num

ber o

f Wor

kers

Dose Range (mSv)

18

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

213 Darlington Nuclear Generating Station

Owned and operated by Ontario Power Generation the Darlington Nuclear Generating Station has four nuclear reactors the first of which began operating in 1989 The facility is located near Bowmanville on the shore of Lake Ontario

Figures 29ndash212 present dose information for the Darlington Nuclear Generating Station from 2001 to 2007

Figure 29 Average Dose Trends for Darlington N uclear Generating Stati on (Non- Zero R esults Only)

)S

v(m

e os

D

250

200

150

100

050

000

Year

19

Tritium Neutrons External Effective

Neutrons External Tritium

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 210 Average Dose Trends for Darlington N uclear Generating Stati on (All Monitoring R esults)

090

080

070

060

050

040

030

020

010

000

)S

v(m

e os

D

Year

Figure 211 Collective Dose Trends for Darlington N uclear Generating Stati on

4500

4000

3500

3000

2500

2000

1500

1000

500

0

)vSm-nosrep (es

Do

eiv

llect

Co

Year

20

2001 2002 2003 2004 2005 2006 2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 212 Distribution o f Effective Doses Among A ll Workers at Darlington Nuclear Generating Stati on

0

500

1000

1500

2000

2500

3000

3500

ers

ork

W of

be

r um

N

Dose Range (mSv)

21

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

214 Gentilly-2 Nuclear Generating Station

The Gentilly-2 Nuclear Generating Station owned and operated by Hydro-Queacutebec has a single reactor that began operating in 1982 The facility is located on the south shore of the St Lawrence River near Trois-Riviegraveres Queacutebec

Figures 213ndash216 present dose information for the Gentilly-2 Nuclear Generating Station from 2001 to 2007

Figure 213 Average Dose Trends for Gentilly-2 Nuclear Generating Stati on (Based o n N on-Zero R esults)

0

05

1

15

2

25

3

35

4

45

)S

v(m

e os

D

Year

22

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 214 Average Dose Trends for Gentilly-2 Nuclear Generating Stati on (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

)S

v(m

e os

D

Year

Figure 215 Collective Dose Trends for Gentilly-2 Nuclear Generating Stati on

0

500

1000

1500

2000

2500

3000

3500

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Neutrons

External

Tritium

Year

23

000-0

009

001-5

00

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 216 Distribution of Effective Doses Among All Workers at Gentilly-2 Nuclear Generating Station

2500

2000

1500

1000

500

0

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

24

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

215 Point Lepreau Nuclear Generating Station

The Point Lepreau Nuclear Generating Station has one reactor that began operating in 1982 Owned and operated by New Brunswick Power Nuclear the station is located in Point Lepreau New Brunswick about 40 km west of Saint John on the shores of the Bay of Fundy

Figures 217ndash220 present dose information for the Point Lepreau Nuclear Generating Station from 2001 to 2007

Figure 217 Average Dose Trends for Point Lepreau N uclear Generating Stati on (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

)S

v(m

e os

D

Tritium Neutron External Effective

Year

25

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 218 Average Dose Trends for Point Lepreau N uclear Generating Stati on (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

)S

v(m

e os

D

Tritium Neutrons External Effective

Year

Figure 219 Collective Dose Trends for Point Lepreau N uclear Generating Station

0

200

400

600

800

1000

1200

1400

1600

1800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Neutrons

External

Tritium

Year

26

0

1400

1200

1000

800

600

400

200

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 220 Distribution of Effective Doses Among All Workers at Point Lepreau Nuclear Generating Station

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

27

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

22 Uranium Mines and Mills This section presents dose information for mine and mill sites in the following regions

bull Cluff Lake (Section 221) bull McClean Lake (Section 222) bull McArthur River (Section 223) bull Key Lake (Section 224) bull Cigar Lake (Section 225) bull Rabbit Lake (Section 226)

Graphs indicate the following data for each site from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for uranium mines and mills

1 Effective doses are composed of the following reported components bull doses from photons (labelled on the charts as ldquoexternalrdquo) bull doses from radon progeny bull doses from long-lived radioactive dust bull doses from radon gas (in some cases)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of photon radon progeny long-lived radioactive dust and radon gas doses

3 The NDR lists radon progeny in working level months (WLM) For this report radon progeny exposures were converted4 to doses expressed in mSv

221 Cluff Lake Operation

The Cluff Lake mining facilities operated by AREVA Resources Canada Inc are located in northwestern Saskatchewan Work began in 1980 and ended in 2002 with the site now being decommissioned The site consisted of three open-pit and two underground mines a mill and a tailings management facility During 2005 and 2006 most of the infrastructure was removed and the affected areas were remediated

Figures 221ndash224 present dose information for the Cluff Lake operation from 2001 to 2007

4 Doses were converted using the International Commission on Radiation Protection (ICRP)rsquos conversion convention of 1 WLM = 5 mSv This convention was established in the ICRP publication Protection against Radon at Home and at Work (ICRP 65)

28

Long-lived radioactive dust Radon progeny External Effective

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 221 Average Dose Trends for the Cluff Lake Operation (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

Year

Figure 222 Average Dose Trends for the Cluff Lake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

200

Long-lived radioactive dust Radon progeny External Effective

)S

v(m

e os

D)

Sv

(me

osD

Year

29

600

500

400

300

200

100

0

External Radon progeny Long-lived radioactive dust

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 223 Collective Dose Trends for the Cluff Lake Operation s

erkor

of W

ber

Num

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Year

Figure 224 Distribution o f Effective Doses Among A ll Workers at the Cluff Lake Operation

0

20

40

60

80

100

120

140

160

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

30

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

222 McClean Lake Operation

AREVA Resources Canada Inc runs the McClean Lake mining operation in northeastern Saskatchewan It comprises open pit mines a mill and a tailings management facility Mining began in 1995 while milling started in 1999

Figures 225ndash228 present dose information for the McClean Lake operation from 2001 to 2007

Figure 225 Average Dose Trends for the McClean L ake Operation (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

31

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 226 Average Dose Trends for the McClean L ake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 227 Collective Dose Trends for the McClean L ake Operation

0

100

200

300

400

500

600

700

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External

Radon progeny

Long-lived radioactive dust

Year

32

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 228 Distribution o f Effective Doses Among A ll Workers at the McClean Lake Operation

0

100

200

300

400

500

600

700

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

33

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

223 McArthur River Operation

Cameco Corporation operates the McArthur River underground mine in north-central Saskatchewan Ore from the mine which began production in 1999 is processed at the Key Lake Mill located 80 km south of McArthur River

Figures 229ndash232 present dose information for the McArthur River operation from 2001 to 2007

Figure 229 Average Dose Trends for the McArthur River Operation (Based o n N on-Zero R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

34

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 230 Average Dose Trends for the McArthur River Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

Figure 231 Collective Dose Trends for the McArthur River Operation

0

200

400

600

800

1000

1200

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Radon gas External Radon progeny Long-lived radioactive dust

Year

35

00

0-000

9

001-5

00

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 232 Distribution o f Effective Doses Among A ll Workers at the McArthur River Operation

0

100

200

300

400

500

600

700

800

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

36

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

224 Key Lake Operation

Cameco Corporation operates mining facilities in Key Lake located in north-central Saskatchewan The Key Lake operation includes two mined-out open pit mines (used for tailings management) a mill and two dry tailings management facilities Mining began in 1983 and ceased in 1997 the mill continued to process ore from the McArthur River mine during the reporting period

Figures 233ndash236 present dose information for the Key Lake operation from 2001 to 2007

Figure 233 Average Dose Trends for the Key Lake Operation (Based o n N on-Zero R esults)

00

20

40

60

80

00

20

40

60

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

37

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

00

20

40

60

80

00

20

40

60

Figure 234 Average Dose Trends for the Key Lake Operation (Based o n A ll Monitoring R esults)

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 235 Collective Dose Trends for the Key Lake Operation

0

100

200

300

400

500

600

700

800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External Radon progeny Long-lived radioactive dust

Year

38

00

0-000

9

001-5

0

501-1

000

gt 1001

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 236 Distribution o f Effective Doses Among A ll Workers at the Key Lake Operation

0

200

400

600

800

1000

1200

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose Range (mSv)

39

se

(mS

v)o

D

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

225 Cigar Lake Operation

Cameco Corporation manages the Cigar Lake underground mine located in northern Saskatchewan at the southern end of Waterbury Lake The mine was under construction at the time of this reportrsquos publication Test mining in ore was carried out in 1991 1992 and 2000

Figures 237ndash240 present dose information for the Cigar Lake operation from

Figure 2 37 Average D ose T rends fo r th e C igar L ake O peration (Based on Non-Zero Results)

2001 to 2007

Year

000

005

010

015

020

025

Long-lived radioactive dust Radon Progeny External Effective

40

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 238 Average Dose Trends for the Cigar Lake Operation (Based on All Monitoring Results)

000

005

010

015

020

025

030

035

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny

External

Effective

Year

Figure 239 Collective Dose Trends for the Cigar Lake Operation

0

50

100

150

200

250

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

External Radon progeny Long-lived radioactive dust

Year

41

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 240 Distribution of Effective Doses Among All Workers at the Cigar Lake Operation

0

200

400

600

800

1000

1200

1400

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

42

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

226 Rabbit Lake Operation

Cameco Corporation owns and operates mining facilities in Rabbit Lake located in north-eastern Saskatchewan Facilities include an underground mine four mined-out open-pit mines a mill and two tailings management facilities Mining and milling began in 1975

Figures 241ndash244 present dose information for the Rabbit Lake operation from 2001 to 2007

Figure 241 Average Dose Trends for the Rabbit Lake Operation (Based on Non-Zero Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

43

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 242 Average Dose Trends for the Rabbit Lake Operation (Based on All Monitoring Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

Figure 243 Collective Dose Trends for the Rabbit Lake Operation

0

200

400

600

800

1000

1200

1400

1600

1800

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Radon gas External Radon progeny Long-lived radioactive dust

Year

44

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

gt300

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 244 Distribution of Effective Doses Among All Workers at the Rabbit Lake Operation

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

900

800

700

600

500

400

300

200

100

0

Dose (mSv)

45

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

23 Uranium Refineries This section presents data for the following two facilities

bull a uranium refining facility in Blind River (Section 231) bull a uranium conversion facility in Port Hope (Section 232)

Graphs indicate the following average doses at each facility from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Note on data for uranium refineries

1 Doses from photons from external sources are measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay and lung counting Historically while these internal doses have been measured they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

231 Blind River Refinery

Cameco Corporation owns and is licensed to operate a uranium refinery in Blind River Ontario The facility which began operating in 1983 converts uranium ore concentrate to uranium trioxide The uranium trioxide is shipped to Camecorsquos uranium conversion facility in Port Hope Ontario where it is processed into uranium dioxide (for use in the fabrication of fuel for nuclear reactors in Canada) or uranium hexafluoride (exported for enrichment and fabrication into fuel for nuclear power reactors around the world)

Figures 245ndash248 present dose information for the Blind River refinery from 2001 to 2007

46

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 245 Average Dose Trends for the Blind River Refinery (Based on Non-Zero Results)

0

05

1

15

2

25

Year

Figure 246 Average Dose Trends for the Blind River Refinery (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

47

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 247 Collective Dose Trends for the Blind River Refinery

0

50

100

150

200

250

300 C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 248 Distribution of Effective Doses Among All Workers at the Blind River Refinery

0

20

40

60

80

100

120

140

160

180

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

48

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

232 Port Hope Conversion Facility

Cameco Corporation owns and is licensed to operate a uranium conversion facility in Port Hope Ontario The facility processes uranium trioxide received from the refinery in Blind River into uranium dioxide and uranium hexafluoride

Figures 249ndash252 present dose information for the Port Hope uranium conversion facility from 2001 to 2007

Figure 249 Average Dose Trends for the Port Hope Conversion Facility (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

49

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 250 Average Dose Trends for the Port Hope Conversion Facility (Based on All Monitoring Results)

0

01

02

03

04

05

06

07

08

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 251 Collective Dose Trends for the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

50

000-0

009

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 252 Distribution of Effective Doses Among All Workers at the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

400

450

500

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

51

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

24 Fuel Fabrication Facilities This section presents data for three nuclear fuel fabrication facilities

bull Two facilities owned and operated by General Electric Canada Inc (Section 241) bull One facility in Port Hope operated by Zircatec Precision Industries (Section 242)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average doses

Notes on data for fuel fabrication facilities

1 Effective doses for the three facilities are composed of the following reported components bull dose from photons (labelled on the charts as ldquoexternalrdquo) bull doses from internal intakes of uranium dust (long-lived radioactive dust) from

uranium in air concentrations (for General Electricrsquos Toronto facility only)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components photon doses and doses from long-lived radioactive dust

241 General Electric Nuclear Fuel Facilities

General Electric Canada Inc operates two nuclear fuel facilities in Ontario

bull At the Toronto facility uranium dioxide pellets are produced from natural or depleted uranium dioxide powder

bull At the Peterborough facility uranium dioxide fuel bundles are created from the pellets produced at the Toronto facility

Figures 253ndash256 present dose information for General Electric Canada Incrsquos fuel fabrication facilities from 2001 to 2007 Graphs do not distinguish between the doses received at the Peterborough facility versus those at the Toronto facility

52

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 253 Average Dose Trends for the General Electric Fuel Facility (Based on Non-Zero Results Only)

0

05

1

15

2

25

3

35

Long Lived Radioactive Dust External Effective

Year

Figure 254 Average Dose Trends for the General Electric Fuel Facility (Based on All Monitoring Results)

0

05

1

15

2

25

3

Long Lived Radioactive Dust External Effective

Year

Dos

e (m

Sv)

Dos

e (m

Sv)

53

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 255 Collective Dose Trends for the General Electric Fuel Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Long Lived Radioactive Dust External

Year

Figure 256 Distribution of Effective Doses among all Workers at the General Electric Fuel Facility

0

10

20

30

40

50

60

70

80

90

100

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

54

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

242 Zircatec Nuclear Fuel Facility

Zircatec Precision Industries Inc operates a nuclear fuel facility in Port Hope Ontario where it makes fuel pellets from uranium dioxide powder received from Port Hopersquos uranium conversion facility The nuclear fuel facility also manufactures fuel bundles for nuclear reactors in Canada

Notes on data for the Zircatec nuclear fuel facility

1 Graphs indicate the following data bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of average effective doses

2 Doses from photons from external sources were measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay Historically although these internal doses have been measured and submitted to the CNSC they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

Figures 257ndash260 present dose information for the Zircatec nuclear fuel facility from 2001 to 2007

Figure 257 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on Non-Zero Results)

0

05

1

15

2

25

3

35

Effe

ctiv

e D

ose

(mS

v)

Year

55

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 258 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

18

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 259 Collective Dose Trends for the Zircatec Nuclear Fuel Facility

0

50

100

150

200

250

300

350

400

450

500

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

56

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 260 Distribution of Effective Doses Among All Workers at the Zircatec Nuclear Fuel Facility

300

Num

ber o

f Wor

kers

250

200

150

100

50

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

57

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

25 Research and Radioisotope Production Facilities This section presents dose information for the following research and radioisotope production facilities from 2001 to 2007

bull Chalk River Laboratories and Whiteshell Laboratories (Section 251) bull A radioisotope production facility operated by MDS Nordion (Section 252) bull The Tri-University Meson Facility (TRIUMF) (Section 253)

Note on data for research and radioisotope production facilities

1 Graphs indicate the following data for each facility bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of effective doses

251 Chalk River Laboratories and Whiteshell Laboratories

Atomic Energy of Canada Limited (AECL) owns and is licensed to operate Chalk River Laboratories and Whiteshell Laboratories

Situated in Renfrew County on the south shore of the Ottawa River the Chalk River Laboratories site hosts the National Research Universal Reactor along with numerous other facilities occupying some 160 buildings in an area of approximately 40 km2 Activities consist of radioisotope production for nuclear medicine testing and development of structural materials in support of power reactor operations fuel fabrication research and radioactive waste management and storage

The Whiteshell Laboratories site is located approximately 10 km west of Pinawa Manitoba and 100 km northeast of Winnipeg on the east bank of the Winnipeg River AECL established the laboratories for nuclear research and testing during the early 1960s and has since discontinued operations which are being decommissioned under a licence from the CNSC

Figures 261ndash264 present dose information for Chalk River Laboratories and Whiteshell Laboratories from 2001 to 2007

Notes on data for Chalk River Laboratories and Whiteshell Laboratories

1 Effective doses are composed of the following reported components bull external doses5 (from both photon and neutron doses) bull tritium doses

Due to issues with AECLrsquos in-house dosimetry management system neutron doses were not reported separately to the NDR during the reporting period As a result external doses from photons and neutrons were totaled The reporting discrepancy has since been rectified

58

5

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of external (photon and neutron) and tritium doses Intakes of other radionuclides occasionally occur and these radionuclides are not included here because their associated doses are very small For this reason certain collective doses in this report may have values slightly lower than the sum of their respective components as listed

Figure 261 Average Dose Trends for Chalk River and Whiteshell Laboratories (Non-Zero Results Only)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Tritium External Effective

Year

59

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 262 Average Dose Trends for Chalk River and Whiteshell Laboratories (All Monitoring Results)

000

020

040

060

080

100

120

Dos

e (m

Sv)

Tritium External Effective

Year

Figure 263 Collective Dose Trends for Chalk River and Whiteshell Laboratories

0

500

1000

1500

2000

2500

3000

3500

Col

lect

ive

Dos

e (p

erso

n- m

Sv)

External Tritium

Year

60

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 264 Distribution of Effective Doses Among All Workers at Chalk River and Whiteshell Laboratories

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

3500

3000

2500

2000

1500

1000

500

Dose (mSv)

61

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

252 MDS Nordion (Nuclear Substance Processing Facility and Canadian Irradiation Centre)

MDS Nordion owns and operates a nuclear substance processing facility in Ottawa Ontario where it processes unsealed radioisotopes and manufactures sealed radiation sources In operation since the early 1970s the facility was purchased by Nordion International in 1991

In cooperation with the Universiteacute du Queacutebecrsquos Institut Armand-Frappier MDS Nordion also operates the Canadian Irradiation Centre which conducts various irradiation services which include training testing and development The centre is located in Laval Quebec on the Universiteacute du Queacutebec campus

Figures 265ndash268 present dose information for MDS Nordionrsquos Ottawa nuclear substance processing facility and for the Canadian Irradiation Centre from 2001 to 2007

Notes on data for MDS Nordionrsquos nuclear substance processing facility and the Canadian Irradiation Centre

1 Doses from photons from external sources were measured and reported to the NDR MDS Nordion also has a routine thyroid monitoring program very occasionally small recordable doses of radiation have occurred from thyroid uptake of iodine The resulting doses have not been historically submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided

Figure 265 Average Dose Trends for MDS Nordion (Based on Non-Zero Results)

0

05

1

15

2

25

Effe

ctiv

e D

ose

(mS

v)

Year

62

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 266 Average Dose Trends for MDS Nordion (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

Figure 267 Collective Dose Trends for MDS Nordion

0

100

200

300

400

500

600

700

800

Year

63

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 268 Distribution of Effective Doses Among All Workers at MDS Nordion

0

5 0

1 0 0

1 5 0

2 0 0

2 5 0

3 0 0

3 5 0

4 0 0

4 5 0

5 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

64

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

253 Tri-University Meson Facility

The Tri-University Meson facility (TRIUMF) is situated in Vancouver on the campus of the University of British Columbia TRIUMF which began operating in the early 1970s with one cyclotron now has two cyclotrons and associated laboratories for research and radioisotope production The laboratory provides research facilities for Canadian and international users and also produces radioisotopes which are used by medical facilities and by a commercial organization (MDS Nordion) MDS Nordion staff also work at the TRIUMF site however MDS Nordion oversees this work and has its own radiation protection program

Figures 269ndash272 present dose information for the TRIUMF facility from 2001 to 2007 Please note that data sets do not distinguish between doses received by TRIUMF staff and MDS Nordion staff who work on the site as the data for these two groups was submitted collectively to the NDR for the reporting period shown Future data for each group will be submitted separately to the NDR

Note on data for TRIUMF

1 Effective doses are composed of the following reported components bull doses from photons (labeled as ldquoexternalrdquo in the charts) bull neutron doses

Figure 269 Average Dose Trends for TRIUMF (Non-Zero Results Only)

000

020

040

060

080

100

120

140

160

Dos

e (m

Sv)

Neutrons External Effective

Year

65

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 22: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

Tritium Neutrons External Effective

Neutrons External Tritium

1 2 3 4 5 6 70 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

1 2 3 4 5 6 7 0 0 0 0 0 0 00 0 0 0 0 0 02 2 2 2 2 2 2

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 26 Average Dose Trends for Pickering N uclear Generating Stati on (Based o n A ll Monitoring R esults)

12

1

08

06

04

02

0

Year

Figure 27 Collective Dose Trends for Pickering N uclear Generating Stati on

12000

10000

8000

6000

4000

2000

0

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

)

Sv

(me

osD

Year

17

2001 2002 2003 2004 2005 2006 2007

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 28 Distribution o f Effective Doses Among A ll Workers at Pickering Nuclear Generating Stati on

6000

5000

4000

3000

2000

1000

0

Num

ber o

f Wor

kers

Dose Range (mSv)

18

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

213 Darlington Nuclear Generating Station

Owned and operated by Ontario Power Generation the Darlington Nuclear Generating Station has four nuclear reactors the first of which began operating in 1989 The facility is located near Bowmanville on the shore of Lake Ontario

Figures 29ndash212 present dose information for the Darlington Nuclear Generating Station from 2001 to 2007

Figure 29 Average Dose Trends for Darlington N uclear Generating Stati on (Non- Zero R esults Only)

)S

v(m

e os

D

250

200

150

100

050

000

Year

19

Tritium Neutrons External Effective

Neutrons External Tritium

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 210 Average Dose Trends for Darlington N uclear Generating Stati on (All Monitoring R esults)

090

080

070

060

050

040

030

020

010

000

)S

v(m

e os

D

Year

Figure 211 Collective Dose Trends for Darlington N uclear Generating Stati on

4500

4000

3500

3000

2500

2000

1500

1000

500

0

)vSm-nosrep (es

Do

eiv

llect

Co

Year

20

2001 2002 2003 2004 2005 2006 2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 212 Distribution o f Effective Doses Among A ll Workers at Darlington Nuclear Generating Stati on

0

500

1000

1500

2000

2500

3000

3500

ers

ork

W of

be

r um

N

Dose Range (mSv)

21

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

214 Gentilly-2 Nuclear Generating Station

The Gentilly-2 Nuclear Generating Station owned and operated by Hydro-Queacutebec has a single reactor that began operating in 1982 The facility is located on the south shore of the St Lawrence River near Trois-Riviegraveres Queacutebec

Figures 213ndash216 present dose information for the Gentilly-2 Nuclear Generating Station from 2001 to 2007

Figure 213 Average Dose Trends for Gentilly-2 Nuclear Generating Stati on (Based o n N on-Zero R esults)

0

05

1

15

2

25

3

35

4

45

)S

v(m

e os

D

Year

22

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 214 Average Dose Trends for Gentilly-2 Nuclear Generating Stati on (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

)S

v(m

e os

D

Year

Figure 215 Collective Dose Trends for Gentilly-2 Nuclear Generating Stati on

0

500

1000

1500

2000

2500

3000

3500

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Neutrons

External

Tritium

Year

23

000-0

009

001-5

00

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 216 Distribution of Effective Doses Among All Workers at Gentilly-2 Nuclear Generating Station

2500

2000

1500

1000

500

0

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

24

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

215 Point Lepreau Nuclear Generating Station

The Point Lepreau Nuclear Generating Station has one reactor that began operating in 1982 Owned and operated by New Brunswick Power Nuclear the station is located in Point Lepreau New Brunswick about 40 km west of Saint John on the shores of the Bay of Fundy

Figures 217ndash220 present dose information for the Point Lepreau Nuclear Generating Station from 2001 to 2007

Figure 217 Average Dose Trends for Point Lepreau N uclear Generating Stati on (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

)S

v(m

e os

D

Tritium Neutron External Effective

Year

25

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 218 Average Dose Trends for Point Lepreau N uclear Generating Stati on (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

)S

v(m

e os

D

Tritium Neutrons External Effective

Year

Figure 219 Collective Dose Trends for Point Lepreau N uclear Generating Station

0

200

400

600

800

1000

1200

1400

1600

1800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Neutrons

External

Tritium

Year

26

0

1400

1200

1000

800

600

400

200

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 220 Distribution of Effective Doses Among All Workers at Point Lepreau Nuclear Generating Station

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

27

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

22 Uranium Mines and Mills This section presents dose information for mine and mill sites in the following regions

bull Cluff Lake (Section 221) bull McClean Lake (Section 222) bull McArthur River (Section 223) bull Key Lake (Section 224) bull Cigar Lake (Section 225) bull Rabbit Lake (Section 226)

Graphs indicate the following data for each site from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for uranium mines and mills

1 Effective doses are composed of the following reported components bull doses from photons (labelled on the charts as ldquoexternalrdquo) bull doses from radon progeny bull doses from long-lived radioactive dust bull doses from radon gas (in some cases)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of photon radon progeny long-lived radioactive dust and radon gas doses

3 The NDR lists radon progeny in working level months (WLM) For this report radon progeny exposures were converted4 to doses expressed in mSv

221 Cluff Lake Operation

The Cluff Lake mining facilities operated by AREVA Resources Canada Inc are located in northwestern Saskatchewan Work began in 1980 and ended in 2002 with the site now being decommissioned The site consisted of three open-pit and two underground mines a mill and a tailings management facility During 2005 and 2006 most of the infrastructure was removed and the affected areas were remediated

Figures 221ndash224 present dose information for the Cluff Lake operation from 2001 to 2007

4 Doses were converted using the International Commission on Radiation Protection (ICRP)rsquos conversion convention of 1 WLM = 5 mSv This convention was established in the ICRP publication Protection against Radon at Home and at Work (ICRP 65)

28

Long-lived radioactive dust Radon progeny External Effective

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 221 Average Dose Trends for the Cluff Lake Operation (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

Year

Figure 222 Average Dose Trends for the Cluff Lake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

200

Long-lived radioactive dust Radon progeny External Effective

)S

v(m

e os

D)

Sv

(me

osD

Year

29

600

500

400

300

200

100

0

External Radon progeny Long-lived radioactive dust

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 223 Collective Dose Trends for the Cluff Lake Operation s

erkor

of W

ber

Num

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Year

Figure 224 Distribution o f Effective Doses Among A ll Workers at the Cluff Lake Operation

0

20

40

60

80

100

120

140

160

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

30

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

222 McClean Lake Operation

AREVA Resources Canada Inc runs the McClean Lake mining operation in northeastern Saskatchewan It comprises open pit mines a mill and a tailings management facility Mining began in 1995 while milling started in 1999

Figures 225ndash228 present dose information for the McClean Lake operation from 2001 to 2007

Figure 225 Average Dose Trends for the McClean L ake Operation (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

31

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 226 Average Dose Trends for the McClean L ake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 227 Collective Dose Trends for the McClean L ake Operation

0

100

200

300

400

500

600

700

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External

Radon progeny

Long-lived radioactive dust

Year

32

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 228 Distribution o f Effective Doses Among A ll Workers at the McClean Lake Operation

0

100

200

300

400

500

600

700

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

33

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

223 McArthur River Operation

Cameco Corporation operates the McArthur River underground mine in north-central Saskatchewan Ore from the mine which began production in 1999 is processed at the Key Lake Mill located 80 km south of McArthur River

Figures 229ndash232 present dose information for the McArthur River operation from 2001 to 2007

Figure 229 Average Dose Trends for the McArthur River Operation (Based o n N on-Zero R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

34

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 230 Average Dose Trends for the McArthur River Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

Figure 231 Collective Dose Trends for the McArthur River Operation

0

200

400

600

800

1000

1200

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Radon gas External Radon progeny Long-lived radioactive dust

Year

35

00

0-000

9

001-5

00

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 232 Distribution o f Effective Doses Among A ll Workers at the McArthur River Operation

0

100

200

300

400

500

600

700

800

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

36

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

224 Key Lake Operation

Cameco Corporation operates mining facilities in Key Lake located in north-central Saskatchewan The Key Lake operation includes two mined-out open pit mines (used for tailings management) a mill and two dry tailings management facilities Mining began in 1983 and ceased in 1997 the mill continued to process ore from the McArthur River mine during the reporting period

Figures 233ndash236 present dose information for the Key Lake operation from 2001 to 2007

Figure 233 Average Dose Trends for the Key Lake Operation (Based o n N on-Zero R esults)

00

20

40

60

80

00

20

40

60

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

37

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

00

20

40

60

80

00

20

40

60

Figure 234 Average Dose Trends for the Key Lake Operation (Based o n A ll Monitoring R esults)

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 235 Collective Dose Trends for the Key Lake Operation

0

100

200

300

400

500

600

700

800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External Radon progeny Long-lived radioactive dust

Year

38

00

0-000

9

001-5

0

501-1

000

gt 1001

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 236 Distribution o f Effective Doses Among A ll Workers at the Key Lake Operation

0

200

400

600

800

1000

1200

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose Range (mSv)

39

se

(mS

v)o

D

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

225 Cigar Lake Operation

Cameco Corporation manages the Cigar Lake underground mine located in northern Saskatchewan at the southern end of Waterbury Lake The mine was under construction at the time of this reportrsquos publication Test mining in ore was carried out in 1991 1992 and 2000

Figures 237ndash240 present dose information for the Cigar Lake operation from

Figure 2 37 Average D ose T rends fo r th e C igar L ake O peration (Based on Non-Zero Results)

2001 to 2007

Year

000

005

010

015

020

025

Long-lived radioactive dust Radon Progeny External Effective

40

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 238 Average Dose Trends for the Cigar Lake Operation (Based on All Monitoring Results)

000

005

010

015

020

025

030

035

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny

External

Effective

Year

Figure 239 Collective Dose Trends for the Cigar Lake Operation

0

50

100

150

200

250

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

External Radon progeny Long-lived radioactive dust

Year

41

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 240 Distribution of Effective Doses Among All Workers at the Cigar Lake Operation

0

200

400

600

800

1000

1200

1400

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

42

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

226 Rabbit Lake Operation

Cameco Corporation owns and operates mining facilities in Rabbit Lake located in north-eastern Saskatchewan Facilities include an underground mine four mined-out open-pit mines a mill and two tailings management facilities Mining and milling began in 1975

Figures 241ndash244 present dose information for the Rabbit Lake operation from 2001 to 2007

Figure 241 Average Dose Trends for the Rabbit Lake Operation (Based on Non-Zero Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

43

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 242 Average Dose Trends for the Rabbit Lake Operation (Based on All Monitoring Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

Figure 243 Collective Dose Trends for the Rabbit Lake Operation

0

200

400

600

800

1000

1200

1400

1600

1800

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Radon gas External Radon progeny Long-lived radioactive dust

Year

44

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

gt300

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 244 Distribution of Effective Doses Among All Workers at the Rabbit Lake Operation

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

900

800

700

600

500

400

300

200

100

0

Dose (mSv)

45

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

23 Uranium Refineries This section presents data for the following two facilities

bull a uranium refining facility in Blind River (Section 231) bull a uranium conversion facility in Port Hope (Section 232)

Graphs indicate the following average doses at each facility from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Note on data for uranium refineries

1 Doses from photons from external sources are measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay and lung counting Historically while these internal doses have been measured they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

231 Blind River Refinery

Cameco Corporation owns and is licensed to operate a uranium refinery in Blind River Ontario The facility which began operating in 1983 converts uranium ore concentrate to uranium trioxide The uranium trioxide is shipped to Camecorsquos uranium conversion facility in Port Hope Ontario where it is processed into uranium dioxide (for use in the fabrication of fuel for nuclear reactors in Canada) or uranium hexafluoride (exported for enrichment and fabrication into fuel for nuclear power reactors around the world)

Figures 245ndash248 present dose information for the Blind River refinery from 2001 to 2007

46

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 245 Average Dose Trends for the Blind River Refinery (Based on Non-Zero Results)

0

05

1

15

2

25

Year

Figure 246 Average Dose Trends for the Blind River Refinery (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

47

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 247 Collective Dose Trends for the Blind River Refinery

0

50

100

150

200

250

300 C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 248 Distribution of Effective Doses Among All Workers at the Blind River Refinery

0

20

40

60

80

100

120

140

160

180

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

48

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

232 Port Hope Conversion Facility

Cameco Corporation owns and is licensed to operate a uranium conversion facility in Port Hope Ontario The facility processes uranium trioxide received from the refinery in Blind River into uranium dioxide and uranium hexafluoride

Figures 249ndash252 present dose information for the Port Hope uranium conversion facility from 2001 to 2007

Figure 249 Average Dose Trends for the Port Hope Conversion Facility (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

49

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 250 Average Dose Trends for the Port Hope Conversion Facility (Based on All Monitoring Results)

0

01

02

03

04

05

06

07

08

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 251 Collective Dose Trends for the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

50

000-0

009

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 252 Distribution of Effective Doses Among All Workers at the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

400

450

500

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

51

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

24 Fuel Fabrication Facilities This section presents data for three nuclear fuel fabrication facilities

bull Two facilities owned and operated by General Electric Canada Inc (Section 241) bull One facility in Port Hope operated by Zircatec Precision Industries (Section 242)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average doses

Notes on data for fuel fabrication facilities

1 Effective doses for the three facilities are composed of the following reported components bull dose from photons (labelled on the charts as ldquoexternalrdquo) bull doses from internal intakes of uranium dust (long-lived radioactive dust) from

uranium in air concentrations (for General Electricrsquos Toronto facility only)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components photon doses and doses from long-lived radioactive dust

241 General Electric Nuclear Fuel Facilities

General Electric Canada Inc operates two nuclear fuel facilities in Ontario

bull At the Toronto facility uranium dioxide pellets are produced from natural or depleted uranium dioxide powder

bull At the Peterborough facility uranium dioxide fuel bundles are created from the pellets produced at the Toronto facility

Figures 253ndash256 present dose information for General Electric Canada Incrsquos fuel fabrication facilities from 2001 to 2007 Graphs do not distinguish between the doses received at the Peterborough facility versus those at the Toronto facility

52

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 253 Average Dose Trends for the General Electric Fuel Facility (Based on Non-Zero Results Only)

0

05

1

15

2

25

3

35

Long Lived Radioactive Dust External Effective

Year

Figure 254 Average Dose Trends for the General Electric Fuel Facility (Based on All Monitoring Results)

0

05

1

15

2

25

3

Long Lived Radioactive Dust External Effective

Year

Dos

e (m

Sv)

Dos

e (m

Sv)

53

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 255 Collective Dose Trends for the General Electric Fuel Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Long Lived Radioactive Dust External

Year

Figure 256 Distribution of Effective Doses among all Workers at the General Electric Fuel Facility

0

10

20

30

40

50

60

70

80

90

100

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

54

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

242 Zircatec Nuclear Fuel Facility

Zircatec Precision Industries Inc operates a nuclear fuel facility in Port Hope Ontario where it makes fuel pellets from uranium dioxide powder received from Port Hopersquos uranium conversion facility The nuclear fuel facility also manufactures fuel bundles for nuclear reactors in Canada

Notes on data for the Zircatec nuclear fuel facility

1 Graphs indicate the following data bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of average effective doses

2 Doses from photons from external sources were measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay Historically although these internal doses have been measured and submitted to the CNSC they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

Figures 257ndash260 present dose information for the Zircatec nuclear fuel facility from 2001 to 2007

Figure 257 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on Non-Zero Results)

0

05

1

15

2

25

3

35

Effe

ctiv

e D

ose

(mS

v)

Year

55

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 258 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

18

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 259 Collective Dose Trends for the Zircatec Nuclear Fuel Facility

0

50

100

150

200

250

300

350

400

450

500

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

56

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 260 Distribution of Effective Doses Among All Workers at the Zircatec Nuclear Fuel Facility

300

Num

ber o

f Wor

kers

250

200

150

100

50

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

57

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

25 Research and Radioisotope Production Facilities This section presents dose information for the following research and radioisotope production facilities from 2001 to 2007

bull Chalk River Laboratories and Whiteshell Laboratories (Section 251) bull A radioisotope production facility operated by MDS Nordion (Section 252) bull The Tri-University Meson Facility (TRIUMF) (Section 253)

Note on data for research and radioisotope production facilities

1 Graphs indicate the following data for each facility bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of effective doses

251 Chalk River Laboratories and Whiteshell Laboratories

Atomic Energy of Canada Limited (AECL) owns and is licensed to operate Chalk River Laboratories and Whiteshell Laboratories

Situated in Renfrew County on the south shore of the Ottawa River the Chalk River Laboratories site hosts the National Research Universal Reactor along with numerous other facilities occupying some 160 buildings in an area of approximately 40 km2 Activities consist of radioisotope production for nuclear medicine testing and development of structural materials in support of power reactor operations fuel fabrication research and radioactive waste management and storage

The Whiteshell Laboratories site is located approximately 10 km west of Pinawa Manitoba and 100 km northeast of Winnipeg on the east bank of the Winnipeg River AECL established the laboratories for nuclear research and testing during the early 1960s and has since discontinued operations which are being decommissioned under a licence from the CNSC

Figures 261ndash264 present dose information for Chalk River Laboratories and Whiteshell Laboratories from 2001 to 2007

Notes on data for Chalk River Laboratories and Whiteshell Laboratories

1 Effective doses are composed of the following reported components bull external doses5 (from both photon and neutron doses) bull tritium doses

Due to issues with AECLrsquos in-house dosimetry management system neutron doses were not reported separately to the NDR during the reporting period As a result external doses from photons and neutrons were totaled The reporting discrepancy has since been rectified

58

5

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of external (photon and neutron) and tritium doses Intakes of other radionuclides occasionally occur and these radionuclides are not included here because their associated doses are very small For this reason certain collective doses in this report may have values slightly lower than the sum of their respective components as listed

Figure 261 Average Dose Trends for Chalk River and Whiteshell Laboratories (Non-Zero Results Only)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Tritium External Effective

Year

59

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 262 Average Dose Trends for Chalk River and Whiteshell Laboratories (All Monitoring Results)

000

020

040

060

080

100

120

Dos

e (m

Sv)

Tritium External Effective

Year

Figure 263 Collective Dose Trends for Chalk River and Whiteshell Laboratories

0

500

1000

1500

2000

2500

3000

3500

Col

lect

ive

Dos

e (p

erso

n- m

Sv)

External Tritium

Year

60

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 264 Distribution of Effective Doses Among All Workers at Chalk River and Whiteshell Laboratories

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

3500

3000

2500

2000

1500

1000

500

Dose (mSv)

61

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

252 MDS Nordion (Nuclear Substance Processing Facility and Canadian Irradiation Centre)

MDS Nordion owns and operates a nuclear substance processing facility in Ottawa Ontario where it processes unsealed radioisotopes and manufactures sealed radiation sources In operation since the early 1970s the facility was purchased by Nordion International in 1991

In cooperation with the Universiteacute du Queacutebecrsquos Institut Armand-Frappier MDS Nordion also operates the Canadian Irradiation Centre which conducts various irradiation services which include training testing and development The centre is located in Laval Quebec on the Universiteacute du Queacutebec campus

Figures 265ndash268 present dose information for MDS Nordionrsquos Ottawa nuclear substance processing facility and for the Canadian Irradiation Centre from 2001 to 2007

Notes on data for MDS Nordionrsquos nuclear substance processing facility and the Canadian Irradiation Centre

1 Doses from photons from external sources were measured and reported to the NDR MDS Nordion also has a routine thyroid monitoring program very occasionally small recordable doses of radiation have occurred from thyroid uptake of iodine The resulting doses have not been historically submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided

Figure 265 Average Dose Trends for MDS Nordion (Based on Non-Zero Results)

0

05

1

15

2

25

Effe

ctiv

e D

ose

(mS

v)

Year

62

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 266 Average Dose Trends for MDS Nordion (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

Figure 267 Collective Dose Trends for MDS Nordion

0

100

200

300

400

500

600

700

800

Year

63

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 268 Distribution of Effective Doses Among All Workers at MDS Nordion

0

5 0

1 0 0

1 5 0

2 0 0

2 5 0

3 0 0

3 5 0

4 0 0

4 5 0

5 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

64

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

253 Tri-University Meson Facility

The Tri-University Meson facility (TRIUMF) is situated in Vancouver on the campus of the University of British Columbia TRIUMF which began operating in the early 1970s with one cyclotron now has two cyclotrons and associated laboratories for research and radioisotope production The laboratory provides research facilities for Canadian and international users and also produces radioisotopes which are used by medical facilities and by a commercial organization (MDS Nordion) MDS Nordion staff also work at the TRIUMF site however MDS Nordion oversees this work and has its own radiation protection program

Figures 269ndash272 present dose information for the TRIUMF facility from 2001 to 2007 Please note that data sets do not distinguish between doses received by TRIUMF staff and MDS Nordion staff who work on the site as the data for these two groups was submitted collectively to the NDR for the reporting period shown Future data for each group will be submitted separately to the NDR

Note on data for TRIUMF

1 Effective doses are composed of the following reported components bull doses from photons (labeled as ldquoexternalrdquo in the charts) bull neutron doses

Figure 269 Average Dose Trends for TRIUMF (Non-Zero Results Only)

000

020

040

060

080

100

120

140

160

Dos

e (m

Sv)

Neutrons External Effective

Year

65

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 23: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

2001 2002 2003 2004 2005 2006 2007

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 28 Distribution o f Effective Doses Among A ll Workers at Pickering Nuclear Generating Stati on

6000

5000

4000

3000

2000

1000

0

Num

ber o

f Wor

kers

Dose Range (mSv)

18

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

213 Darlington Nuclear Generating Station

Owned and operated by Ontario Power Generation the Darlington Nuclear Generating Station has four nuclear reactors the first of which began operating in 1989 The facility is located near Bowmanville on the shore of Lake Ontario

Figures 29ndash212 present dose information for the Darlington Nuclear Generating Station from 2001 to 2007

Figure 29 Average Dose Trends for Darlington N uclear Generating Stati on (Non- Zero R esults Only)

)S

v(m

e os

D

250

200

150

100

050

000

Year

19

Tritium Neutrons External Effective

Neutrons External Tritium

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 210 Average Dose Trends for Darlington N uclear Generating Stati on (All Monitoring R esults)

090

080

070

060

050

040

030

020

010

000

)S

v(m

e os

D

Year

Figure 211 Collective Dose Trends for Darlington N uclear Generating Stati on

4500

4000

3500

3000

2500

2000

1500

1000

500

0

)vSm-nosrep (es

Do

eiv

llect

Co

Year

20

2001 2002 2003 2004 2005 2006 2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 212 Distribution o f Effective Doses Among A ll Workers at Darlington Nuclear Generating Stati on

0

500

1000

1500

2000

2500

3000

3500

ers

ork

W of

be

r um

N

Dose Range (mSv)

21

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

214 Gentilly-2 Nuclear Generating Station

The Gentilly-2 Nuclear Generating Station owned and operated by Hydro-Queacutebec has a single reactor that began operating in 1982 The facility is located on the south shore of the St Lawrence River near Trois-Riviegraveres Queacutebec

Figures 213ndash216 present dose information for the Gentilly-2 Nuclear Generating Station from 2001 to 2007

Figure 213 Average Dose Trends for Gentilly-2 Nuclear Generating Stati on (Based o n N on-Zero R esults)

0

05

1

15

2

25

3

35

4

45

)S

v(m

e os

D

Year

22

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 214 Average Dose Trends for Gentilly-2 Nuclear Generating Stati on (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

)S

v(m

e os

D

Year

Figure 215 Collective Dose Trends for Gentilly-2 Nuclear Generating Stati on

0

500

1000

1500

2000

2500

3000

3500

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Neutrons

External

Tritium

Year

23

000-0

009

001-5

00

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 216 Distribution of Effective Doses Among All Workers at Gentilly-2 Nuclear Generating Station

2500

2000

1500

1000

500

0

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

24

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

215 Point Lepreau Nuclear Generating Station

The Point Lepreau Nuclear Generating Station has one reactor that began operating in 1982 Owned and operated by New Brunswick Power Nuclear the station is located in Point Lepreau New Brunswick about 40 km west of Saint John on the shores of the Bay of Fundy

Figures 217ndash220 present dose information for the Point Lepreau Nuclear Generating Station from 2001 to 2007

Figure 217 Average Dose Trends for Point Lepreau N uclear Generating Stati on (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

)S

v(m

e os

D

Tritium Neutron External Effective

Year

25

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 218 Average Dose Trends for Point Lepreau N uclear Generating Stati on (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

)S

v(m

e os

D

Tritium Neutrons External Effective

Year

Figure 219 Collective Dose Trends for Point Lepreau N uclear Generating Station

0

200

400

600

800

1000

1200

1400

1600

1800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Neutrons

External

Tritium

Year

26

0

1400

1200

1000

800

600

400

200

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 220 Distribution of Effective Doses Among All Workers at Point Lepreau Nuclear Generating Station

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

27

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

22 Uranium Mines and Mills This section presents dose information for mine and mill sites in the following regions

bull Cluff Lake (Section 221) bull McClean Lake (Section 222) bull McArthur River (Section 223) bull Key Lake (Section 224) bull Cigar Lake (Section 225) bull Rabbit Lake (Section 226)

Graphs indicate the following data for each site from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for uranium mines and mills

1 Effective doses are composed of the following reported components bull doses from photons (labelled on the charts as ldquoexternalrdquo) bull doses from radon progeny bull doses from long-lived radioactive dust bull doses from radon gas (in some cases)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of photon radon progeny long-lived radioactive dust and radon gas doses

3 The NDR lists radon progeny in working level months (WLM) For this report radon progeny exposures were converted4 to doses expressed in mSv

221 Cluff Lake Operation

The Cluff Lake mining facilities operated by AREVA Resources Canada Inc are located in northwestern Saskatchewan Work began in 1980 and ended in 2002 with the site now being decommissioned The site consisted of three open-pit and two underground mines a mill and a tailings management facility During 2005 and 2006 most of the infrastructure was removed and the affected areas were remediated

Figures 221ndash224 present dose information for the Cluff Lake operation from 2001 to 2007

4 Doses were converted using the International Commission on Radiation Protection (ICRP)rsquos conversion convention of 1 WLM = 5 mSv This convention was established in the ICRP publication Protection against Radon at Home and at Work (ICRP 65)

28

Long-lived radioactive dust Radon progeny External Effective

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 221 Average Dose Trends for the Cluff Lake Operation (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

Year

Figure 222 Average Dose Trends for the Cluff Lake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

200

Long-lived radioactive dust Radon progeny External Effective

)S

v(m

e os

D)

Sv

(me

osD

Year

29

600

500

400

300

200

100

0

External Radon progeny Long-lived radioactive dust

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 223 Collective Dose Trends for the Cluff Lake Operation s

erkor

of W

ber

Num

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Year

Figure 224 Distribution o f Effective Doses Among A ll Workers at the Cluff Lake Operation

0

20

40

60

80

100

120

140

160

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

30

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

222 McClean Lake Operation

AREVA Resources Canada Inc runs the McClean Lake mining operation in northeastern Saskatchewan It comprises open pit mines a mill and a tailings management facility Mining began in 1995 while milling started in 1999

Figures 225ndash228 present dose information for the McClean Lake operation from 2001 to 2007

Figure 225 Average Dose Trends for the McClean L ake Operation (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

31

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 226 Average Dose Trends for the McClean L ake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 227 Collective Dose Trends for the McClean L ake Operation

0

100

200

300

400

500

600

700

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External

Radon progeny

Long-lived radioactive dust

Year

32

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 228 Distribution o f Effective Doses Among A ll Workers at the McClean Lake Operation

0

100

200

300

400

500

600

700

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

33

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

223 McArthur River Operation

Cameco Corporation operates the McArthur River underground mine in north-central Saskatchewan Ore from the mine which began production in 1999 is processed at the Key Lake Mill located 80 km south of McArthur River

Figures 229ndash232 present dose information for the McArthur River operation from 2001 to 2007

Figure 229 Average Dose Trends for the McArthur River Operation (Based o n N on-Zero R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

34

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 230 Average Dose Trends for the McArthur River Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

Figure 231 Collective Dose Trends for the McArthur River Operation

0

200

400

600

800

1000

1200

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Radon gas External Radon progeny Long-lived radioactive dust

Year

35

00

0-000

9

001-5

00

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 232 Distribution o f Effective Doses Among A ll Workers at the McArthur River Operation

0

100

200

300

400

500

600

700

800

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

36

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

224 Key Lake Operation

Cameco Corporation operates mining facilities in Key Lake located in north-central Saskatchewan The Key Lake operation includes two mined-out open pit mines (used for tailings management) a mill and two dry tailings management facilities Mining began in 1983 and ceased in 1997 the mill continued to process ore from the McArthur River mine during the reporting period

Figures 233ndash236 present dose information for the Key Lake operation from 2001 to 2007

Figure 233 Average Dose Trends for the Key Lake Operation (Based o n N on-Zero R esults)

00

20

40

60

80

00

20

40

60

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

37

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

00

20

40

60

80

00

20

40

60

Figure 234 Average Dose Trends for the Key Lake Operation (Based o n A ll Monitoring R esults)

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 235 Collective Dose Trends for the Key Lake Operation

0

100

200

300

400

500

600

700

800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External Radon progeny Long-lived radioactive dust

Year

38

00

0-000

9

001-5

0

501-1

000

gt 1001

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 236 Distribution o f Effective Doses Among A ll Workers at the Key Lake Operation

0

200

400

600

800

1000

1200

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose Range (mSv)

39

se

(mS

v)o

D

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

225 Cigar Lake Operation

Cameco Corporation manages the Cigar Lake underground mine located in northern Saskatchewan at the southern end of Waterbury Lake The mine was under construction at the time of this reportrsquos publication Test mining in ore was carried out in 1991 1992 and 2000

Figures 237ndash240 present dose information for the Cigar Lake operation from

Figure 2 37 Average D ose T rends fo r th e C igar L ake O peration (Based on Non-Zero Results)

2001 to 2007

Year

000

005

010

015

020

025

Long-lived radioactive dust Radon Progeny External Effective

40

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 238 Average Dose Trends for the Cigar Lake Operation (Based on All Monitoring Results)

000

005

010

015

020

025

030

035

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny

External

Effective

Year

Figure 239 Collective Dose Trends for the Cigar Lake Operation

0

50

100

150

200

250

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

External Radon progeny Long-lived radioactive dust

Year

41

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 240 Distribution of Effective Doses Among All Workers at the Cigar Lake Operation

0

200

400

600

800

1000

1200

1400

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

42

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

226 Rabbit Lake Operation

Cameco Corporation owns and operates mining facilities in Rabbit Lake located in north-eastern Saskatchewan Facilities include an underground mine four mined-out open-pit mines a mill and two tailings management facilities Mining and milling began in 1975

Figures 241ndash244 present dose information for the Rabbit Lake operation from 2001 to 2007

Figure 241 Average Dose Trends for the Rabbit Lake Operation (Based on Non-Zero Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

43

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 242 Average Dose Trends for the Rabbit Lake Operation (Based on All Monitoring Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

Figure 243 Collective Dose Trends for the Rabbit Lake Operation

0

200

400

600

800

1000

1200

1400

1600

1800

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Radon gas External Radon progeny Long-lived radioactive dust

Year

44

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

gt300

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 244 Distribution of Effective Doses Among All Workers at the Rabbit Lake Operation

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

900

800

700

600

500

400

300

200

100

0

Dose (mSv)

45

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

23 Uranium Refineries This section presents data for the following two facilities

bull a uranium refining facility in Blind River (Section 231) bull a uranium conversion facility in Port Hope (Section 232)

Graphs indicate the following average doses at each facility from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Note on data for uranium refineries

1 Doses from photons from external sources are measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay and lung counting Historically while these internal doses have been measured they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

231 Blind River Refinery

Cameco Corporation owns and is licensed to operate a uranium refinery in Blind River Ontario The facility which began operating in 1983 converts uranium ore concentrate to uranium trioxide The uranium trioxide is shipped to Camecorsquos uranium conversion facility in Port Hope Ontario where it is processed into uranium dioxide (for use in the fabrication of fuel for nuclear reactors in Canada) or uranium hexafluoride (exported for enrichment and fabrication into fuel for nuclear power reactors around the world)

Figures 245ndash248 present dose information for the Blind River refinery from 2001 to 2007

46

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 245 Average Dose Trends for the Blind River Refinery (Based on Non-Zero Results)

0

05

1

15

2

25

Year

Figure 246 Average Dose Trends for the Blind River Refinery (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

47

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 247 Collective Dose Trends for the Blind River Refinery

0

50

100

150

200

250

300 C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 248 Distribution of Effective Doses Among All Workers at the Blind River Refinery

0

20

40

60

80

100

120

140

160

180

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

48

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

232 Port Hope Conversion Facility

Cameco Corporation owns and is licensed to operate a uranium conversion facility in Port Hope Ontario The facility processes uranium trioxide received from the refinery in Blind River into uranium dioxide and uranium hexafluoride

Figures 249ndash252 present dose information for the Port Hope uranium conversion facility from 2001 to 2007

Figure 249 Average Dose Trends for the Port Hope Conversion Facility (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

49

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 250 Average Dose Trends for the Port Hope Conversion Facility (Based on All Monitoring Results)

0

01

02

03

04

05

06

07

08

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 251 Collective Dose Trends for the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

50

000-0

009

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 252 Distribution of Effective Doses Among All Workers at the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

400

450

500

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

51

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

24 Fuel Fabrication Facilities This section presents data for three nuclear fuel fabrication facilities

bull Two facilities owned and operated by General Electric Canada Inc (Section 241) bull One facility in Port Hope operated by Zircatec Precision Industries (Section 242)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average doses

Notes on data for fuel fabrication facilities

1 Effective doses for the three facilities are composed of the following reported components bull dose from photons (labelled on the charts as ldquoexternalrdquo) bull doses from internal intakes of uranium dust (long-lived radioactive dust) from

uranium in air concentrations (for General Electricrsquos Toronto facility only)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components photon doses and doses from long-lived radioactive dust

241 General Electric Nuclear Fuel Facilities

General Electric Canada Inc operates two nuclear fuel facilities in Ontario

bull At the Toronto facility uranium dioxide pellets are produced from natural or depleted uranium dioxide powder

bull At the Peterborough facility uranium dioxide fuel bundles are created from the pellets produced at the Toronto facility

Figures 253ndash256 present dose information for General Electric Canada Incrsquos fuel fabrication facilities from 2001 to 2007 Graphs do not distinguish between the doses received at the Peterborough facility versus those at the Toronto facility

52

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 253 Average Dose Trends for the General Electric Fuel Facility (Based on Non-Zero Results Only)

0

05

1

15

2

25

3

35

Long Lived Radioactive Dust External Effective

Year

Figure 254 Average Dose Trends for the General Electric Fuel Facility (Based on All Monitoring Results)

0

05

1

15

2

25

3

Long Lived Radioactive Dust External Effective

Year

Dos

e (m

Sv)

Dos

e (m

Sv)

53

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 255 Collective Dose Trends for the General Electric Fuel Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Long Lived Radioactive Dust External

Year

Figure 256 Distribution of Effective Doses among all Workers at the General Electric Fuel Facility

0

10

20

30

40

50

60

70

80

90

100

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

54

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

242 Zircatec Nuclear Fuel Facility

Zircatec Precision Industries Inc operates a nuclear fuel facility in Port Hope Ontario where it makes fuel pellets from uranium dioxide powder received from Port Hopersquos uranium conversion facility The nuclear fuel facility also manufactures fuel bundles for nuclear reactors in Canada

Notes on data for the Zircatec nuclear fuel facility

1 Graphs indicate the following data bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of average effective doses

2 Doses from photons from external sources were measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay Historically although these internal doses have been measured and submitted to the CNSC they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

Figures 257ndash260 present dose information for the Zircatec nuclear fuel facility from 2001 to 2007

Figure 257 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on Non-Zero Results)

0

05

1

15

2

25

3

35

Effe

ctiv

e D

ose

(mS

v)

Year

55

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 258 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

18

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 259 Collective Dose Trends for the Zircatec Nuclear Fuel Facility

0

50

100

150

200

250

300

350

400

450

500

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

56

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 260 Distribution of Effective Doses Among All Workers at the Zircatec Nuclear Fuel Facility

300

Num

ber o

f Wor

kers

250

200

150

100

50

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

57

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

25 Research and Radioisotope Production Facilities This section presents dose information for the following research and radioisotope production facilities from 2001 to 2007

bull Chalk River Laboratories and Whiteshell Laboratories (Section 251) bull A radioisotope production facility operated by MDS Nordion (Section 252) bull The Tri-University Meson Facility (TRIUMF) (Section 253)

Note on data for research and radioisotope production facilities

1 Graphs indicate the following data for each facility bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of effective doses

251 Chalk River Laboratories and Whiteshell Laboratories

Atomic Energy of Canada Limited (AECL) owns and is licensed to operate Chalk River Laboratories and Whiteshell Laboratories

Situated in Renfrew County on the south shore of the Ottawa River the Chalk River Laboratories site hosts the National Research Universal Reactor along with numerous other facilities occupying some 160 buildings in an area of approximately 40 km2 Activities consist of radioisotope production for nuclear medicine testing and development of structural materials in support of power reactor operations fuel fabrication research and radioactive waste management and storage

The Whiteshell Laboratories site is located approximately 10 km west of Pinawa Manitoba and 100 km northeast of Winnipeg on the east bank of the Winnipeg River AECL established the laboratories for nuclear research and testing during the early 1960s and has since discontinued operations which are being decommissioned under a licence from the CNSC

Figures 261ndash264 present dose information for Chalk River Laboratories and Whiteshell Laboratories from 2001 to 2007

Notes on data for Chalk River Laboratories and Whiteshell Laboratories

1 Effective doses are composed of the following reported components bull external doses5 (from both photon and neutron doses) bull tritium doses

Due to issues with AECLrsquos in-house dosimetry management system neutron doses were not reported separately to the NDR during the reporting period As a result external doses from photons and neutrons were totaled The reporting discrepancy has since been rectified

58

5

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of external (photon and neutron) and tritium doses Intakes of other radionuclides occasionally occur and these radionuclides are not included here because their associated doses are very small For this reason certain collective doses in this report may have values slightly lower than the sum of their respective components as listed

Figure 261 Average Dose Trends for Chalk River and Whiteshell Laboratories (Non-Zero Results Only)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Tritium External Effective

Year

59

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 262 Average Dose Trends for Chalk River and Whiteshell Laboratories (All Monitoring Results)

000

020

040

060

080

100

120

Dos

e (m

Sv)

Tritium External Effective

Year

Figure 263 Collective Dose Trends for Chalk River and Whiteshell Laboratories

0

500

1000

1500

2000

2500

3000

3500

Col

lect

ive

Dos

e (p

erso

n- m

Sv)

External Tritium

Year

60

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 264 Distribution of Effective Doses Among All Workers at Chalk River and Whiteshell Laboratories

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

3500

3000

2500

2000

1500

1000

500

Dose (mSv)

61

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

252 MDS Nordion (Nuclear Substance Processing Facility and Canadian Irradiation Centre)

MDS Nordion owns and operates a nuclear substance processing facility in Ottawa Ontario where it processes unsealed radioisotopes and manufactures sealed radiation sources In operation since the early 1970s the facility was purchased by Nordion International in 1991

In cooperation with the Universiteacute du Queacutebecrsquos Institut Armand-Frappier MDS Nordion also operates the Canadian Irradiation Centre which conducts various irradiation services which include training testing and development The centre is located in Laval Quebec on the Universiteacute du Queacutebec campus

Figures 265ndash268 present dose information for MDS Nordionrsquos Ottawa nuclear substance processing facility and for the Canadian Irradiation Centre from 2001 to 2007

Notes on data for MDS Nordionrsquos nuclear substance processing facility and the Canadian Irradiation Centre

1 Doses from photons from external sources were measured and reported to the NDR MDS Nordion also has a routine thyroid monitoring program very occasionally small recordable doses of radiation have occurred from thyroid uptake of iodine The resulting doses have not been historically submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided

Figure 265 Average Dose Trends for MDS Nordion (Based on Non-Zero Results)

0

05

1

15

2

25

Effe

ctiv

e D

ose

(mS

v)

Year

62

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 266 Average Dose Trends for MDS Nordion (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

Figure 267 Collective Dose Trends for MDS Nordion

0

100

200

300

400

500

600

700

800

Year

63

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 268 Distribution of Effective Doses Among All Workers at MDS Nordion

0

5 0

1 0 0

1 5 0

2 0 0

2 5 0

3 0 0

3 5 0

4 0 0

4 5 0

5 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

64

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

253 Tri-University Meson Facility

The Tri-University Meson facility (TRIUMF) is situated in Vancouver on the campus of the University of British Columbia TRIUMF which began operating in the early 1970s with one cyclotron now has two cyclotrons and associated laboratories for research and radioisotope production The laboratory provides research facilities for Canadian and international users and also produces radioisotopes which are used by medical facilities and by a commercial organization (MDS Nordion) MDS Nordion staff also work at the TRIUMF site however MDS Nordion oversees this work and has its own radiation protection program

Figures 269ndash272 present dose information for the TRIUMF facility from 2001 to 2007 Please note that data sets do not distinguish between doses received by TRIUMF staff and MDS Nordion staff who work on the site as the data for these two groups was submitted collectively to the NDR for the reporting period shown Future data for each group will be submitted separately to the NDR

Note on data for TRIUMF

1 Effective doses are composed of the following reported components bull doses from photons (labeled as ldquoexternalrdquo in the charts) bull neutron doses

Figure 269 Average Dose Trends for TRIUMF (Non-Zero Results Only)

000

020

040

060

080

100

120

140

160

Dos

e (m

Sv)

Neutrons External Effective

Year

65

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 24: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

213 Darlington Nuclear Generating Station

Owned and operated by Ontario Power Generation the Darlington Nuclear Generating Station has four nuclear reactors the first of which began operating in 1989 The facility is located near Bowmanville on the shore of Lake Ontario

Figures 29ndash212 present dose information for the Darlington Nuclear Generating Station from 2001 to 2007

Figure 29 Average Dose Trends for Darlington N uclear Generating Stati on (Non- Zero R esults Only)

)S

v(m

e os

D

250

200

150

100

050

000

Year

19

Tritium Neutrons External Effective

Neutrons External Tritium

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 210 Average Dose Trends for Darlington N uclear Generating Stati on (All Monitoring R esults)

090

080

070

060

050

040

030

020

010

000

)S

v(m

e os

D

Year

Figure 211 Collective Dose Trends for Darlington N uclear Generating Stati on

4500

4000

3500

3000

2500

2000

1500

1000

500

0

)vSm-nosrep (es

Do

eiv

llect

Co

Year

20

2001 2002 2003 2004 2005 2006 2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 212 Distribution o f Effective Doses Among A ll Workers at Darlington Nuclear Generating Stati on

0

500

1000

1500

2000

2500

3000

3500

ers

ork

W of

be

r um

N

Dose Range (mSv)

21

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

214 Gentilly-2 Nuclear Generating Station

The Gentilly-2 Nuclear Generating Station owned and operated by Hydro-Queacutebec has a single reactor that began operating in 1982 The facility is located on the south shore of the St Lawrence River near Trois-Riviegraveres Queacutebec

Figures 213ndash216 present dose information for the Gentilly-2 Nuclear Generating Station from 2001 to 2007

Figure 213 Average Dose Trends for Gentilly-2 Nuclear Generating Stati on (Based o n N on-Zero R esults)

0

05

1

15

2

25

3

35

4

45

)S

v(m

e os

D

Year

22

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 214 Average Dose Trends for Gentilly-2 Nuclear Generating Stati on (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

)S

v(m

e os

D

Year

Figure 215 Collective Dose Trends for Gentilly-2 Nuclear Generating Stati on

0

500

1000

1500

2000

2500

3000

3500

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Neutrons

External

Tritium

Year

23

000-0

009

001-5

00

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 216 Distribution of Effective Doses Among All Workers at Gentilly-2 Nuclear Generating Station

2500

2000

1500

1000

500

0

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

24

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

215 Point Lepreau Nuclear Generating Station

The Point Lepreau Nuclear Generating Station has one reactor that began operating in 1982 Owned and operated by New Brunswick Power Nuclear the station is located in Point Lepreau New Brunswick about 40 km west of Saint John on the shores of the Bay of Fundy

Figures 217ndash220 present dose information for the Point Lepreau Nuclear Generating Station from 2001 to 2007

Figure 217 Average Dose Trends for Point Lepreau N uclear Generating Stati on (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

)S

v(m

e os

D

Tritium Neutron External Effective

Year

25

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 218 Average Dose Trends for Point Lepreau N uclear Generating Stati on (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

)S

v(m

e os

D

Tritium Neutrons External Effective

Year

Figure 219 Collective Dose Trends for Point Lepreau N uclear Generating Station

0

200

400

600

800

1000

1200

1400

1600

1800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Neutrons

External

Tritium

Year

26

0

1400

1200

1000

800

600

400

200

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 220 Distribution of Effective Doses Among All Workers at Point Lepreau Nuclear Generating Station

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

27

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

22 Uranium Mines and Mills This section presents dose information for mine and mill sites in the following regions

bull Cluff Lake (Section 221) bull McClean Lake (Section 222) bull McArthur River (Section 223) bull Key Lake (Section 224) bull Cigar Lake (Section 225) bull Rabbit Lake (Section 226)

Graphs indicate the following data for each site from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for uranium mines and mills

1 Effective doses are composed of the following reported components bull doses from photons (labelled on the charts as ldquoexternalrdquo) bull doses from radon progeny bull doses from long-lived radioactive dust bull doses from radon gas (in some cases)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of photon radon progeny long-lived radioactive dust and radon gas doses

3 The NDR lists radon progeny in working level months (WLM) For this report radon progeny exposures were converted4 to doses expressed in mSv

221 Cluff Lake Operation

The Cluff Lake mining facilities operated by AREVA Resources Canada Inc are located in northwestern Saskatchewan Work began in 1980 and ended in 2002 with the site now being decommissioned The site consisted of three open-pit and two underground mines a mill and a tailings management facility During 2005 and 2006 most of the infrastructure was removed and the affected areas were remediated

Figures 221ndash224 present dose information for the Cluff Lake operation from 2001 to 2007

4 Doses were converted using the International Commission on Radiation Protection (ICRP)rsquos conversion convention of 1 WLM = 5 mSv This convention was established in the ICRP publication Protection against Radon at Home and at Work (ICRP 65)

28

Long-lived radioactive dust Radon progeny External Effective

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 221 Average Dose Trends for the Cluff Lake Operation (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

Year

Figure 222 Average Dose Trends for the Cluff Lake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

200

Long-lived radioactive dust Radon progeny External Effective

)S

v(m

e os

D)

Sv

(me

osD

Year

29

600

500

400

300

200

100

0

External Radon progeny Long-lived radioactive dust

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 223 Collective Dose Trends for the Cluff Lake Operation s

erkor

of W

ber

Num

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Year

Figure 224 Distribution o f Effective Doses Among A ll Workers at the Cluff Lake Operation

0

20

40

60

80

100

120

140

160

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

30

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

222 McClean Lake Operation

AREVA Resources Canada Inc runs the McClean Lake mining operation in northeastern Saskatchewan It comprises open pit mines a mill and a tailings management facility Mining began in 1995 while milling started in 1999

Figures 225ndash228 present dose information for the McClean Lake operation from 2001 to 2007

Figure 225 Average Dose Trends for the McClean L ake Operation (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

31

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 226 Average Dose Trends for the McClean L ake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 227 Collective Dose Trends for the McClean L ake Operation

0

100

200

300

400

500

600

700

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External

Radon progeny

Long-lived radioactive dust

Year

32

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 228 Distribution o f Effective Doses Among A ll Workers at the McClean Lake Operation

0

100

200

300

400

500

600

700

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

33

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

223 McArthur River Operation

Cameco Corporation operates the McArthur River underground mine in north-central Saskatchewan Ore from the mine which began production in 1999 is processed at the Key Lake Mill located 80 km south of McArthur River

Figures 229ndash232 present dose information for the McArthur River operation from 2001 to 2007

Figure 229 Average Dose Trends for the McArthur River Operation (Based o n N on-Zero R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

34

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 230 Average Dose Trends for the McArthur River Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

Figure 231 Collective Dose Trends for the McArthur River Operation

0

200

400

600

800

1000

1200

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Radon gas External Radon progeny Long-lived radioactive dust

Year

35

00

0-000

9

001-5

00

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 232 Distribution o f Effective Doses Among A ll Workers at the McArthur River Operation

0

100

200

300

400

500

600

700

800

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

36

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

224 Key Lake Operation

Cameco Corporation operates mining facilities in Key Lake located in north-central Saskatchewan The Key Lake operation includes two mined-out open pit mines (used for tailings management) a mill and two dry tailings management facilities Mining began in 1983 and ceased in 1997 the mill continued to process ore from the McArthur River mine during the reporting period

Figures 233ndash236 present dose information for the Key Lake operation from 2001 to 2007

Figure 233 Average Dose Trends for the Key Lake Operation (Based o n N on-Zero R esults)

00

20

40

60

80

00

20

40

60

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

37

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

00

20

40

60

80

00

20

40

60

Figure 234 Average Dose Trends for the Key Lake Operation (Based o n A ll Monitoring R esults)

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 235 Collective Dose Trends for the Key Lake Operation

0

100

200

300

400

500

600

700

800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External Radon progeny Long-lived radioactive dust

Year

38

00

0-000

9

001-5

0

501-1

000

gt 1001

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 236 Distribution o f Effective Doses Among A ll Workers at the Key Lake Operation

0

200

400

600

800

1000

1200

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose Range (mSv)

39

se

(mS

v)o

D

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

225 Cigar Lake Operation

Cameco Corporation manages the Cigar Lake underground mine located in northern Saskatchewan at the southern end of Waterbury Lake The mine was under construction at the time of this reportrsquos publication Test mining in ore was carried out in 1991 1992 and 2000

Figures 237ndash240 present dose information for the Cigar Lake operation from

Figure 2 37 Average D ose T rends fo r th e C igar L ake O peration (Based on Non-Zero Results)

2001 to 2007

Year

000

005

010

015

020

025

Long-lived radioactive dust Radon Progeny External Effective

40

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 238 Average Dose Trends for the Cigar Lake Operation (Based on All Monitoring Results)

000

005

010

015

020

025

030

035

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny

External

Effective

Year

Figure 239 Collective Dose Trends for the Cigar Lake Operation

0

50

100

150

200

250

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

External Radon progeny Long-lived radioactive dust

Year

41

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 240 Distribution of Effective Doses Among All Workers at the Cigar Lake Operation

0

200

400

600

800

1000

1200

1400

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

42

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

226 Rabbit Lake Operation

Cameco Corporation owns and operates mining facilities in Rabbit Lake located in north-eastern Saskatchewan Facilities include an underground mine four mined-out open-pit mines a mill and two tailings management facilities Mining and milling began in 1975

Figures 241ndash244 present dose information for the Rabbit Lake operation from 2001 to 2007

Figure 241 Average Dose Trends for the Rabbit Lake Operation (Based on Non-Zero Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

43

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 242 Average Dose Trends for the Rabbit Lake Operation (Based on All Monitoring Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

Figure 243 Collective Dose Trends for the Rabbit Lake Operation

0

200

400

600

800

1000

1200

1400

1600

1800

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Radon gas External Radon progeny Long-lived radioactive dust

Year

44

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

gt300

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 244 Distribution of Effective Doses Among All Workers at the Rabbit Lake Operation

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

900

800

700

600

500

400

300

200

100

0

Dose (mSv)

45

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

23 Uranium Refineries This section presents data for the following two facilities

bull a uranium refining facility in Blind River (Section 231) bull a uranium conversion facility in Port Hope (Section 232)

Graphs indicate the following average doses at each facility from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Note on data for uranium refineries

1 Doses from photons from external sources are measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay and lung counting Historically while these internal doses have been measured they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

231 Blind River Refinery

Cameco Corporation owns and is licensed to operate a uranium refinery in Blind River Ontario The facility which began operating in 1983 converts uranium ore concentrate to uranium trioxide The uranium trioxide is shipped to Camecorsquos uranium conversion facility in Port Hope Ontario where it is processed into uranium dioxide (for use in the fabrication of fuel for nuclear reactors in Canada) or uranium hexafluoride (exported for enrichment and fabrication into fuel for nuclear power reactors around the world)

Figures 245ndash248 present dose information for the Blind River refinery from 2001 to 2007

46

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 245 Average Dose Trends for the Blind River Refinery (Based on Non-Zero Results)

0

05

1

15

2

25

Year

Figure 246 Average Dose Trends for the Blind River Refinery (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

47

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 247 Collective Dose Trends for the Blind River Refinery

0

50

100

150

200

250

300 C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 248 Distribution of Effective Doses Among All Workers at the Blind River Refinery

0

20

40

60

80

100

120

140

160

180

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

48

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

232 Port Hope Conversion Facility

Cameco Corporation owns and is licensed to operate a uranium conversion facility in Port Hope Ontario The facility processes uranium trioxide received from the refinery in Blind River into uranium dioxide and uranium hexafluoride

Figures 249ndash252 present dose information for the Port Hope uranium conversion facility from 2001 to 2007

Figure 249 Average Dose Trends for the Port Hope Conversion Facility (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

49

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 250 Average Dose Trends for the Port Hope Conversion Facility (Based on All Monitoring Results)

0

01

02

03

04

05

06

07

08

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 251 Collective Dose Trends for the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

50

000-0

009

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 252 Distribution of Effective Doses Among All Workers at the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

400

450

500

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

51

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

24 Fuel Fabrication Facilities This section presents data for three nuclear fuel fabrication facilities

bull Two facilities owned and operated by General Electric Canada Inc (Section 241) bull One facility in Port Hope operated by Zircatec Precision Industries (Section 242)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average doses

Notes on data for fuel fabrication facilities

1 Effective doses for the three facilities are composed of the following reported components bull dose from photons (labelled on the charts as ldquoexternalrdquo) bull doses from internal intakes of uranium dust (long-lived radioactive dust) from

uranium in air concentrations (for General Electricrsquos Toronto facility only)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components photon doses and doses from long-lived radioactive dust

241 General Electric Nuclear Fuel Facilities

General Electric Canada Inc operates two nuclear fuel facilities in Ontario

bull At the Toronto facility uranium dioxide pellets are produced from natural or depleted uranium dioxide powder

bull At the Peterborough facility uranium dioxide fuel bundles are created from the pellets produced at the Toronto facility

Figures 253ndash256 present dose information for General Electric Canada Incrsquos fuel fabrication facilities from 2001 to 2007 Graphs do not distinguish between the doses received at the Peterborough facility versus those at the Toronto facility

52

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 253 Average Dose Trends for the General Electric Fuel Facility (Based on Non-Zero Results Only)

0

05

1

15

2

25

3

35

Long Lived Radioactive Dust External Effective

Year

Figure 254 Average Dose Trends for the General Electric Fuel Facility (Based on All Monitoring Results)

0

05

1

15

2

25

3

Long Lived Radioactive Dust External Effective

Year

Dos

e (m

Sv)

Dos

e (m

Sv)

53

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 255 Collective Dose Trends for the General Electric Fuel Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Long Lived Radioactive Dust External

Year

Figure 256 Distribution of Effective Doses among all Workers at the General Electric Fuel Facility

0

10

20

30

40

50

60

70

80

90

100

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

54

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

242 Zircatec Nuclear Fuel Facility

Zircatec Precision Industries Inc operates a nuclear fuel facility in Port Hope Ontario where it makes fuel pellets from uranium dioxide powder received from Port Hopersquos uranium conversion facility The nuclear fuel facility also manufactures fuel bundles for nuclear reactors in Canada

Notes on data for the Zircatec nuclear fuel facility

1 Graphs indicate the following data bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of average effective doses

2 Doses from photons from external sources were measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay Historically although these internal doses have been measured and submitted to the CNSC they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

Figures 257ndash260 present dose information for the Zircatec nuclear fuel facility from 2001 to 2007

Figure 257 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on Non-Zero Results)

0

05

1

15

2

25

3

35

Effe

ctiv

e D

ose

(mS

v)

Year

55

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 258 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

18

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 259 Collective Dose Trends for the Zircatec Nuclear Fuel Facility

0

50

100

150

200

250

300

350

400

450

500

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

56

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 260 Distribution of Effective Doses Among All Workers at the Zircatec Nuclear Fuel Facility

300

Num

ber o

f Wor

kers

250

200

150

100

50

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

57

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

25 Research and Radioisotope Production Facilities This section presents dose information for the following research and radioisotope production facilities from 2001 to 2007

bull Chalk River Laboratories and Whiteshell Laboratories (Section 251) bull A radioisotope production facility operated by MDS Nordion (Section 252) bull The Tri-University Meson Facility (TRIUMF) (Section 253)

Note on data for research and radioisotope production facilities

1 Graphs indicate the following data for each facility bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of effective doses

251 Chalk River Laboratories and Whiteshell Laboratories

Atomic Energy of Canada Limited (AECL) owns and is licensed to operate Chalk River Laboratories and Whiteshell Laboratories

Situated in Renfrew County on the south shore of the Ottawa River the Chalk River Laboratories site hosts the National Research Universal Reactor along with numerous other facilities occupying some 160 buildings in an area of approximately 40 km2 Activities consist of radioisotope production for nuclear medicine testing and development of structural materials in support of power reactor operations fuel fabrication research and radioactive waste management and storage

The Whiteshell Laboratories site is located approximately 10 km west of Pinawa Manitoba and 100 km northeast of Winnipeg on the east bank of the Winnipeg River AECL established the laboratories for nuclear research and testing during the early 1960s and has since discontinued operations which are being decommissioned under a licence from the CNSC

Figures 261ndash264 present dose information for Chalk River Laboratories and Whiteshell Laboratories from 2001 to 2007

Notes on data for Chalk River Laboratories and Whiteshell Laboratories

1 Effective doses are composed of the following reported components bull external doses5 (from both photon and neutron doses) bull tritium doses

Due to issues with AECLrsquos in-house dosimetry management system neutron doses were not reported separately to the NDR during the reporting period As a result external doses from photons and neutrons were totaled The reporting discrepancy has since been rectified

58

5

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of external (photon and neutron) and tritium doses Intakes of other radionuclides occasionally occur and these radionuclides are not included here because their associated doses are very small For this reason certain collective doses in this report may have values slightly lower than the sum of their respective components as listed

Figure 261 Average Dose Trends for Chalk River and Whiteshell Laboratories (Non-Zero Results Only)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Tritium External Effective

Year

59

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 262 Average Dose Trends for Chalk River and Whiteshell Laboratories (All Monitoring Results)

000

020

040

060

080

100

120

Dos

e (m

Sv)

Tritium External Effective

Year

Figure 263 Collective Dose Trends for Chalk River and Whiteshell Laboratories

0

500

1000

1500

2000

2500

3000

3500

Col

lect

ive

Dos

e (p

erso

n- m

Sv)

External Tritium

Year

60

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 264 Distribution of Effective Doses Among All Workers at Chalk River and Whiteshell Laboratories

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

3500

3000

2500

2000

1500

1000

500

Dose (mSv)

61

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

252 MDS Nordion (Nuclear Substance Processing Facility and Canadian Irradiation Centre)

MDS Nordion owns and operates a nuclear substance processing facility in Ottawa Ontario where it processes unsealed radioisotopes and manufactures sealed radiation sources In operation since the early 1970s the facility was purchased by Nordion International in 1991

In cooperation with the Universiteacute du Queacutebecrsquos Institut Armand-Frappier MDS Nordion also operates the Canadian Irradiation Centre which conducts various irradiation services which include training testing and development The centre is located in Laval Quebec on the Universiteacute du Queacutebec campus

Figures 265ndash268 present dose information for MDS Nordionrsquos Ottawa nuclear substance processing facility and for the Canadian Irradiation Centre from 2001 to 2007

Notes on data for MDS Nordionrsquos nuclear substance processing facility and the Canadian Irradiation Centre

1 Doses from photons from external sources were measured and reported to the NDR MDS Nordion also has a routine thyroid monitoring program very occasionally small recordable doses of radiation have occurred from thyroid uptake of iodine The resulting doses have not been historically submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided

Figure 265 Average Dose Trends for MDS Nordion (Based on Non-Zero Results)

0

05

1

15

2

25

Effe

ctiv

e D

ose

(mS

v)

Year

62

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 266 Average Dose Trends for MDS Nordion (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

Figure 267 Collective Dose Trends for MDS Nordion

0

100

200

300

400

500

600

700

800

Year

63

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 268 Distribution of Effective Doses Among All Workers at MDS Nordion

0

5 0

1 0 0

1 5 0

2 0 0

2 5 0

3 0 0

3 5 0

4 0 0

4 5 0

5 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

64

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

253 Tri-University Meson Facility

The Tri-University Meson facility (TRIUMF) is situated in Vancouver on the campus of the University of British Columbia TRIUMF which began operating in the early 1970s with one cyclotron now has two cyclotrons and associated laboratories for research and radioisotope production The laboratory provides research facilities for Canadian and international users and also produces radioisotopes which are used by medical facilities and by a commercial organization (MDS Nordion) MDS Nordion staff also work at the TRIUMF site however MDS Nordion oversees this work and has its own radiation protection program

Figures 269ndash272 present dose information for the TRIUMF facility from 2001 to 2007 Please note that data sets do not distinguish between doses received by TRIUMF staff and MDS Nordion staff who work on the site as the data for these two groups was submitted collectively to the NDR for the reporting period shown Future data for each group will be submitted separately to the NDR

Note on data for TRIUMF

1 Effective doses are composed of the following reported components bull doses from photons (labeled as ldquoexternalrdquo in the charts) bull neutron doses

Figure 269 Average Dose Trends for TRIUMF (Non-Zero Results Only)

000

020

040

060

080

100

120

140

160

Dos

e (m

Sv)

Neutrons External Effective

Year

65

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 25: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

Tritium Neutrons External Effective

Neutrons External Tritium

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 210 Average Dose Trends for Darlington N uclear Generating Stati on (All Monitoring R esults)

090

080

070

060

050

040

030

020

010

000

)S

v(m

e os

D

Year

Figure 211 Collective Dose Trends for Darlington N uclear Generating Stati on

4500

4000

3500

3000

2500

2000

1500

1000

500

0

)vSm-nosrep (es

Do

eiv

llect

Co

Year

20

2001 2002 2003 2004 2005 2006 2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 212 Distribution o f Effective Doses Among A ll Workers at Darlington Nuclear Generating Stati on

0

500

1000

1500

2000

2500

3000

3500

ers

ork

W of

be

r um

N

Dose Range (mSv)

21

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

214 Gentilly-2 Nuclear Generating Station

The Gentilly-2 Nuclear Generating Station owned and operated by Hydro-Queacutebec has a single reactor that began operating in 1982 The facility is located on the south shore of the St Lawrence River near Trois-Riviegraveres Queacutebec

Figures 213ndash216 present dose information for the Gentilly-2 Nuclear Generating Station from 2001 to 2007

Figure 213 Average Dose Trends for Gentilly-2 Nuclear Generating Stati on (Based o n N on-Zero R esults)

0

05

1

15

2

25

3

35

4

45

)S

v(m

e os

D

Year

22

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 214 Average Dose Trends for Gentilly-2 Nuclear Generating Stati on (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

)S

v(m

e os

D

Year

Figure 215 Collective Dose Trends for Gentilly-2 Nuclear Generating Stati on

0

500

1000

1500

2000

2500

3000

3500

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Neutrons

External

Tritium

Year

23

000-0

009

001-5

00

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 216 Distribution of Effective Doses Among All Workers at Gentilly-2 Nuclear Generating Station

2500

2000

1500

1000

500

0

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

24

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

215 Point Lepreau Nuclear Generating Station

The Point Lepreau Nuclear Generating Station has one reactor that began operating in 1982 Owned and operated by New Brunswick Power Nuclear the station is located in Point Lepreau New Brunswick about 40 km west of Saint John on the shores of the Bay of Fundy

Figures 217ndash220 present dose information for the Point Lepreau Nuclear Generating Station from 2001 to 2007

Figure 217 Average Dose Trends for Point Lepreau N uclear Generating Stati on (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

)S

v(m

e os

D

Tritium Neutron External Effective

Year

25

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 218 Average Dose Trends for Point Lepreau N uclear Generating Stati on (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

)S

v(m

e os

D

Tritium Neutrons External Effective

Year

Figure 219 Collective Dose Trends for Point Lepreau N uclear Generating Station

0

200

400

600

800

1000

1200

1400

1600

1800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Neutrons

External

Tritium

Year

26

0

1400

1200

1000

800

600

400

200

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 220 Distribution of Effective Doses Among All Workers at Point Lepreau Nuclear Generating Station

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

27

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

22 Uranium Mines and Mills This section presents dose information for mine and mill sites in the following regions

bull Cluff Lake (Section 221) bull McClean Lake (Section 222) bull McArthur River (Section 223) bull Key Lake (Section 224) bull Cigar Lake (Section 225) bull Rabbit Lake (Section 226)

Graphs indicate the following data for each site from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for uranium mines and mills

1 Effective doses are composed of the following reported components bull doses from photons (labelled on the charts as ldquoexternalrdquo) bull doses from radon progeny bull doses from long-lived radioactive dust bull doses from radon gas (in some cases)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of photon radon progeny long-lived radioactive dust and radon gas doses

3 The NDR lists radon progeny in working level months (WLM) For this report radon progeny exposures were converted4 to doses expressed in mSv

221 Cluff Lake Operation

The Cluff Lake mining facilities operated by AREVA Resources Canada Inc are located in northwestern Saskatchewan Work began in 1980 and ended in 2002 with the site now being decommissioned The site consisted of three open-pit and two underground mines a mill and a tailings management facility During 2005 and 2006 most of the infrastructure was removed and the affected areas were remediated

Figures 221ndash224 present dose information for the Cluff Lake operation from 2001 to 2007

4 Doses were converted using the International Commission on Radiation Protection (ICRP)rsquos conversion convention of 1 WLM = 5 mSv This convention was established in the ICRP publication Protection against Radon at Home and at Work (ICRP 65)

28

Long-lived radioactive dust Radon progeny External Effective

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 221 Average Dose Trends for the Cluff Lake Operation (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

Year

Figure 222 Average Dose Trends for the Cluff Lake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

200

Long-lived radioactive dust Radon progeny External Effective

)S

v(m

e os

D)

Sv

(me

osD

Year

29

600

500

400

300

200

100

0

External Radon progeny Long-lived radioactive dust

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 223 Collective Dose Trends for the Cluff Lake Operation s

erkor

of W

ber

Num

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Year

Figure 224 Distribution o f Effective Doses Among A ll Workers at the Cluff Lake Operation

0

20

40

60

80

100

120

140

160

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

30

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

222 McClean Lake Operation

AREVA Resources Canada Inc runs the McClean Lake mining operation in northeastern Saskatchewan It comprises open pit mines a mill and a tailings management facility Mining began in 1995 while milling started in 1999

Figures 225ndash228 present dose information for the McClean Lake operation from 2001 to 2007

Figure 225 Average Dose Trends for the McClean L ake Operation (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

31

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 226 Average Dose Trends for the McClean L ake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 227 Collective Dose Trends for the McClean L ake Operation

0

100

200

300

400

500

600

700

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External

Radon progeny

Long-lived radioactive dust

Year

32

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 228 Distribution o f Effective Doses Among A ll Workers at the McClean Lake Operation

0

100

200

300

400

500

600

700

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

33

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

223 McArthur River Operation

Cameco Corporation operates the McArthur River underground mine in north-central Saskatchewan Ore from the mine which began production in 1999 is processed at the Key Lake Mill located 80 km south of McArthur River

Figures 229ndash232 present dose information for the McArthur River operation from 2001 to 2007

Figure 229 Average Dose Trends for the McArthur River Operation (Based o n N on-Zero R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

34

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 230 Average Dose Trends for the McArthur River Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

Figure 231 Collective Dose Trends for the McArthur River Operation

0

200

400

600

800

1000

1200

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Radon gas External Radon progeny Long-lived radioactive dust

Year

35

00

0-000

9

001-5

00

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 232 Distribution o f Effective Doses Among A ll Workers at the McArthur River Operation

0

100

200

300

400

500

600

700

800

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

36

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

224 Key Lake Operation

Cameco Corporation operates mining facilities in Key Lake located in north-central Saskatchewan The Key Lake operation includes two mined-out open pit mines (used for tailings management) a mill and two dry tailings management facilities Mining began in 1983 and ceased in 1997 the mill continued to process ore from the McArthur River mine during the reporting period

Figures 233ndash236 present dose information for the Key Lake operation from 2001 to 2007

Figure 233 Average Dose Trends for the Key Lake Operation (Based o n N on-Zero R esults)

00

20

40

60

80

00

20

40

60

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

37

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

00

20

40

60

80

00

20

40

60

Figure 234 Average Dose Trends for the Key Lake Operation (Based o n A ll Monitoring R esults)

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 235 Collective Dose Trends for the Key Lake Operation

0

100

200

300

400

500

600

700

800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External Radon progeny Long-lived radioactive dust

Year

38

00

0-000

9

001-5

0

501-1

000

gt 1001

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 236 Distribution o f Effective Doses Among A ll Workers at the Key Lake Operation

0

200

400

600

800

1000

1200

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose Range (mSv)

39

se

(mS

v)o

D

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

225 Cigar Lake Operation

Cameco Corporation manages the Cigar Lake underground mine located in northern Saskatchewan at the southern end of Waterbury Lake The mine was under construction at the time of this reportrsquos publication Test mining in ore was carried out in 1991 1992 and 2000

Figures 237ndash240 present dose information for the Cigar Lake operation from

Figure 2 37 Average D ose T rends fo r th e C igar L ake O peration (Based on Non-Zero Results)

2001 to 2007

Year

000

005

010

015

020

025

Long-lived radioactive dust Radon Progeny External Effective

40

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 238 Average Dose Trends for the Cigar Lake Operation (Based on All Monitoring Results)

000

005

010

015

020

025

030

035

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny

External

Effective

Year

Figure 239 Collective Dose Trends for the Cigar Lake Operation

0

50

100

150

200

250

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

External Radon progeny Long-lived radioactive dust

Year

41

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 240 Distribution of Effective Doses Among All Workers at the Cigar Lake Operation

0

200

400

600

800

1000

1200

1400

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

42

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

226 Rabbit Lake Operation

Cameco Corporation owns and operates mining facilities in Rabbit Lake located in north-eastern Saskatchewan Facilities include an underground mine four mined-out open-pit mines a mill and two tailings management facilities Mining and milling began in 1975

Figures 241ndash244 present dose information for the Rabbit Lake operation from 2001 to 2007

Figure 241 Average Dose Trends for the Rabbit Lake Operation (Based on Non-Zero Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

43

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 242 Average Dose Trends for the Rabbit Lake Operation (Based on All Monitoring Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

Figure 243 Collective Dose Trends for the Rabbit Lake Operation

0

200

400

600

800

1000

1200

1400

1600

1800

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Radon gas External Radon progeny Long-lived radioactive dust

Year

44

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

gt300

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 244 Distribution of Effective Doses Among All Workers at the Rabbit Lake Operation

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

900

800

700

600

500

400

300

200

100

0

Dose (mSv)

45

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

23 Uranium Refineries This section presents data for the following two facilities

bull a uranium refining facility in Blind River (Section 231) bull a uranium conversion facility in Port Hope (Section 232)

Graphs indicate the following average doses at each facility from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Note on data for uranium refineries

1 Doses from photons from external sources are measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay and lung counting Historically while these internal doses have been measured they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

231 Blind River Refinery

Cameco Corporation owns and is licensed to operate a uranium refinery in Blind River Ontario The facility which began operating in 1983 converts uranium ore concentrate to uranium trioxide The uranium trioxide is shipped to Camecorsquos uranium conversion facility in Port Hope Ontario where it is processed into uranium dioxide (for use in the fabrication of fuel for nuclear reactors in Canada) or uranium hexafluoride (exported for enrichment and fabrication into fuel for nuclear power reactors around the world)

Figures 245ndash248 present dose information for the Blind River refinery from 2001 to 2007

46

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 245 Average Dose Trends for the Blind River Refinery (Based on Non-Zero Results)

0

05

1

15

2

25

Year

Figure 246 Average Dose Trends for the Blind River Refinery (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

47

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 247 Collective Dose Trends for the Blind River Refinery

0

50

100

150

200

250

300 C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 248 Distribution of Effective Doses Among All Workers at the Blind River Refinery

0

20

40

60

80

100

120

140

160

180

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

48

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

232 Port Hope Conversion Facility

Cameco Corporation owns and is licensed to operate a uranium conversion facility in Port Hope Ontario The facility processes uranium trioxide received from the refinery in Blind River into uranium dioxide and uranium hexafluoride

Figures 249ndash252 present dose information for the Port Hope uranium conversion facility from 2001 to 2007

Figure 249 Average Dose Trends for the Port Hope Conversion Facility (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

49

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 250 Average Dose Trends for the Port Hope Conversion Facility (Based on All Monitoring Results)

0

01

02

03

04

05

06

07

08

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 251 Collective Dose Trends for the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

50

000-0

009

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 252 Distribution of Effective Doses Among All Workers at the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

400

450

500

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

51

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

24 Fuel Fabrication Facilities This section presents data for three nuclear fuel fabrication facilities

bull Two facilities owned and operated by General Electric Canada Inc (Section 241) bull One facility in Port Hope operated by Zircatec Precision Industries (Section 242)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average doses

Notes on data for fuel fabrication facilities

1 Effective doses for the three facilities are composed of the following reported components bull dose from photons (labelled on the charts as ldquoexternalrdquo) bull doses from internal intakes of uranium dust (long-lived radioactive dust) from

uranium in air concentrations (for General Electricrsquos Toronto facility only)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components photon doses and doses from long-lived radioactive dust

241 General Electric Nuclear Fuel Facilities

General Electric Canada Inc operates two nuclear fuel facilities in Ontario

bull At the Toronto facility uranium dioxide pellets are produced from natural or depleted uranium dioxide powder

bull At the Peterborough facility uranium dioxide fuel bundles are created from the pellets produced at the Toronto facility

Figures 253ndash256 present dose information for General Electric Canada Incrsquos fuel fabrication facilities from 2001 to 2007 Graphs do not distinguish between the doses received at the Peterborough facility versus those at the Toronto facility

52

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 253 Average Dose Trends for the General Electric Fuel Facility (Based on Non-Zero Results Only)

0

05

1

15

2

25

3

35

Long Lived Radioactive Dust External Effective

Year

Figure 254 Average Dose Trends for the General Electric Fuel Facility (Based on All Monitoring Results)

0

05

1

15

2

25

3

Long Lived Radioactive Dust External Effective

Year

Dos

e (m

Sv)

Dos

e (m

Sv)

53

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 255 Collective Dose Trends for the General Electric Fuel Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Long Lived Radioactive Dust External

Year

Figure 256 Distribution of Effective Doses among all Workers at the General Electric Fuel Facility

0

10

20

30

40

50

60

70

80

90

100

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

54

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

242 Zircatec Nuclear Fuel Facility

Zircatec Precision Industries Inc operates a nuclear fuel facility in Port Hope Ontario where it makes fuel pellets from uranium dioxide powder received from Port Hopersquos uranium conversion facility The nuclear fuel facility also manufactures fuel bundles for nuclear reactors in Canada

Notes on data for the Zircatec nuclear fuel facility

1 Graphs indicate the following data bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of average effective doses

2 Doses from photons from external sources were measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay Historically although these internal doses have been measured and submitted to the CNSC they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

Figures 257ndash260 present dose information for the Zircatec nuclear fuel facility from 2001 to 2007

Figure 257 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on Non-Zero Results)

0

05

1

15

2

25

3

35

Effe

ctiv

e D

ose

(mS

v)

Year

55

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 258 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

18

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 259 Collective Dose Trends for the Zircatec Nuclear Fuel Facility

0

50

100

150

200

250

300

350

400

450

500

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

56

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 260 Distribution of Effective Doses Among All Workers at the Zircatec Nuclear Fuel Facility

300

Num

ber o

f Wor

kers

250

200

150

100

50

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

57

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

25 Research and Radioisotope Production Facilities This section presents dose information for the following research and radioisotope production facilities from 2001 to 2007

bull Chalk River Laboratories and Whiteshell Laboratories (Section 251) bull A radioisotope production facility operated by MDS Nordion (Section 252) bull The Tri-University Meson Facility (TRIUMF) (Section 253)

Note on data for research and radioisotope production facilities

1 Graphs indicate the following data for each facility bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of effective doses

251 Chalk River Laboratories and Whiteshell Laboratories

Atomic Energy of Canada Limited (AECL) owns and is licensed to operate Chalk River Laboratories and Whiteshell Laboratories

Situated in Renfrew County on the south shore of the Ottawa River the Chalk River Laboratories site hosts the National Research Universal Reactor along with numerous other facilities occupying some 160 buildings in an area of approximately 40 km2 Activities consist of radioisotope production for nuclear medicine testing and development of structural materials in support of power reactor operations fuel fabrication research and radioactive waste management and storage

The Whiteshell Laboratories site is located approximately 10 km west of Pinawa Manitoba and 100 km northeast of Winnipeg on the east bank of the Winnipeg River AECL established the laboratories for nuclear research and testing during the early 1960s and has since discontinued operations which are being decommissioned under a licence from the CNSC

Figures 261ndash264 present dose information for Chalk River Laboratories and Whiteshell Laboratories from 2001 to 2007

Notes on data for Chalk River Laboratories and Whiteshell Laboratories

1 Effective doses are composed of the following reported components bull external doses5 (from both photon and neutron doses) bull tritium doses

Due to issues with AECLrsquos in-house dosimetry management system neutron doses were not reported separately to the NDR during the reporting period As a result external doses from photons and neutrons were totaled The reporting discrepancy has since been rectified

58

5

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of external (photon and neutron) and tritium doses Intakes of other radionuclides occasionally occur and these radionuclides are not included here because their associated doses are very small For this reason certain collective doses in this report may have values slightly lower than the sum of their respective components as listed

Figure 261 Average Dose Trends for Chalk River and Whiteshell Laboratories (Non-Zero Results Only)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Tritium External Effective

Year

59

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 262 Average Dose Trends for Chalk River and Whiteshell Laboratories (All Monitoring Results)

000

020

040

060

080

100

120

Dos

e (m

Sv)

Tritium External Effective

Year

Figure 263 Collective Dose Trends for Chalk River and Whiteshell Laboratories

0

500

1000

1500

2000

2500

3000

3500

Col

lect

ive

Dos

e (p

erso

n- m

Sv)

External Tritium

Year

60

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 264 Distribution of Effective Doses Among All Workers at Chalk River and Whiteshell Laboratories

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

3500

3000

2500

2000

1500

1000

500

Dose (mSv)

61

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

252 MDS Nordion (Nuclear Substance Processing Facility and Canadian Irradiation Centre)

MDS Nordion owns and operates a nuclear substance processing facility in Ottawa Ontario where it processes unsealed radioisotopes and manufactures sealed radiation sources In operation since the early 1970s the facility was purchased by Nordion International in 1991

In cooperation with the Universiteacute du Queacutebecrsquos Institut Armand-Frappier MDS Nordion also operates the Canadian Irradiation Centre which conducts various irradiation services which include training testing and development The centre is located in Laval Quebec on the Universiteacute du Queacutebec campus

Figures 265ndash268 present dose information for MDS Nordionrsquos Ottawa nuclear substance processing facility and for the Canadian Irradiation Centre from 2001 to 2007

Notes on data for MDS Nordionrsquos nuclear substance processing facility and the Canadian Irradiation Centre

1 Doses from photons from external sources were measured and reported to the NDR MDS Nordion also has a routine thyroid monitoring program very occasionally small recordable doses of radiation have occurred from thyroid uptake of iodine The resulting doses have not been historically submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided

Figure 265 Average Dose Trends for MDS Nordion (Based on Non-Zero Results)

0

05

1

15

2

25

Effe

ctiv

e D

ose

(mS

v)

Year

62

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 266 Average Dose Trends for MDS Nordion (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

Figure 267 Collective Dose Trends for MDS Nordion

0

100

200

300

400

500

600

700

800

Year

63

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 268 Distribution of Effective Doses Among All Workers at MDS Nordion

0

5 0

1 0 0

1 5 0

2 0 0

2 5 0

3 0 0

3 5 0

4 0 0

4 5 0

5 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

64

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

253 Tri-University Meson Facility

The Tri-University Meson facility (TRIUMF) is situated in Vancouver on the campus of the University of British Columbia TRIUMF which began operating in the early 1970s with one cyclotron now has two cyclotrons and associated laboratories for research and radioisotope production The laboratory provides research facilities for Canadian and international users and also produces radioisotopes which are used by medical facilities and by a commercial organization (MDS Nordion) MDS Nordion staff also work at the TRIUMF site however MDS Nordion oversees this work and has its own radiation protection program

Figures 269ndash272 present dose information for the TRIUMF facility from 2001 to 2007 Please note that data sets do not distinguish between doses received by TRIUMF staff and MDS Nordion staff who work on the site as the data for these two groups was submitted collectively to the NDR for the reporting period shown Future data for each group will be submitted separately to the NDR

Note on data for TRIUMF

1 Effective doses are composed of the following reported components bull doses from photons (labeled as ldquoexternalrdquo in the charts) bull neutron doses

Figure 269 Average Dose Trends for TRIUMF (Non-Zero Results Only)

000

020

040

060

080

100

120

140

160

Dos

e (m

Sv)

Neutrons External Effective

Year

65

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 26: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

2001 2002 2003 2004 2005 2006 2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 212 Distribution o f Effective Doses Among A ll Workers at Darlington Nuclear Generating Stati on

0

500

1000

1500

2000

2500

3000

3500

ers

ork

W of

be

r um

N

Dose Range (mSv)

21

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

214 Gentilly-2 Nuclear Generating Station

The Gentilly-2 Nuclear Generating Station owned and operated by Hydro-Queacutebec has a single reactor that began operating in 1982 The facility is located on the south shore of the St Lawrence River near Trois-Riviegraveres Queacutebec

Figures 213ndash216 present dose information for the Gentilly-2 Nuclear Generating Station from 2001 to 2007

Figure 213 Average Dose Trends for Gentilly-2 Nuclear Generating Stati on (Based o n N on-Zero R esults)

0

05

1

15

2

25

3

35

4

45

)S

v(m

e os

D

Year

22

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 214 Average Dose Trends for Gentilly-2 Nuclear Generating Stati on (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

)S

v(m

e os

D

Year

Figure 215 Collective Dose Trends for Gentilly-2 Nuclear Generating Stati on

0

500

1000

1500

2000

2500

3000

3500

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Neutrons

External

Tritium

Year

23

000-0

009

001-5

00

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 216 Distribution of Effective Doses Among All Workers at Gentilly-2 Nuclear Generating Station

2500

2000

1500

1000

500

0

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

24

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

215 Point Lepreau Nuclear Generating Station

The Point Lepreau Nuclear Generating Station has one reactor that began operating in 1982 Owned and operated by New Brunswick Power Nuclear the station is located in Point Lepreau New Brunswick about 40 km west of Saint John on the shores of the Bay of Fundy

Figures 217ndash220 present dose information for the Point Lepreau Nuclear Generating Station from 2001 to 2007

Figure 217 Average Dose Trends for Point Lepreau N uclear Generating Stati on (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

)S

v(m

e os

D

Tritium Neutron External Effective

Year

25

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 218 Average Dose Trends for Point Lepreau N uclear Generating Stati on (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

)S

v(m

e os

D

Tritium Neutrons External Effective

Year

Figure 219 Collective Dose Trends for Point Lepreau N uclear Generating Station

0

200

400

600

800

1000

1200

1400

1600

1800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Neutrons

External

Tritium

Year

26

0

1400

1200

1000

800

600

400

200

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 220 Distribution of Effective Doses Among All Workers at Point Lepreau Nuclear Generating Station

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

27

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

22 Uranium Mines and Mills This section presents dose information for mine and mill sites in the following regions

bull Cluff Lake (Section 221) bull McClean Lake (Section 222) bull McArthur River (Section 223) bull Key Lake (Section 224) bull Cigar Lake (Section 225) bull Rabbit Lake (Section 226)

Graphs indicate the following data for each site from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for uranium mines and mills

1 Effective doses are composed of the following reported components bull doses from photons (labelled on the charts as ldquoexternalrdquo) bull doses from radon progeny bull doses from long-lived radioactive dust bull doses from radon gas (in some cases)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of photon radon progeny long-lived radioactive dust and radon gas doses

3 The NDR lists radon progeny in working level months (WLM) For this report radon progeny exposures were converted4 to doses expressed in mSv

221 Cluff Lake Operation

The Cluff Lake mining facilities operated by AREVA Resources Canada Inc are located in northwestern Saskatchewan Work began in 1980 and ended in 2002 with the site now being decommissioned The site consisted of three open-pit and two underground mines a mill and a tailings management facility During 2005 and 2006 most of the infrastructure was removed and the affected areas were remediated

Figures 221ndash224 present dose information for the Cluff Lake operation from 2001 to 2007

4 Doses were converted using the International Commission on Radiation Protection (ICRP)rsquos conversion convention of 1 WLM = 5 mSv This convention was established in the ICRP publication Protection against Radon at Home and at Work (ICRP 65)

28

Long-lived radioactive dust Radon progeny External Effective

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 221 Average Dose Trends for the Cluff Lake Operation (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

Year

Figure 222 Average Dose Trends for the Cluff Lake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

200

Long-lived radioactive dust Radon progeny External Effective

)S

v(m

e os

D)

Sv

(me

osD

Year

29

600

500

400

300

200

100

0

External Radon progeny Long-lived radioactive dust

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 223 Collective Dose Trends for the Cluff Lake Operation s

erkor

of W

ber

Num

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Year

Figure 224 Distribution o f Effective Doses Among A ll Workers at the Cluff Lake Operation

0

20

40

60

80

100

120

140

160

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

30

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

222 McClean Lake Operation

AREVA Resources Canada Inc runs the McClean Lake mining operation in northeastern Saskatchewan It comprises open pit mines a mill and a tailings management facility Mining began in 1995 while milling started in 1999

Figures 225ndash228 present dose information for the McClean Lake operation from 2001 to 2007

Figure 225 Average Dose Trends for the McClean L ake Operation (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

31

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 226 Average Dose Trends for the McClean L ake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 227 Collective Dose Trends for the McClean L ake Operation

0

100

200

300

400

500

600

700

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External

Radon progeny

Long-lived radioactive dust

Year

32

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 228 Distribution o f Effective Doses Among A ll Workers at the McClean Lake Operation

0

100

200

300

400

500

600

700

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

33

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

223 McArthur River Operation

Cameco Corporation operates the McArthur River underground mine in north-central Saskatchewan Ore from the mine which began production in 1999 is processed at the Key Lake Mill located 80 km south of McArthur River

Figures 229ndash232 present dose information for the McArthur River operation from 2001 to 2007

Figure 229 Average Dose Trends for the McArthur River Operation (Based o n N on-Zero R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

34

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 230 Average Dose Trends for the McArthur River Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

Figure 231 Collective Dose Trends for the McArthur River Operation

0

200

400

600

800

1000

1200

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Radon gas External Radon progeny Long-lived radioactive dust

Year

35

00

0-000

9

001-5

00

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 232 Distribution o f Effective Doses Among A ll Workers at the McArthur River Operation

0

100

200

300

400

500

600

700

800

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

36

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

224 Key Lake Operation

Cameco Corporation operates mining facilities in Key Lake located in north-central Saskatchewan The Key Lake operation includes two mined-out open pit mines (used for tailings management) a mill and two dry tailings management facilities Mining began in 1983 and ceased in 1997 the mill continued to process ore from the McArthur River mine during the reporting period

Figures 233ndash236 present dose information for the Key Lake operation from 2001 to 2007

Figure 233 Average Dose Trends for the Key Lake Operation (Based o n N on-Zero R esults)

00

20

40

60

80

00

20

40

60

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

37

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

00

20

40

60

80

00

20

40

60

Figure 234 Average Dose Trends for the Key Lake Operation (Based o n A ll Monitoring R esults)

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 235 Collective Dose Trends for the Key Lake Operation

0

100

200

300

400

500

600

700

800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External Radon progeny Long-lived radioactive dust

Year

38

00

0-000

9

001-5

0

501-1

000

gt 1001

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 236 Distribution o f Effective Doses Among A ll Workers at the Key Lake Operation

0

200

400

600

800

1000

1200

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose Range (mSv)

39

se

(mS

v)o

D

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

225 Cigar Lake Operation

Cameco Corporation manages the Cigar Lake underground mine located in northern Saskatchewan at the southern end of Waterbury Lake The mine was under construction at the time of this reportrsquos publication Test mining in ore was carried out in 1991 1992 and 2000

Figures 237ndash240 present dose information for the Cigar Lake operation from

Figure 2 37 Average D ose T rends fo r th e C igar L ake O peration (Based on Non-Zero Results)

2001 to 2007

Year

000

005

010

015

020

025

Long-lived radioactive dust Radon Progeny External Effective

40

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 238 Average Dose Trends for the Cigar Lake Operation (Based on All Monitoring Results)

000

005

010

015

020

025

030

035

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny

External

Effective

Year

Figure 239 Collective Dose Trends for the Cigar Lake Operation

0

50

100

150

200

250

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

External Radon progeny Long-lived radioactive dust

Year

41

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 240 Distribution of Effective Doses Among All Workers at the Cigar Lake Operation

0

200

400

600

800

1000

1200

1400

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

42

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

226 Rabbit Lake Operation

Cameco Corporation owns and operates mining facilities in Rabbit Lake located in north-eastern Saskatchewan Facilities include an underground mine four mined-out open-pit mines a mill and two tailings management facilities Mining and milling began in 1975

Figures 241ndash244 present dose information for the Rabbit Lake operation from 2001 to 2007

Figure 241 Average Dose Trends for the Rabbit Lake Operation (Based on Non-Zero Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

43

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 242 Average Dose Trends for the Rabbit Lake Operation (Based on All Monitoring Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

Figure 243 Collective Dose Trends for the Rabbit Lake Operation

0

200

400

600

800

1000

1200

1400

1600

1800

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Radon gas External Radon progeny Long-lived radioactive dust

Year

44

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

gt300

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 244 Distribution of Effective Doses Among All Workers at the Rabbit Lake Operation

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

900

800

700

600

500

400

300

200

100

0

Dose (mSv)

45

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

23 Uranium Refineries This section presents data for the following two facilities

bull a uranium refining facility in Blind River (Section 231) bull a uranium conversion facility in Port Hope (Section 232)

Graphs indicate the following average doses at each facility from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Note on data for uranium refineries

1 Doses from photons from external sources are measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay and lung counting Historically while these internal doses have been measured they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

231 Blind River Refinery

Cameco Corporation owns and is licensed to operate a uranium refinery in Blind River Ontario The facility which began operating in 1983 converts uranium ore concentrate to uranium trioxide The uranium trioxide is shipped to Camecorsquos uranium conversion facility in Port Hope Ontario where it is processed into uranium dioxide (for use in the fabrication of fuel for nuclear reactors in Canada) or uranium hexafluoride (exported for enrichment and fabrication into fuel for nuclear power reactors around the world)

Figures 245ndash248 present dose information for the Blind River refinery from 2001 to 2007

46

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 245 Average Dose Trends for the Blind River Refinery (Based on Non-Zero Results)

0

05

1

15

2

25

Year

Figure 246 Average Dose Trends for the Blind River Refinery (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

47

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 247 Collective Dose Trends for the Blind River Refinery

0

50

100

150

200

250

300 C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 248 Distribution of Effective Doses Among All Workers at the Blind River Refinery

0

20

40

60

80

100

120

140

160

180

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

48

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

232 Port Hope Conversion Facility

Cameco Corporation owns and is licensed to operate a uranium conversion facility in Port Hope Ontario The facility processes uranium trioxide received from the refinery in Blind River into uranium dioxide and uranium hexafluoride

Figures 249ndash252 present dose information for the Port Hope uranium conversion facility from 2001 to 2007

Figure 249 Average Dose Trends for the Port Hope Conversion Facility (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

49

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 250 Average Dose Trends for the Port Hope Conversion Facility (Based on All Monitoring Results)

0

01

02

03

04

05

06

07

08

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 251 Collective Dose Trends for the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

50

000-0

009

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 252 Distribution of Effective Doses Among All Workers at the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

400

450

500

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

51

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

24 Fuel Fabrication Facilities This section presents data for three nuclear fuel fabrication facilities

bull Two facilities owned and operated by General Electric Canada Inc (Section 241) bull One facility in Port Hope operated by Zircatec Precision Industries (Section 242)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average doses

Notes on data for fuel fabrication facilities

1 Effective doses for the three facilities are composed of the following reported components bull dose from photons (labelled on the charts as ldquoexternalrdquo) bull doses from internal intakes of uranium dust (long-lived radioactive dust) from

uranium in air concentrations (for General Electricrsquos Toronto facility only)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components photon doses and doses from long-lived radioactive dust

241 General Electric Nuclear Fuel Facilities

General Electric Canada Inc operates two nuclear fuel facilities in Ontario

bull At the Toronto facility uranium dioxide pellets are produced from natural or depleted uranium dioxide powder

bull At the Peterborough facility uranium dioxide fuel bundles are created from the pellets produced at the Toronto facility

Figures 253ndash256 present dose information for General Electric Canada Incrsquos fuel fabrication facilities from 2001 to 2007 Graphs do not distinguish between the doses received at the Peterborough facility versus those at the Toronto facility

52

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 253 Average Dose Trends for the General Electric Fuel Facility (Based on Non-Zero Results Only)

0

05

1

15

2

25

3

35

Long Lived Radioactive Dust External Effective

Year

Figure 254 Average Dose Trends for the General Electric Fuel Facility (Based on All Monitoring Results)

0

05

1

15

2

25

3

Long Lived Radioactive Dust External Effective

Year

Dos

e (m

Sv)

Dos

e (m

Sv)

53

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 255 Collective Dose Trends for the General Electric Fuel Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Long Lived Radioactive Dust External

Year

Figure 256 Distribution of Effective Doses among all Workers at the General Electric Fuel Facility

0

10

20

30

40

50

60

70

80

90

100

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

54

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

242 Zircatec Nuclear Fuel Facility

Zircatec Precision Industries Inc operates a nuclear fuel facility in Port Hope Ontario where it makes fuel pellets from uranium dioxide powder received from Port Hopersquos uranium conversion facility The nuclear fuel facility also manufactures fuel bundles for nuclear reactors in Canada

Notes on data for the Zircatec nuclear fuel facility

1 Graphs indicate the following data bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of average effective doses

2 Doses from photons from external sources were measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay Historically although these internal doses have been measured and submitted to the CNSC they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

Figures 257ndash260 present dose information for the Zircatec nuclear fuel facility from 2001 to 2007

Figure 257 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on Non-Zero Results)

0

05

1

15

2

25

3

35

Effe

ctiv

e D

ose

(mS

v)

Year

55

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 258 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

18

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 259 Collective Dose Trends for the Zircatec Nuclear Fuel Facility

0

50

100

150

200

250

300

350

400

450

500

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

56

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 260 Distribution of Effective Doses Among All Workers at the Zircatec Nuclear Fuel Facility

300

Num

ber o

f Wor

kers

250

200

150

100

50

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

57

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

25 Research and Radioisotope Production Facilities This section presents dose information for the following research and radioisotope production facilities from 2001 to 2007

bull Chalk River Laboratories and Whiteshell Laboratories (Section 251) bull A radioisotope production facility operated by MDS Nordion (Section 252) bull The Tri-University Meson Facility (TRIUMF) (Section 253)

Note on data for research and radioisotope production facilities

1 Graphs indicate the following data for each facility bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of effective doses

251 Chalk River Laboratories and Whiteshell Laboratories

Atomic Energy of Canada Limited (AECL) owns and is licensed to operate Chalk River Laboratories and Whiteshell Laboratories

Situated in Renfrew County on the south shore of the Ottawa River the Chalk River Laboratories site hosts the National Research Universal Reactor along with numerous other facilities occupying some 160 buildings in an area of approximately 40 km2 Activities consist of radioisotope production for nuclear medicine testing and development of structural materials in support of power reactor operations fuel fabrication research and radioactive waste management and storage

The Whiteshell Laboratories site is located approximately 10 km west of Pinawa Manitoba and 100 km northeast of Winnipeg on the east bank of the Winnipeg River AECL established the laboratories for nuclear research and testing during the early 1960s and has since discontinued operations which are being decommissioned under a licence from the CNSC

Figures 261ndash264 present dose information for Chalk River Laboratories and Whiteshell Laboratories from 2001 to 2007

Notes on data for Chalk River Laboratories and Whiteshell Laboratories

1 Effective doses are composed of the following reported components bull external doses5 (from both photon and neutron doses) bull tritium doses

Due to issues with AECLrsquos in-house dosimetry management system neutron doses were not reported separately to the NDR during the reporting period As a result external doses from photons and neutrons were totaled The reporting discrepancy has since been rectified

58

5

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of external (photon and neutron) and tritium doses Intakes of other radionuclides occasionally occur and these radionuclides are not included here because their associated doses are very small For this reason certain collective doses in this report may have values slightly lower than the sum of their respective components as listed

Figure 261 Average Dose Trends for Chalk River and Whiteshell Laboratories (Non-Zero Results Only)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Tritium External Effective

Year

59

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 262 Average Dose Trends for Chalk River and Whiteshell Laboratories (All Monitoring Results)

000

020

040

060

080

100

120

Dos

e (m

Sv)

Tritium External Effective

Year

Figure 263 Collective Dose Trends for Chalk River and Whiteshell Laboratories

0

500

1000

1500

2000

2500

3000

3500

Col

lect

ive

Dos

e (p

erso

n- m

Sv)

External Tritium

Year

60

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 264 Distribution of Effective Doses Among All Workers at Chalk River and Whiteshell Laboratories

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

3500

3000

2500

2000

1500

1000

500

Dose (mSv)

61

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

252 MDS Nordion (Nuclear Substance Processing Facility and Canadian Irradiation Centre)

MDS Nordion owns and operates a nuclear substance processing facility in Ottawa Ontario where it processes unsealed radioisotopes and manufactures sealed radiation sources In operation since the early 1970s the facility was purchased by Nordion International in 1991

In cooperation with the Universiteacute du Queacutebecrsquos Institut Armand-Frappier MDS Nordion also operates the Canadian Irradiation Centre which conducts various irradiation services which include training testing and development The centre is located in Laval Quebec on the Universiteacute du Queacutebec campus

Figures 265ndash268 present dose information for MDS Nordionrsquos Ottawa nuclear substance processing facility and for the Canadian Irradiation Centre from 2001 to 2007

Notes on data for MDS Nordionrsquos nuclear substance processing facility and the Canadian Irradiation Centre

1 Doses from photons from external sources were measured and reported to the NDR MDS Nordion also has a routine thyroid monitoring program very occasionally small recordable doses of radiation have occurred from thyroid uptake of iodine The resulting doses have not been historically submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided

Figure 265 Average Dose Trends for MDS Nordion (Based on Non-Zero Results)

0

05

1

15

2

25

Effe

ctiv

e D

ose

(mS

v)

Year

62

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 266 Average Dose Trends for MDS Nordion (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

Figure 267 Collective Dose Trends for MDS Nordion

0

100

200

300

400

500

600

700

800

Year

63

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 268 Distribution of Effective Doses Among All Workers at MDS Nordion

0

5 0

1 0 0

1 5 0

2 0 0

2 5 0

3 0 0

3 5 0

4 0 0

4 5 0

5 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

64

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

253 Tri-University Meson Facility

The Tri-University Meson facility (TRIUMF) is situated in Vancouver on the campus of the University of British Columbia TRIUMF which began operating in the early 1970s with one cyclotron now has two cyclotrons and associated laboratories for research and radioisotope production The laboratory provides research facilities for Canadian and international users and also produces radioisotopes which are used by medical facilities and by a commercial organization (MDS Nordion) MDS Nordion staff also work at the TRIUMF site however MDS Nordion oversees this work and has its own radiation protection program

Figures 269ndash272 present dose information for the TRIUMF facility from 2001 to 2007 Please note that data sets do not distinguish between doses received by TRIUMF staff and MDS Nordion staff who work on the site as the data for these two groups was submitted collectively to the NDR for the reporting period shown Future data for each group will be submitted separately to the NDR

Note on data for TRIUMF

1 Effective doses are composed of the following reported components bull doses from photons (labeled as ldquoexternalrdquo in the charts) bull neutron doses

Figure 269 Average Dose Trends for TRIUMF (Non-Zero Results Only)

000

020

040

060

080

100

120

140

160

Dos

e (m

Sv)

Neutrons External Effective

Year

65

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 27: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

214 Gentilly-2 Nuclear Generating Station

The Gentilly-2 Nuclear Generating Station owned and operated by Hydro-Queacutebec has a single reactor that began operating in 1982 The facility is located on the south shore of the St Lawrence River near Trois-Riviegraveres Queacutebec

Figures 213ndash216 present dose information for the Gentilly-2 Nuclear Generating Station from 2001 to 2007

Figure 213 Average Dose Trends for Gentilly-2 Nuclear Generating Stati on (Based o n N on-Zero R esults)

0

05

1

15

2

25

3

35

4

45

)S

v(m

e os

D

Year

22

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 214 Average Dose Trends for Gentilly-2 Nuclear Generating Stati on (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

)S

v(m

e os

D

Year

Figure 215 Collective Dose Trends for Gentilly-2 Nuclear Generating Stati on

0

500

1000

1500

2000

2500

3000

3500

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Neutrons

External

Tritium

Year

23

000-0

009

001-5

00

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 216 Distribution of Effective Doses Among All Workers at Gentilly-2 Nuclear Generating Station

2500

2000

1500

1000

500

0

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

24

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

215 Point Lepreau Nuclear Generating Station

The Point Lepreau Nuclear Generating Station has one reactor that began operating in 1982 Owned and operated by New Brunswick Power Nuclear the station is located in Point Lepreau New Brunswick about 40 km west of Saint John on the shores of the Bay of Fundy

Figures 217ndash220 present dose information for the Point Lepreau Nuclear Generating Station from 2001 to 2007

Figure 217 Average Dose Trends for Point Lepreau N uclear Generating Stati on (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

)S

v(m

e os

D

Tritium Neutron External Effective

Year

25

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 218 Average Dose Trends for Point Lepreau N uclear Generating Stati on (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

)S

v(m

e os

D

Tritium Neutrons External Effective

Year

Figure 219 Collective Dose Trends for Point Lepreau N uclear Generating Station

0

200

400

600

800

1000

1200

1400

1600

1800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Neutrons

External

Tritium

Year

26

0

1400

1200

1000

800

600

400

200

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 220 Distribution of Effective Doses Among All Workers at Point Lepreau Nuclear Generating Station

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

27

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

22 Uranium Mines and Mills This section presents dose information for mine and mill sites in the following regions

bull Cluff Lake (Section 221) bull McClean Lake (Section 222) bull McArthur River (Section 223) bull Key Lake (Section 224) bull Cigar Lake (Section 225) bull Rabbit Lake (Section 226)

Graphs indicate the following data for each site from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for uranium mines and mills

1 Effective doses are composed of the following reported components bull doses from photons (labelled on the charts as ldquoexternalrdquo) bull doses from radon progeny bull doses from long-lived radioactive dust bull doses from radon gas (in some cases)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of photon radon progeny long-lived radioactive dust and radon gas doses

3 The NDR lists radon progeny in working level months (WLM) For this report radon progeny exposures were converted4 to doses expressed in mSv

221 Cluff Lake Operation

The Cluff Lake mining facilities operated by AREVA Resources Canada Inc are located in northwestern Saskatchewan Work began in 1980 and ended in 2002 with the site now being decommissioned The site consisted of three open-pit and two underground mines a mill and a tailings management facility During 2005 and 2006 most of the infrastructure was removed and the affected areas were remediated

Figures 221ndash224 present dose information for the Cluff Lake operation from 2001 to 2007

4 Doses were converted using the International Commission on Radiation Protection (ICRP)rsquos conversion convention of 1 WLM = 5 mSv This convention was established in the ICRP publication Protection against Radon at Home and at Work (ICRP 65)

28

Long-lived radioactive dust Radon progeny External Effective

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 221 Average Dose Trends for the Cluff Lake Operation (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

Year

Figure 222 Average Dose Trends for the Cluff Lake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

200

Long-lived radioactive dust Radon progeny External Effective

)S

v(m

e os

D)

Sv

(me

osD

Year

29

600

500

400

300

200

100

0

External Radon progeny Long-lived radioactive dust

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 223 Collective Dose Trends for the Cluff Lake Operation s

erkor

of W

ber

Num

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Year

Figure 224 Distribution o f Effective Doses Among A ll Workers at the Cluff Lake Operation

0

20

40

60

80

100

120

140

160

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

30

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

222 McClean Lake Operation

AREVA Resources Canada Inc runs the McClean Lake mining operation in northeastern Saskatchewan It comprises open pit mines a mill and a tailings management facility Mining began in 1995 while milling started in 1999

Figures 225ndash228 present dose information for the McClean Lake operation from 2001 to 2007

Figure 225 Average Dose Trends for the McClean L ake Operation (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

31

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 226 Average Dose Trends for the McClean L ake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 227 Collective Dose Trends for the McClean L ake Operation

0

100

200

300

400

500

600

700

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External

Radon progeny

Long-lived radioactive dust

Year

32

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 228 Distribution o f Effective Doses Among A ll Workers at the McClean Lake Operation

0

100

200

300

400

500

600

700

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

33

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

223 McArthur River Operation

Cameco Corporation operates the McArthur River underground mine in north-central Saskatchewan Ore from the mine which began production in 1999 is processed at the Key Lake Mill located 80 km south of McArthur River

Figures 229ndash232 present dose information for the McArthur River operation from 2001 to 2007

Figure 229 Average Dose Trends for the McArthur River Operation (Based o n N on-Zero R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

34

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 230 Average Dose Trends for the McArthur River Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

Figure 231 Collective Dose Trends for the McArthur River Operation

0

200

400

600

800

1000

1200

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Radon gas External Radon progeny Long-lived radioactive dust

Year

35

00

0-000

9

001-5

00

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 232 Distribution o f Effective Doses Among A ll Workers at the McArthur River Operation

0

100

200

300

400

500

600

700

800

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

36

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

224 Key Lake Operation

Cameco Corporation operates mining facilities in Key Lake located in north-central Saskatchewan The Key Lake operation includes two mined-out open pit mines (used for tailings management) a mill and two dry tailings management facilities Mining began in 1983 and ceased in 1997 the mill continued to process ore from the McArthur River mine during the reporting period

Figures 233ndash236 present dose information for the Key Lake operation from 2001 to 2007

Figure 233 Average Dose Trends for the Key Lake Operation (Based o n N on-Zero R esults)

00

20

40

60

80

00

20

40

60

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

37

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

00

20

40

60

80

00

20

40

60

Figure 234 Average Dose Trends for the Key Lake Operation (Based o n A ll Monitoring R esults)

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 235 Collective Dose Trends for the Key Lake Operation

0

100

200

300

400

500

600

700

800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External Radon progeny Long-lived radioactive dust

Year

38

00

0-000

9

001-5

0

501-1

000

gt 1001

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 236 Distribution o f Effective Doses Among A ll Workers at the Key Lake Operation

0

200

400

600

800

1000

1200

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose Range (mSv)

39

se

(mS

v)o

D

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

225 Cigar Lake Operation

Cameco Corporation manages the Cigar Lake underground mine located in northern Saskatchewan at the southern end of Waterbury Lake The mine was under construction at the time of this reportrsquos publication Test mining in ore was carried out in 1991 1992 and 2000

Figures 237ndash240 present dose information for the Cigar Lake operation from

Figure 2 37 Average D ose T rends fo r th e C igar L ake O peration (Based on Non-Zero Results)

2001 to 2007

Year

000

005

010

015

020

025

Long-lived radioactive dust Radon Progeny External Effective

40

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 238 Average Dose Trends for the Cigar Lake Operation (Based on All Monitoring Results)

000

005

010

015

020

025

030

035

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny

External

Effective

Year

Figure 239 Collective Dose Trends for the Cigar Lake Operation

0

50

100

150

200

250

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

External Radon progeny Long-lived radioactive dust

Year

41

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 240 Distribution of Effective Doses Among All Workers at the Cigar Lake Operation

0

200

400

600

800

1000

1200

1400

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

42

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

226 Rabbit Lake Operation

Cameco Corporation owns and operates mining facilities in Rabbit Lake located in north-eastern Saskatchewan Facilities include an underground mine four mined-out open-pit mines a mill and two tailings management facilities Mining and milling began in 1975

Figures 241ndash244 present dose information for the Rabbit Lake operation from 2001 to 2007

Figure 241 Average Dose Trends for the Rabbit Lake Operation (Based on Non-Zero Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

43

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 242 Average Dose Trends for the Rabbit Lake Operation (Based on All Monitoring Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

Figure 243 Collective Dose Trends for the Rabbit Lake Operation

0

200

400

600

800

1000

1200

1400

1600

1800

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Radon gas External Radon progeny Long-lived radioactive dust

Year

44

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

gt300

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 244 Distribution of Effective Doses Among All Workers at the Rabbit Lake Operation

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

900

800

700

600

500

400

300

200

100

0

Dose (mSv)

45

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

23 Uranium Refineries This section presents data for the following two facilities

bull a uranium refining facility in Blind River (Section 231) bull a uranium conversion facility in Port Hope (Section 232)

Graphs indicate the following average doses at each facility from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Note on data for uranium refineries

1 Doses from photons from external sources are measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay and lung counting Historically while these internal doses have been measured they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

231 Blind River Refinery

Cameco Corporation owns and is licensed to operate a uranium refinery in Blind River Ontario The facility which began operating in 1983 converts uranium ore concentrate to uranium trioxide The uranium trioxide is shipped to Camecorsquos uranium conversion facility in Port Hope Ontario where it is processed into uranium dioxide (for use in the fabrication of fuel for nuclear reactors in Canada) or uranium hexafluoride (exported for enrichment and fabrication into fuel for nuclear power reactors around the world)

Figures 245ndash248 present dose information for the Blind River refinery from 2001 to 2007

46

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 245 Average Dose Trends for the Blind River Refinery (Based on Non-Zero Results)

0

05

1

15

2

25

Year

Figure 246 Average Dose Trends for the Blind River Refinery (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

47

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 247 Collective Dose Trends for the Blind River Refinery

0

50

100

150

200

250

300 C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 248 Distribution of Effective Doses Among All Workers at the Blind River Refinery

0

20

40

60

80

100

120

140

160

180

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

48

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

232 Port Hope Conversion Facility

Cameco Corporation owns and is licensed to operate a uranium conversion facility in Port Hope Ontario The facility processes uranium trioxide received from the refinery in Blind River into uranium dioxide and uranium hexafluoride

Figures 249ndash252 present dose information for the Port Hope uranium conversion facility from 2001 to 2007

Figure 249 Average Dose Trends for the Port Hope Conversion Facility (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

49

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 250 Average Dose Trends for the Port Hope Conversion Facility (Based on All Monitoring Results)

0

01

02

03

04

05

06

07

08

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 251 Collective Dose Trends for the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

50

000-0

009

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 252 Distribution of Effective Doses Among All Workers at the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

400

450

500

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

51

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

24 Fuel Fabrication Facilities This section presents data for three nuclear fuel fabrication facilities

bull Two facilities owned and operated by General Electric Canada Inc (Section 241) bull One facility in Port Hope operated by Zircatec Precision Industries (Section 242)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average doses

Notes on data for fuel fabrication facilities

1 Effective doses for the three facilities are composed of the following reported components bull dose from photons (labelled on the charts as ldquoexternalrdquo) bull doses from internal intakes of uranium dust (long-lived radioactive dust) from

uranium in air concentrations (for General Electricrsquos Toronto facility only)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components photon doses and doses from long-lived radioactive dust

241 General Electric Nuclear Fuel Facilities

General Electric Canada Inc operates two nuclear fuel facilities in Ontario

bull At the Toronto facility uranium dioxide pellets are produced from natural or depleted uranium dioxide powder

bull At the Peterborough facility uranium dioxide fuel bundles are created from the pellets produced at the Toronto facility

Figures 253ndash256 present dose information for General Electric Canada Incrsquos fuel fabrication facilities from 2001 to 2007 Graphs do not distinguish between the doses received at the Peterborough facility versus those at the Toronto facility

52

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 253 Average Dose Trends for the General Electric Fuel Facility (Based on Non-Zero Results Only)

0

05

1

15

2

25

3

35

Long Lived Radioactive Dust External Effective

Year

Figure 254 Average Dose Trends for the General Electric Fuel Facility (Based on All Monitoring Results)

0

05

1

15

2

25

3

Long Lived Radioactive Dust External Effective

Year

Dos

e (m

Sv)

Dos

e (m

Sv)

53

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 255 Collective Dose Trends for the General Electric Fuel Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Long Lived Radioactive Dust External

Year

Figure 256 Distribution of Effective Doses among all Workers at the General Electric Fuel Facility

0

10

20

30

40

50

60

70

80

90

100

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

54

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

242 Zircatec Nuclear Fuel Facility

Zircatec Precision Industries Inc operates a nuclear fuel facility in Port Hope Ontario where it makes fuel pellets from uranium dioxide powder received from Port Hopersquos uranium conversion facility The nuclear fuel facility also manufactures fuel bundles for nuclear reactors in Canada

Notes on data for the Zircatec nuclear fuel facility

1 Graphs indicate the following data bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of average effective doses

2 Doses from photons from external sources were measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay Historically although these internal doses have been measured and submitted to the CNSC they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

Figures 257ndash260 present dose information for the Zircatec nuclear fuel facility from 2001 to 2007

Figure 257 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on Non-Zero Results)

0

05

1

15

2

25

3

35

Effe

ctiv

e D

ose

(mS

v)

Year

55

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 258 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

18

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 259 Collective Dose Trends for the Zircatec Nuclear Fuel Facility

0

50

100

150

200

250

300

350

400

450

500

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

56

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 260 Distribution of Effective Doses Among All Workers at the Zircatec Nuclear Fuel Facility

300

Num

ber o

f Wor

kers

250

200

150

100

50

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

57

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

25 Research and Radioisotope Production Facilities This section presents dose information for the following research and radioisotope production facilities from 2001 to 2007

bull Chalk River Laboratories and Whiteshell Laboratories (Section 251) bull A radioisotope production facility operated by MDS Nordion (Section 252) bull The Tri-University Meson Facility (TRIUMF) (Section 253)

Note on data for research and radioisotope production facilities

1 Graphs indicate the following data for each facility bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of effective doses

251 Chalk River Laboratories and Whiteshell Laboratories

Atomic Energy of Canada Limited (AECL) owns and is licensed to operate Chalk River Laboratories and Whiteshell Laboratories

Situated in Renfrew County on the south shore of the Ottawa River the Chalk River Laboratories site hosts the National Research Universal Reactor along with numerous other facilities occupying some 160 buildings in an area of approximately 40 km2 Activities consist of radioisotope production for nuclear medicine testing and development of structural materials in support of power reactor operations fuel fabrication research and radioactive waste management and storage

The Whiteshell Laboratories site is located approximately 10 km west of Pinawa Manitoba and 100 km northeast of Winnipeg on the east bank of the Winnipeg River AECL established the laboratories for nuclear research and testing during the early 1960s and has since discontinued operations which are being decommissioned under a licence from the CNSC

Figures 261ndash264 present dose information for Chalk River Laboratories and Whiteshell Laboratories from 2001 to 2007

Notes on data for Chalk River Laboratories and Whiteshell Laboratories

1 Effective doses are composed of the following reported components bull external doses5 (from both photon and neutron doses) bull tritium doses

Due to issues with AECLrsquos in-house dosimetry management system neutron doses were not reported separately to the NDR during the reporting period As a result external doses from photons and neutrons were totaled The reporting discrepancy has since been rectified

58

5

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of external (photon and neutron) and tritium doses Intakes of other radionuclides occasionally occur and these radionuclides are not included here because their associated doses are very small For this reason certain collective doses in this report may have values slightly lower than the sum of their respective components as listed

Figure 261 Average Dose Trends for Chalk River and Whiteshell Laboratories (Non-Zero Results Only)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Tritium External Effective

Year

59

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 262 Average Dose Trends for Chalk River and Whiteshell Laboratories (All Monitoring Results)

000

020

040

060

080

100

120

Dos

e (m

Sv)

Tritium External Effective

Year

Figure 263 Collective Dose Trends for Chalk River and Whiteshell Laboratories

0

500

1000

1500

2000

2500

3000

3500

Col

lect

ive

Dos

e (p

erso

n- m

Sv)

External Tritium

Year

60

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 264 Distribution of Effective Doses Among All Workers at Chalk River and Whiteshell Laboratories

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

3500

3000

2500

2000

1500

1000

500

Dose (mSv)

61

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

252 MDS Nordion (Nuclear Substance Processing Facility and Canadian Irradiation Centre)

MDS Nordion owns and operates a nuclear substance processing facility in Ottawa Ontario where it processes unsealed radioisotopes and manufactures sealed radiation sources In operation since the early 1970s the facility was purchased by Nordion International in 1991

In cooperation with the Universiteacute du Queacutebecrsquos Institut Armand-Frappier MDS Nordion also operates the Canadian Irradiation Centre which conducts various irradiation services which include training testing and development The centre is located in Laval Quebec on the Universiteacute du Queacutebec campus

Figures 265ndash268 present dose information for MDS Nordionrsquos Ottawa nuclear substance processing facility and for the Canadian Irradiation Centre from 2001 to 2007

Notes on data for MDS Nordionrsquos nuclear substance processing facility and the Canadian Irradiation Centre

1 Doses from photons from external sources were measured and reported to the NDR MDS Nordion also has a routine thyroid monitoring program very occasionally small recordable doses of radiation have occurred from thyroid uptake of iodine The resulting doses have not been historically submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided

Figure 265 Average Dose Trends for MDS Nordion (Based on Non-Zero Results)

0

05

1

15

2

25

Effe

ctiv

e D

ose

(mS

v)

Year

62

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 266 Average Dose Trends for MDS Nordion (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

Figure 267 Collective Dose Trends for MDS Nordion

0

100

200

300

400

500

600

700

800

Year

63

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 268 Distribution of Effective Doses Among All Workers at MDS Nordion

0

5 0

1 0 0

1 5 0

2 0 0

2 5 0

3 0 0

3 5 0

4 0 0

4 5 0

5 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

64

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

253 Tri-University Meson Facility

The Tri-University Meson facility (TRIUMF) is situated in Vancouver on the campus of the University of British Columbia TRIUMF which began operating in the early 1970s with one cyclotron now has two cyclotrons and associated laboratories for research and radioisotope production The laboratory provides research facilities for Canadian and international users and also produces radioisotopes which are used by medical facilities and by a commercial organization (MDS Nordion) MDS Nordion staff also work at the TRIUMF site however MDS Nordion oversees this work and has its own radiation protection program

Figures 269ndash272 present dose information for the TRIUMF facility from 2001 to 2007 Please note that data sets do not distinguish between doses received by TRIUMF staff and MDS Nordion staff who work on the site as the data for these two groups was submitted collectively to the NDR for the reporting period shown Future data for each group will be submitted separately to the NDR

Note on data for TRIUMF

1 Effective doses are composed of the following reported components bull doses from photons (labeled as ldquoexternalrdquo in the charts) bull neutron doses

Figure 269 Average Dose Trends for TRIUMF (Non-Zero Results Only)

000

020

040

060

080

100

120

140

160

Dos

e (m

Sv)

Neutrons External Effective

Year

65

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 28: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

Tritium Neutrons External Effective

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 214 Average Dose Trends for Gentilly-2 Nuclear Generating Stati on (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

)S

v(m

e os

D

Year

Figure 215 Collective Dose Trends for Gentilly-2 Nuclear Generating Stati on

0

500

1000

1500

2000

2500

3000

3500

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Neutrons

External

Tritium

Year

23

000-0

009

001-5

00

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 216 Distribution of Effective Doses Among All Workers at Gentilly-2 Nuclear Generating Station

2500

2000

1500

1000

500

0

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

24

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

215 Point Lepreau Nuclear Generating Station

The Point Lepreau Nuclear Generating Station has one reactor that began operating in 1982 Owned and operated by New Brunswick Power Nuclear the station is located in Point Lepreau New Brunswick about 40 km west of Saint John on the shores of the Bay of Fundy

Figures 217ndash220 present dose information for the Point Lepreau Nuclear Generating Station from 2001 to 2007

Figure 217 Average Dose Trends for Point Lepreau N uclear Generating Stati on (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

)S

v(m

e os

D

Tritium Neutron External Effective

Year

25

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 218 Average Dose Trends for Point Lepreau N uclear Generating Stati on (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

)S

v(m

e os

D

Tritium Neutrons External Effective

Year

Figure 219 Collective Dose Trends for Point Lepreau N uclear Generating Station

0

200

400

600

800

1000

1200

1400

1600

1800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Neutrons

External

Tritium

Year

26

0

1400

1200

1000

800

600

400

200

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 220 Distribution of Effective Doses Among All Workers at Point Lepreau Nuclear Generating Station

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

27

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

22 Uranium Mines and Mills This section presents dose information for mine and mill sites in the following regions

bull Cluff Lake (Section 221) bull McClean Lake (Section 222) bull McArthur River (Section 223) bull Key Lake (Section 224) bull Cigar Lake (Section 225) bull Rabbit Lake (Section 226)

Graphs indicate the following data for each site from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for uranium mines and mills

1 Effective doses are composed of the following reported components bull doses from photons (labelled on the charts as ldquoexternalrdquo) bull doses from radon progeny bull doses from long-lived radioactive dust bull doses from radon gas (in some cases)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of photon radon progeny long-lived radioactive dust and radon gas doses

3 The NDR lists radon progeny in working level months (WLM) For this report radon progeny exposures were converted4 to doses expressed in mSv

221 Cluff Lake Operation

The Cluff Lake mining facilities operated by AREVA Resources Canada Inc are located in northwestern Saskatchewan Work began in 1980 and ended in 2002 with the site now being decommissioned The site consisted of three open-pit and two underground mines a mill and a tailings management facility During 2005 and 2006 most of the infrastructure was removed and the affected areas were remediated

Figures 221ndash224 present dose information for the Cluff Lake operation from 2001 to 2007

4 Doses were converted using the International Commission on Radiation Protection (ICRP)rsquos conversion convention of 1 WLM = 5 mSv This convention was established in the ICRP publication Protection against Radon at Home and at Work (ICRP 65)

28

Long-lived radioactive dust Radon progeny External Effective

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 221 Average Dose Trends for the Cluff Lake Operation (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

Year

Figure 222 Average Dose Trends for the Cluff Lake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

200

Long-lived radioactive dust Radon progeny External Effective

)S

v(m

e os

D)

Sv

(me

osD

Year

29

600

500

400

300

200

100

0

External Radon progeny Long-lived radioactive dust

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 223 Collective Dose Trends for the Cluff Lake Operation s

erkor

of W

ber

Num

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Year

Figure 224 Distribution o f Effective Doses Among A ll Workers at the Cluff Lake Operation

0

20

40

60

80

100

120

140

160

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

30

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

222 McClean Lake Operation

AREVA Resources Canada Inc runs the McClean Lake mining operation in northeastern Saskatchewan It comprises open pit mines a mill and a tailings management facility Mining began in 1995 while milling started in 1999

Figures 225ndash228 present dose information for the McClean Lake operation from 2001 to 2007

Figure 225 Average Dose Trends for the McClean L ake Operation (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

31

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 226 Average Dose Trends for the McClean L ake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 227 Collective Dose Trends for the McClean L ake Operation

0

100

200

300

400

500

600

700

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External

Radon progeny

Long-lived radioactive dust

Year

32

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 228 Distribution o f Effective Doses Among A ll Workers at the McClean Lake Operation

0

100

200

300

400

500

600

700

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

33

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

223 McArthur River Operation

Cameco Corporation operates the McArthur River underground mine in north-central Saskatchewan Ore from the mine which began production in 1999 is processed at the Key Lake Mill located 80 km south of McArthur River

Figures 229ndash232 present dose information for the McArthur River operation from 2001 to 2007

Figure 229 Average Dose Trends for the McArthur River Operation (Based o n N on-Zero R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

34

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 230 Average Dose Trends for the McArthur River Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

Figure 231 Collective Dose Trends for the McArthur River Operation

0

200

400

600

800

1000

1200

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Radon gas External Radon progeny Long-lived radioactive dust

Year

35

00

0-000

9

001-5

00

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 232 Distribution o f Effective Doses Among A ll Workers at the McArthur River Operation

0

100

200

300

400

500

600

700

800

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

36

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

224 Key Lake Operation

Cameco Corporation operates mining facilities in Key Lake located in north-central Saskatchewan The Key Lake operation includes two mined-out open pit mines (used for tailings management) a mill and two dry tailings management facilities Mining began in 1983 and ceased in 1997 the mill continued to process ore from the McArthur River mine during the reporting period

Figures 233ndash236 present dose information for the Key Lake operation from 2001 to 2007

Figure 233 Average Dose Trends for the Key Lake Operation (Based o n N on-Zero R esults)

00

20

40

60

80

00

20

40

60

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

37

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

00

20

40

60

80

00

20

40

60

Figure 234 Average Dose Trends for the Key Lake Operation (Based o n A ll Monitoring R esults)

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 235 Collective Dose Trends for the Key Lake Operation

0

100

200

300

400

500

600

700

800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External Radon progeny Long-lived radioactive dust

Year

38

00

0-000

9

001-5

0

501-1

000

gt 1001

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 236 Distribution o f Effective Doses Among A ll Workers at the Key Lake Operation

0

200

400

600

800

1000

1200

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose Range (mSv)

39

se

(mS

v)o

D

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

225 Cigar Lake Operation

Cameco Corporation manages the Cigar Lake underground mine located in northern Saskatchewan at the southern end of Waterbury Lake The mine was under construction at the time of this reportrsquos publication Test mining in ore was carried out in 1991 1992 and 2000

Figures 237ndash240 present dose information for the Cigar Lake operation from

Figure 2 37 Average D ose T rends fo r th e C igar L ake O peration (Based on Non-Zero Results)

2001 to 2007

Year

000

005

010

015

020

025

Long-lived radioactive dust Radon Progeny External Effective

40

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 238 Average Dose Trends for the Cigar Lake Operation (Based on All Monitoring Results)

000

005

010

015

020

025

030

035

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny

External

Effective

Year

Figure 239 Collective Dose Trends for the Cigar Lake Operation

0

50

100

150

200

250

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

External Radon progeny Long-lived radioactive dust

Year

41

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 240 Distribution of Effective Doses Among All Workers at the Cigar Lake Operation

0

200

400

600

800

1000

1200

1400

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

42

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

226 Rabbit Lake Operation

Cameco Corporation owns and operates mining facilities in Rabbit Lake located in north-eastern Saskatchewan Facilities include an underground mine four mined-out open-pit mines a mill and two tailings management facilities Mining and milling began in 1975

Figures 241ndash244 present dose information for the Rabbit Lake operation from 2001 to 2007

Figure 241 Average Dose Trends for the Rabbit Lake Operation (Based on Non-Zero Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

43

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 242 Average Dose Trends for the Rabbit Lake Operation (Based on All Monitoring Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

Figure 243 Collective Dose Trends for the Rabbit Lake Operation

0

200

400

600

800

1000

1200

1400

1600

1800

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Radon gas External Radon progeny Long-lived radioactive dust

Year

44

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

gt300

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 244 Distribution of Effective Doses Among All Workers at the Rabbit Lake Operation

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

900

800

700

600

500

400

300

200

100

0

Dose (mSv)

45

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

23 Uranium Refineries This section presents data for the following two facilities

bull a uranium refining facility in Blind River (Section 231) bull a uranium conversion facility in Port Hope (Section 232)

Graphs indicate the following average doses at each facility from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Note on data for uranium refineries

1 Doses from photons from external sources are measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay and lung counting Historically while these internal doses have been measured they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

231 Blind River Refinery

Cameco Corporation owns and is licensed to operate a uranium refinery in Blind River Ontario The facility which began operating in 1983 converts uranium ore concentrate to uranium trioxide The uranium trioxide is shipped to Camecorsquos uranium conversion facility in Port Hope Ontario where it is processed into uranium dioxide (for use in the fabrication of fuel for nuclear reactors in Canada) or uranium hexafluoride (exported for enrichment and fabrication into fuel for nuclear power reactors around the world)

Figures 245ndash248 present dose information for the Blind River refinery from 2001 to 2007

46

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 245 Average Dose Trends for the Blind River Refinery (Based on Non-Zero Results)

0

05

1

15

2

25

Year

Figure 246 Average Dose Trends for the Blind River Refinery (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

47

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 247 Collective Dose Trends for the Blind River Refinery

0

50

100

150

200

250

300 C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 248 Distribution of Effective Doses Among All Workers at the Blind River Refinery

0

20

40

60

80

100

120

140

160

180

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

48

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

232 Port Hope Conversion Facility

Cameco Corporation owns and is licensed to operate a uranium conversion facility in Port Hope Ontario The facility processes uranium trioxide received from the refinery in Blind River into uranium dioxide and uranium hexafluoride

Figures 249ndash252 present dose information for the Port Hope uranium conversion facility from 2001 to 2007

Figure 249 Average Dose Trends for the Port Hope Conversion Facility (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

49

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 250 Average Dose Trends for the Port Hope Conversion Facility (Based on All Monitoring Results)

0

01

02

03

04

05

06

07

08

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 251 Collective Dose Trends for the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

50

000-0

009

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 252 Distribution of Effective Doses Among All Workers at the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

400

450

500

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

51

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

24 Fuel Fabrication Facilities This section presents data for three nuclear fuel fabrication facilities

bull Two facilities owned and operated by General Electric Canada Inc (Section 241) bull One facility in Port Hope operated by Zircatec Precision Industries (Section 242)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average doses

Notes on data for fuel fabrication facilities

1 Effective doses for the three facilities are composed of the following reported components bull dose from photons (labelled on the charts as ldquoexternalrdquo) bull doses from internal intakes of uranium dust (long-lived radioactive dust) from

uranium in air concentrations (for General Electricrsquos Toronto facility only)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components photon doses and doses from long-lived radioactive dust

241 General Electric Nuclear Fuel Facilities

General Electric Canada Inc operates two nuclear fuel facilities in Ontario

bull At the Toronto facility uranium dioxide pellets are produced from natural or depleted uranium dioxide powder

bull At the Peterborough facility uranium dioxide fuel bundles are created from the pellets produced at the Toronto facility

Figures 253ndash256 present dose information for General Electric Canada Incrsquos fuel fabrication facilities from 2001 to 2007 Graphs do not distinguish between the doses received at the Peterborough facility versus those at the Toronto facility

52

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 253 Average Dose Trends for the General Electric Fuel Facility (Based on Non-Zero Results Only)

0

05

1

15

2

25

3

35

Long Lived Radioactive Dust External Effective

Year

Figure 254 Average Dose Trends for the General Electric Fuel Facility (Based on All Monitoring Results)

0

05

1

15

2

25

3

Long Lived Radioactive Dust External Effective

Year

Dos

e (m

Sv)

Dos

e (m

Sv)

53

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 255 Collective Dose Trends for the General Electric Fuel Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Long Lived Radioactive Dust External

Year

Figure 256 Distribution of Effective Doses among all Workers at the General Electric Fuel Facility

0

10

20

30

40

50

60

70

80

90

100

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

54

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

242 Zircatec Nuclear Fuel Facility

Zircatec Precision Industries Inc operates a nuclear fuel facility in Port Hope Ontario where it makes fuel pellets from uranium dioxide powder received from Port Hopersquos uranium conversion facility The nuclear fuel facility also manufactures fuel bundles for nuclear reactors in Canada

Notes on data for the Zircatec nuclear fuel facility

1 Graphs indicate the following data bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of average effective doses

2 Doses from photons from external sources were measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay Historically although these internal doses have been measured and submitted to the CNSC they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

Figures 257ndash260 present dose information for the Zircatec nuclear fuel facility from 2001 to 2007

Figure 257 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on Non-Zero Results)

0

05

1

15

2

25

3

35

Effe

ctiv

e D

ose

(mS

v)

Year

55

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 258 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

18

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 259 Collective Dose Trends for the Zircatec Nuclear Fuel Facility

0

50

100

150

200

250

300

350

400

450

500

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

56

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 260 Distribution of Effective Doses Among All Workers at the Zircatec Nuclear Fuel Facility

300

Num

ber o

f Wor

kers

250

200

150

100

50

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

57

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

25 Research and Radioisotope Production Facilities This section presents dose information for the following research and radioisotope production facilities from 2001 to 2007

bull Chalk River Laboratories and Whiteshell Laboratories (Section 251) bull A radioisotope production facility operated by MDS Nordion (Section 252) bull The Tri-University Meson Facility (TRIUMF) (Section 253)

Note on data for research and radioisotope production facilities

1 Graphs indicate the following data for each facility bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of effective doses

251 Chalk River Laboratories and Whiteshell Laboratories

Atomic Energy of Canada Limited (AECL) owns and is licensed to operate Chalk River Laboratories and Whiteshell Laboratories

Situated in Renfrew County on the south shore of the Ottawa River the Chalk River Laboratories site hosts the National Research Universal Reactor along with numerous other facilities occupying some 160 buildings in an area of approximately 40 km2 Activities consist of radioisotope production for nuclear medicine testing and development of structural materials in support of power reactor operations fuel fabrication research and radioactive waste management and storage

The Whiteshell Laboratories site is located approximately 10 km west of Pinawa Manitoba and 100 km northeast of Winnipeg on the east bank of the Winnipeg River AECL established the laboratories for nuclear research and testing during the early 1960s and has since discontinued operations which are being decommissioned under a licence from the CNSC

Figures 261ndash264 present dose information for Chalk River Laboratories and Whiteshell Laboratories from 2001 to 2007

Notes on data for Chalk River Laboratories and Whiteshell Laboratories

1 Effective doses are composed of the following reported components bull external doses5 (from both photon and neutron doses) bull tritium doses

Due to issues with AECLrsquos in-house dosimetry management system neutron doses were not reported separately to the NDR during the reporting period As a result external doses from photons and neutrons were totaled The reporting discrepancy has since been rectified

58

5

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of external (photon and neutron) and tritium doses Intakes of other radionuclides occasionally occur and these radionuclides are not included here because their associated doses are very small For this reason certain collective doses in this report may have values slightly lower than the sum of their respective components as listed

Figure 261 Average Dose Trends for Chalk River and Whiteshell Laboratories (Non-Zero Results Only)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Tritium External Effective

Year

59

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 262 Average Dose Trends for Chalk River and Whiteshell Laboratories (All Monitoring Results)

000

020

040

060

080

100

120

Dos

e (m

Sv)

Tritium External Effective

Year

Figure 263 Collective Dose Trends for Chalk River and Whiteshell Laboratories

0

500

1000

1500

2000

2500

3000

3500

Col

lect

ive

Dos

e (p

erso

n- m

Sv)

External Tritium

Year

60

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 264 Distribution of Effective Doses Among All Workers at Chalk River and Whiteshell Laboratories

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

3500

3000

2500

2000

1500

1000

500

Dose (mSv)

61

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

252 MDS Nordion (Nuclear Substance Processing Facility and Canadian Irradiation Centre)

MDS Nordion owns and operates a nuclear substance processing facility in Ottawa Ontario where it processes unsealed radioisotopes and manufactures sealed radiation sources In operation since the early 1970s the facility was purchased by Nordion International in 1991

In cooperation with the Universiteacute du Queacutebecrsquos Institut Armand-Frappier MDS Nordion also operates the Canadian Irradiation Centre which conducts various irradiation services which include training testing and development The centre is located in Laval Quebec on the Universiteacute du Queacutebec campus

Figures 265ndash268 present dose information for MDS Nordionrsquos Ottawa nuclear substance processing facility and for the Canadian Irradiation Centre from 2001 to 2007

Notes on data for MDS Nordionrsquos nuclear substance processing facility and the Canadian Irradiation Centre

1 Doses from photons from external sources were measured and reported to the NDR MDS Nordion also has a routine thyroid monitoring program very occasionally small recordable doses of radiation have occurred from thyroid uptake of iodine The resulting doses have not been historically submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided

Figure 265 Average Dose Trends for MDS Nordion (Based on Non-Zero Results)

0

05

1

15

2

25

Effe

ctiv

e D

ose

(mS

v)

Year

62

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 266 Average Dose Trends for MDS Nordion (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

Figure 267 Collective Dose Trends for MDS Nordion

0

100

200

300

400

500

600

700

800

Year

63

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 268 Distribution of Effective Doses Among All Workers at MDS Nordion

0

5 0

1 0 0

1 5 0

2 0 0

2 5 0

3 0 0

3 5 0

4 0 0

4 5 0

5 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

64

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

253 Tri-University Meson Facility

The Tri-University Meson facility (TRIUMF) is situated in Vancouver on the campus of the University of British Columbia TRIUMF which began operating in the early 1970s with one cyclotron now has two cyclotrons and associated laboratories for research and radioisotope production The laboratory provides research facilities for Canadian and international users and also produces radioisotopes which are used by medical facilities and by a commercial organization (MDS Nordion) MDS Nordion staff also work at the TRIUMF site however MDS Nordion oversees this work and has its own radiation protection program

Figures 269ndash272 present dose information for the TRIUMF facility from 2001 to 2007 Please note that data sets do not distinguish between doses received by TRIUMF staff and MDS Nordion staff who work on the site as the data for these two groups was submitted collectively to the NDR for the reporting period shown Future data for each group will be submitted separately to the NDR

Note on data for TRIUMF

1 Effective doses are composed of the following reported components bull doses from photons (labeled as ldquoexternalrdquo in the charts) bull neutron doses

Figure 269 Average Dose Trends for TRIUMF (Non-Zero Results Only)

000

020

040

060

080

100

120

140

160

Dos

e (m

Sv)

Neutrons External Effective

Year

65

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 29: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

000-0

009

001-5

00

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 216 Distribution of Effective Doses Among All Workers at Gentilly-2 Nuclear Generating Station

2500

2000

1500

1000

500

0

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

24

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

215 Point Lepreau Nuclear Generating Station

The Point Lepreau Nuclear Generating Station has one reactor that began operating in 1982 Owned and operated by New Brunswick Power Nuclear the station is located in Point Lepreau New Brunswick about 40 km west of Saint John on the shores of the Bay of Fundy

Figures 217ndash220 present dose information for the Point Lepreau Nuclear Generating Station from 2001 to 2007

Figure 217 Average Dose Trends for Point Lepreau N uclear Generating Stati on (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

)S

v(m

e os

D

Tritium Neutron External Effective

Year

25

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 218 Average Dose Trends for Point Lepreau N uclear Generating Stati on (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

)S

v(m

e os

D

Tritium Neutrons External Effective

Year

Figure 219 Collective Dose Trends for Point Lepreau N uclear Generating Station

0

200

400

600

800

1000

1200

1400

1600

1800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Neutrons

External

Tritium

Year

26

0

1400

1200

1000

800

600

400

200

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 220 Distribution of Effective Doses Among All Workers at Point Lepreau Nuclear Generating Station

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

27

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

22 Uranium Mines and Mills This section presents dose information for mine and mill sites in the following regions

bull Cluff Lake (Section 221) bull McClean Lake (Section 222) bull McArthur River (Section 223) bull Key Lake (Section 224) bull Cigar Lake (Section 225) bull Rabbit Lake (Section 226)

Graphs indicate the following data for each site from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for uranium mines and mills

1 Effective doses are composed of the following reported components bull doses from photons (labelled on the charts as ldquoexternalrdquo) bull doses from radon progeny bull doses from long-lived radioactive dust bull doses from radon gas (in some cases)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of photon radon progeny long-lived radioactive dust and radon gas doses

3 The NDR lists radon progeny in working level months (WLM) For this report radon progeny exposures were converted4 to doses expressed in mSv

221 Cluff Lake Operation

The Cluff Lake mining facilities operated by AREVA Resources Canada Inc are located in northwestern Saskatchewan Work began in 1980 and ended in 2002 with the site now being decommissioned The site consisted of three open-pit and two underground mines a mill and a tailings management facility During 2005 and 2006 most of the infrastructure was removed and the affected areas were remediated

Figures 221ndash224 present dose information for the Cluff Lake operation from 2001 to 2007

4 Doses were converted using the International Commission on Radiation Protection (ICRP)rsquos conversion convention of 1 WLM = 5 mSv This convention was established in the ICRP publication Protection against Radon at Home and at Work (ICRP 65)

28

Long-lived radioactive dust Radon progeny External Effective

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 221 Average Dose Trends for the Cluff Lake Operation (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

Year

Figure 222 Average Dose Trends for the Cluff Lake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

200

Long-lived radioactive dust Radon progeny External Effective

)S

v(m

e os

D)

Sv

(me

osD

Year

29

600

500

400

300

200

100

0

External Radon progeny Long-lived radioactive dust

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 223 Collective Dose Trends for the Cluff Lake Operation s

erkor

of W

ber

Num

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Year

Figure 224 Distribution o f Effective Doses Among A ll Workers at the Cluff Lake Operation

0

20

40

60

80

100

120

140

160

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

30

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

222 McClean Lake Operation

AREVA Resources Canada Inc runs the McClean Lake mining operation in northeastern Saskatchewan It comprises open pit mines a mill and a tailings management facility Mining began in 1995 while milling started in 1999

Figures 225ndash228 present dose information for the McClean Lake operation from 2001 to 2007

Figure 225 Average Dose Trends for the McClean L ake Operation (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

31

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 226 Average Dose Trends for the McClean L ake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 227 Collective Dose Trends for the McClean L ake Operation

0

100

200

300

400

500

600

700

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External

Radon progeny

Long-lived radioactive dust

Year

32

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 228 Distribution o f Effective Doses Among A ll Workers at the McClean Lake Operation

0

100

200

300

400

500

600

700

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

33

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

223 McArthur River Operation

Cameco Corporation operates the McArthur River underground mine in north-central Saskatchewan Ore from the mine which began production in 1999 is processed at the Key Lake Mill located 80 km south of McArthur River

Figures 229ndash232 present dose information for the McArthur River operation from 2001 to 2007

Figure 229 Average Dose Trends for the McArthur River Operation (Based o n N on-Zero R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

34

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 230 Average Dose Trends for the McArthur River Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

Figure 231 Collective Dose Trends for the McArthur River Operation

0

200

400

600

800

1000

1200

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Radon gas External Radon progeny Long-lived radioactive dust

Year

35

00

0-000

9

001-5

00

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 232 Distribution o f Effective Doses Among A ll Workers at the McArthur River Operation

0

100

200

300

400

500

600

700

800

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

36

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

224 Key Lake Operation

Cameco Corporation operates mining facilities in Key Lake located in north-central Saskatchewan The Key Lake operation includes two mined-out open pit mines (used for tailings management) a mill and two dry tailings management facilities Mining began in 1983 and ceased in 1997 the mill continued to process ore from the McArthur River mine during the reporting period

Figures 233ndash236 present dose information for the Key Lake operation from 2001 to 2007

Figure 233 Average Dose Trends for the Key Lake Operation (Based o n N on-Zero R esults)

00

20

40

60

80

00

20

40

60

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

37

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

00

20

40

60

80

00

20

40

60

Figure 234 Average Dose Trends for the Key Lake Operation (Based o n A ll Monitoring R esults)

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 235 Collective Dose Trends for the Key Lake Operation

0

100

200

300

400

500

600

700

800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External Radon progeny Long-lived radioactive dust

Year

38

00

0-000

9

001-5

0

501-1

000

gt 1001

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 236 Distribution o f Effective Doses Among A ll Workers at the Key Lake Operation

0

200

400

600

800

1000

1200

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose Range (mSv)

39

se

(mS

v)o

D

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

225 Cigar Lake Operation

Cameco Corporation manages the Cigar Lake underground mine located in northern Saskatchewan at the southern end of Waterbury Lake The mine was under construction at the time of this reportrsquos publication Test mining in ore was carried out in 1991 1992 and 2000

Figures 237ndash240 present dose information for the Cigar Lake operation from

Figure 2 37 Average D ose T rends fo r th e C igar L ake O peration (Based on Non-Zero Results)

2001 to 2007

Year

000

005

010

015

020

025

Long-lived radioactive dust Radon Progeny External Effective

40

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 238 Average Dose Trends for the Cigar Lake Operation (Based on All Monitoring Results)

000

005

010

015

020

025

030

035

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny

External

Effective

Year

Figure 239 Collective Dose Trends for the Cigar Lake Operation

0

50

100

150

200

250

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

External Radon progeny Long-lived radioactive dust

Year

41

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 240 Distribution of Effective Doses Among All Workers at the Cigar Lake Operation

0

200

400

600

800

1000

1200

1400

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

42

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

226 Rabbit Lake Operation

Cameco Corporation owns and operates mining facilities in Rabbit Lake located in north-eastern Saskatchewan Facilities include an underground mine four mined-out open-pit mines a mill and two tailings management facilities Mining and milling began in 1975

Figures 241ndash244 present dose information for the Rabbit Lake operation from 2001 to 2007

Figure 241 Average Dose Trends for the Rabbit Lake Operation (Based on Non-Zero Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

43

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 242 Average Dose Trends for the Rabbit Lake Operation (Based on All Monitoring Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

Figure 243 Collective Dose Trends for the Rabbit Lake Operation

0

200

400

600

800

1000

1200

1400

1600

1800

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Radon gas External Radon progeny Long-lived radioactive dust

Year

44

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

gt300

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 244 Distribution of Effective Doses Among All Workers at the Rabbit Lake Operation

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

900

800

700

600

500

400

300

200

100

0

Dose (mSv)

45

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

23 Uranium Refineries This section presents data for the following two facilities

bull a uranium refining facility in Blind River (Section 231) bull a uranium conversion facility in Port Hope (Section 232)

Graphs indicate the following average doses at each facility from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Note on data for uranium refineries

1 Doses from photons from external sources are measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay and lung counting Historically while these internal doses have been measured they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

231 Blind River Refinery

Cameco Corporation owns and is licensed to operate a uranium refinery in Blind River Ontario The facility which began operating in 1983 converts uranium ore concentrate to uranium trioxide The uranium trioxide is shipped to Camecorsquos uranium conversion facility in Port Hope Ontario where it is processed into uranium dioxide (for use in the fabrication of fuel for nuclear reactors in Canada) or uranium hexafluoride (exported for enrichment and fabrication into fuel for nuclear power reactors around the world)

Figures 245ndash248 present dose information for the Blind River refinery from 2001 to 2007

46

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 245 Average Dose Trends for the Blind River Refinery (Based on Non-Zero Results)

0

05

1

15

2

25

Year

Figure 246 Average Dose Trends for the Blind River Refinery (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

47

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 247 Collective Dose Trends for the Blind River Refinery

0

50

100

150

200

250

300 C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 248 Distribution of Effective Doses Among All Workers at the Blind River Refinery

0

20

40

60

80

100

120

140

160

180

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

48

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

232 Port Hope Conversion Facility

Cameco Corporation owns and is licensed to operate a uranium conversion facility in Port Hope Ontario The facility processes uranium trioxide received from the refinery in Blind River into uranium dioxide and uranium hexafluoride

Figures 249ndash252 present dose information for the Port Hope uranium conversion facility from 2001 to 2007

Figure 249 Average Dose Trends for the Port Hope Conversion Facility (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

49

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 250 Average Dose Trends for the Port Hope Conversion Facility (Based on All Monitoring Results)

0

01

02

03

04

05

06

07

08

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 251 Collective Dose Trends for the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

50

000-0

009

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 252 Distribution of Effective Doses Among All Workers at the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

400

450

500

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

51

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

24 Fuel Fabrication Facilities This section presents data for three nuclear fuel fabrication facilities

bull Two facilities owned and operated by General Electric Canada Inc (Section 241) bull One facility in Port Hope operated by Zircatec Precision Industries (Section 242)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average doses

Notes on data for fuel fabrication facilities

1 Effective doses for the three facilities are composed of the following reported components bull dose from photons (labelled on the charts as ldquoexternalrdquo) bull doses from internal intakes of uranium dust (long-lived radioactive dust) from

uranium in air concentrations (for General Electricrsquos Toronto facility only)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components photon doses and doses from long-lived radioactive dust

241 General Electric Nuclear Fuel Facilities

General Electric Canada Inc operates two nuclear fuel facilities in Ontario

bull At the Toronto facility uranium dioxide pellets are produced from natural or depleted uranium dioxide powder

bull At the Peterborough facility uranium dioxide fuel bundles are created from the pellets produced at the Toronto facility

Figures 253ndash256 present dose information for General Electric Canada Incrsquos fuel fabrication facilities from 2001 to 2007 Graphs do not distinguish between the doses received at the Peterborough facility versus those at the Toronto facility

52

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 253 Average Dose Trends for the General Electric Fuel Facility (Based on Non-Zero Results Only)

0

05

1

15

2

25

3

35

Long Lived Radioactive Dust External Effective

Year

Figure 254 Average Dose Trends for the General Electric Fuel Facility (Based on All Monitoring Results)

0

05

1

15

2

25

3

Long Lived Radioactive Dust External Effective

Year

Dos

e (m

Sv)

Dos

e (m

Sv)

53

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 255 Collective Dose Trends for the General Electric Fuel Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Long Lived Radioactive Dust External

Year

Figure 256 Distribution of Effective Doses among all Workers at the General Electric Fuel Facility

0

10

20

30

40

50

60

70

80

90

100

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

54

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

242 Zircatec Nuclear Fuel Facility

Zircatec Precision Industries Inc operates a nuclear fuel facility in Port Hope Ontario where it makes fuel pellets from uranium dioxide powder received from Port Hopersquos uranium conversion facility The nuclear fuel facility also manufactures fuel bundles for nuclear reactors in Canada

Notes on data for the Zircatec nuclear fuel facility

1 Graphs indicate the following data bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of average effective doses

2 Doses from photons from external sources were measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay Historically although these internal doses have been measured and submitted to the CNSC they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

Figures 257ndash260 present dose information for the Zircatec nuclear fuel facility from 2001 to 2007

Figure 257 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on Non-Zero Results)

0

05

1

15

2

25

3

35

Effe

ctiv

e D

ose

(mS

v)

Year

55

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 258 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

18

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 259 Collective Dose Trends for the Zircatec Nuclear Fuel Facility

0

50

100

150

200

250

300

350

400

450

500

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

56

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 260 Distribution of Effective Doses Among All Workers at the Zircatec Nuclear Fuel Facility

300

Num

ber o

f Wor

kers

250

200

150

100

50

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

57

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

25 Research and Radioisotope Production Facilities This section presents dose information for the following research and radioisotope production facilities from 2001 to 2007

bull Chalk River Laboratories and Whiteshell Laboratories (Section 251) bull A radioisotope production facility operated by MDS Nordion (Section 252) bull The Tri-University Meson Facility (TRIUMF) (Section 253)

Note on data for research and radioisotope production facilities

1 Graphs indicate the following data for each facility bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of effective doses

251 Chalk River Laboratories and Whiteshell Laboratories

Atomic Energy of Canada Limited (AECL) owns and is licensed to operate Chalk River Laboratories and Whiteshell Laboratories

Situated in Renfrew County on the south shore of the Ottawa River the Chalk River Laboratories site hosts the National Research Universal Reactor along with numerous other facilities occupying some 160 buildings in an area of approximately 40 km2 Activities consist of radioisotope production for nuclear medicine testing and development of structural materials in support of power reactor operations fuel fabrication research and radioactive waste management and storage

The Whiteshell Laboratories site is located approximately 10 km west of Pinawa Manitoba and 100 km northeast of Winnipeg on the east bank of the Winnipeg River AECL established the laboratories for nuclear research and testing during the early 1960s and has since discontinued operations which are being decommissioned under a licence from the CNSC

Figures 261ndash264 present dose information for Chalk River Laboratories and Whiteshell Laboratories from 2001 to 2007

Notes on data for Chalk River Laboratories and Whiteshell Laboratories

1 Effective doses are composed of the following reported components bull external doses5 (from both photon and neutron doses) bull tritium doses

Due to issues with AECLrsquos in-house dosimetry management system neutron doses were not reported separately to the NDR during the reporting period As a result external doses from photons and neutrons were totaled The reporting discrepancy has since been rectified

58

5

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of external (photon and neutron) and tritium doses Intakes of other radionuclides occasionally occur and these radionuclides are not included here because their associated doses are very small For this reason certain collective doses in this report may have values slightly lower than the sum of their respective components as listed

Figure 261 Average Dose Trends for Chalk River and Whiteshell Laboratories (Non-Zero Results Only)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Tritium External Effective

Year

59

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 262 Average Dose Trends for Chalk River and Whiteshell Laboratories (All Monitoring Results)

000

020

040

060

080

100

120

Dos

e (m

Sv)

Tritium External Effective

Year

Figure 263 Collective Dose Trends for Chalk River and Whiteshell Laboratories

0

500

1000

1500

2000

2500

3000

3500

Col

lect

ive

Dos

e (p

erso

n- m

Sv)

External Tritium

Year

60

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 264 Distribution of Effective Doses Among All Workers at Chalk River and Whiteshell Laboratories

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

3500

3000

2500

2000

1500

1000

500

Dose (mSv)

61

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

252 MDS Nordion (Nuclear Substance Processing Facility and Canadian Irradiation Centre)

MDS Nordion owns and operates a nuclear substance processing facility in Ottawa Ontario where it processes unsealed radioisotopes and manufactures sealed radiation sources In operation since the early 1970s the facility was purchased by Nordion International in 1991

In cooperation with the Universiteacute du Queacutebecrsquos Institut Armand-Frappier MDS Nordion also operates the Canadian Irradiation Centre which conducts various irradiation services which include training testing and development The centre is located in Laval Quebec on the Universiteacute du Queacutebec campus

Figures 265ndash268 present dose information for MDS Nordionrsquos Ottawa nuclear substance processing facility and for the Canadian Irradiation Centre from 2001 to 2007

Notes on data for MDS Nordionrsquos nuclear substance processing facility and the Canadian Irradiation Centre

1 Doses from photons from external sources were measured and reported to the NDR MDS Nordion also has a routine thyroid monitoring program very occasionally small recordable doses of radiation have occurred from thyroid uptake of iodine The resulting doses have not been historically submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided

Figure 265 Average Dose Trends for MDS Nordion (Based on Non-Zero Results)

0

05

1

15

2

25

Effe

ctiv

e D

ose

(mS

v)

Year

62

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 266 Average Dose Trends for MDS Nordion (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

Figure 267 Collective Dose Trends for MDS Nordion

0

100

200

300

400

500

600

700

800

Year

63

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 268 Distribution of Effective Doses Among All Workers at MDS Nordion

0

5 0

1 0 0

1 5 0

2 0 0

2 5 0

3 0 0

3 5 0

4 0 0

4 5 0

5 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

64

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

253 Tri-University Meson Facility

The Tri-University Meson facility (TRIUMF) is situated in Vancouver on the campus of the University of British Columbia TRIUMF which began operating in the early 1970s with one cyclotron now has two cyclotrons and associated laboratories for research and radioisotope production The laboratory provides research facilities for Canadian and international users and also produces radioisotopes which are used by medical facilities and by a commercial organization (MDS Nordion) MDS Nordion staff also work at the TRIUMF site however MDS Nordion oversees this work and has its own radiation protection program

Figures 269ndash272 present dose information for the TRIUMF facility from 2001 to 2007 Please note that data sets do not distinguish between doses received by TRIUMF staff and MDS Nordion staff who work on the site as the data for these two groups was submitted collectively to the NDR for the reporting period shown Future data for each group will be submitted separately to the NDR

Note on data for TRIUMF

1 Effective doses are composed of the following reported components bull doses from photons (labeled as ldquoexternalrdquo in the charts) bull neutron doses

Figure 269 Average Dose Trends for TRIUMF (Non-Zero Results Only)

000

020

040

060

080

100

120

140

160

Dos

e (m

Sv)

Neutrons External Effective

Year

65

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 30: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

215 Point Lepreau Nuclear Generating Station

The Point Lepreau Nuclear Generating Station has one reactor that began operating in 1982 Owned and operated by New Brunswick Power Nuclear the station is located in Point Lepreau New Brunswick about 40 km west of Saint John on the shores of the Bay of Fundy

Figures 217ndash220 present dose information for the Point Lepreau Nuclear Generating Station from 2001 to 2007

Figure 217 Average Dose Trends for Point Lepreau N uclear Generating Stati on (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

)S

v(m

e os

D

Tritium Neutron External Effective

Year

25

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 218 Average Dose Trends for Point Lepreau N uclear Generating Stati on (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

)S

v(m

e os

D

Tritium Neutrons External Effective

Year

Figure 219 Collective Dose Trends for Point Lepreau N uclear Generating Station

0

200

400

600

800

1000

1200

1400

1600

1800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Neutrons

External

Tritium

Year

26

0

1400

1200

1000

800

600

400

200

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 220 Distribution of Effective Doses Among All Workers at Point Lepreau Nuclear Generating Station

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

27

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

22 Uranium Mines and Mills This section presents dose information for mine and mill sites in the following regions

bull Cluff Lake (Section 221) bull McClean Lake (Section 222) bull McArthur River (Section 223) bull Key Lake (Section 224) bull Cigar Lake (Section 225) bull Rabbit Lake (Section 226)

Graphs indicate the following data for each site from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for uranium mines and mills

1 Effective doses are composed of the following reported components bull doses from photons (labelled on the charts as ldquoexternalrdquo) bull doses from radon progeny bull doses from long-lived radioactive dust bull doses from radon gas (in some cases)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of photon radon progeny long-lived radioactive dust and radon gas doses

3 The NDR lists radon progeny in working level months (WLM) For this report radon progeny exposures were converted4 to doses expressed in mSv

221 Cluff Lake Operation

The Cluff Lake mining facilities operated by AREVA Resources Canada Inc are located in northwestern Saskatchewan Work began in 1980 and ended in 2002 with the site now being decommissioned The site consisted of three open-pit and two underground mines a mill and a tailings management facility During 2005 and 2006 most of the infrastructure was removed and the affected areas were remediated

Figures 221ndash224 present dose information for the Cluff Lake operation from 2001 to 2007

4 Doses were converted using the International Commission on Radiation Protection (ICRP)rsquos conversion convention of 1 WLM = 5 mSv This convention was established in the ICRP publication Protection against Radon at Home and at Work (ICRP 65)

28

Long-lived radioactive dust Radon progeny External Effective

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 221 Average Dose Trends for the Cluff Lake Operation (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

Year

Figure 222 Average Dose Trends for the Cluff Lake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

200

Long-lived radioactive dust Radon progeny External Effective

)S

v(m

e os

D)

Sv

(me

osD

Year

29

600

500

400

300

200

100

0

External Radon progeny Long-lived radioactive dust

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 223 Collective Dose Trends for the Cluff Lake Operation s

erkor

of W

ber

Num

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Year

Figure 224 Distribution o f Effective Doses Among A ll Workers at the Cluff Lake Operation

0

20

40

60

80

100

120

140

160

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

30

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

222 McClean Lake Operation

AREVA Resources Canada Inc runs the McClean Lake mining operation in northeastern Saskatchewan It comprises open pit mines a mill and a tailings management facility Mining began in 1995 while milling started in 1999

Figures 225ndash228 present dose information for the McClean Lake operation from 2001 to 2007

Figure 225 Average Dose Trends for the McClean L ake Operation (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

31

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 226 Average Dose Trends for the McClean L ake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 227 Collective Dose Trends for the McClean L ake Operation

0

100

200

300

400

500

600

700

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External

Radon progeny

Long-lived radioactive dust

Year

32

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 228 Distribution o f Effective Doses Among A ll Workers at the McClean Lake Operation

0

100

200

300

400

500

600

700

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

33

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

223 McArthur River Operation

Cameco Corporation operates the McArthur River underground mine in north-central Saskatchewan Ore from the mine which began production in 1999 is processed at the Key Lake Mill located 80 km south of McArthur River

Figures 229ndash232 present dose information for the McArthur River operation from 2001 to 2007

Figure 229 Average Dose Trends for the McArthur River Operation (Based o n N on-Zero R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

34

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 230 Average Dose Trends for the McArthur River Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

Figure 231 Collective Dose Trends for the McArthur River Operation

0

200

400

600

800

1000

1200

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Radon gas External Radon progeny Long-lived radioactive dust

Year

35

00

0-000

9

001-5

00

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 232 Distribution o f Effective Doses Among A ll Workers at the McArthur River Operation

0

100

200

300

400

500

600

700

800

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

36

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

224 Key Lake Operation

Cameco Corporation operates mining facilities in Key Lake located in north-central Saskatchewan The Key Lake operation includes two mined-out open pit mines (used for tailings management) a mill and two dry tailings management facilities Mining began in 1983 and ceased in 1997 the mill continued to process ore from the McArthur River mine during the reporting period

Figures 233ndash236 present dose information for the Key Lake operation from 2001 to 2007

Figure 233 Average Dose Trends for the Key Lake Operation (Based o n N on-Zero R esults)

00

20

40

60

80

00

20

40

60

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

37

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

00

20

40

60

80

00

20

40

60

Figure 234 Average Dose Trends for the Key Lake Operation (Based o n A ll Monitoring R esults)

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 235 Collective Dose Trends for the Key Lake Operation

0

100

200

300

400

500

600

700

800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External Radon progeny Long-lived radioactive dust

Year

38

00

0-000

9

001-5

0

501-1

000

gt 1001

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 236 Distribution o f Effective Doses Among A ll Workers at the Key Lake Operation

0

200

400

600

800

1000

1200

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose Range (mSv)

39

se

(mS

v)o

D

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

225 Cigar Lake Operation

Cameco Corporation manages the Cigar Lake underground mine located in northern Saskatchewan at the southern end of Waterbury Lake The mine was under construction at the time of this reportrsquos publication Test mining in ore was carried out in 1991 1992 and 2000

Figures 237ndash240 present dose information for the Cigar Lake operation from

Figure 2 37 Average D ose T rends fo r th e C igar L ake O peration (Based on Non-Zero Results)

2001 to 2007

Year

000

005

010

015

020

025

Long-lived radioactive dust Radon Progeny External Effective

40

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 238 Average Dose Trends for the Cigar Lake Operation (Based on All Monitoring Results)

000

005

010

015

020

025

030

035

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny

External

Effective

Year

Figure 239 Collective Dose Trends for the Cigar Lake Operation

0

50

100

150

200

250

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

External Radon progeny Long-lived radioactive dust

Year

41

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 240 Distribution of Effective Doses Among All Workers at the Cigar Lake Operation

0

200

400

600

800

1000

1200

1400

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

42

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

226 Rabbit Lake Operation

Cameco Corporation owns and operates mining facilities in Rabbit Lake located in north-eastern Saskatchewan Facilities include an underground mine four mined-out open-pit mines a mill and two tailings management facilities Mining and milling began in 1975

Figures 241ndash244 present dose information for the Rabbit Lake operation from 2001 to 2007

Figure 241 Average Dose Trends for the Rabbit Lake Operation (Based on Non-Zero Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

43

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 242 Average Dose Trends for the Rabbit Lake Operation (Based on All Monitoring Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

Figure 243 Collective Dose Trends for the Rabbit Lake Operation

0

200

400

600

800

1000

1200

1400

1600

1800

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Radon gas External Radon progeny Long-lived radioactive dust

Year

44

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

gt300

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 244 Distribution of Effective Doses Among All Workers at the Rabbit Lake Operation

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

900

800

700

600

500

400

300

200

100

0

Dose (mSv)

45

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

23 Uranium Refineries This section presents data for the following two facilities

bull a uranium refining facility in Blind River (Section 231) bull a uranium conversion facility in Port Hope (Section 232)

Graphs indicate the following average doses at each facility from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Note on data for uranium refineries

1 Doses from photons from external sources are measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay and lung counting Historically while these internal doses have been measured they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

231 Blind River Refinery

Cameco Corporation owns and is licensed to operate a uranium refinery in Blind River Ontario The facility which began operating in 1983 converts uranium ore concentrate to uranium trioxide The uranium trioxide is shipped to Camecorsquos uranium conversion facility in Port Hope Ontario where it is processed into uranium dioxide (for use in the fabrication of fuel for nuclear reactors in Canada) or uranium hexafluoride (exported for enrichment and fabrication into fuel for nuclear power reactors around the world)

Figures 245ndash248 present dose information for the Blind River refinery from 2001 to 2007

46

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 245 Average Dose Trends for the Blind River Refinery (Based on Non-Zero Results)

0

05

1

15

2

25

Year

Figure 246 Average Dose Trends for the Blind River Refinery (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

47

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 247 Collective Dose Trends for the Blind River Refinery

0

50

100

150

200

250

300 C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 248 Distribution of Effective Doses Among All Workers at the Blind River Refinery

0

20

40

60

80

100

120

140

160

180

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

48

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

232 Port Hope Conversion Facility

Cameco Corporation owns and is licensed to operate a uranium conversion facility in Port Hope Ontario The facility processes uranium trioxide received from the refinery in Blind River into uranium dioxide and uranium hexafluoride

Figures 249ndash252 present dose information for the Port Hope uranium conversion facility from 2001 to 2007

Figure 249 Average Dose Trends for the Port Hope Conversion Facility (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

49

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 250 Average Dose Trends for the Port Hope Conversion Facility (Based on All Monitoring Results)

0

01

02

03

04

05

06

07

08

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 251 Collective Dose Trends for the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

50

000-0

009

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 252 Distribution of Effective Doses Among All Workers at the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

400

450

500

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

51

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

24 Fuel Fabrication Facilities This section presents data for three nuclear fuel fabrication facilities

bull Two facilities owned and operated by General Electric Canada Inc (Section 241) bull One facility in Port Hope operated by Zircatec Precision Industries (Section 242)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average doses

Notes on data for fuel fabrication facilities

1 Effective doses for the three facilities are composed of the following reported components bull dose from photons (labelled on the charts as ldquoexternalrdquo) bull doses from internal intakes of uranium dust (long-lived radioactive dust) from

uranium in air concentrations (for General Electricrsquos Toronto facility only)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components photon doses and doses from long-lived radioactive dust

241 General Electric Nuclear Fuel Facilities

General Electric Canada Inc operates two nuclear fuel facilities in Ontario

bull At the Toronto facility uranium dioxide pellets are produced from natural or depleted uranium dioxide powder

bull At the Peterborough facility uranium dioxide fuel bundles are created from the pellets produced at the Toronto facility

Figures 253ndash256 present dose information for General Electric Canada Incrsquos fuel fabrication facilities from 2001 to 2007 Graphs do not distinguish between the doses received at the Peterborough facility versus those at the Toronto facility

52

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 253 Average Dose Trends for the General Electric Fuel Facility (Based on Non-Zero Results Only)

0

05

1

15

2

25

3

35

Long Lived Radioactive Dust External Effective

Year

Figure 254 Average Dose Trends for the General Electric Fuel Facility (Based on All Monitoring Results)

0

05

1

15

2

25

3

Long Lived Radioactive Dust External Effective

Year

Dos

e (m

Sv)

Dos

e (m

Sv)

53

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 255 Collective Dose Trends for the General Electric Fuel Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Long Lived Radioactive Dust External

Year

Figure 256 Distribution of Effective Doses among all Workers at the General Electric Fuel Facility

0

10

20

30

40

50

60

70

80

90

100

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

54

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

242 Zircatec Nuclear Fuel Facility

Zircatec Precision Industries Inc operates a nuclear fuel facility in Port Hope Ontario where it makes fuel pellets from uranium dioxide powder received from Port Hopersquos uranium conversion facility The nuclear fuel facility also manufactures fuel bundles for nuclear reactors in Canada

Notes on data for the Zircatec nuclear fuel facility

1 Graphs indicate the following data bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of average effective doses

2 Doses from photons from external sources were measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay Historically although these internal doses have been measured and submitted to the CNSC they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

Figures 257ndash260 present dose information for the Zircatec nuclear fuel facility from 2001 to 2007

Figure 257 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on Non-Zero Results)

0

05

1

15

2

25

3

35

Effe

ctiv

e D

ose

(mS

v)

Year

55

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 258 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

18

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 259 Collective Dose Trends for the Zircatec Nuclear Fuel Facility

0

50

100

150

200

250

300

350

400

450

500

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

56

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 260 Distribution of Effective Doses Among All Workers at the Zircatec Nuclear Fuel Facility

300

Num

ber o

f Wor

kers

250

200

150

100

50

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

57

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

25 Research and Radioisotope Production Facilities This section presents dose information for the following research and radioisotope production facilities from 2001 to 2007

bull Chalk River Laboratories and Whiteshell Laboratories (Section 251) bull A radioisotope production facility operated by MDS Nordion (Section 252) bull The Tri-University Meson Facility (TRIUMF) (Section 253)

Note on data for research and radioisotope production facilities

1 Graphs indicate the following data for each facility bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of effective doses

251 Chalk River Laboratories and Whiteshell Laboratories

Atomic Energy of Canada Limited (AECL) owns and is licensed to operate Chalk River Laboratories and Whiteshell Laboratories

Situated in Renfrew County on the south shore of the Ottawa River the Chalk River Laboratories site hosts the National Research Universal Reactor along with numerous other facilities occupying some 160 buildings in an area of approximately 40 km2 Activities consist of radioisotope production for nuclear medicine testing and development of structural materials in support of power reactor operations fuel fabrication research and radioactive waste management and storage

The Whiteshell Laboratories site is located approximately 10 km west of Pinawa Manitoba and 100 km northeast of Winnipeg on the east bank of the Winnipeg River AECL established the laboratories for nuclear research and testing during the early 1960s and has since discontinued operations which are being decommissioned under a licence from the CNSC

Figures 261ndash264 present dose information for Chalk River Laboratories and Whiteshell Laboratories from 2001 to 2007

Notes on data for Chalk River Laboratories and Whiteshell Laboratories

1 Effective doses are composed of the following reported components bull external doses5 (from both photon and neutron doses) bull tritium doses

Due to issues with AECLrsquos in-house dosimetry management system neutron doses were not reported separately to the NDR during the reporting period As a result external doses from photons and neutrons were totaled The reporting discrepancy has since been rectified

58

5

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of external (photon and neutron) and tritium doses Intakes of other radionuclides occasionally occur and these radionuclides are not included here because their associated doses are very small For this reason certain collective doses in this report may have values slightly lower than the sum of their respective components as listed

Figure 261 Average Dose Trends for Chalk River and Whiteshell Laboratories (Non-Zero Results Only)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Tritium External Effective

Year

59

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 262 Average Dose Trends for Chalk River and Whiteshell Laboratories (All Monitoring Results)

000

020

040

060

080

100

120

Dos

e (m

Sv)

Tritium External Effective

Year

Figure 263 Collective Dose Trends for Chalk River and Whiteshell Laboratories

0

500

1000

1500

2000

2500

3000

3500

Col

lect

ive

Dos

e (p

erso

n- m

Sv)

External Tritium

Year

60

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 264 Distribution of Effective Doses Among All Workers at Chalk River and Whiteshell Laboratories

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

3500

3000

2500

2000

1500

1000

500

Dose (mSv)

61

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

252 MDS Nordion (Nuclear Substance Processing Facility and Canadian Irradiation Centre)

MDS Nordion owns and operates a nuclear substance processing facility in Ottawa Ontario where it processes unsealed radioisotopes and manufactures sealed radiation sources In operation since the early 1970s the facility was purchased by Nordion International in 1991

In cooperation with the Universiteacute du Queacutebecrsquos Institut Armand-Frappier MDS Nordion also operates the Canadian Irradiation Centre which conducts various irradiation services which include training testing and development The centre is located in Laval Quebec on the Universiteacute du Queacutebec campus

Figures 265ndash268 present dose information for MDS Nordionrsquos Ottawa nuclear substance processing facility and for the Canadian Irradiation Centre from 2001 to 2007

Notes on data for MDS Nordionrsquos nuclear substance processing facility and the Canadian Irradiation Centre

1 Doses from photons from external sources were measured and reported to the NDR MDS Nordion also has a routine thyroid monitoring program very occasionally small recordable doses of radiation have occurred from thyroid uptake of iodine The resulting doses have not been historically submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided

Figure 265 Average Dose Trends for MDS Nordion (Based on Non-Zero Results)

0

05

1

15

2

25

Effe

ctiv

e D

ose

(mS

v)

Year

62

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 266 Average Dose Trends for MDS Nordion (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

Figure 267 Collective Dose Trends for MDS Nordion

0

100

200

300

400

500

600

700

800

Year

63

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 268 Distribution of Effective Doses Among All Workers at MDS Nordion

0

5 0

1 0 0

1 5 0

2 0 0

2 5 0

3 0 0

3 5 0

4 0 0

4 5 0

5 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

64

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

253 Tri-University Meson Facility

The Tri-University Meson facility (TRIUMF) is situated in Vancouver on the campus of the University of British Columbia TRIUMF which began operating in the early 1970s with one cyclotron now has two cyclotrons and associated laboratories for research and radioisotope production The laboratory provides research facilities for Canadian and international users and also produces radioisotopes which are used by medical facilities and by a commercial organization (MDS Nordion) MDS Nordion staff also work at the TRIUMF site however MDS Nordion oversees this work and has its own radiation protection program

Figures 269ndash272 present dose information for the TRIUMF facility from 2001 to 2007 Please note that data sets do not distinguish between doses received by TRIUMF staff and MDS Nordion staff who work on the site as the data for these two groups was submitted collectively to the NDR for the reporting period shown Future data for each group will be submitted separately to the NDR

Note on data for TRIUMF

1 Effective doses are composed of the following reported components bull doses from photons (labeled as ldquoexternalrdquo in the charts) bull neutron doses

Figure 269 Average Dose Trends for TRIUMF (Non-Zero Results Only)

000

020

040

060

080

100

120

140

160

Dos

e (m

Sv)

Neutrons External Effective

Year

65

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 31: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 218 Average Dose Trends for Point Lepreau N uclear Generating Stati on (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

)S

v(m

e os

D

Tritium Neutrons External Effective

Year

Figure 219 Collective Dose Trends for Point Lepreau N uclear Generating Station

0

200

400

600

800

1000

1200

1400

1600

1800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Neutrons

External

Tritium

Year

26

0

1400

1200

1000

800

600

400

200

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 220 Distribution of Effective Doses Among All Workers at Point Lepreau Nuclear Generating Station

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

27

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

22 Uranium Mines and Mills This section presents dose information for mine and mill sites in the following regions

bull Cluff Lake (Section 221) bull McClean Lake (Section 222) bull McArthur River (Section 223) bull Key Lake (Section 224) bull Cigar Lake (Section 225) bull Rabbit Lake (Section 226)

Graphs indicate the following data for each site from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for uranium mines and mills

1 Effective doses are composed of the following reported components bull doses from photons (labelled on the charts as ldquoexternalrdquo) bull doses from radon progeny bull doses from long-lived radioactive dust bull doses from radon gas (in some cases)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of photon radon progeny long-lived radioactive dust and radon gas doses

3 The NDR lists radon progeny in working level months (WLM) For this report radon progeny exposures were converted4 to doses expressed in mSv

221 Cluff Lake Operation

The Cluff Lake mining facilities operated by AREVA Resources Canada Inc are located in northwestern Saskatchewan Work began in 1980 and ended in 2002 with the site now being decommissioned The site consisted of three open-pit and two underground mines a mill and a tailings management facility During 2005 and 2006 most of the infrastructure was removed and the affected areas were remediated

Figures 221ndash224 present dose information for the Cluff Lake operation from 2001 to 2007

4 Doses were converted using the International Commission on Radiation Protection (ICRP)rsquos conversion convention of 1 WLM = 5 mSv This convention was established in the ICRP publication Protection against Radon at Home and at Work (ICRP 65)

28

Long-lived radioactive dust Radon progeny External Effective

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 221 Average Dose Trends for the Cluff Lake Operation (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

Year

Figure 222 Average Dose Trends for the Cluff Lake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

200

Long-lived radioactive dust Radon progeny External Effective

)S

v(m

e os

D)

Sv

(me

osD

Year

29

600

500

400

300

200

100

0

External Radon progeny Long-lived radioactive dust

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 223 Collective Dose Trends for the Cluff Lake Operation s

erkor

of W

ber

Num

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Year

Figure 224 Distribution o f Effective Doses Among A ll Workers at the Cluff Lake Operation

0

20

40

60

80

100

120

140

160

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

30

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

222 McClean Lake Operation

AREVA Resources Canada Inc runs the McClean Lake mining operation in northeastern Saskatchewan It comprises open pit mines a mill and a tailings management facility Mining began in 1995 while milling started in 1999

Figures 225ndash228 present dose information for the McClean Lake operation from 2001 to 2007

Figure 225 Average Dose Trends for the McClean L ake Operation (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

31

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 226 Average Dose Trends for the McClean L ake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 227 Collective Dose Trends for the McClean L ake Operation

0

100

200

300

400

500

600

700

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External

Radon progeny

Long-lived radioactive dust

Year

32

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 228 Distribution o f Effective Doses Among A ll Workers at the McClean Lake Operation

0

100

200

300

400

500

600

700

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

33

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

223 McArthur River Operation

Cameco Corporation operates the McArthur River underground mine in north-central Saskatchewan Ore from the mine which began production in 1999 is processed at the Key Lake Mill located 80 km south of McArthur River

Figures 229ndash232 present dose information for the McArthur River operation from 2001 to 2007

Figure 229 Average Dose Trends for the McArthur River Operation (Based o n N on-Zero R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

34

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 230 Average Dose Trends for the McArthur River Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

Figure 231 Collective Dose Trends for the McArthur River Operation

0

200

400

600

800

1000

1200

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Radon gas External Radon progeny Long-lived radioactive dust

Year

35

00

0-000

9

001-5

00

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 232 Distribution o f Effective Doses Among A ll Workers at the McArthur River Operation

0

100

200

300

400

500

600

700

800

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

36

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

224 Key Lake Operation

Cameco Corporation operates mining facilities in Key Lake located in north-central Saskatchewan The Key Lake operation includes two mined-out open pit mines (used for tailings management) a mill and two dry tailings management facilities Mining began in 1983 and ceased in 1997 the mill continued to process ore from the McArthur River mine during the reporting period

Figures 233ndash236 present dose information for the Key Lake operation from 2001 to 2007

Figure 233 Average Dose Trends for the Key Lake Operation (Based o n N on-Zero R esults)

00

20

40

60

80

00

20

40

60

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

37

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

00

20

40

60

80

00

20

40

60

Figure 234 Average Dose Trends for the Key Lake Operation (Based o n A ll Monitoring R esults)

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 235 Collective Dose Trends for the Key Lake Operation

0

100

200

300

400

500

600

700

800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External Radon progeny Long-lived radioactive dust

Year

38

00

0-000

9

001-5

0

501-1

000

gt 1001

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 236 Distribution o f Effective Doses Among A ll Workers at the Key Lake Operation

0

200

400

600

800

1000

1200

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose Range (mSv)

39

se

(mS

v)o

D

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

225 Cigar Lake Operation

Cameco Corporation manages the Cigar Lake underground mine located in northern Saskatchewan at the southern end of Waterbury Lake The mine was under construction at the time of this reportrsquos publication Test mining in ore was carried out in 1991 1992 and 2000

Figures 237ndash240 present dose information for the Cigar Lake operation from

Figure 2 37 Average D ose T rends fo r th e C igar L ake O peration (Based on Non-Zero Results)

2001 to 2007

Year

000

005

010

015

020

025

Long-lived radioactive dust Radon Progeny External Effective

40

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 238 Average Dose Trends for the Cigar Lake Operation (Based on All Monitoring Results)

000

005

010

015

020

025

030

035

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny

External

Effective

Year

Figure 239 Collective Dose Trends for the Cigar Lake Operation

0

50

100

150

200

250

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

External Radon progeny Long-lived radioactive dust

Year

41

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 240 Distribution of Effective Doses Among All Workers at the Cigar Lake Operation

0

200

400

600

800

1000

1200

1400

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

42

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

226 Rabbit Lake Operation

Cameco Corporation owns and operates mining facilities in Rabbit Lake located in north-eastern Saskatchewan Facilities include an underground mine four mined-out open-pit mines a mill and two tailings management facilities Mining and milling began in 1975

Figures 241ndash244 present dose information for the Rabbit Lake operation from 2001 to 2007

Figure 241 Average Dose Trends for the Rabbit Lake Operation (Based on Non-Zero Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

43

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 242 Average Dose Trends for the Rabbit Lake Operation (Based on All Monitoring Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

Figure 243 Collective Dose Trends for the Rabbit Lake Operation

0

200

400

600

800

1000

1200

1400

1600

1800

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Radon gas External Radon progeny Long-lived radioactive dust

Year

44

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

gt300

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 244 Distribution of Effective Doses Among All Workers at the Rabbit Lake Operation

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

900

800

700

600

500

400

300

200

100

0

Dose (mSv)

45

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

23 Uranium Refineries This section presents data for the following two facilities

bull a uranium refining facility in Blind River (Section 231) bull a uranium conversion facility in Port Hope (Section 232)

Graphs indicate the following average doses at each facility from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Note on data for uranium refineries

1 Doses from photons from external sources are measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay and lung counting Historically while these internal doses have been measured they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

231 Blind River Refinery

Cameco Corporation owns and is licensed to operate a uranium refinery in Blind River Ontario The facility which began operating in 1983 converts uranium ore concentrate to uranium trioxide The uranium trioxide is shipped to Camecorsquos uranium conversion facility in Port Hope Ontario where it is processed into uranium dioxide (for use in the fabrication of fuel for nuclear reactors in Canada) or uranium hexafluoride (exported for enrichment and fabrication into fuel for nuclear power reactors around the world)

Figures 245ndash248 present dose information for the Blind River refinery from 2001 to 2007

46

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 245 Average Dose Trends for the Blind River Refinery (Based on Non-Zero Results)

0

05

1

15

2

25

Year

Figure 246 Average Dose Trends for the Blind River Refinery (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

47

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 247 Collective Dose Trends for the Blind River Refinery

0

50

100

150

200

250

300 C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 248 Distribution of Effective Doses Among All Workers at the Blind River Refinery

0

20

40

60

80

100

120

140

160

180

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

48

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

232 Port Hope Conversion Facility

Cameco Corporation owns and is licensed to operate a uranium conversion facility in Port Hope Ontario The facility processes uranium trioxide received from the refinery in Blind River into uranium dioxide and uranium hexafluoride

Figures 249ndash252 present dose information for the Port Hope uranium conversion facility from 2001 to 2007

Figure 249 Average Dose Trends for the Port Hope Conversion Facility (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

49

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 250 Average Dose Trends for the Port Hope Conversion Facility (Based on All Monitoring Results)

0

01

02

03

04

05

06

07

08

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 251 Collective Dose Trends for the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

50

000-0

009

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 252 Distribution of Effective Doses Among All Workers at the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

400

450

500

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

51

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

24 Fuel Fabrication Facilities This section presents data for three nuclear fuel fabrication facilities

bull Two facilities owned and operated by General Electric Canada Inc (Section 241) bull One facility in Port Hope operated by Zircatec Precision Industries (Section 242)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average doses

Notes on data for fuel fabrication facilities

1 Effective doses for the three facilities are composed of the following reported components bull dose from photons (labelled on the charts as ldquoexternalrdquo) bull doses from internal intakes of uranium dust (long-lived radioactive dust) from

uranium in air concentrations (for General Electricrsquos Toronto facility only)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components photon doses and doses from long-lived radioactive dust

241 General Electric Nuclear Fuel Facilities

General Electric Canada Inc operates two nuclear fuel facilities in Ontario

bull At the Toronto facility uranium dioxide pellets are produced from natural or depleted uranium dioxide powder

bull At the Peterborough facility uranium dioxide fuel bundles are created from the pellets produced at the Toronto facility

Figures 253ndash256 present dose information for General Electric Canada Incrsquos fuel fabrication facilities from 2001 to 2007 Graphs do not distinguish between the doses received at the Peterborough facility versus those at the Toronto facility

52

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 253 Average Dose Trends for the General Electric Fuel Facility (Based on Non-Zero Results Only)

0

05

1

15

2

25

3

35

Long Lived Radioactive Dust External Effective

Year

Figure 254 Average Dose Trends for the General Electric Fuel Facility (Based on All Monitoring Results)

0

05

1

15

2

25

3

Long Lived Radioactive Dust External Effective

Year

Dos

e (m

Sv)

Dos

e (m

Sv)

53

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 255 Collective Dose Trends for the General Electric Fuel Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Long Lived Radioactive Dust External

Year

Figure 256 Distribution of Effective Doses among all Workers at the General Electric Fuel Facility

0

10

20

30

40

50

60

70

80

90

100

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

54

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

242 Zircatec Nuclear Fuel Facility

Zircatec Precision Industries Inc operates a nuclear fuel facility in Port Hope Ontario where it makes fuel pellets from uranium dioxide powder received from Port Hopersquos uranium conversion facility The nuclear fuel facility also manufactures fuel bundles for nuclear reactors in Canada

Notes on data for the Zircatec nuclear fuel facility

1 Graphs indicate the following data bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of average effective doses

2 Doses from photons from external sources were measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay Historically although these internal doses have been measured and submitted to the CNSC they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

Figures 257ndash260 present dose information for the Zircatec nuclear fuel facility from 2001 to 2007

Figure 257 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on Non-Zero Results)

0

05

1

15

2

25

3

35

Effe

ctiv

e D

ose

(mS

v)

Year

55

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 258 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

18

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 259 Collective Dose Trends for the Zircatec Nuclear Fuel Facility

0

50

100

150

200

250

300

350

400

450

500

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

56

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 260 Distribution of Effective Doses Among All Workers at the Zircatec Nuclear Fuel Facility

300

Num

ber o

f Wor

kers

250

200

150

100

50

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

57

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

25 Research and Radioisotope Production Facilities This section presents dose information for the following research and radioisotope production facilities from 2001 to 2007

bull Chalk River Laboratories and Whiteshell Laboratories (Section 251) bull A radioisotope production facility operated by MDS Nordion (Section 252) bull The Tri-University Meson Facility (TRIUMF) (Section 253)

Note on data for research and radioisotope production facilities

1 Graphs indicate the following data for each facility bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of effective doses

251 Chalk River Laboratories and Whiteshell Laboratories

Atomic Energy of Canada Limited (AECL) owns and is licensed to operate Chalk River Laboratories and Whiteshell Laboratories

Situated in Renfrew County on the south shore of the Ottawa River the Chalk River Laboratories site hosts the National Research Universal Reactor along with numerous other facilities occupying some 160 buildings in an area of approximately 40 km2 Activities consist of radioisotope production for nuclear medicine testing and development of structural materials in support of power reactor operations fuel fabrication research and radioactive waste management and storage

The Whiteshell Laboratories site is located approximately 10 km west of Pinawa Manitoba and 100 km northeast of Winnipeg on the east bank of the Winnipeg River AECL established the laboratories for nuclear research and testing during the early 1960s and has since discontinued operations which are being decommissioned under a licence from the CNSC

Figures 261ndash264 present dose information for Chalk River Laboratories and Whiteshell Laboratories from 2001 to 2007

Notes on data for Chalk River Laboratories and Whiteshell Laboratories

1 Effective doses are composed of the following reported components bull external doses5 (from both photon and neutron doses) bull tritium doses

Due to issues with AECLrsquos in-house dosimetry management system neutron doses were not reported separately to the NDR during the reporting period As a result external doses from photons and neutrons were totaled The reporting discrepancy has since been rectified

58

5

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of external (photon and neutron) and tritium doses Intakes of other radionuclides occasionally occur and these radionuclides are not included here because their associated doses are very small For this reason certain collective doses in this report may have values slightly lower than the sum of their respective components as listed

Figure 261 Average Dose Trends for Chalk River and Whiteshell Laboratories (Non-Zero Results Only)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Tritium External Effective

Year

59

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 262 Average Dose Trends for Chalk River and Whiteshell Laboratories (All Monitoring Results)

000

020

040

060

080

100

120

Dos

e (m

Sv)

Tritium External Effective

Year

Figure 263 Collective Dose Trends for Chalk River and Whiteshell Laboratories

0

500

1000

1500

2000

2500

3000

3500

Col

lect

ive

Dos

e (p

erso

n- m

Sv)

External Tritium

Year

60

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 264 Distribution of Effective Doses Among All Workers at Chalk River and Whiteshell Laboratories

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

3500

3000

2500

2000

1500

1000

500

Dose (mSv)

61

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

252 MDS Nordion (Nuclear Substance Processing Facility and Canadian Irradiation Centre)

MDS Nordion owns and operates a nuclear substance processing facility in Ottawa Ontario where it processes unsealed radioisotopes and manufactures sealed radiation sources In operation since the early 1970s the facility was purchased by Nordion International in 1991

In cooperation with the Universiteacute du Queacutebecrsquos Institut Armand-Frappier MDS Nordion also operates the Canadian Irradiation Centre which conducts various irradiation services which include training testing and development The centre is located in Laval Quebec on the Universiteacute du Queacutebec campus

Figures 265ndash268 present dose information for MDS Nordionrsquos Ottawa nuclear substance processing facility and for the Canadian Irradiation Centre from 2001 to 2007

Notes on data for MDS Nordionrsquos nuclear substance processing facility and the Canadian Irradiation Centre

1 Doses from photons from external sources were measured and reported to the NDR MDS Nordion also has a routine thyroid monitoring program very occasionally small recordable doses of radiation have occurred from thyroid uptake of iodine The resulting doses have not been historically submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided

Figure 265 Average Dose Trends for MDS Nordion (Based on Non-Zero Results)

0

05

1

15

2

25

Effe

ctiv

e D

ose

(mS

v)

Year

62

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 266 Average Dose Trends for MDS Nordion (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

Figure 267 Collective Dose Trends for MDS Nordion

0

100

200

300

400

500

600

700

800

Year

63

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 268 Distribution of Effective Doses Among All Workers at MDS Nordion

0

5 0

1 0 0

1 5 0

2 0 0

2 5 0

3 0 0

3 5 0

4 0 0

4 5 0

5 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

64

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

253 Tri-University Meson Facility

The Tri-University Meson facility (TRIUMF) is situated in Vancouver on the campus of the University of British Columbia TRIUMF which began operating in the early 1970s with one cyclotron now has two cyclotrons and associated laboratories for research and radioisotope production The laboratory provides research facilities for Canadian and international users and also produces radioisotopes which are used by medical facilities and by a commercial organization (MDS Nordion) MDS Nordion staff also work at the TRIUMF site however MDS Nordion oversees this work and has its own radiation protection program

Figures 269ndash272 present dose information for the TRIUMF facility from 2001 to 2007 Please note that data sets do not distinguish between doses received by TRIUMF staff and MDS Nordion staff who work on the site as the data for these two groups was submitted collectively to the NDR for the reporting period shown Future data for each group will be submitted separately to the NDR

Note on data for TRIUMF

1 Effective doses are composed of the following reported components bull doses from photons (labeled as ldquoexternalrdquo in the charts) bull neutron doses

Figure 269 Average Dose Trends for TRIUMF (Non-Zero Results Only)

000

020

040

060

080

100

120

140

160

Dos

e (m

Sv)

Neutrons External Effective

Year

65

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 32: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

0

1400

1200

1000

800

600

400

200

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 220 Distribution of Effective Doses Among All Workers at Point Lepreau Nuclear Generating Station

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

27

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

22 Uranium Mines and Mills This section presents dose information for mine and mill sites in the following regions

bull Cluff Lake (Section 221) bull McClean Lake (Section 222) bull McArthur River (Section 223) bull Key Lake (Section 224) bull Cigar Lake (Section 225) bull Rabbit Lake (Section 226)

Graphs indicate the following data for each site from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for uranium mines and mills

1 Effective doses are composed of the following reported components bull doses from photons (labelled on the charts as ldquoexternalrdquo) bull doses from radon progeny bull doses from long-lived radioactive dust bull doses from radon gas (in some cases)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of photon radon progeny long-lived radioactive dust and radon gas doses

3 The NDR lists radon progeny in working level months (WLM) For this report radon progeny exposures were converted4 to doses expressed in mSv

221 Cluff Lake Operation

The Cluff Lake mining facilities operated by AREVA Resources Canada Inc are located in northwestern Saskatchewan Work began in 1980 and ended in 2002 with the site now being decommissioned The site consisted of three open-pit and two underground mines a mill and a tailings management facility During 2005 and 2006 most of the infrastructure was removed and the affected areas were remediated

Figures 221ndash224 present dose information for the Cluff Lake operation from 2001 to 2007

4 Doses were converted using the International Commission on Radiation Protection (ICRP)rsquos conversion convention of 1 WLM = 5 mSv This convention was established in the ICRP publication Protection against Radon at Home and at Work (ICRP 65)

28

Long-lived radioactive dust Radon progeny External Effective

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 221 Average Dose Trends for the Cluff Lake Operation (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

Year

Figure 222 Average Dose Trends for the Cluff Lake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

200

Long-lived radioactive dust Radon progeny External Effective

)S

v(m

e os

D)

Sv

(me

osD

Year

29

600

500

400

300

200

100

0

External Radon progeny Long-lived radioactive dust

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 223 Collective Dose Trends for the Cluff Lake Operation s

erkor

of W

ber

Num

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Year

Figure 224 Distribution o f Effective Doses Among A ll Workers at the Cluff Lake Operation

0

20

40

60

80

100

120

140

160

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

30

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

222 McClean Lake Operation

AREVA Resources Canada Inc runs the McClean Lake mining operation in northeastern Saskatchewan It comprises open pit mines a mill and a tailings management facility Mining began in 1995 while milling started in 1999

Figures 225ndash228 present dose information for the McClean Lake operation from 2001 to 2007

Figure 225 Average Dose Trends for the McClean L ake Operation (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

31

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 226 Average Dose Trends for the McClean L ake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 227 Collective Dose Trends for the McClean L ake Operation

0

100

200

300

400

500

600

700

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External

Radon progeny

Long-lived radioactive dust

Year

32

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 228 Distribution o f Effective Doses Among A ll Workers at the McClean Lake Operation

0

100

200

300

400

500

600

700

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

33

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

223 McArthur River Operation

Cameco Corporation operates the McArthur River underground mine in north-central Saskatchewan Ore from the mine which began production in 1999 is processed at the Key Lake Mill located 80 km south of McArthur River

Figures 229ndash232 present dose information for the McArthur River operation from 2001 to 2007

Figure 229 Average Dose Trends for the McArthur River Operation (Based o n N on-Zero R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

34

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 230 Average Dose Trends for the McArthur River Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

Figure 231 Collective Dose Trends for the McArthur River Operation

0

200

400

600

800

1000

1200

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Radon gas External Radon progeny Long-lived radioactive dust

Year

35

00

0-000

9

001-5

00

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 232 Distribution o f Effective Doses Among A ll Workers at the McArthur River Operation

0

100

200

300

400

500

600

700

800

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

36

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

224 Key Lake Operation

Cameco Corporation operates mining facilities in Key Lake located in north-central Saskatchewan The Key Lake operation includes two mined-out open pit mines (used for tailings management) a mill and two dry tailings management facilities Mining began in 1983 and ceased in 1997 the mill continued to process ore from the McArthur River mine during the reporting period

Figures 233ndash236 present dose information for the Key Lake operation from 2001 to 2007

Figure 233 Average Dose Trends for the Key Lake Operation (Based o n N on-Zero R esults)

00

20

40

60

80

00

20

40

60

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

37

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

00

20

40

60

80

00

20

40

60

Figure 234 Average Dose Trends for the Key Lake Operation (Based o n A ll Monitoring R esults)

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 235 Collective Dose Trends for the Key Lake Operation

0

100

200

300

400

500

600

700

800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External Radon progeny Long-lived radioactive dust

Year

38

00

0-000

9

001-5

0

501-1

000

gt 1001

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 236 Distribution o f Effective Doses Among A ll Workers at the Key Lake Operation

0

200

400

600

800

1000

1200

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose Range (mSv)

39

se

(mS

v)o

D

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

225 Cigar Lake Operation

Cameco Corporation manages the Cigar Lake underground mine located in northern Saskatchewan at the southern end of Waterbury Lake The mine was under construction at the time of this reportrsquos publication Test mining in ore was carried out in 1991 1992 and 2000

Figures 237ndash240 present dose information for the Cigar Lake operation from

Figure 2 37 Average D ose T rends fo r th e C igar L ake O peration (Based on Non-Zero Results)

2001 to 2007

Year

000

005

010

015

020

025

Long-lived radioactive dust Radon Progeny External Effective

40

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 238 Average Dose Trends for the Cigar Lake Operation (Based on All Monitoring Results)

000

005

010

015

020

025

030

035

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny

External

Effective

Year

Figure 239 Collective Dose Trends for the Cigar Lake Operation

0

50

100

150

200

250

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

External Radon progeny Long-lived radioactive dust

Year

41

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 240 Distribution of Effective Doses Among All Workers at the Cigar Lake Operation

0

200

400

600

800

1000

1200

1400

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

42

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

226 Rabbit Lake Operation

Cameco Corporation owns and operates mining facilities in Rabbit Lake located in north-eastern Saskatchewan Facilities include an underground mine four mined-out open-pit mines a mill and two tailings management facilities Mining and milling began in 1975

Figures 241ndash244 present dose information for the Rabbit Lake operation from 2001 to 2007

Figure 241 Average Dose Trends for the Rabbit Lake Operation (Based on Non-Zero Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

43

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 242 Average Dose Trends for the Rabbit Lake Operation (Based on All Monitoring Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

Figure 243 Collective Dose Trends for the Rabbit Lake Operation

0

200

400

600

800

1000

1200

1400

1600

1800

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Radon gas External Radon progeny Long-lived radioactive dust

Year

44

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

gt300

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 244 Distribution of Effective Doses Among All Workers at the Rabbit Lake Operation

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

900

800

700

600

500

400

300

200

100

0

Dose (mSv)

45

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

23 Uranium Refineries This section presents data for the following two facilities

bull a uranium refining facility in Blind River (Section 231) bull a uranium conversion facility in Port Hope (Section 232)

Graphs indicate the following average doses at each facility from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Note on data for uranium refineries

1 Doses from photons from external sources are measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay and lung counting Historically while these internal doses have been measured they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

231 Blind River Refinery

Cameco Corporation owns and is licensed to operate a uranium refinery in Blind River Ontario The facility which began operating in 1983 converts uranium ore concentrate to uranium trioxide The uranium trioxide is shipped to Camecorsquos uranium conversion facility in Port Hope Ontario where it is processed into uranium dioxide (for use in the fabrication of fuel for nuclear reactors in Canada) or uranium hexafluoride (exported for enrichment and fabrication into fuel for nuclear power reactors around the world)

Figures 245ndash248 present dose information for the Blind River refinery from 2001 to 2007

46

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 245 Average Dose Trends for the Blind River Refinery (Based on Non-Zero Results)

0

05

1

15

2

25

Year

Figure 246 Average Dose Trends for the Blind River Refinery (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

47

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 247 Collective Dose Trends for the Blind River Refinery

0

50

100

150

200

250

300 C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 248 Distribution of Effective Doses Among All Workers at the Blind River Refinery

0

20

40

60

80

100

120

140

160

180

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

48

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

232 Port Hope Conversion Facility

Cameco Corporation owns and is licensed to operate a uranium conversion facility in Port Hope Ontario The facility processes uranium trioxide received from the refinery in Blind River into uranium dioxide and uranium hexafluoride

Figures 249ndash252 present dose information for the Port Hope uranium conversion facility from 2001 to 2007

Figure 249 Average Dose Trends for the Port Hope Conversion Facility (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

49

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 250 Average Dose Trends for the Port Hope Conversion Facility (Based on All Monitoring Results)

0

01

02

03

04

05

06

07

08

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 251 Collective Dose Trends for the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

50

000-0

009

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 252 Distribution of Effective Doses Among All Workers at the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

400

450

500

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

51

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

24 Fuel Fabrication Facilities This section presents data for three nuclear fuel fabrication facilities

bull Two facilities owned and operated by General Electric Canada Inc (Section 241) bull One facility in Port Hope operated by Zircatec Precision Industries (Section 242)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average doses

Notes on data for fuel fabrication facilities

1 Effective doses for the three facilities are composed of the following reported components bull dose from photons (labelled on the charts as ldquoexternalrdquo) bull doses from internal intakes of uranium dust (long-lived radioactive dust) from

uranium in air concentrations (for General Electricrsquos Toronto facility only)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components photon doses and doses from long-lived radioactive dust

241 General Electric Nuclear Fuel Facilities

General Electric Canada Inc operates two nuclear fuel facilities in Ontario

bull At the Toronto facility uranium dioxide pellets are produced from natural or depleted uranium dioxide powder

bull At the Peterborough facility uranium dioxide fuel bundles are created from the pellets produced at the Toronto facility

Figures 253ndash256 present dose information for General Electric Canada Incrsquos fuel fabrication facilities from 2001 to 2007 Graphs do not distinguish between the doses received at the Peterborough facility versus those at the Toronto facility

52

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 253 Average Dose Trends for the General Electric Fuel Facility (Based on Non-Zero Results Only)

0

05

1

15

2

25

3

35

Long Lived Radioactive Dust External Effective

Year

Figure 254 Average Dose Trends for the General Electric Fuel Facility (Based on All Monitoring Results)

0

05

1

15

2

25

3

Long Lived Radioactive Dust External Effective

Year

Dos

e (m

Sv)

Dos

e (m

Sv)

53

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 255 Collective Dose Trends for the General Electric Fuel Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Long Lived Radioactive Dust External

Year

Figure 256 Distribution of Effective Doses among all Workers at the General Electric Fuel Facility

0

10

20

30

40

50

60

70

80

90

100

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

54

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

242 Zircatec Nuclear Fuel Facility

Zircatec Precision Industries Inc operates a nuclear fuel facility in Port Hope Ontario where it makes fuel pellets from uranium dioxide powder received from Port Hopersquos uranium conversion facility The nuclear fuel facility also manufactures fuel bundles for nuclear reactors in Canada

Notes on data for the Zircatec nuclear fuel facility

1 Graphs indicate the following data bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of average effective doses

2 Doses from photons from external sources were measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay Historically although these internal doses have been measured and submitted to the CNSC they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

Figures 257ndash260 present dose information for the Zircatec nuclear fuel facility from 2001 to 2007

Figure 257 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on Non-Zero Results)

0

05

1

15

2

25

3

35

Effe

ctiv

e D

ose

(mS

v)

Year

55

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 258 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

18

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 259 Collective Dose Trends for the Zircatec Nuclear Fuel Facility

0

50

100

150

200

250

300

350

400

450

500

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

56

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 260 Distribution of Effective Doses Among All Workers at the Zircatec Nuclear Fuel Facility

300

Num

ber o

f Wor

kers

250

200

150

100

50

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

57

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

25 Research and Radioisotope Production Facilities This section presents dose information for the following research and radioisotope production facilities from 2001 to 2007

bull Chalk River Laboratories and Whiteshell Laboratories (Section 251) bull A radioisotope production facility operated by MDS Nordion (Section 252) bull The Tri-University Meson Facility (TRIUMF) (Section 253)

Note on data for research and radioisotope production facilities

1 Graphs indicate the following data for each facility bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of effective doses

251 Chalk River Laboratories and Whiteshell Laboratories

Atomic Energy of Canada Limited (AECL) owns and is licensed to operate Chalk River Laboratories and Whiteshell Laboratories

Situated in Renfrew County on the south shore of the Ottawa River the Chalk River Laboratories site hosts the National Research Universal Reactor along with numerous other facilities occupying some 160 buildings in an area of approximately 40 km2 Activities consist of radioisotope production for nuclear medicine testing and development of structural materials in support of power reactor operations fuel fabrication research and radioactive waste management and storage

The Whiteshell Laboratories site is located approximately 10 km west of Pinawa Manitoba and 100 km northeast of Winnipeg on the east bank of the Winnipeg River AECL established the laboratories for nuclear research and testing during the early 1960s and has since discontinued operations which are being decommissioned under a licence from the CNSC

Figures 261ndash264 present dose information for Chalk River Laboratories and Whiteshell Laboratories from 2001 to 2007

Notes on data for Chalk River Laboratories and Whiteshell Laboratories

1 Effective doses are composed of the following reported components bull external doses5 (from both photon and neutron doses) bull tritium doses

Due to issues with AECLrsquos in-house dosimetry management system neutron doses were not reported separately to the NDR during the reporting period As a result external doses from photons and neutrons were totaled The reporting discrepancy has since been rectified

58

5

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of external (photon and neutron) and tritium doses Intakes of other radionuclides occasionally occur and these radionuclides are not included here because their associated doses are very small For this reason certain collective doses in this report may have values slightly lower than the sum of their respective components as listed

Figure 261 Average Dose Trends for Chalk River and Whiteshell Laboratories (Non-Zero Results Only)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Tritium External Effective

Year

59

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 262 Average Dose Trends for Chalk River and Whiteshell Laboratories (All Monitoring Results)

000

020

040

060

080

100

120

Dos

e (m

Sv)

Tritium External Effective

Year

Figure 263 Collective Dose Trends for Chalk River and Whiteshell Laboratories

0

500

1000

1500

2000

2500

3000

3500

Col

lect

ive

Dos

e (p

erso

n- m

Sv)

External Tritium

Year

60

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 264 Distribution of Effective Doses Among All Workers at Chalk River and Whiteshell Laboratories

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

3500

3000

2500

2000

1500

1000

500

Dose (mSv)

61

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

252 MDS Nordion (Nuclear Substance Processing Facility and Canadian Irradiation Centre)

MDS Nordion owns and operates a nuclear substance processing facility in Ottawa Ontario where it processes unsealed radioisotopes and manufactures sealed radiation sources In operation since the early 1970s the facility was purchased by Nordion International in 1991

In cooperation with the Universiteacute du Queacutebecrsquos Institut Armand-Frappier MDS Nordion also operates the Canadian Irradiation Centre which conducts various irradiation services which include training testing and development The centre is located in Laval Quebec on the Universiteacute du Queacutebec campus

Figures 265ndash268 present dose information for MDS Nordionrsquos Ottawa nuclear substance processing facility and for the Canadian Irradiation Centre from 2001 to 2007

Notes on data for MDS Nordionrsquos nuclear substance processing facility and the Canadian Irradiation Centre

1 Doses from photons from external sources were measured and reported to the NDR MDS Nordion also has a routine thyroid monitoring program very occasionally small recordable doses of radiation have occurred from thyroid uptake of iodine The resulting doses have not been historically submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided

Figure 265 Average Dose Trends for MDS Nordion (Based on Non-Zero Results)

0

05

1

15

2

25

Effe

ctiv

e D

ose

(mS

v)

Year

62

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 266 Average Dose Trends for MDS Nordion (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

Figure 267 Collective Dose Trends for MDS Nordion

0

100

200

300

400

500

600

700

800

Year

63

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 268 Distribution of Effective Doses Among All Workers at MDS Nordion

0

5 0

1 0 0

1 5 0

2 0 0

2 5 0

3 0 0

3 5 0

4 0 0

4 5 0

5 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

64

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

253 Tri-University Meson Facility

The Tri-University Meson facility (TRIUMF) is situated in Vancouver on the campus of the University of British Columbia TRIUMF which began operating in the early 1970s with one cyclotron now has two cyclotrons and associated laboratories for research and radioisotope production The laboratory provides research facilities for Canadian and international users and also produces radioisotopes which are used by medical facilities and by a commercial organization (MDS Nordion) MDS Nordion staff also work at the TRIUMF site however MDS Nordion oversees this work and has its own radiation protection program

Figures 269ndash272 present dose information for the TRIUMF facility from 2001 to 2007 Please note that data sets do not distinguish between doses received by TRIUMF staff and MDS Nordion staff who work on the site as the data for these two groups was submitted collectively to the NDR for the reporting period shown Future data for each group will be submitted separately to the NDR

Note on data for TRIUMF

1 Effective doses are composed of the following reported components bull doses from photons (labeled as ldquoexternalrdquo in the charts) bull neutron doses

Figure 269 Average Dose Trends for TRIUMF (Non-Zero Results Only)

000

020

040

060

080

100

120

140

160

Dos

e (m

Sv)

Neutrons External Effective

Year

65

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 33: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

22 Uranium Mines and Mills This section presents dose information for mine and mill sites in the following regions

bull Cluff Lake (Section 221) bull McClean Lake (Section 222) bull McArthur River (Section 223) bull Key Lake (Section 224) bull Cigar Lake (Section 225) bull Rabbit Lake (Section 226)

Graphs indicate the following data for each site from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for uranium mines and mills

1 Effective doses are composed of the following reported components bull doses from photons (labelled on the charts as ldquoexternalrdquo) bull doses from radon progeny bull doses from long-lived radioactive dust bull doses from radon gas (in some cases)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of photon radon progeny long-lived radioactive dust and radon gas doses

3 The NDR lists radon progeny in working level months (WLM) For this report radon progeny exposures were converted4 to doses expressed in mSv

221 Cluff Lake Operation

The Cluff Lake mining facilities operated by AREVA Resources Canada Inc are located in northwestern Saskatchewan Work began in 1980 and ended in 2002 with the site now being decommissioned The site consisted of three open-pit and two underground mines a mill and a tailings management facility During 2005 and 2006 most of the infrastructure was removed and the affected areas were remediated

Figures 221ndash224 present dose information for the Cluff Lake operation from 2001 to 2007

4 Doses were converted using the International Commission on Radiation Protection (ICRP)rsquos conversion convention of 1 WLM = 5 mSv This convention was established in the ICRP publication Protection against Radon at Home and at Work (ICRP 65)

28

Long-lived radioactive dust Radon progeny External Effective

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 221 Average Dose Trends for the Cluff Lake Operation (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

Year

Figure 222 Average Dose Trends for the Cluff Lake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

200

Long-lived radioactive dust Radon progeny External Effective

)S

v(m

e os

D)

Sv

(me

osD

Year

29

600

500

400

300

200

100

0

External Radon progeny Long-lived radioactive dust

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 223 Collective Dose Trends for the Cluff Lake Operation s

erkor

of W

ber

Num

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Year

Figure 224 Distribution o f Effective Doses Among A ll Workers at the Cluff Lake Operation

0

20

40

60

80

100

120

140

160

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

30

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

222 McClean Lake Operation

AREVA Resources Canada Inc runs the McClean Lake mining operation in northeastern Saskatchewan It comprises open pit mines a mill and a tailings management facility Mining began in 1995 while milling started in 1999

Figures 225ndash228 present dose information for the McClean Lake operation from 2001 to 2007

Figure 225 Average Dose Trends for the McClean L ake Operation (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

31

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 226 Average Dose Trends for the McClean L ake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 227 Collective Dose Trends for the McClean L ake Operation

0

100

200

300

400

500

600

700

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External

Radon progeny

Long-lived radioactive dust

Year

32

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 228 Distribution o f Effective Doses Among A ll Workers at the McClean Lake Operation

0

100

200

300

400

500

600

700

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

33

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

223 McArthur River Operation

Cameco Corporation operates the McArthur River underground mine in north-central Saskatchewan Ore from the mine which began production in 1999 is processed at the Key Lake Mill located 80 km south of McArthur River

Figures 229ndash232 present dose information for the McArthur River operation from 2001 to 2007

Figure 229 Average Dose Trends for the McArthur River Operation (Based o n N on-Zero R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

34

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 230 Average Dose Trends for the McArthur River Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

Figure 231 Collective Dose Trends for the McArthur River Operation

0

200

400

600

800

1000

1200

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Radon gas External Radon progeny Long-lived radioactive dust

Year

35

00

0-000

9

001-5

00

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 232 Distribution o f Effective Doses Among A ll Workers at the McArthur River Operation

0

100

200

300

400

500

600

700

800

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

36

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

224 Key Lake Operation

Cameco Corporation operates mining facilities in Key Lake located in north-central Saskatchewan The Key Lake operation includes two mined-out open pit mines (used for tailings management) a mill and two dry tailings management facilities Mining began in 1983 and ceased in 1997 the mill continued to process ore from the McArthur River mine during the reporting period

Figures 233ndash236 present dose information for the Key Lake operation from 2001 to 2007

Figure 233 Average Dose Trends for the Key Lake Operation (Based o n N on-Zero R esults)

00

20

40

60

80

00

20

40

60

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

37

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

00

20

40

60

80

00

20

40

60

Figure 234 Average Dose Trends for the Key Lake Operation (Based o n A ll Monitoring R esults)

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 235 Collective Dose Trends for the Key Lake Operation

0

100

200

300

400

500

600

700

800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External Radon progeny Long-lived radioactive dust

Year

38

00

0-000

9

001-5

0

501-1

000

gt 1001

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 236 Distribution o f Effective Doses Among A ll Workers at the Key Lake Operation

0

200

400

600

800

1000

1200

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose Range (mSv)

39

se

(mS

v)o

D

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

225 Cigar Lake Operation

Cameco Corporation manages the Cigar Lake underground mine located in northern Saskatchewan at the southern end of Waterbury Lake The mine was under construction at the time of this reportrsquos publication Test mining in ore was carried out in 1991 1992 and 2000

Figures 237ndash240 present dose information for the Cigar Lake operation from

Figure 2 37 Average D ose T rends fo r th e C igar L ake O peration (Based on Non-Zero Results)

2001 to 2007

Year

000

005

010

015

020

025

Long-lived radioactive dust Radon Progeny External Effective

40

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 238 Average Dose Trends for the Cigar Lake Operation (Based on All Monitoring Results)

000

005

010

015

020

025

030

035

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny

External

Effective

Year

Figure 239 Collective Dose Trends for the Cigar Lake Operation

0

50

100

150

200

250

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

External Radon progeny Long-lived radioactive dust

Year

41

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 240 Distribution of Effective Doses Among All Workers at the Cigar Lake Operation

0

200

400

600

800

1000

1200

1400

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

42

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

226 Rabbit Lake Operation

Cameco Corporation owns and operates mining facilities in Rabbit Lake located in north-eastern Saskatchewan Facilities include an underground mine four mined-out open-pit mines a mill and two tailings management facilities Mining and milling began in 1975

Figures 241ndash244 present dose information for the Rabbit Lake operation from 2001 to 2007

Figure 241 Average Dose Trends for the Rabbit Lake Operation (Based on Non-Zero Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

43

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 242 Average Dose Trends for the Rabbit Lake Operation (Based on All Monitoring Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

Figure 243 Collective Dose Trends for the Rabbit Lake Operation

0

200

400

600

800

1000

1200

1400

1600

1800

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Radon gas External Radon progeny Long-lived radioactive dust

Year

44

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

gt300

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 244 Distribution of Effective Doses Among All Workers at the Rabbit Lake Operation

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

900

800

700

600

500

400

300

200

100

0

Dose (mSv)

45

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

23 Uranium Refineries This section presents data for the following two facilities

bull a uranium refining facility in Blind River (Section 231) bull a uranium conversion facility in Port Hope (Section 232)

Graphs indicate the following average doses at each facility from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Note on data for uranium refineries

1 Doses from photons from external sources are measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay and lung counting Historically while these internal doses have been measured they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

231 Blind River Refinery

Cameco Corporation owns and is licensed to operate a uranium refinery in Blind River Ontario The facility which began operating in 1983 converts uranium ore concentrate to uranium trioxide The uranium trioxide is shipped to Camecorsquos uranium conversion facility in Port Hope Ontario where it is processed into uranium dioxide (for use in the fabrication of fuel for nuclear reactors in Canada) or uranium hexafluoride (exported for enrichment and fabrication into fuel for nuclear power reactors around the world)

Figures 245ndash248 present dose information for the Blind River refinery from 2001 to 2007

46

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 245 Average Dose Trends for the Blind River Refinery (Based on Non-Zero Results)

0

05

1

15

2

25

Year

Figure 246 Average Dose Trends for the Blind River Refinery (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

47

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 247 Collective Dose Trends for the Blind River Refinery

0

50

100

150

200

250

300 C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 248 Distribution of Effective Doses Among All Workers at the Blind River Refinery

0

20

40

60

80

100

120

140

160

180

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

48

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

232 Port Hope Conversion Facility

Cameco Corporation owns and is licensed to operate a uranium conversion facility in Port Hope Ontario The facility processes uranium trioxide received from the refinery in Blind River into uranium dioxide and uranium hexafluoride

Figures 249ndash252 present dose information for the Port Hope uranium conversion facility from 2001 to 2007

Figure 249 Average Dose Trends for the Port Hope Conversion Facility (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

49

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 250 Average Dose Trends for the Port Hope Conversion Facility (Based on All Monitoring Results)

0

01

02

03

04

05

06

07

08

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 251 Collective Dose Trends for the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

50

000-0

009

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 252 Distribution of Effective Doses Among All Workers at the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

400

450

500

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

51

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

24 Fuel Fabrication Facilities This section presents data for three nuclear fuel fabrication facilities

bull Two facilities owned and operated by General Electric Canada Inc (Section 241) bull One facility in Port Hope operated by Zircatec Precision Industries (Section 242)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average doses

Notes on data for fuel fabrication facilities

1 Effective doses for the three facilities are composed of the following reported components bull dose from photons (labelled on the charts as ldquoexternalrdquo) bull doses from internal intakes of uranium dust (long-lived radioactive dust) from

uranium in air concentrations (for General Electricrsquos Toronto facility only)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components photon doses and doses from long-lived radioactive dust

241 General Electric Nuclear Fuel Facilities

General Electric Canada Inc operates two nuclear fuel facilities in Ontario

bull At the Toronto facility uranium dioxide pellets are produced from natural or depleted uranium dioxide powder

bull At the Peterborough facility uranium dioxide fuel bundles are created from the pellets produced at the Toronto facility

Figures 253ndash256 present dose information for General Electric Canada Incrsquos fuel fabrication facilities from 2001 to 2007 Graphs do not distinguish between the doses received at the Peterborough facility versus those at the Toronto facility

52

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 253 Average Dose Trends for the General Electric Fuel Facility (Based on Non-Zero Results Only)

0

05

1

15

2

25

3

35

Long Lived Radioactive Dust External Effective

Year

Figure 254 Average Dose Trends for the General Electric Fuel Facility (Based on All Monitoring Results)

0

05

1

15

2

25

3

Long Lived Radioactive Dust External Effective

Year

Dos

e (m

Sv)

Dos

e (m

Sv)

53

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 255 Collective Dose Trends for the General Electric Fuel Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Long Lived Radioactive Dust External

Year

Figure 256 Distribution of Effective Doses among all Workers at the General Electric Fuel Facility

0

10

20

30

40

50

60

70

80

90

100

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

54

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

242 Zircatec Nuclear Fuel Facility

Zircatec Precision Industries Inc operates a nuclear fuel facility in Port Hope Ontario where it makes fuel pellets from uranium dioxide powder received from Port Hopersquos uranium conversion facility The nuclear fuel facility also manufactures fuel bundles for nuclear reactors in Canada

Notes on data for the Zircatec nuclear fuel facility

1 Graphs indicate the following data bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of average effective doses

2 Doses from photons from external sources were measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay Historically although these internal doses have been measured and submitted to the CNSC they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

Figures 257ndash260 present dose information for the Zircatec nuclear fuel facility from 2001 to 2007

Figure 257 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on Non-Zero Results)

0

05

1

15

2

25

3

35

Effe

ctiv

e D

ose

(mS

v)

Year

55

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 258 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

18

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 259 Collective Dose Trends for the Zircatec Nuclear Fuel Facility

0

50

100

150

200

250

300

350

400

450

500

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

56

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 260 Distribution of Effective Doses Among All Workers at the Zircatec Nuclear Fuel Facility

300

Num

ber o

f Wor

kers

250

200

150

100

50

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

57

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

25 Research and Radioisotope Production Facilities This section presents dose information for the following research and radioisotope production facilities from 2001 to 2007

bull Chalk River Laboratories and Whiteshell Laboratories (Section 251) bull A radioisotope production facility operated by MDS Nordion (Section 252) bull The Tri-University Meson Facility (TRIUMF) (Section 253)

Note on data for research and radioisotope production facilities

1 Graphs indicate the following data for each facility bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of effective doses

251 Chalk River Laboratories and Whiteshell Laboratories

Atomic Energy of Canada Limited (AECL) owns and is licensed to operate Chalk River Laboratories and Whiteshell Laboratories

Situated in Renfrew County on the south shore of the Ottawa River the Chalk River Laboratories site hosts the National Research Universal Reactor along with numerous other facilities occupying some 160 buildings in an area of approximately 40 km2 Activities consist of radioisotope production for nuclear medicine testing and development of structural materials in support of power reactor operations fuel fabrication research and radioactive waste management and storage

The Whiteshell Laboratories site is located approximately 10 km west of Pinawa Manitoba and 100 km northeast of Winnipeg on the east bank of the Winnipeg River AECL established the laboratories for nuclear research and testing during the early 1960s and has since discontinued operations which are being decommissioned under a licence from the CNSC

Figures 261ndash264 present dose information for Chalk River Laboratories and Whiteshell Laboratories from 2001 to 2007

Notes on data for Chalk River Laboratories and Whiteshell Laboratories

1 Effective doses are composed of the following reported components bull external doses5 (from both photon and neutron doses) bull tritium doses

Due to issues with AECLrsquos in-house dosimetry management system neutron doses were not reported separately to the NDR during the reporting period As a result external doses from photons and neutrons were totaled The reporting discrepancy has since been rectified

58

5

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of external (photon and neutron) and tritium doses Intakes of other radionuclides occasionally occur and these radionuclides are not included here because their associated doses are very small For this reason certain collective doses in this report may have values slightly lower than the sum of their respective components as listed

Figure 261 Average Dose Trends for Chalk River and Whiteshell Laboratories (Non-Zero Results Only)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Tritium External Effective

Year

59

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 262 Average Dose Trends for Chalk River and Whiteshell Laboratories (All Monitoring Results)

000

020

040

060

080

100

120

Dos

e (m

Sv)

Tritium External Effective

Year

Figure 263 Collective Dose Trends for Chalk River and Whiteshell Laboratories

0

500

1000

1500

2000

2500

3000

3500

Col

lect

ive

Dos

e (p

erso

n- m

Sv)

External Tritium

Year

60

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 264 Distribution of Effective Doses Among All Workers at Chalk River and Whiteshell Laboratories

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

3500

3000

2500

2000

1500

1000

500

Dose (mSv)

61

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

252 MDS Nordion (Nuclear Substance Processing Facility and Canadian Irradiation Centre)

MDS Nordion owns and operates a nuclear substance processing facility in Ottawa Ontario where it processes unsealed radioisotopes and manufactures sealed radiation sources In operation since the early 1970s the facility was purchased by Nordion International in 1991

In cooperation with the Universiteacute du Queacutebecrsquos Institut Armand-Frappier MDS Nordion also operates the Canadian Irradiation Centre which conducts various irradiation services which include training testing and development The centre is located in Laval Quebec on the Universiteacute du Queacutebec campus

Figures 265ndash268 present dose information for MDS Nordionrsquos Ottawa nuclear substance processing facility and for the Canadian Irradiation Centre from 2001 to 2007

Notes on data for MDS Nordionrsquos nuclear substance processing facility and the Canadian Irradiation Centre

1 Doses from photons from external sources were measured and reported to the NDR MDS Nordion also has a routine thyroid monitoring program very occasionally small recordable doses of radiation have occurred from thyroid uptake of iodine The resulting doses have not been historically submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided

Figure 265 Average Dose Trends for MDS Nordion (Based on Non-Zero Results)

0

05

1

15

2

25

Effe

ctiv

e D

ose

(mS

v)

Year

62

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 266 Average Dose Trends for MDS Nordion (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

Figure 267 Collective Dose Trends for MDS Nordion

0

100

200

300

400

500

600

700

800

Year

63

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 268 Distribution of Effective Doses Among All Workers at MDS Nordion

0

5 0

1 0 0

1 5 0

2 0 0

2 5 0

3 0 0

3 5 0

4 0 0

4 5 0

5 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

64

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

253 Tri-University Meson Facility

The Tri-University Meson facility (TRIUMF) is situated in Vancouver on the campus of the University of British Columbia TRIUMF which began operating in the early 1970s with one cyclotron now has two cyclotrons and associated laboratories for research and radioisotope production The laboratory provides research facilities for Canadian and international users and also produces radioisotopes which are used by medical facilities and by a commercial organization (MDS Nordion) MDS Nordion staff also work at the TRIUMF site however MDS Nordion oversees this work and has its own radiation protection program

Figures 269ndash272 present dose information for the TRIUMF facility from 2001 to 2007 Please note that data sets do not distinguish between doses received by TRIUMF staff and MDS Nordion staff who work on the site as the data for these two groups was submitted collectively to the NDR for the reporting period shown Future data for each group will be submitted separately to the NDR

Note on data for TRIUMF

1 Effective doses are composed of the following reported components bull doses from photons (labeled as ldquoexternalrdquo in the charts) bull neutron doses

Figure 269 Average Dose Trends for TRIUMF (Non-Zero Results Only)

000

020

040

060

080

100

120

140

160

Dos

e (m

Sv)

Neutrons External Effective

Year

65

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 34: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

Long-lived radioactive dust Radon progeny External Effective

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 221 Average Dose Trends for the Cluff Lake Operation (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

Year

Figure 222 Average Dose Trends for the Cluff Lake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

200

Long-lived radioactive dust Radon progeny External Effective

)S

v(m

e os

D)

Sv

(me

osD

Year

29

600

500

400

300

200

100

0

External Radon progeny Long-lived radioactive dust

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 223 Collective Dose Trends for the Cluff Lake Operation s

erkor

of W

ber

Num

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Year

Figure 224 Distribution o f Effective Doses Among A ll Workers at the Cluff Lake Operation

0

20

40

60

80

100

120

140

160

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

30

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

222 McClean Lake Operation

AREVA Resources Canada Inc runs the McClean Lake mining operation in northeastern Saskatchewan It comprises open pit mines a mill and a tailings management facility Mining began in 1995 while milling started in 1999

Figures 225ndash228 present dose information for the McClean Lake operation from 2001 to 2007

Figure 225 Average Dose Trends for the McClean L ake Operation (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

31

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 226 Average Dose Trends for the McClean L ake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 227 Collective Dose Trends for the McClean L ake Operation

0

100

200

300

400

500

600

700

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External

Radon progeny

Long-lived radioactive dust

Year

32

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 228 Distribution o f Effective Doses Among A ll Workers at the McClean Lake Operation

0

100

200

300

400

500

600

700

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

33

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

223 McArthur River Operation

Cameco Corporation operates the McArthur River underground mine in north-central Saskatchewan Ore from the mine which began production in 1999 is processed at the Key Lake Mill located 80 km south of McArthur River

Figures 229ndash232 present dose information for the McArthur River operation from 2001 to 2007

Figure 229 Average Dose Trends for the McArthur River Operation (Based o n N on-Zero R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

34

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 230 Average Dose Trends for the McArthur River Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

Figure 231 Collective Dose Trends for the McArthur River Operation

0

200

400

600

800

1000

1200

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Radon gas External Radon progeny Long-lived radioactive dust

Year

35

00

0-000

9

001-5

00

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 232 Distribution o f Effective Doses Among A ll Workers at the McArthur River Operation

0

100

200

300

400

500

600

700

800

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

36

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

224 Key Lake Operation

Cameco Corporation operates mining facilities in Key Lake located in north-central Saskatchewan The Key Lake operation includes two mined-out open pit mines (used for tailings management) a mill and two dry tailings management facilities Mining began in 1983 and ceased in 1997 the mill continued to process ore from the McArthur River mine during the reporting period

Figures 233ndash236 present dose information for the Key Lake operation from 2001 to 2007

Figure 233 Average Dose Trends for the Key Lake Operation (Based o n N on-Zero R esults)

00

20

40

60

80

00

20

40

60

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

37

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

00

20

40

60

80

00

20

40

60

Figure 234 Average Dose Trends for the Key Lake Operation (Based o n A ll Monitoring R esults)

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 235 Collective Dose Trends for the Key Lake Operation

0

100

200

300

400

500

600

700

800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External Radon progeny Long-lived radioactive dust

Year

38

00

0-000

9

001-5

0

501-1

000

gt 1001

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 236 Distribution o f Effective Doses Among A ll Workers at the Key Lake Operation

0

200

400

600

800

1000

1200

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose Range (mSv)

39

se

(mS

v)o

D

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

225 Cigar Lake Operation

Cameco Corporation manages the Cigar Lake underground mine located in northern Saskatchewan at the southern end of Waterbury Lake The mine was under construction at the time of this reportrsquos publication Test mining in ore was carried out in 1991 1992 and 2000

Figures 237ndash240 present dose information for the Cigar Lake operation from

Figure 2 37 Average D ose T rends fo r th e C igar L ake O peration (Based on Non-Zero Results)

2001 to 2007

Year

000

005

010

015

020

025

Long-lived radioactive dust Radon Progeny External Effective

40

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 238 Average Dose Trends for the Cigar Lake Operation (Based on All Monitoring Results)

000

005

010

015

020

025

030

035

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny

External

Effective

Year

Figure 239 Collective Dose Trends for the Cigar Lake Operation

0

50

100

150

200

250

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

External Radon progeny Long-lived radioactive dust

Year

41

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 240 Distribution of Effective Doses Among All Workers at the Cigar Lake Operation

0

200

400

600

800

1000

1200

1400

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

42

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

226 Rabbit Lake Operation

Cameco Corporation owns and operates mining facilities in Rabbit Lake located in north-eastern Saskatchewan Facilities include an underground mine four mined-out open-pit mines a mill and two tailings management facilities Mining and milling began in 1975

Figures 241ndash244 present dose information for the Rabbit Lake operation from 2001 to 2007

Figure 241 Average Dose Trends for the Rabbit Lake Operation (Based on Non-Zero Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

43

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 242 Average Dose Trends for the Rabbit Lake Operation (Based on All Monitoring Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

Figure 243 Collective Dose Trends for the Rabbit Lake Operation

0

200

400

600

800

1000

1200

1400

1600

1800

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Radon gas External Radon progeny Long-lived radioactive dust

Year

44

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

gt300

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 244 Distribution of Effective Doses Among All Workers at the Rabbit Lake Operation

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

900

800

700

600

500

400

300

200

100

0

Dose (mSv)

45

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

23 Uranium Refineries This section presents data for the following two facilities

bull a uranium refining facility in Blind River (Section 231) bull a uranium conversion facility in Port Hope (Section 232)

Graphs indicate the following average doses at each facility from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Note on data for uranium refineries

1 Doses from photons from external sources are measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay and lung counting Historically while these internal doses have been measured they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

231 Blind River Refinery

Cameco Corporation owns and is licensed to operate a uranium refinery in Blind River Ontario The facility which began operating in 1983 converts uranium ore concentrate to uranium trioxide The uranium trioxide is shipped to Camecorsquos uranium conversion facility in Port Hope Ontario where it is processed into uranium dioxide (for use in the fabrication of fuel for nuclear reactors in Canada) or uranium hexafluoride (exported for enrichment and fabrication into fuel for nuclear power reactors around the world)

Figures 245ndash248 present dose information for the Blind River refinery from 2001 to 2007

46

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 245 Average Dose Trends for the Blind River Refinery (Based on Non-Zero Results)

0

05

1

15

2

25

Year

Figure 246 Average Dose Trends for the Blind River Refinery (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

47

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 247 Collective Dose Trends for the Blind River Refinery

0

50

100

150

200

250

300 C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 248 Distribution of Effective Doses Among All Workers at the Blind River Refinery

0

20

40

60

80

100

120

140

160

180

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

48

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

232 Port Hope Conversion Facility

Cameco Corporation owns and is licensed to operate a uranium conversion facility in Port Hope Ontario The facility processes uranium trioxide received from the refinery in Blind River into uranium dioxide and uranium hexafluoride

Figures 249ndash252 present dose information for the Port Hope uranium conversion facility from 2001 to 2007

Figure 249 Average Dose Trends for the Port Hope Conversion Facility (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

49

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 250 Average Dose Trends for the Port Hope Conversion Facility (Based on All Monitoring Results)

0

01

02

03

04

05

06

07

08

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 251 Collective Dose Trends for the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

50

000-0

009

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 252 Distribution of Effective Doses Among All Workers at the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

400

450

500

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

51

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

24 Fuel Fabrication Facilities This section presents data for three nuclear fuel fabrication facilities

bull Two facilities owned and operated by General Electric Canada Inc (Section 241) bull One facility in Port Hope operated by Zircatec Precision Industries (Section 242)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average doses

Notes on data for fuel fabrication facilities

1 Effective doses for the three facilities are composed of the following reported components bull dose from photons (labelled on the charts as ldquoexternalrdquo) bull doses from internal intakes of uranium dust (long-lived radioactive dust) from

uranium in air concentrations (for General Electricrsquos Toronto facility only)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components photon doses and doses from long-lived radioactive dust

241 General Electric Nuclear Fuel Facilities

General Electric Canada Inc operates two nuclear fuel facilities in Ontario

bull At the Toronto facility uranium dioxide pellets are produced from natural or depleted uranium dioxide powder

bull At the Peterborough facility uranium dioxide fuel bundles are created from the pellets produced at the Toronto facility

Figures 253ndash256 present dose information for General Electric Canada Incrsquos fuel fabrication facilities from 2001 to 2007 Graphs do not distinguish between the doses received at the Peterborough facility versus those at the Toronto facility

52

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 253 Average Dose Trends for the General Electric Fuel Facility (Based on Non-Zero Results Only)

0

05

1

15

2

25

3

35

Long Lived Radioactive Dust External Effective

Year

Figure 254 Average Dose Trends for the General Electric Fuel Facility (Based on All Monitoring Results)

0

05

1

15

2

25

3

Long Lived Radioactive Dust External Effective

Year

Dos

e (m

Sv)

Dos

e (m

Sv)

53

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 255 Collective Dose Trends for the General Electric Fuel Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Long Lived Radioactive Dust External

Year

Figure 256 Distribution of Effective Doses among all Workers at the General Electric Fuel Facility

0

10

20

30

40

50

60

70

80

90

100

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

54

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

242 Zircatec Nuclear Fuel Facility

Zircatec Precision Industries Inc operates a nuclear fuel facility in Port Hope Ontario where it makes fuel pellets from uranium dioxide powder received from Port Hopersquos uranium conversion facility The nuclear fuel facility also manufactures fuel bundles for nuclear reactors in Canada

Notes on data for the Zircatec nuclear fuel facility

1 Graphs indicate the following data bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of average effective doses

2 Doses from photons from external sources were measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay Historically although these internal doses have been measured and submitted to the CNSC they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

Figures 257ndash260 present dose information for the Zircatec nuclear fuel facility from 2001 to 2007

Figure 257 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on Non-Zero Results)

0

05

1

15

2

25

3

35

Effe

ctiv

e D

ose

(mS

v)

Year

55

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 258 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

18

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 259 Collective Dose Trends for the Zircatec Nuclear Fuel Facility

0

50

100

150

200

250

300

350

400

450

500

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

56

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 260 Distribution of Effective Doses Among All Workers at the Zircatec Nuclear Fuel Facility

300

Num

ber o

f Wor

kers

250

200

150

100

50

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

57

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

25 Research and Radioisotope Production Facilities This section presents dose information for the following research and radioisotope production facilities from 2001 to 2007

bull Chalk River Laboratories and Whiteshell Laboratories (Section 251) bull A radioisotope production facility operated by MDS Nordion (Section 252) bull The Tri-University Meson Facility (TRIUMF) (Section 253)

Note on data for research and radioisotope production facilities

1 Graphs indicate the following data for each facility bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of effective doses

251 Chalk River Laboratories and Whiteshell Laboratories

Atomic Energy of Canada Limited (AECL) owns and is licensed to operate Chalk River Laboratories and Whiteshell Laboratories

Situated in Renfrew County on the south shore of the Ottawa River the Chalk River Laboratories site hosts the National Research Universal Reactor along with numerous other facilities occupying some 160 buildings in an area of approximately 40 km2 Activities consist of radioisotope production for nuclear medicine testing and development of structural materials in support of power reactor operations fuel fabrication research and radioactive waste management and storage

The Whiteshell Laboratories site is located approximately 10 km west of Pinawa Manitoba and 100 km northeast of Winnipeg on the east bank of the Winnipeg River AECL established the laboratories for nuclear research and testing during the early 1960s and has since discontinued operations which are being decommissioned under a licence from the CNSC

Figures 261ndash264 present dose information for Chalk River Laboratories and Whiteshell Laboratories from 2001 to 2007

Notes on data for Chalk River Laboratories and Whiteshell Laboratories

1 Effective doses are composed of the following reported components bull external doses5 (from both photon and neutron doses) bull tritium doses

Due to issues with AECLrsquos in-house dosimetry management system neutron doses were not reported separately to the NDR during the reporting period As a result external doses from photons and neutrons were totaled The reporting discrepancy has since been rectified

58

5

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of external (photon and neutron) and tritium doses Intakes of other radionuclides occasionally occur and these radionuclides are not included here because their associated doses are very small For this reason certain collective doses in this report may have values slightly lower than the sum of their respective components as listed

Figure 261 Average Dose Trends for Chalk River and Whiteshell Laboratories (Non-Zero Results Only)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Tritium External Effective

Year

59

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 262 Average Dose Trends for Chalk River and Whiteshell Laboratories (All Monitoring Results)

000

020

040

060

080

100

120

Dos

e (m

Sv)

Tritium External Effective

Year

Figure 263 Collective Dose Trends for Chalk River and Whiteshell Laboratories

0

500

1000

1500

2000

2500

3000

3500

Col

lect

ive

Dos

e (p

erso

n- m

Sv)

External Tritium

Year

60

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 264 Distribution of Effective Doses Among All Workers at Chalk River and Whiteshell Laboratories

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

3500

3000

2500

2000

1500

1000

500

Dose (mSv)

61

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

252 MDS Nordion (Nuclear Substance Processing Facility and Canadian Irradiation Centre)

MDS Nordion owns and operates a nuclear substance processing facility in Ottawa Ontario where it processes unsealed radioisotopes and manufactures sealed radiation sources In operation since the early 1970s the facility was purchased by Nordion International in 1991

In cooperation with the Universiteacute du Queacutebecrsquos Institut Armand-Frappier MDS Nordion also operates the Canadian Irradiation Centre which conducts various irradiation services which include training testing and development The centre is located in Laval Quebec on the Universiteacute du Queacutebec campus

Figures 265ndash268 present dose information for MDS Nordionrsquos Ottawa nuclear substance processing facility and for the Canadian Irradiation Centre from 2001 to 2007

Notes on data for MDS Nordionrsquos nuclear substance processing facility and the Canadian Irradiation Centre

1 Doses from photons from external sources were measured and reported to the NDR MDS Nordion also has a routine thyroid monitoring program very occasionally small recordable doses of radiation have occurred from thyroid uptake of iodine The resulting doses have not been historically submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided

Figure 265 Average Dose Trends for MDS Nordion (Based on Non-Zero Results)

0

05

1

15

2

25

Effe

ctiv

e D

ose

(mS

v)

Year

62

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 266 Average Dose Trends for MDS Nordion (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

Figure 267 Collective Dose Trends for MDS Nordion

0

100

200

300

400

500

600

700

800

Year

63

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 268 Distribution of Effective Doses Among All Workers at MDS Nordion

0

5 0

1 0 0

1 5 0

2 0 0

2 5 0

3 0 0

3 5 0

4 0 0

4 5 0

5 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

64

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

253 Tri-University Meson Facility

The Tri-University Meson facility (TRIUMF) is situated in Vancouver on the campus of the University of British Columbia TRIUMF which began operating in the early 1970s with one cyclotron now has two cyclotrons and associated laboratories for research and radioisotope production The laboratory provides research facilities for Canadian and international users and also produces radioisotopes which are used by medical facilities and by a commercial organization (MDS Nordion) MDS Nordion staff also work at the TRIUMF site however MDS Nordion oversees this work and has its own radiation protection program

Figures 269ndash272 present dose information for the TRIUMF facility from 2001 to 2007 Please note that data sets do not distinguish between doses received by TRIUMF staff and MDS Nordion staff who work on the site as the data for these two groups was submitted collectively to the NDR for the reporting period shown Future data for each group will be submitted separately to the NDR

Note on data for TRIUMF

1 Effective doses are composed of the following reported components bull doses from photons (labeled as ldquoexternalrdquo in the charts) bull neutron doses

Figure 269 Average Dose Trends for TRIUMF (Non-Zero Results Only)

000

020

040

060

080

100

120

140

160

Dos

e (m

Sv)

Neutrons External Effective

Year

65

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 35: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

600

500

400

300

200

100

0

External Radon progeny Long-lived radioactive dust

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 223 Collective Dose Trends for the Cluff Lake Operation s

erkor

of W

ber

Num

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Year

Figure 224 Distribution o f Effective Doses Among A ll Workers at the Cluff Lake Operation

0

20

40

60

80

100

120

140

160

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

30

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

222 McClean Lake Operation

AREVA Resources Canada Inc runs the McClean Lake mining operation in northeastern Saskatchewan It comprises open pit mines a mill and a tailings management facility Mining began in 1995 while milling started in 1999

Figures 225ndash228 present dose information for the McClean Lake operation from 2001 to 2007

Figure 225 Average Dose Trends for the McClean L ake Operation (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

31

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 226 Average Dose Trends for the McClean L ake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 227 Collective Dose Trends for the McClean L ake Operation

0

100

200

300

400

500

600

700

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External

Radon progeny

Long-lived radioactive dust

Year

32

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 228 Distribution o f Effective Doses Among A ll Workers at the McClean Lake Operation

0

100

200

300

400

500

600

700

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

33

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

223 McArthur River Operation

Cameco Corporation operates the McArthur River underground mine in north-central Saskatchewan Ore from the mine which began production in 1999 is processed at the Key Lake Mill located 80 km south of McArthur River

Figures 229ndash232 present dose information for the McArthur River operation from 2001 to 2007

Figure 229 Average Dose Trends for the McArthur River Operation (Based o n N on-Zero R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

34

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 230 Average Dose Trends for the McArthur River Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

Figure 231 Collective Dose Trends for the McArthur River Operation

0

200

400

600

800

1000

1200

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Radon gas External Radon progeny Long-lived radioactive dust

Year

35

00

0-000

9

001-5

00

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 232 Distribution o f Effective Doses Among A ll Workers at the McArthur River Operation

0

100

200

300

400

500

600

700

800

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

36

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

224 Key Lake Operation

Cameco Corporation operates mining facilities in Key Lake located in north-central Saskatchewan The Key Lake operation includes two mined-out open pit mines (used for tailings management) a mill and two dry tailings management facilities Mining began in 1983 and ceased in 1997 the mill continued to process ore from the McArthur River mine during the reporting period

Figures 233ndash236 present dose information for the Key Lake operation from 2001 to 2007

Figure 233 Average Dose Trends for the Key Lake Operation (Based o n N on-Zero R esults)

00

20

40

60

80

00

20

40

60

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

37

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

00

20

40

60

80

00

20

40

60

Figure 234 Average Dose Trends for the Key Lake Operation (Based o n A ll Monitoring R esults)

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 235 Collective Dose Trends for the Key Lake Operation

0

100

200

300

400

500

600

700

800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External Radon progeny Long-lived radioactive dust

Year

38

00

0-000

9

001-5

0

501-1

000

gt 1001

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 236 Distribution o f Effective Doses Among A ll Workers at the Key Lake Operation

0

200

400

600

800

1000

1200

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose Range (mSv)

39

se

(mS

v)o

D

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

225 Cigar Lake Operation

Cameco Corporation manages the Cigar Lake underground mine located in northern Saskatchewan at the southern end of Waterbury Lake The mine was under construction at the time of this reportrsquos publication Test mining in ore was carried out in 1991 1992 and 2000

Figures 237ndash240 present dose information for the Cigar Lake operation from

Figure 2 37 Average D ose T rends fo r th e C igar L ake O peration (Based on Non-Zero Results)

2001 to 2007

Year

000

005

010

015

020

025

Long-lived radioactive dust Radon Progeny External Effective

40

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 238 Average Dose Trends for the Cigar Lake Operation (Based on All Monitoring Results)

000

005

010

015

020

025

030

035

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny

External

Effective

Year

Figure 239 Collective Dose Trends for the Cigar Lake Operation

0

50

100

150

200

250

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

External Radon progeny Long-lived radioactive dust

Year

41

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 240 Distribution of Effective Doses Among All Workers at the Cigar Lake Operation

0

200

400

600

800

1000

1200

1400

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

42

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

226 Rabbit Lake Operation

Cameco Corporation owns and operates mining facilities in Rabbit Lake located in north-eastern Saskatchewan Facilities include an underground mine four mined-out open-pit mines a mill and two tailings management facilities Mining and milling began in 1975

Figures 241ndash244 present dose information for the Rabbit Lake operation from 2001 to 2007

Figure 241 Average Dose Trends for the Rabbit Lake Operation (Based on Non-Zero Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

43

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 242 Average Dose Trends for the Rabbit Lake Operation (Based on All Monitoring Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

Figure 243 Collective Dose Trends for the Rabbit Lake Operation

0

200

400

600

800

1000

1200

1400

1600

1800

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Radon gas External Radon progeny Long-lived radioactive dust

Year

44

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

gt300

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 244 Distribution of Effective Doses Among All Workers at the Rabbit Lake Operation

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

900

800

700

600

500

400

300

200

100

0

Dose (mSv)

45

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

23 Uranium Refineries This section presents data for the following two facilities

bull a uranium refining facility in Blind River (Section 231) bull a uranium conversion facility in Port Hope (Section 232)

Graphs indicate the following average doses at each facility from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Note on data for uranium refineries

1 Doses from photons from external sources are measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay and lung counting Historically while these internal doses have been measured they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

231 Blind River Refinery

Cameco Corporation owns and is licensed to operate a uranium refinery in Blind River Ontario The facility which began operating in 1983 converts uranium ore concentrate to uranium trioxide The uranium trioxide is shipped to Camecorsquos uranium conversion facility in Port Hope Ontario where it is processed into uranium dioxide (for use in the fabrication of fuel for nuclear reactors in Canada) or uranium hexafluoride (exported for enrichment and fabrication into fuel for nuclear power reactors around the world)

Figures 245ndash248 present dose information for the Blind River refinery from 2001 to 2007

46

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 245 Average Dose Trends for the Blind River Refinery (Based on Non-Zero Results)

0

05

1

15

2

25

Year

Figure 246 Average Dose Trends for the Blind River Refinery (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

47

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 247 Collective Dose Trends for the Blind River Refinery

0

50

100

150

200

250

300 C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 248 Distribution of Effective Doses Among All Workers at the Blind River Refinery

0

20

40

60

80

100

120

140

160

180

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

48

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

232 Port Hope Conversion Facility

Cameco Corporation owns and is licensed to operate a uranium conversion facility in Port Hope Ontario The facility processes uranium trioxide received from the refinery in Blind River into uranium dioxide and uranium hexafluoride

Figures 249ndash252 present dose information for the Port Hope uranium conversion facility from 2001 to 2007

Figure 249 Average Dose Trends for the Port Hope Conversion Facility (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

49

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 250 Average Dose Trends for the Port Hope Conversion Facility (Based on All Monitoring Results)

0

01

02

03

04

05

06

07

08

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 251 Collective Dose Trends for the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

50

000-0

009

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 252 Distribution of Effective Doses Among All Workers at the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

400

450

500

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

51

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

24 Fuel Fabrication Facilities This section presents data for three nuclear fuel fabrication facilities

bull Two facilities owned and operated by General Electric Canada Inc (Section 241) bull One facility in Port Hope operated by Zircatec Precision Industries (Section 242)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average doses

Notes on data for fuel fabrication facilities

1 Effective doses for the three facilities are composed of the following reported components bull dose from photons (labelled on the charts as ldquoexternalrdquo) bull doses from internal intakes of uranium dust (long-lived radioactive dust) from

uranium in air concentrations (for General Electricrsquos Toronto facility only)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components photon doses and doses from long-lived radioactive dust

241 General Electric Nuclear Fuel Facilities

General Electric Canada Inc operates two nuclear fuel facilities in Ontario

bull At the Toronto facility uranium dioxide pellets are produced from natural or depleted uranium dioxide powder

bull At the Peterborough facility uranium dioxide fuel bundles are created from the pellets produced at the Toronto facility

Figures 253ndash256 present dose information for General Electric Canada Incrsquos fuel fabrication facilities from 2001 to 2007 Graphs do not distinguish between the doses received at the Peterborough facility versus those at the Toronto facility

52

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 253 Average Dose Trends for the General Electric Fuel Facility (Based on Non-Zero Results Only)

0

05

1

15

2

25

3

35

Long Lived Radioactive Dust External Effective

Year

Figure 254 Average Dose Trends for the General Electric Fuel Facility (Based on All Monitoring Results)

0

05

1

15

2

25

3

Long Lived Radioactive Dust External Effective

Year

Dos

e (m

Sv)

Dos

e (m

Sv)

53

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 255 Collective Dose Trends for the General Electric Fuel Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Long Lived Radioactive Dust External

Year

Figure 256 Distribution of Effective Doses among all Workers at the General Electric Fuel Facility

0

10

20

30

40

50

60

70

80

90

100

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

54

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

242 Zircatec Nuclear Fuel Facility

Zircatec Precision Industries Inc operates a nuclear fuel facility in Port Hope Ontario where it makes fuel pellets from uranium dioxide powder received from Port Hopersquos uranium conversion facility The nuclear fuel facility also manufactures fuel bundles for nuclear reactors in Canada

Notes on data for the Zircatec nuclear fuel facility

1 Graphs indicate the following data bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of average effective doses

2 Doses from photons from external sources were measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay Historically although these internal doses have been measured and submitted to the CNSC they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

Figures 257ndash260 present dose information for the Zircatec nuclear fuel facility from 2001 to 2007

Figure 257 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on Non-Zero Results)

0

05

1

15

2

25

3

35

Effe

ctiv

e D

ose

(mS

v)

Year

55

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 258 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

18

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 259 Collective Dose Trends for the Zircatec Nuclear Fuel Facility

0

50

100

150

200

250

300

350

400

450

500

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

56

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 260 Distribution of Effective Doses Among All Workers at the Zircatec Nuclear Fuel Facility

300

Num

ber o

f Wor

kers

250

200

150

100

50

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

57

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

25 Research and Radioisotope Production Facilities This section presents dose information for the following research and radioisotope production facilities from 2001 to 2007

bull Chalk River Laboratories and Whiteshell Laboratories (Section 251) bull A radioisotope production facility operated by MDS Nordion (Section 252) bull The Tri-University Meson Facility (TRIUMF) (Section 253)

Note on data for research and radioisotope production facilities

1 Graphs indicate the following data for each facility bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of effective doses

251 Chalk River Laboratories and Whiteshell Laboratories

Atomic Energy of Canada Limited (AECL) owns and is licensed to operate Chalk River Laboratories and Whiteshell Laboratories

Situated in Renfrew County on the south shore of the Ottawa River the Chalk River Laboratories site hosts the National Research Universal Reactor along with numerous other facilities occupying some 160 buildings in an area of approximately 40 km2 Activities consist of radioisotope production for nuclear medicine testing and development of structural materials in support of power reactor operations fuel fabrication research and radioactive waste management and storage

The Whiteshell Laboratories site is located approximately 10 km west of Pinawa Manitoba and 100 km northeast of Winnipeg on the east bank of the Winnipeg River AECL established the laboratories for nuclear research and testing during the early 1960s and has since discontinued operations which are being decommissioned under a licence from the CNSC

Figures 261ndash264 present dose information for Chalk River Laboratories and Whiteshell Laboratories from 2001 to 2007

Notes on data for Chalk River Laboratories and Whiteshell Laboratories

1 Effective doses are composed of the following reported components bull external doses5 (from both photon and neutron doses) bull tritium doses

Due to issues with AECLrsquos in-house dosimetry management system neutron doses were not reported separately to the NDR during the reporting period As a result external doses from photons and neutrons were totaled The reporting discrepancy has since been rectified

58

5

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of external (photon and neutron) and tritium doses Intakes of other radionuclides occasionally occur and these radionuclides are not included here because their associated doses are very small For this reason certain collective doses in this report may have values slightly lower than the sum of their respective components as listed

Figure 261 Average Dose Trends for Chalk River and Whiteshell Laboratories (Non-Zero Results Only)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Tritium External Effective

Year

59

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 262 Average Dose Trends for Chalk River and Whiteshell Laboratories (All Monitoring Results)

000

020

040

060

080

100

120

Dos

e (m

Sv)

Tritium External Effective

Year

Figure 263 Collective Dose Trends for Chalk River and Whiteshell Laboratories

0

500

1000

1500

2000

2500

3000

3500

Col

lect

ive

Dos

e (p

erso

n- m

Sv)

External Tritium

Year

60

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 264 Distribution of Effective Doses Among All Workers at Chalk River and Whiteshell Laboratories

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

3500

3000

2500

2000

1500

1000

500

Dose (mSv)

61

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

252 MDS Nordion (Nuclear Substance Processing Facility and Canadian Irradiation Centre)

MDS Nordion owns and operates a nuclear substance processing facility in Ottawa Ontario where it processes unsealed radioisotopes and manufactures sealed radiation sources In operation since the early 1970s the facility was purchased by Nordion International in 1991

In cooperation with the Universiteacute du Queacutebecrsquos Institut Armand-Frappier MDS Nordion also operates the Canadian Irradiation Centre which conducts various irradiation services which include training testing and development The centre is located in Laval Quebec on the Universiteacute du Queacutebec campus

Figures 265ndash268 present dose information for MDS Nordionrsquos Ottawa nuclear substance processing facility and for the Canadian Irradiation Centre from 2001 to 2007

Notes on data for MDS Nordionrsquos nuclear substance processing facility and the Canadian Irradiation Centre

1 Doses from photons from external sources were measured and reported to the NDR MDS Nordion also has a routine thyroid monitoring program very occasionally small recordable doses of radiation have occurred from thyroid uptake of iodine The resulting doses have not been historically submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided

Figure 265 Average Dose Trends for MDS Nordion (Based on Non-Zero Results)

0

05

1

15

2

25

Effe

ctiv

e D

ose

(mS

v)

Year

62

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 266 Average Dose Trends for MDS Nordion (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

Figure 267 Collective Dose Trends for MDS Nordion

0

100

200

300

400

500

600

700

800

Year

63

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 268 Distribution of Effective Doses Among All Workers at MDS Nordion

0

5 0

1 0 0

1 5 0

2 0 0

2 5 0

3 0 0

3 5 0

4 0 0

4 5 0

5 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

64

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

253 Tri-University Meson Facility

The Tri-University Meson facility (TRIUMF) is situated in Vancouver on the campus of the University of British Columbia TRIUMF which began operating in the early 1970s with one cyclotron now has two cyclotrons and associated laboratories for research and radioisotope production The laboratory provides research facilities for Canadian and international users and also produces radioisotopes which are used by medical facilities and by a commercial organization (MDS Nordion) MDS Nordion staff also work at the TRIUMF site however MDS Nordion oversees this work and has its own radiation protection program

Figures 269ndash272 present dose information for the TRIUMF facility from 2001 to 2007 Please note that data sets do not distinguish between doses received by TRIUMF staff and MDS Nordion staff who work on the site as the data for these two groups was submitted collectively to the NDR for the reporting period shown Future data for each group will be submitted separately to the NDR

Note on data for TRIUMF

1 Effective doses are composed of the following reported components bull doses from photons (labeled as ldquoexternalrdquo in the charts) bull neutron doses

Figure 269 Average Dose Trends for TRIUMF (Non-Zero Results Only)

000

020

040

060

080

100

120

140

160

Dos

e (m

Sv)

Neutrons External Effective

Year

65

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 36: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

222 McClean Lake Operation

AREVA Resources Canada Inc runs the McClean Lake mining operation in northeastern Saskatchewan It comprises open pit mines a mill and a tailings management facility Mining began in 1995 while milling started in 1999

Figures 225ndash228 present dose information for the McClean Lake operation from 2001 to 2007

Figure 225 Average Dose Trends for the McClean L ake Operation (Based o n N on-Zero R esults)

000

050

100

150

200

250

300

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

31

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 226 Average Dose Trends for the McClean L ake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 227 Collective Dose Trends for the McClean L ake Operation

0

100

200

300

400

500

600

700

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External

Radon progeny

Long-lived radioactive dust

Year

32

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 228 Distribution o f Effective Doses Among A ll Workers at the McClean Lake Operation

0

100

200

300

400

500

600

700

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

33

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

223 McArthur River Operation

Cameco Corporation operates the McArthur River underground mine in north-central Saskatchewan Ore from the mine which began production in 1999 is processed at the Key Lake Mill located 80 km south of McArthur River

Figures 229ndash232 present dose information for the McArthur River operation from 2001 to 2007

Figure 229 Average Dose Trends for the McArthur River Operation (Based o n N on-Zero R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

34

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 230 Average Dose Trends for the McArthur River Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

Figure 231 Collective Dose Trends for the McArthur River Operation

0

200

400

600

800

1000

1200

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Radon gas External Radon progeny Long-lived radioactive dust

Year

35

00

0-000

9

001-5

00

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 232 Distribution o f Effective Doses Among A ll Workers at the McArthur River Operation

0

100

200

300

400

500

600

700

800

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

36

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

224 Key Lake Operation

Cameco Corporation operates mining facilities in Key Lake located in north-central Saskatchewan The Key Lake operation includes two mined-out open pit mines (used for tailings management) a mill and two dry tailings management facilities Mining began in 1983 and ceased in 1997 the mill continued to process ore from the McArthur River mine during the reporting period

Figures 233ndash236 present dose information for the Key Lake operation from 2001 to 2007

Figure 233 Average Dose Trends for the Key Lake Operation (Based o n N on-Zero R esults)

00

20

40

60

80

00

20

40

60

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

37

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

00

20

40

60

80

00

20

40

60

Figure 234 Average Dose Trends for the Key Lake Operation (Based o n A ll Monitoring R esults)

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 235 Collective Dose Trends for the Key Lake Operation

0

100

200

300

400

500

600

700

800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External Radon progeny Long-lived radioactive dust

Year

38

00

0-000

9

001-5

0

501-1

000

gt 1001

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 236 Distribution o f Effective Doses Among A ll Workers at the Key Lake Operation

0

200

400

600

800

1000

1200

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose Range (mSv)

39

se

(mS

v)o

D

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

225 Cigar Lake Operation

Cameco Corporation manages the Cigar Lake underground mine located in northern Saskatchewan at the southern end of Waterbury Lake The mine was under construction at the time of this reportrsquos publication Test mining in ore was carried out in 1991 1992 and 2000

Figures 237ndash240 present dose information for the Cigar Lake operation from

Figure 2 37 Average D ose T rends fo r th e C igar L ake O peration (Based on Non-Zero Results)

2001 to 2007

Year

000

005

010

015

020

025

Long-lived radioactive dust Radon Progeny External Effective

40

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 238 Average Dose Trends for the Cigar Lake Operation (Based on All Monitoring Results)

000

005

010

015

020

025

030

035

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny

External

Effective

Year

Figure 239 Collective Dose Trends for the Cigar Lake Operation

0

50

100

150

200

250

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

External Radon progeny Long-lived radioactive dust

Year

41

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 240 Distribution of Effective Doses Among All Workers at the Cigar Lake Operation

0

200

400

600

800

1000

1200

1400

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

42

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

226 Rabbit Lake Operation

Cameco Corporation owns and operates mining facilities in Rabbit Lake located in north-eastern Saskatchewan Facilities include an underground mine four mined-out open-pit mines a mill and two tailings management facilities Mining and milling began in 1975

Figures 241ndash244 present dose information for the Rabbit Lake operation from 2001 to 2007

Figure 241 Average Dose Trends for the Rabbit Lake Operation (Based on Non-Zero Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

43

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 242 Average Dose Trends for the Rabbit Lake Operation (Based on All Monitoring Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

Figure 243 Collective Dose Trends for the Rabbit Lake Operation

0

200

400

600

800

1000

1200

1400

1600

1800

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Radon gas External Radon progeny Long-lived radioactive dust

Year

44

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

gt300

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 244 Distribution of Effective Doses Among All Workers at the Rabbit Lake Operation

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

900

800

700

600

500

400

300

200

100

0

Dose (mSv)

45

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

23 Uranium Refineries This section presents data for the following two facilities

bull a uranium refining facility in Blind River (Section 231) bull a uranium conversion facility in Port Hope (Section 232)

Graphs indicate the following average doses at each facility from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Note on data for uranium refineries

1 Doses from photons from external sources are measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay and lung counting Historically while these internal doses have been measured they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

231 Blind River Refinery

Cameco Corporation owns and is licensed to operate a uranium refinery in Blind River Ontario The facility which began operating in 1983 converts uranium ore concentrate to uranium trioxide The uranium trioxide is shipped to Camecorsquos uranium conversion facility in Port Hope Ontario where it is processed into uranium dioxide (for use in the fabrication of fuel for nuclear reactors in Canada) or uranium hexafluoride (exported for enrichment and fabrication into fuel for nuclear power reactors around the world)

Figures 245ndash248 present dose information for the Blind River refinery from 2001 to 2007

46

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 245 Average Dose Trends for the Blind River Refinery (Based on Non-Zero Results)

0

05

1

15

2

25

Year

Figure 246 Average Dose Trends for the Blind River Refinery (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

47

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 247 Collective Dose Trends for the Blind River Refinery

0

50

100

150

200

250

300 C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 248 Distribution of Effective Doses Among All Workers at the Blind River Refinery

0

20

40

60

80

100

120

140

160

180

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

48

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

232 Port Hope Conversion Facility

Cameco Corporation owns and is licensed to operate a uranium conversion facility in Port Hope Ontario The facility processes uranium trioxide received from the refinery in Blind River into uranium dioxide and uranium hexafluoride

Figures 249ndash252 present dose information for the Port Hope uranium conversion facility from 2001 to 2007

Figure 249 Average Dose Trends for the Port Hope Conversion Facility (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

49

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 250 Average Dose Trends for the Port Hope Conversion Facility (Based on All Monitoring Results)

0

01

02

03

04

05

06

07

08

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 251 Collective Dose Trends for the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

50

000-0

009

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 252 Distribution of Effective Doses Among All Workers at the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

400

450

500

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

51

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

24 Fuel Fabrication Facilities This section presents data for three nuclear fuel fabrication facilities

bull Two facilities owned and operated by General Electric Canada Inc (Section 241) bull One facility in Port Hope operated by Zircatec Precision Industries (Section 242)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average doses

Notes on data for fuel fabrication facilities

1 Effective doses for the three facilities are composed of the following reported components bull dose from photons (labelled on the charts as ldquoexternalrdquo) bull doses from internal intakes of uranium dust (long-lived radioactive dust) from

uranium in air concentrations (for General Electricrsquos Toronto facility only)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components photon doses and doses from long-lived radioactive dust

241 General Electric Nuclear Fuel Facilities

General Electric Canada Inc operates two nuclear fuel facilities in Ontario

bull At the Toronto facility uranium dioxide pellets are produced from natural or depleted uranium dioxide powder

bull At the Peterborough facility uranium dioxide fuel bundles are created from the pellets produced at the Toronto facility

Figures 253ndash256 present dose information for General Electric Canada Incrsquos fuel fabrication facilities from 2001 to 2007 Graphs do not distinguish between the doses received at the Peterborough facility versus those at the Toronto facility

52

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 253 Average Dose Trends for the General Electric Fuel Facility (Based on Non-Zero Results Only)

0

05

1

15

2

25

3

35

Long Lived Radioactive Dust External Effective

Year

Figure 254 Average Dose Trends for the General Electric Fuel Facility (Based on All Monitoring Results)

0

05

1

15

2

25

3

Long Lived Radioactive Dust External Effective

Year

Dos

e (m

Sv)

Dos

e (m

Sv)

53

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 255 Collective Dose Trends for the General Electric Fuel Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Long Lived Radioactive Dust External

Year

Figure 256 Distribution of Effective Doses among all Workers at the General Electric Fuel Facility

0

10

20

30

40

50

60

70

80

90

100

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

54

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

242 Zircatec Nuclear Fuel Facility

Zircatec Precision Industries Inc operates a nuclear fuel facility in Port Hope Ontario where it makes fuel pellets from uranium dioxide powder received from Port Hopersquos uranium conversion facility The nuclear fuel facility also manufactures fuel bundles for nuclear reactors in Canada

Notes on data for the Zircatec nuclear fuel facility

1 Graphs indicate the following data bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of average effective doses

2 Doses from photons from external sources were measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay Historically although these internal doses have been measured and submitted to the CNSC they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

Figures 257ndash260 present dose information for the Zircatec nuclear fuel facility from 2001 to 2007

Figure 257 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on Non-Zero Results)

0

05

1

15

2

25

3

35

Effe

ctiv

e D

ose

(mS

v)

Year

55

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 258 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

18

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 259 Collective Dose Trends for the Zircatec Nuclear Fuel Facility

0

50

100

150

200

250

300

350

400

450

500

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

56

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 260 Distribution of Effective Doses Among All Workers at the Zircatec Nuclear Fuel Facility

300

Num

ber o

f Wor

kers

250

200

150

100

50

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

57

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

25 Research and Radioisotope Production Facilities This section presents dose information for the following research and radioisotope production facilities from 2001 to 2007

bull Chalk River Laboratories and Whiteshell Laboratories (Section 251) bull A radioisotope production facility operated by MDS Nordion (Section 252) bull The Tri-University Meson Facility (TRIUMF) (Section 253)

Note on data for research and radioisotope production facilities

1 Graphs indicate the following data for each facility bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of effective doses

251 Chalk River Laboratories and Whiteshell Laboratories

Atomic Energy of Canada Limited (AECL) owns and is licensed to operate Chalk River Laboratories and Whiteshell Laboratories

Situated in Renfrew County on the south shore of the Ottawa River the Chalk River Laboratories site hosts the National Research Universal Reactor along with numerous other facilities occupying some 160 buildings in an area of approximately 40 km2 Activities consist of radioisotope production for nuclear medicine testing and development of structural materials in support of power reactor operations fuel fabrication research and radioactive waste management and storage

The Whiteshell Laboratories site is located approximately 10 km west of Pinawa Manitoba and 100 km northeast of Winnipeg on the east bank of the Winnipeg River AECL established the laboratories for nuclear research and testing during the early 1960s and has since discontinued operations which are being decommissioned under a licence from the CNSC

Figures 261ndash264 present dose information for Chalk River Laboratories and Whiteshell Laboratories from 2001 to 2007

Notes on data for Chalk River Laboratories and Whiteshell Laboratories

1 Effective doses are composed of the following reported components bull external doses5 (from both photon and neutron doses) bull tritium doses

Due to issues with AECLrsquos in-house dosimetry management system neutron doses were not reported separately to the NDR during the reporting period As a result external doses from photons and neutrons were totaled The reporting discrepancy has since been rectified

58

5

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of external (photon and neutron) and tritium doses Intakes of other radionuclides occasionally occur and these radionuclides are not included here because their associated doses are very small For this reason certain collective doses in this report may have values slightly lower than the sum of their respective components as listed

Figure 261 Average Dose Trends for Chalk River and Whiteshell Laboratories (Non-Zero Results Only)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Tritium External Effective

Year

59

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 262 Average Dose Trends for Chalk River and Whiteshell Laboratories (All Monitoring Results)

000

020

040

060

080

100

120

Dos

e (m

Sv)

Tritium External Effective

Year

Figure 263 Collective Dose Trends for Chalk River and Whiteshell Laboratories

0

500

1000

1500

2000

2500

3000

3500

Col

lect

ive

Dos

e (p

erso

n- m

Sv)

External Tritium

Year

60

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 264 Distribution of Effective Doses Among All Workers at Chalk River and Whiteshell Laboratories

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

3500

3000

2500

2000

1500

1000

500

Dose (mSv)

61

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

252 MDS Nordion (Nuclear Substance Processing Facility and Canadian Irradiation Centre)

MDS Nordion owns and operates a nuclear substance processing facility in Ottawa Ontario where it processes unsealed radioisotopes and manufactures sealed radiation sources In operation since the early 1970s the facility was purchased by Nordion International in 1991

In cooperation with the Universiteacute du Queacutebecrsquos Institut Armand-Frappier MDS Nordion also operates the Canadian Irradiation Centre which conducts various irradiation services which include training testing and development The centre is located in Laval Quebec on the Universiteacute du Queacutebec campus

Figures 265ndash268 present dose information for MDS Nordionrsquos Ottawa nuclear substance processing facility and for the Canadian Irradiation Centre from 2001 to 2007

Notes on data for MDS Nordionrsquos nuclear substance processing facility and the Canadian Irradiation Centre

1 Doses from photons from external sources were measured and reported to the NDR MDS Nordion also has a routine thyroid monitoring program very occasionally small recordable doses of radiation have occurred from thyroid uptake of iodine The resulting doses have not been historically submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided

Figure 265 Average Dose Trends for MDS Nordion (Based on Non-Zero Results)

0

05

1

15

2

25

Effe

ctiv

e D

ose

(mS

v)

Year

62

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 266 Average Dose Trends for MDS Nordion (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

Figure 267 Collective Dose Trends for MDS Nordion

0

100

200

300

400

500

600

700

800

Year

63

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 268 Distribution of Effective Doses Among All Workers at MDS Nordion

0

5 0

1 0 0

1 5 0

2 0 0

2 5 0

3 0 0

3 5 0

4 0 0

4 5 0

5 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

64

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

253 Tri-University Meson Facility

The Tri-University Meson facility (TRIUMF) is situated in Vancouver on the campus of the University of British Columbia TRIUMF which began operating in the early 1970s with one cyclotron now has two cyclotrons and associated laboratories for research and radioisotope production The laboratory provides research facilities for Canadian and international users and also produces radioisotopes which are used by medical facilities and by a commercial organization (MDS Nordion) MDS Nordion staff also work at the TRIUMF site however MDS Nordion oversees this work and has its own radiation protection program

Figures 269ndash272 present dose information for the TRIUMF facility from 2001 to 2007 Please note that data sets do not distinguish between doses received by TRIUMF staff and MDS Nordion staff who work on the site as the data for these two groups was submitted collectively to the NDR for the reporting period shown Future data for each group will be submitted separately to the NDR

Note on data for TRIUMF

1 Effective doses are composed of the following reported components bull doses from photons (labeled as ldquoexternalrdquo in the charts) bull neutron doses

Figure 269 Average Dose Trends for TRIUMF (Non-Zero Results Only)

000

020

040

060

080

100

120

140

160

Dos

e (m

Sv)

Neutrons External Effective

Year

65

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 37: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 226 Average Dose Trends for the McClean L ake Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 227 Collective Dose Trends for the McClean L ake Operation

0

100

200

300

400

500

600

700

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External

Radon progeny

Long-lived radioactive dust

Year

32

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 228 Distribution o f Effective Doses Among A ll Workers at the McClean Lake Operation

0

100

200

300

400

500

600

700

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

33

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

223 McArthur River Operation

Cameco Corporation operates the McArthur River underground mine in north-central Saskatchewan Ore from the mine which began production in 1999 is processed at the Key Lake Mill located 80 km south of McArthur River

Figures 229ndash232 present dose information for the McArthur River operation from 2001 to 2007

Figure 229 Average Dose Trends for the McArthur River Operation (Based o n N on-Zero R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

34

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 230 Average Dose Trends for the McArthur River Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

Figure 231 Collective Dose Trends for the McArthur River Operation

0

200

400

600

800

1000

1200

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Radon gas External Radon progeny Long-lived radioactive dust

Year

35

00

0-000

9

001-5

00

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 232 Distribution o f Effective Doses Among A ll Workers at the McArthur River Operation

0

100

200

300

400

500

600

700

800

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

36

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

224 Key Lake Operation

Cameco Corporation operates mining facilities in Key Lake located in north-central Saskatchewan The Key Lake operation includes two mined-out open pit mines (used for tailings management) a mill and two dry tailings management facilities Mining began in 1983 and ceased in 1997 the mill continued to process ore from the McArthur River mine during the reporting period

Figures 233ndash236 present dose information for the Key Lake operation from 2001 to 2007

Figure 233 Average Dose Trends for the Key Lake Operation (Based o n N on-Zero R esults)

00

20

40

60

80

00

20

40

60

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

37

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

00

20

40

60

80

00

20

40

60

Figure 234 Average Dose Trends for the Key Lake Operation (Based o n A ll Monitoring R esults)

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 235 Collective Dose Trends for the Key Lake Operation

0

100

200

300

400

500

600

700

800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External Radon progeny Long-lived radioactive dust

Year

38

00

0-000

9

001-5

0

501-1

000

gt 1001

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 236 Distribution o f Effective Doses Among A ll Workers at the Key Lake Operation

0

200

400

600

800

1000

1200

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose Range (mSv)

39

se

(mS

v)o

D

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

225 Cigar Lake Operation

Cameco Corporation manages the Cigar Lake underground mine located in northern Saskatchewan at the southern end of Waterbury Lake The mine was under construction at the time of this reportrsquos publication Test mining in ore was carried out in 1991 1992 and 2000

Figures 237ndash240 present dose information for the Cigar Lake operation from

Figure 2 37 Average D ose T rends fo r th e C igar L ake O peration (Based on Non-Zero Results)

2001 to 2007

Year

000

005

010

015

020

025

Long-lived radioactive dust Radon Progeny External Effective

40

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 238 Average Dose Trends for the Cigar Lake Operation (Based on All Monitoring Results)

000

005

010

015

020

025

030

035

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny

External

Effective

Year

Figure 239 Collective Dose Trends for the Cigar Lake Operation

0

50

100

150

200

250

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

External Radon progeny Long-lived radioactive dust

Year

41

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 240 Distribution of Effective Doses Among All Workers at the Cigar Lake Operation

0

200

400

600

800

1000

1200

1400

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

42

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

226 Rabbit Lake Operation

Cameco Corporation owns and operates mining facilities in Rabbit Lake located in north-eastern Saskatchewan Facilities include an underground mine four mined-out open-pit mines a mill and two tailings management facilities Mining and milling began in 1975

Figures 241ndash244 present dose information for the Rabbit Lake operation from 2001 to 2007

Figure 241 Average Dose Trends for the Rabbit Lake Operation (Based on Non-Zero Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

43

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 242 Average Dose Trends for the Rabbit Lake Operation (Based on All Monitoring Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

Figure 243 Collective Dose Trends for the Rabbit Lake Operation

0

200

400

600

800

1000

1200

1400

1600

1800

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Radon gas External Radon progeny Long-lived radioactive dust

Year

44

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

gt300

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 244 Distribution of Effective Doses Among All Workers at the Rabbit Lake Operation

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

900

800

700

600

500

400

300

200

100

0

Dose (mSv)

45

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

23 Uranium Refineries This section presents data for the following two facilities

bull a uranium refining facility in Blind River (Section 231) bull a uranium conversion facility in Port Hope (Section 232)

Graphs indicate the following average doses at each facility from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Note on data for uranium refineries

1 Doses from photons from external sources are measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay and lung counting Historically while these internal doses have been measured they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

231 Blind River Refinery

Cameco Corporation owns and is licensed to operate a uranium refinery in Blind River Ontario The facility which began operating in 1983 converts uranium ore concentrate to uranium trioxide The uranium trioxide is shipped to Camecorsquos uranium conversion facility in Port Hope Ontario where it is processed into uranium dioxide (for use in the fabrication of fuel for nuclear reactors in Canada) or uranium hexafluoride (exported for enrichment and fabrication into fuel for nuclear power reactors around the world)

Figures 245ndash248 present dose information for the Blind River refinery from 2001 to 2007

46

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 245 Average Dose Trends for the Blind River Refinery (Based on Non-Zero Results)

0

05

1

15

2

25

Year

Figure 246 Average Dose Trends for the Blind River Refinery (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

47

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 247 Collective Dose Trends for the Blind River Refinery

0

50

100

150

200

250

300 C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 248 Distribution of Effective Doses Among All Workers at the Blind River Refinery

0

20

40

60

80

100

120

140

160

180

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

48

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

232 Port Hope Conversion Facility

Cameco Corporation owns and is licensed to operate a uranium conversion facility in Port Hope Ontario The facility processes uranium trioxide received from the refinery in Blind River into uranium dioxide and uranium hexafluoride

Figures 249ndash252 present dose information for the Port Hope uranium conversion facility from 2001 to 2007

Figure 249 Average Dose Trends for the Port Hope Conversion Facility (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

49

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 250 Average Dose Trends for the Port Hope Conversion Facility (Based on All Monitoring Results)

0

01

02

03

04

05

06

07

08

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 251 Collective Dose Trends for the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

50

000-0

009

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 252 Distribution of Effective Doses Among All Workers at the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

400

450

500

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

51

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

24 Fuel Fabrication Facilities This section presents data for three nuclear fuel fabrication facilities

bull Two facilities owned and operated by General Electric Canada Inc (Section 241) bull One facility in Port Hope operated by Zircatec Precision Industries (Section 242)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average doses

Notes on data for fuel fabrication facilities

1 Effective doses for the three facilities are composed of the following reported components bull dose from photons (labelled on the charts as ldquoexternalrdquo) bull doses from internal intakes of uranium dust (long-lived radioactive dust) from

uranium in air concentrations (for General Electricrsquos Toronto facility only)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components photon doses and doses from long-lived radioactive dust

241 General Electric Nuclear Fuel Facilities

General Electric Canada Inc operates two nuclear fuel facilities in Ontario

bull At the Toronto facility uranium dioxide pellets are produced from natural or depleted uranium dioxide powder

bull At the Peterborough facility uranium dioxide fuel bundles are created from the pellets produced at the Toronto facility

Figures 253ndash256 present dose information for General Electric Canada Incrsquos fuel fabrication facilities from 2001 to 2007 Graphs do not distinguish between the doses received at the Peterborough facility versus those at the Toronto facility

52

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 253 Average Dose Trends for the General Electric Fuel Facility (Based on Non-Zero Results Only)

0

05

1

15

2

25

3

35

Long Lived Radioactive Dust External Effective

Year

Figure 254 Average Dose Trends for the General Electric Fuel Facility (Based on All Monitoring Results)

0

05

1

15

2

25

3

Long Lived Radioactive Dust External Effective

Year

Dos

e (m

Sv)

Dos

e (m

Sv)

53

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 255 Collective Dose Trends for the General Electric Fuel Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Long Lived Radioactive Dust External

Year

Figure 256 Distribution of Effective Doses among all Workers at the General Electric Fuel Facility

0

10

20

30

40

50

60

70

80

90

100

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

54

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

242 Zircatec Nuclear Fuel Facility

Zircatec Precision Industries Inc operates a nuclear fuel facility in Port Hope Ontario where it makes fuel pellets from uranium dioxide powder received from Port Hopersquos uranium conversion facility The nuclear fuel facility also manufactures fuel bundles for nuclear reactors in Canada

Notes on data for the Zircatec nuclear fuel facility

1 Graphs indicate the following data bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of average effective doses

2 Doses from photons from external sources were measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay Historically although these internal doses have been measured and submitted to the CNSC they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

Figures 257ndash260 present dose information for the Zircatec nuclear fuel facility from 2001 to 2007

Figure 257 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on Non-Zero Results)

0

05

1

15

2

25

3

35

Effe

ctiv

e D

ose

(mS

v)

Year

55

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 258 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

18

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 259 Collective Dose Trends for the Zircatec Nuclear Fuel Facility

0

50

100

150

200

250

300

350

400

450

500

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

56

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 260 Distribution of Effective Doses Among All Workers at the Zircatec Nuclear Fuel Facility

300

Num

ber o

f Wor

kers

250

200

150

100

50

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

57

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

25 Research and Radioisotope Production Facilities This section presents dose information for the following research and radioisotope production facilities from 2001 to 2007

bull Chalk River Laboratories and Whiteshell Laboratories (Section 251) bull A radioisotope production facility operated by MDS Nordion (Section 252) bull The Tri-University Meson Facility (TRIUMF) (Section 253)

Note on data for research and radioisotope production facilities

1 Graphs indicate the following data for each facility bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of effective doses

251 Chalk River Laboratories and Whiteshell Laboratories

Atomic Energy of Canada Limited (AECL) owns and is licensed to operate Chalk River Laboratories and Whiteshell Laboratories

Situated in Renfrew County on the south shore of the Ottawa River the Chalk River Laboratories site hosts the National Research Universal Reactor along with numerous other facilities occupying some 160 buildings in an area of approximately 40 km2 Activities consist of radioisotope production for nuclear medicine testing and development of structural materials in support of power reactor operations fuel fabrication research and radioactive waste management and storage

The Whiteshell Laboratories site is located approximately 10 km west of Pinawa Manitoba and 100 km northeast of Winnipeg on the east bank of the Winnipeg River AECL established the laboratories for nuclear research and testing during the early 1960s and has since discontinued operations which are being decommissioned under a licence from the CNSC

Figures 261ndash264 present dose information for Chalk River Laboratories and Whiteshell Laboratories from 2001 to 2007

Notes on data for Chalk River Laboratories and Whiteshell Laboratories

1 Effective doses are composed of the following reported components bull external doses5 (from both photon and neutron doses) bull tritium doses

Due to issues with AECLrsquos in-house dosimetry management system neutron doses were not reported separately to the NDR during the reporting period As a result external doses from photons and neutrons were totaled The reporting discrepancy has since been rectified

58

5

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of external (photon and neutron) and tritium doses Intakes of other radionuclides occasionally occur and these radionuclides are not included here because their associated doses are very small For this reason certain collective doses in this report may have values slightly lower than the sum of their respective components as listed

Figure 261 Average Dose Trends for Chalk River and Whiteshell Laboratories (Non-Zero Results Only)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Tritium External Effective

Year

59

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 262 Average Dose Trends for Chalk River and Whiteshell Laboratories (All Monitoring Results)

000

020

040

060

080

100

120

Dos

e (m

Sv)

Tritium External Effective

Year

Figure 263 Collective Dose Trends for Chalk River and Whiteshell Laboratories

0

500

1000

1500

2000

2500

3000

3500

Col

lect

ive

Dos

e (p

erso

n- m

Sv)

External Tritium

Year

60

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 264 Distribution of Effective Doses Among All Workers at Chalk River and Whiteshell Laboratories

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

3500

3000

2500

2000

1500

1000

500

Dose (mSv)

61

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

252 MDS Nordion (Nuclear Substance Processing Facility and Canadian Irradiation Centre)

MDS Nordion owns and operates a nuclear substance processing facility in Ottawa Ontario where it processes unsealed radioisotopes and manufactures sealed radiation sources In operation since the early 1970s the facility was purchased by Nordion International in 1991

In cooperation with the Universiteacute du Queacutebecrsquos Institut Armand-Frappier MDS Nordion also operates the Canadian Irradiation Centre which conducts various irradiation services which include training testing and development The centre is located in Laval Quebec on the Universiteacute du Queacutebec campus

Figures 265ndash268 present dose information for MDS Nordionrsquos Ottawa nuclear substance processing facility and for the Canadian Irradiation Centre from 2001 to 2007

Notes on data for MDS Nordionrsquos nuclear substance processing facility and the Canadian Irradiation Centre

1 Doses from photons from external sources were measured and reported to the NDR MDS Nordion also has a routine thyroid monitoring program very occasionally small recordable doses of radiation have occurred from thyroid uptake of iodine The resulting doses have not been historically submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided

Figure 265 Average Dose Trends for MDS Nordion (Based on Non-Zero Results)

0

05

1

15

2

25

Effe

ctiv

e D

ose

(mS

v)

Year

62

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 266 Average Dose Trends for MDS Nordion (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

Figure 267 Collective Dose Trends for MDS Nordion

0

100

200

300

400

500

600

700

800

Year

63

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 268 Distribution of Effective Doses Among All Workers at MDS Nordion

0

5 0

1 0 0

1 5 0

2 0 0

2 5 0

3 0 0

3 5 0

4 0 0

4 5 0

5 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

64

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

253 Tri-University Meson Facility

The Tri-University Meson facility (TRIUMF) is situated in Vancouver on the campus of the University of British Columbia TRIUMF which began operating in the early 1970s with one cyclotron now has two cyclotrons and associated laboratories for research and radioisotope production The laboratory provides research facilities for Canadian and international users and also produces radioisotopes which are used by medical facilities and by a commercial organization (MDS Nordion) MDS Nordion staff also work at the TRIUMF site however MDS Nordion oversees this work and has its own radiation protection program

Figures 269ndash272 present dose information for the TRIUMF facility from 2001 to 2007 Please note that data sets do not distinguish between doses received by TRIUMF staff and MDS Nordion staff who work on the site as the data for these two groups was submitted collectively to the NDR for the reporting period shown Future data for each group will be submitted separately to the NDR

Note on data for TRIUMF

1 Effective doses are composed of the following reported components bull doses from photons (labeled as ldquoexternalrdquo in the charts) bull neutron doses

Figure 269 Average Dose Trends for TRIUMF (Non-Zero Results Only)

000

020

040

060

080

100

120

140

160

Dos

e (m

Sv)

Neutrons External Effective

Year

65

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 38: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 228 Distribution o f Effective Doses Among A ll Workers at the McClean Lake Operation

0

100

200

300

400

500

600

700

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

33

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

223 McArthur River Operation

Cameco Corporation operates the McArthur River underground mine in north-central Saskatchewan Ore from the mine which began production in 1999 is processed at the Key Lake Mill located 80 km south of McArthur River

Figures 229ndash232 present dose information for the McArthur River operation from 2001 to 2007

Figure 229 Average Dose Trends for the McArthur River Operation (Based o n N on-Zero R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

34

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 230 Average Dose Trends for the McArthur River Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

Figure 231 Collective Dose Trends for the McArthur River Operation

0

200

400

600

800

1000

1200

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Radon gas External Radon progeny Long-lived radioactive dust

Year

35

00

0-000

9

001-5

00

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 232 Distribution o f Effective Doses Among A ll Workers at the McArthur River Operation

0

100

200

300

400

500

600

700

800

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

36

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

224 Key Lake Operation

Cameco Corporation operates mining facilities in Key Lake located in north-central Saskatchewan The Key Lake operation includes two mined-out open pit mines (used for tailings management) a mill and two dry tailings management facilities Mining began in 1983 and ceased in 1997 the mill continued to process ore from the McArthur River mine during the reporting period

Figures 233ndash236 present dose information for the Key Lake operation from 2001 to 2007

Figure 233 Average Dose Trends for the Key Lake Operation (Based o n N on-Zero R esults)

00

20

40

60

80

00

20

40

60

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

37

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

00

20

40

60

80

00

20

40

60

Figure 234 Average Dose Trends for the Key Lake Operation (Based o n A ll Monitoring R esults)

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 235 Collective Dose Trends for the Key Lake Operation

0

100

200

300

400

500

600

700

800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External Radon progeny Long-lived radioactive dust

Year

38

00

0-000

9

001-5

0

501-1

000

gt 1001

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 236 Distribution o f Effective Doses Among A ll Workers at the Key Lake Operation

0

200

400

600

800

1000

1200

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose Range (mSv)

39

se

(mS

v)o

D

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

225 Cigar Lake Operation

Cameco Corporation manages the Cigar Lake underground mine located in northern Saskatchewan at the southern end of Waterbury Lake The mine was under construction at the time of this reportrsquos publication Test mining in ore was carried out in 1991 1992 and 2000

Figures 237ndash240 present dose information for the Cigar Lake operation from

Figure 2 37 Average D ose T rends fo r th e C igar L ake O peration (Based on Non-Zero Results)

2001 to 2007

Year

000

005

010

015

020

025

Long-lived radioactive dust Radon Progeny External Effective

40

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 238 Average Dose Trends for the Cigar Lake Operation (Based on All Monitoring Results)

000

005

010

015

020

025

030

035

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny

External

Effective

Year

Figure 239 Collective Dose Trends for the Cigar Lake Operation

0

50

100

150

200

250

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

External Radon progeny Long-lived radioactive dust

Year

41

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 240 Distribution of Effective Doses Among All Workers at the Cigar Lake Operation

0

200

400

600

800

1000

1200

1400

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

42

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

226 Rabbit Lake Operation

Cameco Corporation owns and operates mining facilities in Rabbit Lake located in north-eastern Saskatchewan Facilities include an underground mine four mined-out open-pit mines a mill and two tailings management facilities Mining and milling began in 1975

Figures 241ndash244 present dose information for the Rabbit Lake operation from 2001 to 2007

Figure 241 Average Dose Trends for the Rabbit Lake Operation (Based on Non-Zero Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

43

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 242 Average Dose Trends for the Rabbit Lake Operation (Based on All Monitoring Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

Figure 243 Collective Dose Trends for the Rabbit Lake Operation

0

200

400

600

800

1000

1200

1400

1600

1800

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Radon gas External Radon progeny Long-lived radioactive dust

Year

44

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

gt300

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 244 Distribution of Effective Doses Among All Workers at the Rabbit Lake Operation

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

900

800

700

600

500

400

300

200

100

0

Dose (mSv)

45

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

23 Uranium Refineries This section presents data for the following two facilities

bull a uranium refining facility in Blind River (Section 231) bull a uranium conversion facility in Port Hope (Section 232)

Graphs indicate the following average doses at each facility from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Note on data for uranium refineries

1 Doses from photons from external sources are measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay and lung counting Historically while these internal doses have been measured they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

231 Blind River Refinery

Cameco Corporation owns and is licensed to operate a uranium refinery in Blind River Ontario The facility which began operating in 1983 converts uranium ore concentrate to uranium trioxide The uranium trioxide is shipped to Camecorsquos uranium conversion facility in Port Hope Ontario where it is processed into uranium dioxide (for use in the fabrication of fuel for nuclear reactors in Canada) or uranium hexafluoride (exported for enrichment and fabrication into fuel for nuclear power reactors around the world)

Figures 245ndash248 present dose information for the Blind River refinery from 2001 to 2007

46

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 245 Average Dose Trends for the Blind River Refinery (Based on Non-Zero Results)

0

05

1

15

2

25

Year

Figure 246 Average Dose Trends for the Blind River Refinery (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

47

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 247 Collective Dose Trends for the Blind River Refinery

0

50

100

150

200

250

300 C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 248 Distribution of Effective Doses Among All Workers at the Blind River Refinery

0

20

40

60

80

100

120

140

160

180

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

48

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

232 Port Hope Conversion Facility

Cameco Corporation owns and is licensed to operate a uranium conversion facility in Port Hope Ontario The facility processes uranium trioxide received from the refinery in Blind River into uranium dioxide and uranium hexafluoride

Figures 249ndash252 present dose information for the Port Hope uranium conversion facility from 2001 to 2007

Figure 249 Average Dose Trends for the Port Hope Conversion Facility (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

49

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 250 Average Dose Trends for the Port Hope Conversion Facility (Based on All Monitoring Results)

0

01

02

03

04

05

06

07

08

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 251 Collective Dose Trends for the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

50

000-0

009

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 252 Distribution of Effective Doses Among All Workers at the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

400

450

500

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

51

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

24 Fuel Fabrication Facilities This section presents data for three nuclear fuel fabrication facilities

bull Two facilities owned and operated by General Electric Canada Inc (Section 241) bull One facility in Port Hope operated by Zircatec Precision Industries (Section 242)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average doses

Notes on data for fuel fabrication facilities

1 Effective doses for the three facilities are composed of the following reported components bull dose from photons (labelled on the charts as ldquoexternalrdquo) bull doses from internal intakes of uranium dust (long-lived radioactive dust) from

uranium in air concentrations (for General Electricrsquos Toronto facility only)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components photon doses and doses from long-lived radioactive dust

241 General Electric Nuclear Fuel Facilities

General Electric Canada Inc operates two nuclear fuel facilities in Ontario

bull At the Toronto facility uranium dioxide pellets are produced from natural or depleted uranium dioxide powder

bull At the Peterborough facility uranium dioxide fuel bundles are created from the pellets produced at the Toronto facility

Figures 253ndash256 present dose information for General Electric Canada Incrsquos fuel fabrication facilities from 2001 to 2007 Graphs do not distinguish between the doses received at the Peterborough facility versus those at the Toronto facility

52

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 253 Average Dose Trends for the General Electric Fuel Facility (Based on Non-Zero Results Only)

0

05

1

15

2

25

3

35

Long Lived Radioactive Dust External Effective

Year

Figure 254 Average Dose Trends for the General Electric Fuel Facility (Based on All Monitoring Results)

0

05

1

15

2

25

3

Long Lived Radioactive Dust External Effective

Year

Dos

e (m

Sv)

Dos

e (m

Sv)

53

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 255 Collective Dose Trends for the General Electric Fuel Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Long Lived Radioactive Dust External

Year

Figure 256 Distribution of Effective Doses among all Workers at the General Electric Fuel Facility

0

10

20

30

40

50

60

70

80

90

100

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

54

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

242 Zircatec Nuclear Fuel Facility

Zircatec Precision Industries Inc operates a nuclear fuel facility in Port Hope Ontario where it makes fuel pellets from uranium dioxide powder received from Port Hopersquos uranium conversion facility The nuclear fuel facility also manufactures fuel bundles for nuclear reactors in Canada

Notes on data for the Zircatec nuclear fuel facility

1 Graphs indicate the following data bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of average effective doses

2 Doses from photons from external sources were measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay Historically although these internal doses have been measured and submitted to the CNSC they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

Figures 257ndash260 present dose information for the Zircatec nuclear fuel facility from 2001 to 2007

Figure 257 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on Non-Zero Results)

0

05

1

15

2

25

3

35

Effe

ctiv

e D

ose

(mS

v)

Year

55

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 258 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

18

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 259 Collective Dose Trends for the Zircatec Nuclear Fuel Facility

0

50

100

150

200

250

300

350

400

450

500

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

56

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 260 Distribution of Effective Doses Among All Workers at the Zircatec Nuclear Fuel Facility

300

Num

ber o

f Wor

kers

250

200

150

100

50

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

57

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

25 Research and Radioisotope Production Facilities This section presents dose information for the following research and radioisotope production facilities from 2001 to 2007

bull Chalk River Laboratories and Whiteshell Laboratories (Section 251) bull A radioisotope production facility operated by MDS Nordion (Section 252) bull The Tri-University Meson Facility (TRIUMF) (Section 253)

Note on data for research and radioisotope production facilities

1 Graphs indicate the following data for each facility bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of effective doses

251 Chalk River Laboratories and Whiteshell Laboratories

Atomic Energy of Canada Limited (AECL) owns and is licensed to operate Chalk River Laboratories and Whiteshell Laboratories

Situated in Renfrew County on the south shore of the Ottawa River the Chalk River Laboratories site hosts the National Research Universal Reactor along with numerous other facilities occupying some 160 buildings in an area of approximately 40 km2 Activities consist of radioisotope production for nuclear medicine testing and development of structural materials in support of power reactor operations fuel fabrication research and radioactive waste management and storage

The Whiteshell Laboratories site is located approximately 10 km west of Pinawa Manitoba and 100 km northeast of Winnipeg on the east bank of the Winnipeg River AECL established the laboratories for nuclear research and testing during the early 1960s and has since discontinued operations which are being decommissioned under a licence from the CNSC

Figures 261ndash264 present dose information for Chalk River Laboratories and Whiteshell Laboratories from 2001 to 2007

Notes on data for Chalk River Laboratories and Whiteshell Laboratories

1 Effective doses are composed of the following reported components bull external doses5 (from both photon and neutron doses) bull tritium doses

Due to issues with AECLrsquos in-house dosimetry management system neutron doses were not reported separately to the NDR during the reporting period As a result external doses from photons and neutrons were totaled The reporting discrepancy has since been rectified

58

5

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of external (photon and neutron) and tritium doses Intakes of other radionuclides occasionally occur and these radionuclides are not included here because their associated doses are very small For this reason certain collective doses in this report may have values slightly lower than the sum of their respective components as listed

Figure 261 Average Dose Trends for Chalk River and Whiteshell Laboratories (Non-Zero Results Only)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Tritium External Effective

Year

59

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 262 Average Dose Trends for Chalk River and Whiteshell Laboratories (All Monitoring Results)

000

020

040

060

080

100

120

Dos

e (m

Sv)

Tritium External Effective

Year

Figure 263 Collective Dose Trends for Chalk River and Whiteshell Laboratories

0

500

1000

1500

2000

2500

3000

3500

Col

lect

ive

Dos

e (p

erso

n- m

Sv)

External Tritium

Year

60

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 264 Distribution of Effective Doses Among All Workers at Chalk River and Whiteshell Laboratories

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

3500

3000

2500

2000

1500

1000

500

Dose (mSv)

61

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

252 MDS Nordion (Nuclear Substance Processing Facility and Canadian Irradiation Centre)

MDS Nordion owns and operates a nuclear substance processing facility in Ottawa Ontario where it processes unsealed radioisotopes and manufactures sealed radiation sources In operation since the early 1970s the facility was purchased by Nordion International in 1991

In cooperation with the Universiteacute du Queacutebecrsquos Institut Armand-Frappier MDS Nordion also operates the Canadian Irradiation Centre which conducts various irradiation services which include training testing and development The centre is located in Laval Quebec on the Universiteacute du Queacutebec campus

Figures 265ndash268 present dose information for MDS Nordionrsquos Ottawa nuclear substance processing facility and for the Canadian Irradiation Centre from 2001 to 2007

Notes on data for MDS Nordionrsquos nuclear substance processing facility and the Canadian Irradiation Centre

1 Doses from photons from external sources were measured and reported to the NDR MDS Nordion also has a routine thyroid monitoring program very occasionally small recordable doses of radiation have occurred from thyroid uptake of iodine The resulting doses have not been historically submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided

Figure 265 Average Dose Trends for MDS Nordion (Based on Non-Zero Results)

0

05

1

15

2

25

Effe

ctiv

e D

ose

(mS

v)

Year

62

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 266 Average Dose Trends for MDS Nordion (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

Figure 267 Collective Dose Trends for MDS Nordion

0

100

200

300

400

500

600

700

800

Year

63

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 268 Distribution of Effective Doses Among All Workers at MDS Nordion

0

5 0

1 0 0

1 5 0

2 0 0

2 5 0

3 0 0

3 5 0

4 0 0

4 5 0

5 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

64

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

253 Tri-University Meson Facility

The Tri-University Meson facility (TRIUMF) is situated in Vancouver on the campus of the University of British Columbia TRIUMF which began operating in the early 1970s with one cyclotron now has two cyclotrons and associated laboratories for research and radioisotope production The laboratory provides research facilities for Canadian and international users and also produces radioisotopes which are used by medical facilities and by a commercial organization (MDS Nordion) MDS Nordion staff also work at the TRIUMF site however MDS Nordion oversees this work and has its own radiation protection program

Figures 269ndash272 present dose information for the TRIUMF facility from 2001 to 2007 Please note that data sets do not distinguish between doses received by TRIUMF staff and MDS Nordion staff who work on the site as the data for these two groups was submitted collectively to the NDR for the reporting period shown Future data for each group will be submitted separately to the NDR

Note on data for TRIUMF

1 Effective doses are composed of the following reported components bull doses from photons (labeled as ldquoexternalrdquo in the charts) bull neutron doses

Figure 269 Average Dose Trends for TRIUMF (Non-Zero Results Only)

000

020

040

060

080

100

120

140

160

Dos

e (m

Sv)

Neutrons External Effective

Year

65

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 39: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

223 McArthur River Operation

Cameco Corporation operates the McArthur River underground mine in north-central Saskatchewan Ore from the mine which began production in 1999 is processed at the Key Lake Mill located 80 km south of McArthur River

Figures 229ndash232 present dose information for the McArthur River operation from 2001 to 2007

Figure 229 Average Dose Trends for the McArthur River Operation (Based o n N on-Zero R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

34

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 230 Average Dose Trends for the McArthur River Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

Figure 231 Collective Dose Trends for the McArthur River Operation

0

200

400

600

800

1000

1200

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Radon gas External Radon progeny Long-lived radioactive dust

Year

35

00

0-000

9

001-5

00

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 232 Distribution o f Effective Doses Among A ll Workers at the McArthur River Operation

0

100

200

300

400

500

600

700

800

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

36

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

224 Key Lake Operation

Cameco Corporation operates mining facilities in Key Lake located in north-central Saskatchewan The Key Lake operation includes two mined-out open pit mines (used for tailings management) a mill and two dry tailings management facilities Mining began in 1983 and ceased in 1997 the mill continued to process ore from the McArthur River mine during the reporting period

Figures 233ndash236 present dose information for the Key Lake operation from 2001 to 2007

Figure 233 Average Dose Trends for the Key Lake Operation (Based o n N on-Zero R esults)

00

20

40

60

80

00

20

40

60

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

37

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

00

20

40

60

80

00

20

40

60

Figure 234 Average Dose Trends for the Key Lake Operation (Based o n A ll Monitoring R esults)

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 235 Collective Dose Trends for the Key Lake Operation

0

100

200

300

400

500

600

700

800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External Radon progeny Long-lived radioactive dust

Year

38

00

0-000

9

001-5

0

501-1

000

gt 1001

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 236 Distribution o f Effective Doses Among A ll Workers at the Key Lake Operation

0

200

400

600

800

1000

1200

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose Range (mSv)

39

se

(mS

v)o

D

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

225 Cigar Lake Operation

Cameco Corporation manages the Cigar Lake underground mine located in northern Saskatchewan at the southern end of Waterbury Lake The mine was under construction at the time of this reportrsquos publication Test mining in ore was carried out in 1991 1992 and 2000

Figures 237ndash240 present dose information for the Cigar Lake operation from

Figure 2 37 Average D ose T rends fo r th e C igar L ake O peration (Based on Non-Zero Results)

2001 to 2007

Year

000

005

010

015

020

025

Long-lived radioactive dust Radon Progeny External Effective

40

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 238 Average Dose Trends for the Cigar Lake Operation (Based on All Monitoring Results)

000

005

010

015

020

025

030

035

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny

External

Effective

Year

Figure 239 Collective Dose Trends for the Cigar Lake Operation

0

50

100

150

200

250

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

External Radon progeny Long-lived radioactive dust

Year

41

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 240 Distribution of Effective Doses Among All Workers at the Cigar Lake Operation

0

200

400

600

800

1000

1200

1400

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

42

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

226 Rabbit Lake Operation

Cameco Corporation owns and operates mining facilities in Rabbit Lake located in north-eastern Saskatchewan Facilities include an underground mine four mined-out open-pit mines a mill and two tailings management facilities Mining and milling began in 1975

Figures 241ndash244 present dose information for the Rabbit Lake operation from 2001 to 2007

Figure 241 Average Dose Trends for the Rabbit Lake Operation (Based on Non-Zero Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

43

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 242 Average Dose Trends for the Rabbit Lake Operation (Based on All Monitoring Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

Figure 243 Collective Dose Trends for the Rabbit Lake Operation

0

200

400

600

800

1000

1200

1400

1600

1800

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Radon gas External Radon progeny Long-lived radioactive dust

Year

44

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

gt300

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 244 Distribution of Effective Doses Among All Workers at the Rabbit Lake Operation

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

900

800

700

600

500

400

300

200

100

0

Dose (mSv)

45

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

23 Uranium Refineries This section presents data for the following two facilities

bull a uranium refining facility in Blind River (Section 231) bull a uranium conversion facility in Port Hope (Section 232)

Graphs indicate the following average doses at each facility from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Note on data for uranium refineries

1 Doses from photons from external sources are measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay and lung counting Historically while these internal doses have been measured they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

231 Blind River Refinery

Cameco Corporation owns and is licensed to operate a uranium refinery in Blind River Ontario The facility which began operating in 1983 converts uranium ore concentrate to uranium trioxide The uranium trioxide is shipped to Camecorsquos uranium conversion facility in Port Hope Ontario where it is processed into uranium dioxide (for use in the fabrication of fuel for nuclear reactors in Canada) or uranium hexafluoride (exported for enrichment and fabrication into fuel for nuclear power reactors around the world)

Figures 245ndash248 present dose information for the Blind River refinery from 2001 to 2007

46

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 245 Average Dose Trends for the Blind River Refinery (Based on Non-Zero Results)

0

05

1

15

2

25

Year

Figure 246 Average Dose Trends for the Blind River Refinery (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

47

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 247 Collective Dose Trends for the Blind River Refinery

0

50

100

150

200

250

300 C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 248 Distribution of Effective Doses Among All Workers at the Blind River Refinery

0

20

40

60

80

100

120

140

160

180

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

48

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

232 Port Hope Conversion Facility

Cameco Corporation owns and is licensed to operate a uranium conversion facility in Port Hope Ontario The facility processes uranium trioxide received from the refinery in Blind River into uranium dioxide and uranium hexafluoride

Figures 249ndash252 present dose information for the Port Hope uranium conversion facility from 2001 to 2007

Figure 249 Average Dose Trends for the Port Hope Conversion Facility (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

49

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 250 Average Dose Trends for the Port Hope Conversion Facility (Based on All Monitoring Results)

0

01

02

03

04

05

06

07

08

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 251 Collective Dose Trends for the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

50

000-0

009

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 252 Distribution of Effective Doses Among All Workers at the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

400

450

500

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

51

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

24 Fuel Fabrication Facilities This section presents data for three nuclear fuel fabrication facilities

bull Two facilities owned and operated by General Electric Canada Inc (Section 241) bull One facility in Port Hope operated by Zircatec Precision Industries (Section 242)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average doses

Notes on data for fuel fabrication facilities

1 Effective doses for the three facilities are composed of the following reported components bull dose from photons (labelled on the charts as ldquoexternalrdquo) bull doses from internal intakes of uranium dust (long-lived radioactive dust) from

uranium in air concentrations (for General Electricrsquos Toronto facility only)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components photon doses and doses from long-lived radioactive dust

241 General Electric Nuclear Fuel Facilities

General Electric Canada Inc operates two nuclear fuel facilities in Ontario

bull At the Toronto facility uranium dioxide pellets are produced from natural or depleted uranium dioxide powder

bull At the Peterborough facility uranium dioxide fuel bundles are created from the pellets produced at the Toronto facility

Figures 253ndash256 present dose information for General Electric Canada Incrsquos fuel fabrication facilities from 2001 to 2007 Graphs do not distinguish between the doses received at the Peterborough facility versus those at the Toronto facility

52

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 253 Average Dose Trends for the General Electric Fuel Facility (Based on Non-Zero Results Only)

0

05

1

15

2

25

3

35

Long Lived Radioactive Dust External Effective

Year

Figure 254 Average Dose Trends for the General Electric Fuel Facility (Based on All Monitoring Results)

0

05

1

15

2

25

3

Long Lived Radioactive Dust External Effective

Year

Dos

e (m

Sv)

Dos

e (m

Sv)

53

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 255 Collective Dose Trends for the General Electric Fuel Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Long Lived Radioactive Dust External

Year

Figure 256 Distribution of Effective Doses among all Workers at the General Electric Fuel Facility

0

10

20

30

40

50

60

70

80

90

100

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

54

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

242 Zircatec Nuclear Fuel Facility

Zircatec Precision Industries Inc operates a nuclear fuel facility in Port Hope Ontario where it makes fuel pellets from uranium dioxide powder received from Port Hopersquos uranium conversion facility The nuclear fuel facility also manufactures fuel bundles for nuclear reactors in Canada

Notes on data for the Zircatec nuclear fuel facility

1 Graphs indicate the following data bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of average effective doses

2 Doses from photons from external sources were measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay Historically although these internal doses have been measured and submitted to the CNSC they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

Figures 257ndash260 present dose information for the Zircatec nuclear fuel facility from 2001 to 2007

Figure 257 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on Non-Zero Results)

0

05

1

15

2

25

3

35

Effe

ctiv

e D

ose

(mS

v)

Year

55

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 258 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

18

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 259 Collective Dose Trends for the Zircatec Nuclear Fuel Facility

0

50

100

150

200

250

300

350

400

450

500

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

56

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 260 Distribution of Effective Doses Among All Workers at the Zircatec Nuclear Fuel Facility

300

Num

ber o

f Wor

kers

250

200

150

100

50

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

57

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

25 Research and Radioisotope Production Facilities This section presents dose information for the following research and radioisotope production facilities from 2001 to 2007

bull Chalk River Laboratories and Whiteshell Laboratories (Section 251) bull A radioisotope production facility operated by MDS Nordion (Section 252) bull The Tri-University Meson Facility (TRIUMF) (Section 253)

Note on data for research and radioisotope production facilities

1 Graphs indicate the following data for each facility bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of effective doses

251 Chalk River Laboratories and Whiteshell Laboratories

Atomic Energy of Canada Limited (AECL) owns and is licensed to operate Chalk River Laboratories and Whiteshell Laboratories

Situated in Renfrew County on the south shore of the Ottawa River the Chalk River Laboratories site hosts the National Research Universal Reactor along with numerous other facilities occupying some 160 buildings in an area of approximately 40 km2 Activities consist of radioisotope production for nuclear medicine testing and development of structural materials in support of power reactor operations fuel fabrication research and radioactive waste management and storage

The Whiteshell Laboratories site is located approximately 10 km west of Pinawa Manitoba and 100 km northeast of Winnipeg on the east bank of the Winnipeg River AECL established the laboratories for nuclear research and testing during the early 1960s and has since discontinued operations which are being decommissioned under a licence from the CNSC

Figures 261ndash264 present dose information for Chalk River Laboratories and Whiteshell Laboratories from 2001 to 2007

Notes on data for Chalk River Laboratories and Whiteshell Laboratories

1 Effective doses are composed of the following reported components bull external doses5 (from both photon and neutron doses) bull tritium doses

Due to issues with AECLrsquos in-house dosimetry management system neutron doses were not reported separately to the NDR during the reporting period As a result external doses from photons and neutrons were totaled The reporting discrepancy has since been rectified

58

5

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of external (photon and neutron) and tritium doses Intakes of other radionuclides occasionally occur and these radionuclides are not included here because their associated doses are very small For this reason certain collective doses in this report may have values slightly lower than the sum of their respective components as listed

Figure 261 Average Dose Trends for Chalk River and Whiteshell Laboratories (Non-Zero Results Only)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Tritium External Effective

Year

59

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 262 Average Dose Trends for Chalk River and Whiteshell Laboratories (All Monitoring Results)

000

020

040

060

080

100

120

Dos

e (m

Sv)

Tritium External Effective

Year

Figure 263 Collective Dose Trends for Chalk River and Whiteshell Laboratories

0

500

1000

1500

2000

2500

3000

3500

Col

lect

ive

Dos

e (p

erso

n- m

Sv)

External Tritium

Year

60

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 264 Distribution of Effective Doses Among All Workers at Chalk River and Whiteshell Laboratories

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

3500

3000

2500

2000

1500

1000

500

Dose (mSv)

61

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

252 MDS Nordion (Nuclear Substance Processing Facility and Canadian Irradiation Centre)

MDS Nordion owns and operates a nuclear substance processing facility in Ottawa Ontario where it processes unsealed radioisotopes and manufactures sealed radiation sources In operation since the early 1970s the facility was purchased by Nordion International in 1991

In cooperation with the Universiteacute du Queacutebecrsquos Institut Armand-Frappier MDS Nordion also operates the Canadian Irradiation Centre which conducts various irradiation services which include training testing and development The centre is located in Laval Quebec on the Universiteacute du Queacutebec campus

Figures 265ndash268 present dose information for MDS Nordionrsquos Ottawa nuclear substance processing facility and for the Canadian Irradiation Centre from 2001 to 2007

Notes on data for MDS Nordionrsquos nuclear substance processing facility and the Canadian Irradiation Centre

1 Doses from photons from external sources were measured and reported to the NDR MDS Nordion also has a routine thyroid monitoring program very occasionally small recordable doses of radiation have occurred from thyroid uptake of iodine The resulting doses have not been historically submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided

Figure 265 Average Dose Trends for MDS Nordion (Based on Non-Zero Results)

0

05

1

15

2

25

Effe

ctiv

e D

ose

(mS

v)

Year

62

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 266 Average Dose Trends for MDS Nordion (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

Figure 267 Collective Dose Trends for MDS Nordion

0

100

200

300

400

500

600

700

800

Year

63

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 268 Distribution of Effective Doses Among All Workers at MDS Nordion

0

5 0

1 0 0

1 5 0

2 0 0

2 5 0

3 0 0

3 5 0

4 0 0

4 5 0

5 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

64

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

253 Tri-University Meson Facility

The Tri-University Meson facility (TRIUMF) is situated in Vancouver on the campus of the University of British Columbia TRIUMF which began operating in the early 1970s with one cyclotron now has two cyclotrons and associated laboratories for research and radioisotope production The laboratory provides research facilities for Canadian and international users and also produces radioisotopes which are used by medical facilities and by a commercial organization (MDS Nordion) MDS Nordion staff also work at the TRIUMF site however MDS Nordion oversees this work and has its own radiation protection program

Figures 269ndash272 present dose information for the TRIUMF facility from 2001 to 2007 Please note that data sets do not distinguish between doses received by TRIUMF staff and MDS Nordion staff who work on the site as the data for these two groups was submitted collectively to the NDR for the reporting period shown Future data for each group will be submitted separately to the NDR

Note on data for TRIUMF

1 Effective doses are composed of the following reported components bull doses from photons (labeled as ldquoexternalrdquo in the charts) bull neutron doses

Figure 269 Average Dose Trends for TRIUMF (Non-Zero Results Only)

000

020

040

060

080

100

120

140

160

Dos

e (m

Sv)

Neutrons External Effective

Year

65

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 40: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 230 Average Dose Trends for the McArthur River Operation (Based o n A ll Monitoring R esults)

000

020

040

060

080

100

120

140

160

180

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective Radon gas

Year

Figure 231 Collective Dose Trends for the McArthur River Operation

0

200

400

600

800

1000

1200

)S

von

-m(p

ers

e os

De

ivtol

lec

C

Radon gas External Radon progeny Long-lived radioactive dust

Year

35

00

0-000

9

001-5

00

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 232 Distribution o f Effective Doses Among A ll Workers at the McArthur River Operation

0

100

200

300

400

500

600

700

800

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

36

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

224 Key Lake Operation

Cameco Corporation operates mining facilities in Key Lake located in north-central Saskatchewan The Key Lake operation includes two mined-out open pit mines (used for tailings management) a mill and two dry tailings management facilities Mining began in 1983 and ceased in 1997 the mill continued to process ore from the McArthur River mine during the reporting period

Figures 233ndash236 present dose information for the Key Lake operation from 2001 to 2007

Figure 233 Average Dose Trends for the Key Lake Operation (Based o n N on-Zero R esults)

00

20

40

60

80

00

20

40

60

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

37

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

00

20

40

60

80

00

20

40

60

Figure 234 Average Dose Trends for the Key Lake Operation (Based o n A ll Monitoring R esults)

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 235 Collective Dose Trends for the Key Lake Operation

0

100

200

300

400

500

600

700

800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External Radon progeny Long-lived radioactive dust

Year

38

00

0-000

9

001-5

0

501-1

000

gt 1001

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 236 Distribution o f Effective Doses Among A ll Workers at the Key Lake Operation

0

200

400

600

800

1000

1200

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose Range (mSv)

39

se

(mS

v)o

D

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

225 Cigar Lake Operation

Cameco Corporation manages the Cigar Lake underground mine located in northern Saskatchewan at the southern end of Waterbury Lake The mine was under construction at the time of this reportrsquos publication Test mining in ore was carried out in 1991 1992 and 2000

Figures 237ndash240 present dose information for the Cigar Lake operation from

Figure 2 37 Average D ose T rends fo r th e C igar L ake O peration (Based on Non-Zero Results)

2001 to 2007

Year

000

005

010

015

020

025

Long-lived radioactive dust Radon Progeny External Effective

40

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 238 Average Dose Trends for the Cigar Lake Operation (Based on All Monitoring Results)

000

005

010

015

020

025

030

035

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny

External

Effective

Year

Figure 239 Collective Dose Trends for the Cigar Lake Operation

0

50

100

150

200

250

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

External Radon progeny Long-lived radioactive dust

Year

41

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 240 Distribution of Effective Doses Among All Workers at the Cigar Lake Operation

0

200

400

600

800

1000

1200

1400

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

42

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

226 Rabbit Lake Operation

Cameco Corporation owns and operates mining facilities in Rabbit Lake located in north-eastern Saskatchewan Facilities include an underground mine four mined-out open-pit mines a mill and two tailings management facilities Mining and milling began in 1975

Figures 241ndash244 present dose information for the Rabbit Lake operation from 2001 to 2007

Figure 241 Average Dose Trends for the Rabbit Lake Operation (Based on Non-Zero Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

43

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 242 Average Dose Trends for the Rabbit Lake Operation (Based on All Monitoring Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

Figure 243 Collective Dose Trends for the Rabbit Lake Operation

0

200

400

600

800

1000

1200

1400

1600

1800

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Radon gas External Radon progeny Long-lived radioactive dust

Year

44

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

gt300

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 244 Distribution of Effective Doses Among All Workers at the Rabbit Lake Operation

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

900

800

700

600

500

400

300

200

100

0

Dose (mSv)

45

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

23 Uranium Refineries This section presents data for the following two facilities

bull a uranium refining facility in Blind River (Section 231) bull a uranium conversion facility in Port Hope (Section 232)

Graphs indicate the following average doses at each facility from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Note on data for uranium refineries

1 Doses from photons from external sources are measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay and lung counting Historically while these internal doses have been measured they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

231 Blind River Refinery

Cameco Corporation owns and is licensed to operate a uranium refinery in Blind River Ontario The facility which began operating in 1983 converts uranium ore concentrate to uranium trioxide The uranium trioxide is shipped to Camecorsquos uranium conversion facility in Port Hope Ontario where it is processed into uranium dioxide (for use in the fabrication of fuel for nuclear reactors in Canada) or uranium hexafluoride (exported for enrichment and fabrication into fuel for nuclear power reactors around the world)

Figures 245ndash248 present dose information for the Blind River refinery from 2001 to 2007

46

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 245 Average Dose Trends for the Blind River Refinery (Based on Non-Zero Results)

0

05

1

15

2

25

Year

Figure 246 Average Dose Trends for the Blind River Refinery (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

47

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 247 Collective Dose Trends for the Blind River Refinery

0

50

100

150

200

250

300 C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 248 Distribution of Effective Doses Among All Workers at the Blind River Refinery

0

20

40

60

80

100

120

140

160

180

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

48

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

232 Port Hope Conversion Facility

Cameco Corporation owns and is licensed to operate a uranium conversion facility in Port Hope Ontario The facility processes uranium trioxide received from the refinery in Blind River into uranium dioxide and uranium hexafluoride

Figures 249ndash252 present dose information for the Port Hope uranium conversion facility from 2001 to 2007

Figure 249 Average Dose Trends for the Port Hope Conversion Facility (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

49

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 250 Average Dose Trends for the Port Hope Conversion Facility (Based on All Monitoring Results)

0

01

02

03

04

05

06

07

08

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 251 Collective Dose Trends for the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

50

000-0

009

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 252 Distribution of Effective Doses Among All Workers at the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

400

450

500

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

51

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

24 Fuel Fabrication Facilities This section presents data for three nuclear fuel fabrication facilities

bull Two facilities owned and operated by General Electric Canada Inc (Section 241) bull One facility in Port Hope operated by Zircatec Precision Industries (Section 242)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average doses

Notes on data for fuel fabrication facilities

1 Effective doses for the three facilities are composed of the following reported components bull dose from photons (labelled on the charts as ldquoexternalrdquo) bull doses from internal intakes of uranium dust (long-lived radioactive dust) from

uranium in air concentrations (for General Electricrsquos Toronto facility only)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components photon doses and doses from long-lived radioactive dust

241 General Electric Nuclear Fuel Facilities

General Electric Canada Inc operates two nuclear fuel facilities in Ontario

bull At the Toronto facility uranium dioxide pellets are produced from natural or depleted uranium dioxide powder

bull At the Peterborough facility uranium dioxide fuel bundles are created from the pellets produced at the Toronto facility

Figures 253ndash256 present dose information for General Electric Canada Incrsquos fuel fabrication facilities from 2001 to 2007 Graphs do not distinguish between the doses received at the Peterborough facility versus those at the Toronto facility

52

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 253 Average Dose Trends for the General Electric Fuel Facility (Based on Non-Zero Results Only)

0

05

1

15

2

25

3

35

Long Lived Radioactive Dust External Effective

Year

Figure 254 Average Dose Trends for the General Electric Fuel Facility (Based on All Monitoring Results)

0

05

1

15

2

25

3

Long Lived Radioactive Dust External Effective

Year

Dos

e (m

Sv)

Dos

e (m

Sv)

53

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 255 Collective Dose Trends for the General Electric Fuel Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Long Lived Radioactive Dust External

Year

Figure 256 Distribution of Effective Doses among all Workers at the General Electric Fuel Facility

0

10

20

30

40

50

60

70

80

90

100

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

54

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

242 Zircatec Nuclear Fuel Facility

Zircatec Precision Industries Inc operates a nuclear fuel facility in Port Hope Ontario where it makes fuel pellets from uranium dioxide powder received from Port Hopersquos uranium conversion facility The nuclear fuel facility also manufactures fuel bundles for nuclear reactors in Canada

Notes on data for the Zircatec nuclear fuel facility

1 Graphs indicate the following data bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of average effective doses

2 Doses from photons from external sources were measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay Historically although these internal doses have been measured and submitted to the CNSC they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

Figures 257ndash260 present dose information for the Zircatec nuclear fuel facility from 2001 to 2007

Figure 257 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on Non-Zero Results)

0

05

1

15

2

25

3

35

Effe

ctiv

e D

ose

(mS

v)

Year

55

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 258 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

18

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 259 Collective Dose Trends for the Zircatec Nuclear Fuel Facility

0

50

100

150

200

250

300

350

400

450

500

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

56

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 260 Distribution of Effective Doses Among All Workers at the Zircatec Nuclear Fuel Facility

300

Num

ber o

f Wor

kers

250

200

150

100

50

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

57

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

25 Research and Radioisotope Production Facilities This section presents dose information for the following research and radioisotope production facilities from 2001 to 2007

bull Chalk River Laboratories and Whiteshell Laboratories (Section 251) bull A radioisotope production facility operated by MDS Nordion (Section 252) bull The Tri-University Meson Facility (TRIUMF) (Section 253)

Note on data for research and radioisotope production facilities

1 Graphs indicate the following data for each facility bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of effective doses

251 Chalk River Laboratories and Whiteshell Laboratories

Atomic Energy of Canada Limited (AECL) owns and is licensed to operate Chalk River Laboratories and Whiteshell Laboratories

Situated in Renfrew County on the south shore of the Ottawa River the Chalk River Laboratories site hosts the National Research Universal Reactor along with numerous other facilities occupying some 160 buildings in an area of approximately 40 km2 Activities consist of radioisotope production for nuclear medicine testing and development of structural materials in support of power reactor operations fuel fabrication research and radioactive waste management and storage

The Whiteshell Laboratories site is located approximately 10 km west of Pinawa Manitoba and 100 km northeast of Winnipeg on the east bank of the Winnipeg River AECL established the laboratories for nuclear research and testing during the early 1960s and has since discontinued operations which are being decommissioned under a licence from the CNSC

Figures 261ndash264 present dose information for Chalk River Laboratories and Whiteshell Laboratories from 2001 to 2007

Notes on data for Chalk River Laboratories and Whiteshell Laboratories

1 Effective doses are composed of the following reported components bull external doses5 (from both photon and neutron doses) bull tritium doses

Due to issues with AECLrsquos in-house dosimetry management system neutron doses were not reported separately to the NDR during the reporting period As a result external doses from photons and neutrons were totaled The reporting discrepancy has since been rectified

58

5

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of external (photon and neutron) and tritium doses Intakes of other radionuclides occasionally occur and these radionuclides are not included here because their associated doses are very small For this reason certain collective doses in this report may have values slightly lower than the sum of their respective components as listed

Figure 261 Average Dose Trends for Chalk River and Whiteshell Laboratories (Non-Zero Results Only)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Tritium External Effective

Year

59

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 262 Average Dose Trends for Chalk River and Whiteshell Laboratories (All Monitoring Results)

000

020

040

060

080

100

120

Dos

e (m

Sv)

Tritium External Effective

Year

Figure 263 Collective Dose Trends for Chalk River and Whiteshell Laboratories

0

500

1000

1500

2000

2500

3000

3500

Col

lect

ive

Dos

e (p

erso

n- m

Sv)

External Tritium

Year

60

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 264 Distribution of Effective Doses Among All Workers at Chalk River and Whiteshell Laboratories

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

3500

3000

2500

2000

1500

1000

500

Dose (mSv)

61

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

252 MDS Nordion (Nuclear Substance Processing Facility and Canadian Irradiation Centre)

MDS Nordion owns and operates a nuclear substance processing facility in Ottawa Ontario where it processes unsealed radioisotopes and manufactures sealed radiation sources In operation since the early 1970s the facility was purchased by Nordion International in 1991

In cooperation with the Universiteacute du Queacutebecrsquos Institut Armand-Frappier MDS Nordion also operates the Canadian Irradiation Centre which conducts various irradiation services which include training testing and development The centre is located in Laval Quebec on the Universiteacute du Queacutebec campus

Figures 265ndash268 present dose information for MDS Nordionrsquos Ottawa nuclear substance processing facility and for the Canadian Irradiation Centre from 2001 to 2007

Notes on data for MDS Nordionrsquos nuclear substance processing facility and the Canadian Irradiation Centre

1 Doses from photons from external sources were measured and reported to the NDR MDS Nordion also has a routine thyroid monitoring program very occasionally small recordable doses of radiation have occurred from thyroid uptake of iodine The resulting doses have not been historically submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided

Figure 265 Average Dose Trends for MDS Nordion (Based on Non-Zero Results)

0

05

1

15

2

25

Effe

ctiv

e D

ose

(mS

v)

Year

62

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 266 Average Dose Trends for MDS Nordion (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

Figure 267 Collective Dose Trends for MDS Nordion

0

100

200

300

400

500

600

700

800

Year

63

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 268 Distribution of Effective Doses Among All Workers at MDS Nordion

0

5 0

1 0 0

1 5 0

2 0 0

2 5 0

3 0 0

3 5 0

4 0 0

4 5 0

5 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

64

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

253 Tri-University Meson Facility

The Tri-University Meson facility (TRIUMF) is situated in Vancouver on the campus of the University of British Columbia TRIUMF which began operating in the early 1970s with one cyclotron now has two cyclotrons and associated laboratories for research and radioisotope production The laboratory provides research facilities for Canadian and international users and also produces radioisotopes which are used by medical facilities and by a commercial organization (MDS Nordion) MDS Nordion staff also work at the TRIUMF site however MDS Nordion oversees this work and has its own radiation protection program

Figures 269ndash272 present dose information for the TRIUMF facility from 2001 to 2007 Please note that data sets do not distinguish between doses received by TRIUMF staff and MDS Nordion staff who work on the site as the data for these two groups was submitted collectively to the NDR for the reporting period shown Future data for each group will be submitted separately to the NDR

Note on data for TRIUMF

1 Effective doses are composed of the following reported components bull doses from photons (labeled as ldquoexternalrdquo in the charts) bull neutron doses

Figure 269 Average Dose Trends for TRIUMF (Non-Zero Results Only)

000

020

040

060

080

100

120

140

160

Dos

e (m

Sv)

Neutrons External Effective

Year

65

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 41: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

00

0-000

9

001-5

00

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 232 Distribution o f Effective Doses Among A ll Workers at the McArthur River Operation

0

100

200

300

400

500

600

700

800

Num

ber o

f Wor

kers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

36

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

224 Key Lake Operation

Cameco Corporation operates mining facilities in Key Lake located in north-central Saskatchewan The Key Lake operation includes two mined-out open pit mines (used for tailings management) a mill and two dry tailings management facilities Mining began in 1983 and ceased in 1997 the mill continued to process ore from the McArthur River mine during the reporting period

Figures 233ndash236 present dose information for the Key Lake operation from 2001 to 2007

Figure 233 Average Dose Trends for the Key Lake Operation (Based o n N on-Zero R esults)

00

20

40

60

80

00

20

40

60

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

37

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

00

20

40

60

80

00

20

40

60

Figure 234 Average Dose Trends for the Key Lake Operation (Based o n A ll Monitoring R esults)

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 235 Collective Dose Trends for the Key Lake Operation

0

100

200

300

400

500

600

700

800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External Radon progeny Long-lived radioactive dust

Year

38

00

0-000

9

001-5

0

501-1

000

gt 1001

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 236 Distribution o f Effective Doses Among A ll Workers at the Key Lake Operation

0

200

400

600

800

1000

1200

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose Range (mSv)

39

se

(mS

v)o

D

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

225 Cigar Lake Operation

Cameco Corporation manages the Cigar Lake underground mine located in northern Saskatchewan at the southern end of Waterbury Lake The mine was under construction at the time of this reportrsquos publication Test mining in ore was carried out in 1991 1992 and 2000

Figures 237ndash240 present dose information for the Cigar Lake operation from

Figure 2 37 Average D ose T rends fo r th e C igar L ake O peration (Based on Non-Zero Results)

2001 to 2007

Year

000

005

010

015

020

025

Long-lived radioactive dust Radon Progeny External Effective

40

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 238 Average Dose Trends for the Cigar Lake Operation (Based on All Monitoring Results)

000

005

010

015

020

025

030

035

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny

External

Effective

Year

Figure 239 Collective Dose Trends for the Cigar Lake Operation

0

50

100

150

200

250

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

External Radon progeny Long-lived radioactive dust

Year

41

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 240 Distribution of Effective Doses Among All Workers at the Cigar Lake Operation

0

200

400

600

800

1000

1200

1400

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

42

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

226 Rabbit Lake Operation

Cameco Corporation owns and operates mining facilities in Rabbit Lake located in north-eastern Saskatchewan Facilities include an underground mine four mined-out open-pit mines a mill and two tailings management facilities Mining and milling began in 1975

Figures 241ndash244 present dose information for the Rabbit Lake operation from 2001 to 2007

Figure 241 Average Dose Trends for the Rabbit Lake Operation (Based on Non-Zero Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

43

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 242 Average Dose Trends for the Rabbit Lake Operation (Based on All Monitoring Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

Figure 243 Collective Dose Trends for the Rabbit Lake Operation

0

200

400

600

800

1000

1200

1400

1600

1800

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Radon gas External Radon progeny Long-lived radioactive dust

Year

44

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

gt300

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 244 Distribution of Effective Doses Among All Workers at the Rabbit Lake Operation

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

900

800

700

600

500

400

300

200

100

0

Dose (mSv)

45

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

23 Uranium Refineries This section presents data for the following two facilities

bull a uranium refining facility in Blind River (Section 231) bull a uranium conversion facility in Port Hope (Section 232)

Graphs indicate the following average doses at each facility from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Note on data for uranium refineries

1 Doses from photons from external sources are measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay and lung counting Historically while these internal doses have been measured they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

231 Blind River Refinery

Cameco Corporation owns and is licensed to operate a uranium refinery in Blind River Ontario The facility which began operating in 1983 converts uranium ore concentrate to uranium trioxide The uranium trioxide is shipped to Camecorsquos uranium conversion facility in Port Hope Ontario where it is processed into uranium dioxide (for use in the fabrication of fuel for nuclear reactors in Canada) or uranium hexafluoride (exported for enrichment and fabrication into fuel for nuclear power reactors around the world)

Figures 245ndash248 present dose information for the Blind River refinery from 2001 to 2007

46

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 245 Average Dose Trends for the Blind River Refinery (Based on Non-Zero Results)

0

05

1

15

2

25

Year

Figure 246 Average Dose Trends for the Blind River Refinery (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

47

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 247 Collective Dose Trends for the Blind River Refinery

0

50

100

150

200

250

300 C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 248 Distribution of Effective Doses Among All Workers at the Blind River Refinery

0

20

40

60

80

100

120

140

160

180

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

48

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

232 Port Hope Conversion Facility

Cameco Corporation owns and is licensed to operate a uranium conversion facility in Port Hope Ontario The facility processes uranium trioxide received from the refinery in Blind River into uranium dioxide and uranium hexafluoride

Figures 249ndash252 present dose information for the Port Hope uranium conversion facility from 2001 to 2007

Figure 249 Average Dose Trends for the Port Hope Conversion Facility (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

49

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 250 Average Dose Trends for the Port Hope Conversion Facility (Based on All Monitoring Results)

0

01

02

03

04

05

06

07

08

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 251 Collective Dose Trends for the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

50

000-0

009

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 252 Distribution of Effective Doses Among All Workers at the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

400

450

500

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

51

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

24 Fuel Fabrication Facilities This section presents data for three nuclear fuel fabrication facilities

bull Two facilities owned and operated by General Electric Canada Inc (Section 241) bull One facility in Port Hope operated by Zircatec Precision Industries (Section 242)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average doses

Notes on data for fuel fabrication facilities

1 Effective doses for the three facilities are composed of the following reported components bull dose from photons (labelled on the charts as ldquoexternalrdquo) bull doses from internal intakes of uranium dust (long-lived radioactive dust) from

uranium in air concentrations (for General Electricrsquos Toronto facility only)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components photon doses and doses from long-lived radioactive dust

241 General Electric Nuclear Fuel Facilities

General Electric Canada Inc operates two nuclear fuel facilities in Ontario

bull At the Toronto facility uranium dioxide pellets are produced from natural or depleted uranium dioxide powder

bull At the Peterborough facility uranium dioxide fuel bundles are created from the pellets produced at the Toronto facility

Figures 253ndash256 present dose information for General Electric Canada Incrsquos fuel fabrication facilities from 2001 to 2007 Graphs do not distinguish between the doses received at the Peterborough facility versus those at the Toronto facility

52

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 253 Average Dose Trends for the General Electric Fuel Facility (Based on Non-Zero Results Only)

0

05

1

15

2

25

3

35

Long Lived Radioactive Dust External Effective

Year

Figure 254 Average Dose Trends for the General Electric Fuel Facility (Based on All Monitoring Results)

0

05

1

15

2

25

3

Long Lived Radioactive Dust External Effective

Year

Dos

e (m

Sv)

Dos

e (m

Sv)

53

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 255 Collective Dose Trends for the General Electric Fuel Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Long Lived Radioactive Dust External

Year

Figure 256 Distribution of Effective Doses among all Workers at the General Electric Fuel Facility

0

10

20

30

40

50

60

70

80

90

100

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

54

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

242 Zircatec Nuclear Fuel Facility

Zircatec Precision Industries Inc operates a nuclear fuel facility in Port Hope Ontario where it makes fuel pellets from uranium dioxide powder received from Port Hopersquos uranium conversion facility The nuclear fuel facility also manufactures fuel bundles for nuclear reactors in Canada

Notes on data for the Zircatec nuclear fuel facility

1 Graphs indicate the following data bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of average effective doses

2 Doses from photons from external sources were measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay Historically although these internal doses have been measured and submitted to the CNSC they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

Figures 257ndash260 present dose information for the Zircatec nuclear fuel facility from 2001 to 2007

Figure 257 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on Non-Zero Results)

0

05

1

15

2

25

3

35

Effe

ctiv

e D

ose

(mS

v)

Year

55

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 258 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

18

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 259 Collective Dose Trends for the Zircatec Nuclear Fuel Facility

0

50

100

150

200

250

300

350

400

450

500

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

56

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 260 Distribution of Effective Doses Among All Workers at the Zircatec Nuclear Fuel Facility

300

Num

ber o

f Wor

kers

250

200

150

100

50

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

57

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

25 Research and Radioisotope Production Facilities This section presents dose information for the following research and radioisotope production facilities from 2001 to 2007

bull Chalk River Laboratories and Whiteshell Laboratories (Section 251) bull A radioisotope production facility operated by MDS Nordion (Section 252) bull The Tri-University Meson Facility (TRIUMF) (Section 253)

Note on data for research and radioisotope production facilities

1 Graphs indicate the following data for each facility bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of effective doses

251 Chalk River Laboratories and Whiteshell Laboratories

Atomic Energy of Canada Limited (AECL) owns and is licensed to operate Chalk River Laboratories and Whiteshell Laboratories

Situated in Renfrew County on the south shore of the Ottawa River the Chalk River Laboratories site hosts the National Research Universal Reactor along with numerous other facilities occupying some 160 buildings in an area of approximately 40 km2 Activities consist of radioisotope production for nuclear medicine testing and development of structural materials in support of power reactor operations fuel fabrication research and radioactive waste management and storage

The Whiteshell Laboratories site is located approximately 10 km west of Pinawa Manitoba and 100 km northeast of Winnipeg on the east bank of the Winnipeg River AECL established the laboratories for nuclear research and testing during the early 1960s and has since discontinued operations which are being decommissioned under a licence from the CNSC

Figures 261ndash264 present dose information for Chalk River Laboratories and Whiteshell Laboratories from 2001 to 2007

Notes on data for Chalk River Laboratories and Whiteshell Laboratories

1 Effective doses are composed of the following reported components bull external doses5 (from both photon and neutron doses) bull tritium doses

Due to issues with AECLrsquos in-house dosimetry management system neutron doses were not reported separately to the NDR during the reporting period As a result external doses from photons and neutrons were totaled The reporting discrepancy has since been rectified

58

5

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of external (photon and neutron) and tritium doses Intakes of other radionuclides occasionally occur and these radionuclides are not included here because their associated doses are very small For this reason certain collective doses in this report may have values slightly lower than the sum of their respective components as listed

Figure 261 Average Dose Trends for Chalk River and Whiteshell Laboratories (Non-Zero Results Only)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Tritium External Effective

Year

59

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 262 Average Dose Trends for Chalk River and Whiteshell Laboratories (All Monitoring Results)

000

020

040

060

080

100

120

Dos

e (m

Sv)

Tritium External Effective

Year

Figure 263 Collective Dose Trends for Chalk River and Whiteshell Laboratories

0

500

1000

1500

2000

2500

3000

3500

Col

lect

ive

Dos

e (p

erso

n- m

Sv)

External Tritium

Year

60

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 264 Distribution of Effective Doses Among All Workers at Chalk River and Whiteshell Laboratories

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

3500

3000

2500

2000

1500

1000

500

Dose (mSv)

61

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

252 MDS Nordion (Nuclear Substance Processing Facility and Canadian Irradiation Centre)

MDS Nordion owns and operates a nuclear substance processing facility in Ottawa Ontario where it processes unsealed radioisotopes and manufactures sealed radiation sources In operation since the early 1970s the facility was purchased by Nordion International in 1991

In cooperation with the Universiteacute du Queacutebecrsquos Institut Armand-Frappier MDS Nordion also operates the Canadian Irradiation Centre which conducts various irradiation services which include training testing and development The centre is located in Laval Quebec on the Universiteacute du Queacutebec campus

Figures 265ndash268 present dose information for MDS Nordionrsquos Ottawa nuclear substance processing facility and for the Canadian Irradiation Centre from 2001 to 2007

Notes on data for MDS Nordionrsquos nuclear substance processing facility and the Canadian Irradiation Centre

1 Doses from photons from external sources were measured and reported to the NDR MDS Nordion also has a routine thyroid monitoring program very occasionally small recordable doses of radiation have occurred from thyroid uptake of iodine The resulting doses have not been historically submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided

Figure 265 Average Dose Trends for MDS Nordion (Based on Non-Zero Results)

0

05

1

15

2

25

Effe

ctiv

e D

ose

(mS

v)

Year

62

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 266 Average Dose Trends for MDS Nordion (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

Figure 267 Collective Dose Trends for MDS Nordion

0

100

200

300

400

500

600

700

800

Year

63

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 268 Distribution of Effective Doses Among All Workers at MDS Nordion

0

5 0

1 0 0

1 5 0

2 0 0

2 5 0

3 0 0

3 5 0

4 0 0

4 5 0

5 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

64

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

253 Tri-University Meson Facility

The Tri-University Meson facility (TRIUMF) is situated in Vancouver on the campus of the University of British Columbia TRIUMF which began operating in the early 1970s with one cyclotron now has two cyclotrons and associated laboratories for research and radioisotope production The laboratory provides research facilities for Canadian and international users and also produces radioisotopes which are used by medical facilities and by a commercial organization (MDS Nordion) MDS Nordion staff also work at the TRIUMF site however MDS Nordion oversees this work and has its own radiation protection program

Figures 269ndash272 present dose information for the TRIUMF facility from 2001 to 2007 Please note that data sets do not distinguish between doses received by TRIUMF staff and MDS Nordion staff who work on the site as the data for these two groups was submitted collectively to the NDR for the reporting period shown Future data for each group will be submitted separately to the NDR

Note on data for TRIUMF

1 Effective doses are composed of the following reported components bull doses from photons (labeled as ldquoexternalrdquo in the charts) bull neutron doses

Figure 269 Average Dose Trends for TRIUMF (Non-Zero Results Only)

000

020

040

060

080

100

120

140

160

Dos

e (m

Sv)

Neutrons External Effective

Year

65

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 42: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

224 Key Lake Operation

Cameco Corporation operates mining facilities in Key Lake located in north-central Saskatchewan The Key Lake operation includes two mined-out open pit mines (used for tailings management) a mill and two dry tailings management facilities Mining began in 1983 and ceased in 1997 the mill continued to process ore from the McArthur River mine during the reporting period

Figures 233ndash236 present dose information for the Key Lake operation from 2001 to 2007

Figure 233 Average Dose Trends for the Key Lake Operation (Based o n N on-Zero R esults)

00

20

40

60

80

00

20

40

60

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

37

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

00

20

40

60

80

00

20

40

60

Figure 234 Average Dose Trends for the Key Lake Operation (Based o n A ll Monitoring R esults)

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 235 Collective Dose Trends for the Key Lake Operation

0

100

200

300

400

500

600

700

800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External Radon progeny Long-lived radioactive dust

Year

38

00

0-000

9

001-5

0

501-1

000

gt 1001

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 236 Distribution o f Effective Doses Among A ll Workers at the Key Lake Operation

0

200

400

600

800

1000

1200

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose Range (mSv)

39

se

(mS

v)o

D

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

225 Cigar Lake Operation

Cameco Corporation manages the Cigar Lake underground mine located in northern Saskatchewan at the southern end of Waterbury Lake The mine was under construction at the time of this reportrsquos publication Test mining in ore was carried out in 1991 1992 and 2000

Figures 237ndash240 present dose information for the Cigar Lake operation from

Figure 2 37 Average D ose T rends fo r th e C igar L ake O peration (Based on Non-Zero Results)

2001 to 2007

Year

000

005

010

015

020

025

Long-lived radioactive dust Radon Progeny External Effective

40

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 238 Average Dose Trends for the Cigar Lake Operation (Based on All Monitoring Results)

000

005

010

015

020

025

030

035

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny

External

Effective

Year

Figure 239 Collective Dose Trends for the Cigar Lake Operation

0

50

100

150

200

250

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

External Radon progeny Long-lived radioactive dust

Year

41

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 240 Distribution of Effective Doses Among All Workers at the Cigar Lake Operation

0

200

400

600

800

1000

1200

1400

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

42

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

226 Rabbit Lake Operation

Cameco Corporation owns and operates mining facilities in Rabbit Lake located in north-eastern Saskatchewan Facilities include an underground mine four mined-out open-pit mines a mill and two tailings management facilities Mining and milling began in 1975

Figures 241ndash244 present dose information for the Rabbit Lake operation from 2001 to 2007

Figure 241 Average Dose Trends for the Rabbit Lake Operation (Based on Non-Zero Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

43

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 242 Average Dose Trends for the Rabbit Lake Operation (Based on All Monitoring Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

Figure 243 Collective Dose Trends for the Rabbit Lake Operation

0

200

400

600

800

1000

1200

1400

1600

1800

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Radon gas External Radon progeny Long-lived radioactive dust

Year

44

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

gt300

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 244 Distribution of Effective Doses Among All Workers at the Rabbit Lake Operation

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

900

800

700

600

500

400

300

200

100

0

Dose (mSv)

45

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

23 Uranium Refineries This section presents data for the following two facilities

bull a uranium refining facility in Blind River (Section 231) bull a uranium conversion facility in Port Hope (Section 232)

Graphs indicate the following average doses at each facility from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Note on data for uranium refineries

1 Doses from photons from external sources are measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay and lung counting Historically while these internal doses have been measured they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

231 Blind River Refinery

Cameco Corporation owns and is licensed to operate a uranium refinery in Blind River Ontario The facility which began operating in 1983 converts uranium ore concentrate to uranium trioxide The uranium trioxide is shipped to Camecorsquos uranium conversion facility in Port Hope Ontario where it is processed into uranium dioxide (for use in the fabrication of fuel for nuclear reactors in Canada) or uranium hexafluoride (exported for enrichment and fabrication into fuel for nuclear power reactors around the world)

Figures 245ndash248 present dose information for the Blind River refinery from 2001 to 2007

46

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 245 Average Dose Trends for the Blind River Refinery (Based on Non-Zero Results)

0

05

1

15

2

25

Year

Figure 246 Average Dose Trends for the Blind River Refinery (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

47

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 247 Collective Dose Trends for the Blind River Refinery

0

50

100

150

200

250

300 C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 248 Distribution of Effective Doses Among All Workers at the Blind River Refinery

0

20

40

60

80

100

120

140

160

180

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

48

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

232 Port Hope Conversion Facility

Cameco Corporation owns and is licensed to operate a uranium conversion facility in Port Hope Ontario The facility processes uranium trioxide received from the refinery in Blind River into uranium dioxide and uranium hexafluoride

Figures 249ndash252 present dose information for the Port Hope uranium conversion facility from 2001 to 2007

Figure 249 Average Dose Trends for the Port Hope Conversion Facility (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

49

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 250 Average Dose Trends for the Port Hope Conversion Facility (Based on All Monitoring Results)

0

01

02

03

04

05

06

07

08

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 251 Collective Dose Trends for the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

50

000-0

009

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 252 Distribution of Effective Doses Among All Workers at the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

400

450

500

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

51

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

24 Fuel Fabrication Facilities This section presents data for three nuclear fuel fabrication facilities

bull Two facilities owned and operated by General Electric Canada Inc (Section 241) bull One facility in Port Hope operated by Zircatec Precision Industries (Section 242)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average doses

Notes on data for fuel fabrication facilities

1 Effective doses for the three facilities are composed of the following reported components bull dose from photons (labelled on the charts as ldquoexternalrdquo) bull doses from internal intakes of uranium dust (long-lived radioactive dust) from

uranium in air concentrations (for General Electricrsquos Toronto facility only)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components photon doses and doses from long-lived radioactive dust

241 General Electric Nuclear Fuel Facilities

General Electric Canada Inc operates two nuclear fuel facilities in Ontario

bull At the Toronto facility uranium dioxide pellets are produced from natural or depleted uranium dioxide powder

bull At the Peterborough facility uranium dioxide fuel bundles are created from the pellets produced at the Toronto facility

Figures 253ndash256 present dose information for General Electric Canada Incrsquos fuel fabrication facilities from 2001 to 2007 Graphs do not distinguish between the doses received at the Peterborough facility versus those at the Toronto facility

52

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 253 Average Dose Trends for the General Electric Fuel Facility (Based on Non-Zero Results Only)

0

05

1

15

2

25

3

35

Long Lived Radioactive Dust External Effective

Year

Figure 254 Average Dose Trends for the General Electric Fuel Facility (Based on All Monitoring Results)

0

05

1

15

2

25

3

Long Lived Radioactive Dust External Effective

Year

Dos

e (m

Sv)

Dos

e (m

Sv)

53

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 255 Collective Dose Trends for the General Electric Fuel Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Long Lived Radioactive Dust External

Year

Figure 256 Distribution of Effective Doses among all Workers at the General Electric Fuel Facility

0

10

20

30

40

50

60

70

80

90

100

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

54

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

242 Zircatec Nuclear Fuel Facility

Zircatec Precision Industries Inc operates a nuclear fuel facility in Port Hope Ontario where it makes fuel pellets from uranium dioxide powder received from Port Hopersquos uranium conversion facility The nuclear fuel facility also manufactures fuel bundles for nuclear reactors in Canada

Notes on data for the Zircatec nuclear fuel facility

1 Graphs indicate the following data bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of average effective doses

2 Doses from photons from external sources were measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay Historically although these internal doses have been measured and submitted to the CNSC they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

Figures 257ndash260 present dose information for the Zircatec nuclear fuel facility from 2001 to 2007

Figure 257 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on Non-Zero Results)

0

05

1

15

2

25

3

35

Effe

ctiv

e D

ose

(mS

v)

Year

55

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 258 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

18

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 259 Collective Dose Trends for the Zircatec Nuclear Fuel Facility

0

50

100

150

200

250

300

350

400

450

500

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

56

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 260 Distribution of Effective Doses Among All Workers at the Zircatec Nuclear Fuel Facility

300

Num

ber o

f Wor

kers

250

200

150

100

50

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

57

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

25 Research and Radioisotope Production Facilities This section presents dose information for the following research and radioisotope production facilities from 2001 to 2007

bull Chalk River Laboratories and Whiteshell Laboratories (Section 251) bull A radioisotope production facility operated by MDS Nordion (Section 252) bull The Tri-University Meson Facility (TRIUMF) (Section 253)

Note on data for research and radioisotope production facilities

1 Graphs indicate the following data for each facility bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of effective doses

251 Chalk River Laboratories and Whiteshell Laboratories

Atomic Energy of Canada Limited (AECL) owns and is licensed to operate Chalk River Laboratories and Whiteshell Laboratories

Situated in Renfrew County on the south shore of the Ottawa River the Chalk River Laboratories site hosts the National Research Universal Reactor along with numerous other facilities occupying some 160 buildings in an area of approximately 40 km2 Activities consist of radioisotope production for nuclear medicine testing and development of structural materials in support of power reactor operations fuel fabrication research and radioactive waste management and storage

The Whiteshell Laboratories site is located approximately 10 km west of Pinawa Manitoba and 100 km northeast of Winnipeg on the east bank of the Winnipeg River AECL established the laboratories for nuclear research and testing during the early 1960s and has since discontinued operations which are being decommissioned under a licence from the CNSC

Figures 261ndash264 present dose information for Chalk River Laboratories and Whiteshell Laboratories from 2001 to 2007

Notes on data for Chalk River Laboratories and Whiteshell Laboratories

1 Effective doses are composed of the following reported components bull external doses5 (from both photon and neutron doses) bull tritium doses

Due to issues with AECLrsquos in-house dosimetry management system neutron doses were not reported separately to the NDR during the reporting period As a result external doses from photons and neutrons were totaled The reporting discrepancy has since been rectified

58

5

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of external (photon and neutron) and tritium doses Intakes of other radionuclides occasionally occur and these radionuclides are not included here because their associated doses are very small For this reason certain collective doses in this report may have values slightly lower than the sum of their respective components as listed

Figure 261 Average Dose Trends for Chalk River and Whiteshell Laboratories (Non-Zero Results Only)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Tritium External Effective

Year

59

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 262 Average Dose Trends for Chalk River and Whiteshell Laboratories (All Monitoring Results)

000

020

040

060

080

100

120

Dos

e (m

Sv)

Tritium External Effective

Year

Figure 263 Collective Dose Trends for Chalk River and Whiteshell Laboratories

0

500

1000

1500

2000

2500

3000

3500

Col

lect

ive

Dos

e (p

erso

n- m

Sv)

External Tritium

Year

60

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 264 Distribution of Effective Doses Among All Workers at Chalk River and Whiteshell Laboratories

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

3500

3000

2500

2000

1500

1000

500

Dose (mSv)

61

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

252 MDS Nordion (Nuclear Substance Processing Facility and Canadian Irradiation Centre)

MDS Nordion owns and operates a nuclear substance processing facility in Ottawa Ontario where it processes unsealed radioisotopes and manufactures sealed radiation sources In operation since the early 1970s the facility was purchased by Nordion International in 1991

In cooperation with the Universiteacute du Queacutebecrsquos Institut Armand-Frappier MDS Nordion also operates the Canadian Irradiation Centre which conducts various irradiation services which include training testing and development The centre is located in Laval Quebec on the Universiteacute du Queacutebec campus

Figures 265ndash268 present dose information for MDS Nordionrsquos Ottawa nuclear substance processing facility and for the Canadian Irradiation Centre from 2001 to 2007

Notes on data for MDS Nordionrsquos nuclear substance processing facility and the Canadian Irradiation Centre

1 Doses from photons from external sources were measured and reported to the NDR MDS Nordion also has a routine thyroid monitoring program very occasionally small recordable doses of radiation have occurred from thyroid uptake of iodine The resulting doses have not been historically submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided

Figure 265 Average Dose Trends for MDS Nordion (Based on Non-Zero Results)

0

05

1

15

2

25

Effe

ctiv

e D

ose

(mS

v)

Year

62

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 266 Average Dose Trends for MDS Nordion (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

Figure 267 Collective Dose Trends for MDS Nordion

0

100

200

300

400

500

600

700

800

Year

63

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 268 Distribution of Effective Doses Among All Workers at MDS Nordion

0

5 0

1 0 0

1 5 0

2 0 0

2 5 0

3 0 0

3 5 0

4 0 0

4 5 0

5 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

64

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

253 Tri-University Meson Facility

The Tri-University Meson facility (TRIUMF) is situated in Vancouver on the campus of the University of British Columbia TRIUMF which began operating in the early 1970s with one cyclotron now has two cyclotrons and associated laboratories for research and radioisotope production The laboratory provides research facilities for Canadian and international users and also produces radioisotopes which are used by medical facilities and by a commercial organization (MDS Nordion) MDS Nordion staff also work at the TRIUMF site however MDS Nordion oversees this work and has its own radiation protection program

Figures 269ndash272 present dose information for the TRIUMF facility from 2001 to 2007 Please note that data sets do not distinguish between doses received by TRIUMF staff and MDS Nordion staff who work on the site as the data for these two groups was submitted collectively to the NDR for the reporting period shown Future data for each group will be submitted separately to the NDR

Note on data for TRIUMF

1 Effective doses are composed of the following reported components bull doses from photons (labeled as ldquoexternalrdquo in the charts) bull neutron doses

Figure 269 Average Dose Trends for TRIUMF (Non-Zero Results Only)

000

020

040

060

080

100

120

140

160

Dos

e (m

Sv)

Neutrons External Effective

Year

65

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 43: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

00

20

40

60

80

00

20

40

60

Figure 234 Average Dose Trends for the Key Lake Operation (Based o n A ll Monitoring R esults)

0

0

0

0

0

1

1

1

1

)S

v(m

e os

D

Long-lived radioactive dust Radon progeny External Effective

Year

Figure 235 Collective Dose Trends for the Key Lake Operation

0

100

200

300

400

500

600

700

800

)S

von

-m(p

ers

e os

De

ivtol

lec

C

External Radon progeny Long-lived radioactive dust

Year

38

00

0-000

9

001-5

0

501-1

000

gt 1001

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 236 Distribution o f Effective Doses Among A ll Workers at the Key Lake Operation

0

200

400

600

800

1000

1200

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose Range (mSv)

39

se

(mS

v)o

D

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

225 Cigar Lake Operation

Cameco Corporation manages the Cigar Lake underground mine located in northern Saskatchewan at the southern end of Waterbury Lake The mine was under construction at the time of this reportrsquos publication Test mining in ore was carried out in 1991 1992 and 2000

Figures 237ndash240 present dose information for the Cigar Lake operation from

Figure 2 37 Average D ose T rends fo r th e C igar L ake O peration (Based on Non-Zero Results)

2001 to 2007

Year

000

005

010

015

020

025

Long-lived radioactive dust Radon Progeny External Effective

40

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 238 Average Dose Trends for the Cigar Lake Operation (Based on All Monitoring Results)

000

005

010

015

020

025

030

035

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny

External

Effective

Year

Figure 239 Collective Dose Trends for the Cigar Lake Operation

0

50

100

150

200

250

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

External Radon progeny Long-lived radioactive dust

Year

41

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 240 Distribution of Effective Doses Among All Workers at the Cigar Lake Operation

0

200

400

600

800

1000

1200

1400

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

42

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

226 Rabbit Lake Operation

Cameco Corporation owns and operates mining facilities in Rabbit Lake located in north-eastern Saskatchewan Facilities include an underground mine four mined-out open-pit mines a mill and two tailings management facilities Mining and milling began in 1975

Figures 241ndash244 present dose information for the Rabbit Lake operation from 2001 to 2007

Figure 241 Average Dose Trends for the Rabbit Lake Operation (Based on Non-Zero Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

43

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 242 Average Dose Trends for the Rabbit Lake Operation (Based on All Monitoring Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

Figure 243 Collective Dose Trends for the Rabbit Lake Operation

0

200

400

600

800

1000

1200

1400

1600

1800

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Radon gas External Radon progeny Long-lived radioactive dust

Year

44

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

gt300

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 244 Distribution of Effective Doses Among All Workers at the Rabbit Lake Operation

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

900

800

700

600

500

400

300

200

100

0

Dose (mSv)

45

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

23 Uranium Refineries This section presents data for the following two facilities

bull a uranium refining facility in Blind River (Section 231) bull a uranium conversion facility in Port Hope (Section 232)

Graphs indicate the following average doses at each facility from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Note on data for uranium refineries

1 Doses from photons from external sources are measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay and lung counting Historically while these internal doses have been measured they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

231 Blind River Refinery

Cameco Corporation owns and is licensed to operate a uranium refinery in Blind River Ontario The facility which began operating in 1983 converts uranium ore concentrate to uranium trioxide The uranium trioxide is shipped to Camecorsquos uranium conversion facility in Port Hope Ontario where it is processed into uranium dioxide (for use in the fabrication of fuel for nuclear reactors in Canada) or uranium hexafluoride (exported for enrichment and fabrication into fuel for nuclear power reactors around the world)

Figures 245ndash248 present dose information for the Blind River refinery from 2001 to 2007

46

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 245 Average Dose Trends for the Blind River Refinery (Based on Non-Zero Results)

0

05

1

15

2

25

Year

Figure 246 Average Dose Trends for the Blind River Refinery (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

47

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 247 Collective Dose Trends for the Blind River Refinery

0

50

100

150

200

250

300 C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 248 Distribution of Effective Doses Among All Workers at the Blind River Refinery

0

20

40

60

80

100

120

140

160

180

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

48

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

232 Port Hope Conversion Facility

Cameco Corporation owns and is licensed to operate a uranium conversion facility in Port Hope Ontario The facility processes uranium trioxide received from the refinery in Blind River into uranium dioxide and uranium hexafluoride

Figures 249ndash252 present dose information for the Port Hope uranium conversion facility from 2001 to 2007

Figure 249 Average Dose Trends for the Port Hope Conversion Facility (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

49

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 250 Average Dose Trends for the Port Hope Conversion Facility (Based on All Monitoring Results)

0

01

02

03

04

05

06

07

08

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 251 Collective Dose Trends for the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

50

000-0

009

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 252 Distribution of Effective Doses Among All Workers at the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

400

450

500

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

51

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

24 Fuel Fabrication Facilities This section presents data for three nuclear fuel fabrication facilities

bull Two facilities owned and operated by General Electric Canada Inc (Section 241) bull One facility in Port Hope operated by Zircatec Precision Industries (Section 242)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average doses

Notes on data for fuel fabrication facilities

1 Effective doses for the three facilities are composed of the following reported components bull dose from photons (labelled on the charts as ldquoexternalrdquo) bull doses from internal intakes of uranium dust (long-lived radioactive dust) from

uranium in air concentrations (for General Electricrsquos Toronto facility only)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components photon doses and doses from long-lived radioactive dust

241 General Electric Nuclear Fuel Facilities

General Electric Canada Inc operates two nuclear fuel facilities in Ontario

bull At the Toronto facility uranium dioxide pellets are produced from natural or depleted uranium dioxide powder

bull At the Peterborough facility uranium dioxide fuel bundles are created from the pellets produced at the Toronto facility

Figures 253ndash256 present dose information for General Electric Canada Incrsquos fuel fabrication facilities from 2001 to 2007 Graphs do not distinguish between the doses received at the Peterborough facility versus those at the Toronto facility

52

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 253 Average Dose Trends for the General Electric Fuel Facility (Based on Non-Zero Results Only)

0

05

1

15

2

25

3

35

Long Lived Radioactive Dust External Effective

Year

Figure 254 Average Dose Trends for the General Electric Fuel Facility (Based on All Monitoring Results)

0

05

1

15

2

25

3

Long Lived Radioactive Dust External Effective

Year

Dos

e (m

Sv)

Dos

e (m

Sv)

53

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 255 Collective Dose Trends for the General Electric Fuel Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Long Lived Radioactive Dust External

Year

Figure 256 Distribution of Effective Doses among all Workers at the General Electric Fuel Facility

0

10

20

30

40

50

60

70

80

90

100

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

54

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

242 Zircatec Nuclear Fuel Facility

Zircatec Precision Industries Inc operates a nuclear fuel facility in Port Hope Ontario where it makes fuel pellets from uranium dioxide powder received from Port Hopersquos uranium conversion facility The nuclear fuel facility also manufactures fuel bundles for nuclear reactors in Canada

Notes on data for the Zircatec nuclear fuel facility

1 Graphs indicate the following data bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of average effective doses

2 Doses from photons from external sources were measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay Historically although these internal doses have been measured and submitted to the CNSC they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

Figures 257ndash260 present dose information for the Zircatec nuclear fuel facility from 2001 to 2007

Figure 257 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on Non-Zero Results)

0

05

1

15

2

25

3

35

Effe

ctiv

e D

ose

(mS

v)

Year

55

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 258 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

18

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 259 Collective Dose Trends for the Zircatec Nuclear Fuel Facility

0

50

100

150

200

250

300

350

400

450

500

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

56

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 260 Distribution of Effective Doses Among All Workers at the Zircatec Nuclear Fuel Facility

300

Num

ber o

f Wor

kers

250

200

150

100

50

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

57

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

25 Research and Radioisotope Production Facilities This section presents dose information for the following research and radioisotope production facilities from 2001 to 2007

bull Chalk River Laboratories and Whiteshell Laboratories (Section 251) bull A radioisotope production facility operated by MDS Nordion (Section 252) bull The Tri-University Meson Facility (TRIUMF) (Section 253)

Note on data for research and radioisotope production facilities

1 Graphs indicate the following data for each facility bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of effective doses

251 Chalk River Laboratories and Whiteshell Laboratories

Atomic Energy of Canada Limited (AECL) owns and is licensed to operate Chalk River Laboratories and Whiteshell Laboratories

Situated in Renfrew County on the south shore of the Ottawa River the Chalk River Laboratories site hosts the National Research Universal Reactor along with numerous other facilities occupying some 160 buildings in an area of approximately 40 km2 Activities consist of radioisotope production for nuclear medicine testing and development of structural materials in support of power reactor operations fuel fabrication research and radioactive waste management and storage

The Whiteshell Laboratories site is located approximately 10 km west of Pinawa Manitoba and 100 km northeast of Winnipeg on the east bank of the Winnipeg River AECL established the laboratories for nuclear research and testing during the early 1960s and has since discontinued operations which are being decommissioned under a licence from the CNSC

Figures 261ndash264 present dose information for Chalk River Laboratories and Whiteshell Laboratories from 2001 to 2007

Notes on data for Chalk River Laboratories and Whiteshell Laboratories

1 Effective doses are composed of the following reported components bull external doses5 (from both photon and neutron doses) bull tritium doses

Due to issues with AECLrsquos in-house dosimetry management system neutron doses were not reported separately to the NDR during the reporting period As a result external doses from photons and neutrons were totaled The reporting discrepancy has since been rectified

58

5

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of external (photon and neutron) and tritium doses Intakes of other radionuclides occasionally occur and these radionuclides are not included here because their associated doses are very small For this reason certain collective doses in this report may have values slightly lower than the sum of their respective components as listed

Figure 261 Average Dose Trends for Chalk River and Whiteshell Laboratories (Non-Zero Results Only)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Tritium External Effective

Year

59

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 262 Average Dose Trends for Chalk River and Whiteshell Laboratories (All Monitoring Results)

000

020

040

060

080

100

120

Dos

e (m

Sv)

Tritium External Effective

Year

Figure 263 Collective Dose Trends for Chalk River and Whiteshell Laboratories

0

500

1000

1500

2000

2500

3000

3500

Col

lect

ive

Dos

e (p

erso

n- m

Sv)

External Tritium

Year

60

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 264 Distribution of Effective Doses Among All Workers at Chalk River and Whiteshell Laboratories

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

3500

3000

2500

2000

1500

1000

500

Dose (mSv)

61

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

252 MDS Nordion (Nuclear Substance Processing Facility and Canadian Irradiation Centre)

MDS Nordion owns and operates a nuclear substance processing facility in Ottawa Ontario where it processes unsealed radioisotopes and manufactures sealed radiation sources In operation since the early 1970s the facility was purchased by Nordion International in 1991

In cooperation with the Universiteacute du Queacutebecrsquos Institut Armand-Frappier MDS Nordion also operates the Canadian Irradiation Centre which conducts various irradiation services which include training testing and development The centre is located in Laval Quebec on the Universiteacute du Queacutebec campus

Figures 265ndash268 present dose information for MDS Nordionrsquos Ottawa nuclear substance processing facility and for the Canadian Irradiation Centre from 2001 to 2007

Notes on data for MDS Nordionrsquos nuclear substance processing facility and the Canadian Irradiation Centre

1 Doses from photons from external sources were measured and reported to the NDR MDS Nordion also has a routine thyroid monitoring program very occasionally small recordable doses of radiation have occurred from thyroid uptake of iodine The resulting doses have not been historically submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided

Figure 265 Average Dose Trends for MDS Nordion (Based on Non-Zero Results)

0

05

1

15

2

25

Effe

ctiv

e D

ose

(mS

v)

Year

62

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 266 Average Dose Trends for MDS Nordion (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

Figure 267 Collective Dose Trends for MDS Nordion

0

100

200

300

400

500

600

700

800

Year

63

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 268 Distribution of Effective Doses Among All Workers at MDS Nordion

0

5 0

1 0 0

1 5 0

2 0 0

2 5 0

3 0 0

3 5 0

4 0 0

4 5 0

5 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

64

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

253 Tri-University Meson Facility

The Tri-University Meson facility (TRIUMF) is situated in Vancouver on the campus of the University of British Columbia TRIUMF which began operating in the early 1970s with one cyclotron now has two cyclotrons and associated laboratories for research and radioisotope production The laboratory provides research facilities for Canadian and international users and also produces radioisotopes which are used by medical facilities and by a commercial organization (MDS Nordion) MDS Nordion staff also work at the TRIUMF site however MDS Nordion oversees this work and has its own radiation protection program

Figures 269ndash272 present dose information for the TRIUMF facility from 2001 to 2007 Please note that data sets do not distinguish between doses received by TRIUMF staff and MDS Nordion staff who work on the site as the data for these two groups was submitted collectively to the NDR for the reporting period shown Future data for each group will be submitted separately to the NDR

Note on data for TRIUMF

1 Effective doses are composed of the following reported components bull doses from photons (labeled as ldquoexternalrdquo in the charts) bull neutron doses

Figure 269 Average Dose Trends for TRIUMF (Non-Zero Results Only)

000

020

040

060

080

100

120

140

160

Dos

e (m

Sv)

Neutrons External Effective

Year

65

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 44: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

00

0-000

9

001-5

0

501-1

000

gt 1001

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 236 Distribution o f Effective Doses Among A ll Workers at the Key Lake Operation

0

200

400

600

800

1000

1200

serk

or o

f Wbe

rN

um

2001 2002 2003 2004 2005 2006 2007

Dose Range (mSv)

39

se

(mS

v)o

D

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

225 Cigar Lake Operation

Cameco Corporation manages the Cigar Lake underground mine located in northern Saskatchewan at the southern end of Waterbury Lake The mine was under construction at the time of this reportrsquos publication Test mining in ore was carried out in 1991 1992 and 2000

Figures 237ndash240 present dose information for the Cigar Lake operation from

Figure 2 37 Average D ose T rends fo r th e C igar L ake O peration (Based on Non-Zero Results)

2001 to 2007

Year

000

005

010

015

020

025

Long-lived radioactive dust Radon Progeny External Effective

40

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 238 Average Dose Trends for the Cigar Lake Operation (Based on All Monitoring Results)

000

005

010

015

020

025

030

035

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny

External

Effective

Year

Figure 239 Collective Dose Trends for the Cigar Lake Operation

0

50

100

150

200

250

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

External Radon progeny Long-lived radioactive dust

Year

41

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 240 Distribution of Effective Doses Among All Workers at the Cigar Lake Operation

0

200

400

600

800

1000

1200

1400

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

42

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

226 Rabbit Lake Operation

Cameco Corporation owns and operates mining facilities in Rabbit Lake located in north-eastern Saskatchewan Facilities include an underground mine four mined-out open-pit mines a mill and two tailings management facilities Mining and milling began in 1975

Figures 241ndash244 present dose information for the Rabbit Lake operation from 2001 to 2007

Figure 241 Average Dose Trends for the Rabbit Lake Operation (Based on Non-Zero Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

43

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 242 Average Dose Trends for the Rabbit Lake Operation (Based on All Monitoring Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

Figure 243 Collective Dose Trends for the Rabbit Lake Operation

0

200

400

600

800

1000

1200

1400

1600

1800

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Radon gas External Radon progeny Long-lived radioactive dust

Year

44

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

gt300

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 244 Distribution of Effective Doses Among All Workers at the Rabbit Lake Operation

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

900

800

700

600

500

400

300

200

100

0

Dose (mSv)

45

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

23 Uranium Refineries This section presents data for the following two facilities

bull a uranium refining facility in Blind River (Section 231) bull a uranium conversion facility in Port Hope (Section 232)

Graphs indicate the following average doses at each facility from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Note on data for uranium refineries

1 Doses from photons from external sources are measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay and lung counting Historically while these internal doses have been measured they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

231 Blind River Refinery

Cameco Corporation owns and is licensed to operate a uranium refinery in Blind River Ontario The facility which began operating in 1983 converts uranium ore concentrate to uranium trioxide The uranium trioxide is shipped to Camecorsquos uranium conversion facility in Port Hope Ontario where it is processed into uranium dioxide (for use in the fabrication of fuel for nuclear reactors in Canada) or uranium hexafluoride (exported for enrichment and fabrication into fuel for nuclear power reactors around the world)

Figures 245ndash248 present dose information for the Blind River refinery from 2001 to 2007

46

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 245 Average Dose Trends for the Blind River Refinery (Based on Non-Zero Results)

0

05

1

15

2

25

Year

Figure 246 Average Dose Trends for the Blind River Refinery (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

47

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 247 Collective Dose Trends for the Blind River Refinery

0

50

100

150

200

250

300 C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 248 Distribution of Effective Doses Among All Workers at the Blind River Refinery

0

20

40

60

80

100

120

140

160

180

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

48

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

232 Port Hope Conversion Facility

Cameco Corporation owns and is licensed to operate a uranium conversion facility in Port Hope Ontario The facility processes uranium trioxide received from the refinery in Blind River into uranium dioxide and uranium hexafluoride

Figures 249ndash252 present dose information for the Port Hope uranium conversion facility from 2001 to 2007

Figure 249 Average Dose Trends for the Port Hope Conversion Facility (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

49

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 250 Average Dose Trends for the Port Hope Conversion Facility (Based on All Monitoring Results)

0

01

02

03

04

05

06

07

08

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 251 Collective Dose Trends for the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

50

000-0

009

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 252 Distribution of Effective Doses Among All Workers at the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

400

450

500

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

51

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

24 Fuel Fabrication Facilities This section presents data for three nuclear fuel fabrication facilities

bull Two facilities owned and operated by General Electric Canada Inc (Section 241) bull One facility in Port Hope operated by Zircatec Precision Industries (Section 242)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average doses

Notes on data for fuel fabrication facilities

1 Effective doses for the three facilities are composed of the following reported components bull dose from photons (labelled on the charts as ldquoexternalrdquo) bull doses from internal intakes of uranium dust (long-lived radioactive dust) from

uranium in air concentrations (for General Electricrsquos Toronto facility only)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components photon doses and doses from long-lived radioactive dust

241 General Electric Nuclear Fuel Facilities

General Electric Canada Inc operates two nuclear fuel facilities in Ontario

bull At the Toronto facility uranium dioxide pellets are produced from natural or depleted uranium dioxide powder

bull At the Peterborough facility uranium dioxide fuel bundles are created from the pellets produced at the Toronto facility

Figures 253ndash256 present dose information for General Electric Canada Incrsquos fuel fabrication facilities from 2001 to 2007 Graphs do not distinguish between the doses received at the Peterborough facility versus those at the Toronto facility

52

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 253 Average Dose Trends for the General Electric Fuel Facility (Based on Non-Zero Results Only)

0

05

1

15

2

25

3

35

Long Lived Radioactive Dust External Effective

Year

Figure 254 Average Dose Trends for the General Electric Fuel Facility (Based on All Monitoring Results)

0

05

1

15

2

25

3

Long Lived Radioactive Dust External Effective

Year

Dos

e (m

Sv)

Dos

e (m

Sv)

53

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 255 Collective Dose Trends for the General Electric Fuel Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Long Lived Radioactive Dust External

Year

Figure 256 Distribution of Effective Doses among all Workers at the General Electric Fuel Facility

0

10

20

30

40

50

60

70

80

90

100

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

54

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

242 Zircatec Nuclear Fuel Facility

Zircatec Precision Industries Inc operates a nuclear fuel facility in Port Hope Ontario where it makes fuel pellets from uranium dioxide powder received from Port Hopersquos uranium conversion facility The nuclear fuel facility also manufactures fuel bundles for nuclear reactors in Canada

Notes on data for the Zircatec nuclear fuel facility

1 Graphs indicate the following data bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of average effective doses

2 Doses from photons from external sources were measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay Historically although these internal doses have been measured and submitted to the CNSC they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

Figures 257ndash260 present dose information for the Zircatec nuclear fuel facility from 2001 to 2007

Figure 257 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on Non-Zero Results)

0

05

1

15

2

25

3

35

Effe

ctiv

e D

ose

(mS

v)

Year

55

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 258 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

18

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 259 Collective Dose Trends for the Zircatec Nuclear Fuel Facility

0

50

100

150

200

250

300

350

400

450

500

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

56

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 260 Distribution of Effective Doses Among All Workers at the Zircatec Nuclear Fuel Facility

300

Num

ber o

f Wor

kers

250

200

150

100

50

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

57

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

25 Research and Radioisotope Production Facilities This section presents dose information for the following research and radioisotope production facilities from 2001 to 2007

bull Chalk River Laboratories and Whiteshell Laboratories (Section 251) bull A radioisotope production facility operated by MDS Nordion (Section 252) bull The Tri-University Meson Facility (TRIUMF) (Section 253)

Note on data for research and radioisotope production facilities

1 Graphs indicate the following data for each facility bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of effective doses

251 Chalk River Laboratories and Whiteshell Laboratories

Atomic Energy of Canada Limited (AECL) owns and is licensed to operate Chalk River Laboratories and Whiteshell Laboratories

Situated in Renfrew County on the south shore of the Ottawa River the Chalk River Laboratories site hosts the National Research Universal Reactor along with numerous other facilities occupying some 160 buildings in an area of approximately 40 km2 Activities consist of radioisotope production for nuclear medicine testing and development of structural materials in support of power reactor operations fuel fabrication research and radioactive waste management and storage

The Whiteshell Laboratories site is located approximately 10 km west of Pinawa Manitoba and 100 km northeast of Winnipeg on the east bank of the Winnipeg River AECL established the laboratories for nuclear research and testing during the early 1960s and has since discontinued operations which are being decommissioned under a licence from the CNSC

Figures 261ndash264 present dose information for Chalk River Laboratories and Whiteshell Laboratories from 2001 to 2007

Notes on data for Chalk River Laboratories and Whiteshell Laboratories

1 Effective doses are composed of the following reported components bull external doses5 (from both photon and neutron doses) bull tritium doses

Due to issues with AECLrsquos in-house dosimetry management system neutron doses were not reported separately to the NDR during the reporting period As a result external doses from photons and neutrons were totaled The reporting discrepancy has since been rectified

58

5

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of external (photon and neutron) and tritium doses Intakes of other radionuclides occasionally occur and these radionuclides are not included here because their associated doses are very small For this reason certain collective doses in this report may have values slightly lower than the sum of their respective components as listed

Figure 261 Average Dose Trends for Chalk River and Whiteshell Laboratories (Non-Zero Results Only)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Tritium External Effective

Year

59

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 262 Average Dose Trends for Chalk River and Whiteshell Laboratories (All Monitoring Results)

000

020

040

060

080

100

120

Dos

e (m

Sv)

Tritium External Effective

Year

Figure 263 Collective Dose Trends for Chalk River and Whiteshell Laboratories

0

500

1000

1500

2000

2500

3000

3500

Col

lect

ive

Dos

e (p

erso

n- m

Sv)

External Tritium

Year

60

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 264 Distribution of Effective Doses Among All Workers at Chalk River and Whiteshell Laboratories

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

3500

3000

2500

2000

1500

1000

500

Dose (mSv)

61

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

252 MDS Nordion (Nuclear Substance Processing Facility and Canadian Irradiation Centre)

MDS Nordion owns and operates a nuclear substance processing facility in Ottawa Ontario where it processes unsealed radioisotopes and manufactures sealed radiation sources In operation since the early 1970s the facility was purchased by Nordion International in 1991

In cooperation with the Universiteacute du Queacutebecrsquos Institut Armand-Frappier MDS Nordion also operates the Canadian Irradiation Centre which conducts various irradiation services which include training testing and development The centre is located in Laval Quebec on the Universiteacute du Queacutebec campus

Figures 265ndash268 present dose information for MDS Nordionrsquos Ottawa nuclear substance processing facility and for the Canadian Irradiation Centre from 2001 to 2007

Notes on data for MDS Nordionrsquos nuclear substance processing facility and the Canadian Irradiation Centre

1 Doses from photons from external sources were measured and reported to the NDR MDS Nordion also has a routine thyroid monitoring program very occasionally small recordable doses of radiation have occurred from thyroid uptake of iodine The resulting doses have not been historically submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided

Figure 265 Average Dose Trends for MDS Nordion (Based on Non-Zero Results)

0

05

1

15

2

25

Effe

ctiv

e D

ose

(mS

v)

Year

62

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 266 Average Dose Trends for MDS Nordion (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

Figure 267 Collective Dose Trends for MDS Nordion

0

100

200

300

400

500

600

700

800

Year

63

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 268 Distribution of Effective Doses Among All Workers at MDS Nordion

0

5 0

1 0 0

1 5 0

2 0 0

2 5 0

3 0 0

3 5 0

4 0 0

4 5 0

5 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

64

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

253 Tri-University Meson Facility

The Tri-University Meson facility (TRIUMF) is situated in Vancouver on the campus of the University of British Columbia TRIUMF which began operating in the early 1970s with one cyclotron now has two cyclotrons and associated laboratories for research and radioisotope production The laboratory provides research facilities for Canadian and international users and also produces radioisotopes which are used by medical facilities and by a commercial organization (MDS Nordion) MDS Nordion staff also work at the TRIUMF site however MDS Nordion oversees this work and has its own radiation protection program

Figures 269ndash272 present dose information for the TRIUMF facility from 2001 to 2007 Please note that data sets do not distinguish between doses received by TRIUMF staff and MDS Nordion staff who work on the site as the data for these two groups was submitted collectively to the NDR for the reporting period shown Future data for each group will be submitted separately to the NDR

Note on data for TRIUMF

1 Effective doses are composed of the following reported components bull doses from photons (labeled as ldquoexternalrdquo in the charts) bull neutron doses

Figure 269 Average Dose Trends for TRIUMF (Non-Zero Results Only)

000

020

040

060

080

100

120

140

160

Dos

e (m

Sv)

Neutrons External Effective

Year

65

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 45: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

se

(mS

v)o

D

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

225 Cigar Lake Operation

Cameco Corporation manages the Cigar Lake underground mine located in northern Saskatchewan at the southern end of Waterbury Lake The mine was under construction at the time of this reportrsquos publication Test mining in ore was carried out in 1991 1992 and 2000

Figures 237ndash240 present dose information for the Cigar Lake operation from

Figure 2 37 Average D ose T rends fo r th e C igar L ake O peration (Based on Non-Zero Results)

2001 to 2007

Year

000

005

010

015

020

025

Long-lived radioactive dust Radon Progeny External Effective

40

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 238 Average Dose Trends for the Cigar Lake Operation (Based on All Monitoring Results)

000

005

010

015

020

025

030

035

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny

External

Effective

Year

Figure 239 Collective Dose Trends for the Cigar Lake Operation

0

50

100

150

200

250

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

External Radon progeny Long-lived radioactive dust

Year

41

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 240 Distribution of Effective Doses Among All Workers at the Cigar Lake Operation

0

200

400

600

800

1000

1200

1400

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

42

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

226 Rabbit Lake Operation

Cameco Corporation owns and operates mining facilities in Rabbit Lake located in north-eastern Saskatchewan Facilities include an underground mine four mined-out open-pit mines a mill and two tailings management facilities Mining and milling began in 1975

Figures 241ndash244 present dose information for the Rabbit Lake operation from 2001 to 2007

Figure 241 Average Dose Trends for the Rabbit Lake Operation (Based on Non-Zero Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

43

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 242 Average Dose Trends for the Rabbit Lake Operation (Based on All Monitoring Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

Figure 243 Collective Dose Trends for the Rabbit Lake Operation

0

200

400

600

800

1000

1200

1400

1600

1800

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Radon gas External Radon progeny Long-lived radioactive dust

Year

44

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

gt300

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 244 Distribution of Effective Doses Among All Workers at the Rabbit Lake Operation

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

900

800

700

600

500

400

300

200

100

0

Dose (mSv)

45

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

23 Uranium Refineries This section presents data for the following two facilities

bull a uranium refining facility in Blind River (Section 231) bull a uranium conversion facility in Port Hope (Section 232)

Graphs indicate the following average doses at each facility from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Note on data for uranium refineries

1 Doses from photons from external sources are measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay and lung counting Historically while these internal doses have been measured they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

231 Blind River Refinery

Cameco Corporation owns and is licensed to operate a uranium refinery in Blind River Ontario The facility which began operating in 1983 converts uranium ore concentrate to uranium trioxide The uranium trioxide is shipped to Camecorsquos uranium conversion facility in Port Hope Ontario where it is processed into uranium dioxide (for use in the fabrication of fuel for nuclear reactors in Canada) or uranium hexafluoride (exported for enrichment and fabrication into fuel for nuclear power reactors around the world)

Figures 245ndash248 present dose information for the Blind River refinery from 2001 to 2007

46

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 245 Average Dose Trends for the Blind River Refinery (Based on Non-Zero Results)

0

05

1

15

2

25

Year

Figure 246 Average Dose Trends for the Blind River Refinery (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

47

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 247 Collective Dose Trends for the Blind River Refinery

0

50

100

150

200

250

300 C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 248 Distribution of Effective Doses Among All Workers at the Blind River Refinery

0

20

40

60

80

100

120

140

160

180

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

48

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

232 Port Hope Conversion Facility

Cameco Corporation owns and is licensed to operate a uranium conversion facility in Port Hope Ontario The facility processes uranium trioxide received from the refinery in Blind River into uranium dioxide and uranium hexafluoride

Figures 249ndash252 present dose information for the Port Hope uranium conversion facility from 2001 to 2007

Figure 249 Average Dose Trends for the Port Hope Conversion Facility (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

49

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 250 Average Dose Trends for the Port Hope Conversion Facility (Based on All Monitoring Results)

0

01

02

03

04

05

06

07

08

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 251 Collective Dose Trends for the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

50

000-0

009

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 252 Distribution of Effective Doses Among All Workers at the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

400

450

500

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

51

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

24 Fuel Fabrication Facilities This section presents data for three nuclear fuel fabrication facilities

bull Two facilities owned and operated by General Electric Canada Inc (Section 241) bull One facility in Port Hope operated by Zircatec Precision Industries (Section 242)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average doses

Notes on data for fuel fabrication facilities

1 Effective doses for the three facilities are composed of the following reported components bull dose from photons (labelled on the charts as ldquoexternalrdquo) bull doses from internal intakes of uranium dust (long-lived radioactive dust) from

uranium in air concentrations (for General Electricrsquos Toronto facility only)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components photon doses and doses from long-lived radioactive dust

241 General Electric Nuclear Fuel Facilities

General Electric Canada Inc operates two nuclear fuel facilities in Ontario

bull At the Toronto facility uranium dioxide pellets are produced from natural or depleted uranium dioxide powder

bull At the Peterborough facility uranium dioxide fuel bundles are created from the pellets produced at the Toronto facility

Figures 253ndash256 present dose information for General Electric Canada Incrsquos fuel fabrication facilities from 2001 to 2007 Graphs do not distinguish between the doses received at the Peterborough facility versus those at the Toronto facility

52

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 253 Average Dose Trends for the General Electric Fuel Facility (Based on Non-Zero Results Only)

0

05

1

15

2

25

3

35

Long Lived Radioactive Dust External Effective

Year

Figure 254 Average Dose Trends for the General Electric Fuel Facility (Based on All Monitoring Results)

0

05

1

15

2

25

3

Long Lived Radioactive Dust External Effective

Year

Dos

e (m

Sv)

Dos

e (m

Sv)

53

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 255 Collective Dose Trends for the General Electric Fuel Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Long Lived Radioactive Dust External

Year

Figure 256 Distribution of Effective Doses among all Workers at the General Electric Fuel Facility

0

10

20

30

40

50

60

70

80

90

100

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

54

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

242 Zircatec Nuclear Fuel Facility

Zircatec Precision Industries Inc operates a nuclear fuel facility in Port Hope Ontario where it makes fuel pellets from uranium dioxide powder received from Port Hopersquos uranium conversion facility The nuclear fuel facility also manufactures fuel bundles for nuclear reactors in Canada

Notes on data for the Zircatec nuclear fuel facility

1 Graphs indicate the following data bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of average effective doses

2 Doses from photons from external sources were measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay Historically although these internal doses have been measured and submitted to the CNSC they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

Figures 257ndash260 present dose information for the Zircatec nuclear fuel facility from 2001 to 2007

Figure 257 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on Non-Zero Results)

0

05

1

15

2

25

3

35

Effe

ctiv

e D

ose

(mS

v)

Year

55

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 258 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

18

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 259 Collective Dose Trends for the Zircatec Nuclear Fuel Facility

0

50

100

150

200

250

300

350

400

450

500

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

56

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 260 Distribution of Effective Doses Among All Workers at the Zircatec Nuclear Fuel Facility

300

Num

ber o

f Wor

kers

250

200

150

100

50

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

57

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

25 Research and Radioisotope Production Facilities This section presents dose information for the following research and radioisotope production facilities from 2001 to 2007

bull Chalk River Laboratories and Whiteshell Laboratories (Section 251) bull A radioisotope production facility operated by MDS Nordion (Section 252) bull The Tri-University Meson Facility (TRIUMF) (Section 253)

Note on data for research and radioisotope production facilities

1 Graphs indicate the following data for each facility bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of effective doses

251 Chalk River Laboratories and Whiteshell Laboratories

Atomic Energy of Canada Limited (AECL) owns and is licensed to operate Chalk River Laboratories and Whiteshell Laboratories

Situated in Renfrew County on the south shore of the Ottawa River the Chalk River Laboratories site hosts the National Research Universal Reactor along with numerous other facilities occupying some 160 buildings in an area of approximately 40 km2 Activities consist of radioisotope production for nuclear medicine testing and development of structural materials in support of power reactor operations fuel fabrication research and radioactive waste management and storage

The Whiteshell Laboratories site is located approximately 10 km west of Pinawa Manitoba and 100 km northeast of Winnipeg on the east bank of the Winnipeg River AECL established the laboratories for nuclear research and testing during the early 1960s and has since discontinued operations which are being decommissioned under a licence from the CNSC

Figures 261ndash264 present dose information for Chalk River Laboratories and Whiteshell Laboratories from 2001 to 2007

Notes on data for Chalk River Laboratories and Whiteshell Laboratories

1 Effective doses are composed of the following reported components bull external doses5 (from both photon and neutron doses) bull tritium doses

Due to issues with AECLrsquos in-house dosimetry management system neutron doses were not reported separately to the NDR during the reporting period As a result external doses from photons and neutrons were totaled The reporting discrepancy has since been rectified

58

5

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of external (photon and neutron) and tritium doses Intakes of other radionuclides occasionally occur and these radionuclides are not included here because their associated doses are very small For this reason certain collective doses in this report may have values slightly lower than the sum of their respective components as listed

Figure 261 Average Dose Trends for Chalk River and Whiteshell Laboratories (Non-Zero Results Only)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Tritium External Effective

Year

59

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 262 Average Dose Trends for Chalk River and Whiteshell Laboratories (All Monitoring Results)

000

020

040

060

080

100

120

Dos

e (m

Sv)

Tritium External Effective

Year

Figure 263 Collective Dose Trends for Chalk River and Whiteshell Laboratories

0

500

1000

1500

2000

2500

3000

3500

Col

lect

ive

Dos

e (p

erso

n- m

Sv)

External Tritium

Year

60

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 264 Distribution of Effective Doses Among All Workers at Chalk River and Whiteshell Laboratories

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

3500

3000

2500

2000

1500

1000

500

Dose (mSv)

61

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

252 MDS Nordion (Nuclear Substance Processing Facility and Canadian Irradiation Centre)

MDS Nordion owns and operates a nuclear substance processing facility in Ottawa Ontario where it processes unsealed radioisotopes and manufactures sealed radiation sources In operation since the early 1970s the facility was purchased by Nordion International in 1991

In cooperation with the Universiteacute du Queacutebecrsquos Institut Armand-Frappier MDS Nordion also operates the Canadian Irradiation Centre which conducts various irradiation services which include training testing and development The centre is located in Laval Quebec on the Universiteacute du Queacutebec campus

Figures 265ndash268 present dose information for MDS Nordionrsquos Ottawa nuclear substance processing facility and for the Canadian Irradiation Centre from 2001 to 2007

Notes on data for MDS Nordionrsquos nuclear substance processing facility and the Canadian Irradiation Centre

1 Doses from photons from external sources were measured and reported to the NDR MDS Nordion also has a routine thyroid monitoring program very occasionally small recordable doses of radiation have occurred from thyroid uptake of iodine The resulting doses have not been historically submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided

Figure 265 Average Dose Trends for MDS Nordion (Based on Non-Zero Results)

0

05

1

15

2

25

Effe

ctiv

e D

ose

(mS

v)

Year

62

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 266 Average Dose Trends for MDS Nordion (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

Figure 267 Collective Dose Trends for MDS Nordion

0

100

200

300

400

500

600

700

800

Year

63

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 268 Distribution of Effective Doses Among All Workers at MDS Nordion

0

5 0

1 0 0

1 5 0

2 0 0

2 5 0

3 0 0

3 5 0

4 0 0

4 5 0

5 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

64

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

253 Tri-University Meson Facility

The Tri-University Meson facility (TRIUMF) is situated in Vancouver on the campus of the University of British Columbia TRIUMF which began operating in the early 1970s with one cyclotron now has two cyclotrons and associated laboratories for research and radioisotope production The laboratory provides research facilities for Canadian and international users and also produces radioisotopes which are used by medical facilities and by a commercial organization (MDS Nordion) MDS Nordion staff also work at the TRIUMF site however MDS Nordion oversees this work and has its own radiation protection program

Figures 269ndash272 present dose information for the TRIUMF facility from 2001 to 2007 Please note that data sets do not distinguish between doses received by TRIUMF staff and MDS Nordion staff who work on the site as the data for these two groups was submitted collectively to the NDR for the reporting period shown Future data for each group will be submitted separately to the NDR

Note on data for TRIUMF

1 Effective doses are composed of the following reported components bull doses from photons (labeled as ldquoexternalrdquo in the charts) bull neutron doses

Figure 269 Average Dose Trends for TRIUMF (Non-Zero Results Only)

000

020

040

060

080

100

120

140

160

Dos

e (m

Sv)

Neutrons External Effective

Year

65

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 46: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 238 Average Dose Trends for the Cigar Lake Operation (Based on All Monitoring Results)

000

005

010

015

020

025

030

035

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny

External

Effective

Year

Figure 239 Collective Dose Trends for the Cigar Lake Operation

0

50

100

150

200

250

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

External Radon progeny Long-lived radioactive dust

Year

41

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 240 Distribution of Effective Doses Among All Workers at the Cigar Lake Operation

0

200

400

600

800

1000

1200

1400

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

42

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

226 Rabbit Lake Operation

Cameco Corporation owns and operates mining facilities in Rabbit Lake located in north-eastern Saskatchewan Facilities include an underground mine four mined-out open-pit mines a mill and two tailings management facilities Mining and milling began in 1975

Figures 241ndash244 present dose information for the Rabbit Lake operation from 2001 to 2007

Figure 241 Average Dose Trends for the Rabbit Lake Operation (Based on Non-Zero Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

43

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 242 Average Dose Trends for the Rabbit Lake Operation (Based on All Monitoring Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

Figure 243 Collective Dose Trends for the Rabbit Lake Operation

0

200

400

600

800

1000

1200

1400

1600

1800

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Radon gas External Radon progeny Long-lived radioactive dust

Year

44

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

gt300

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 244 Distribution of Effective Doses Among All Workers at the Rabbit Lake Operation

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

900

800

700

600

500

400

300

200

100

0

Dose (mSv)

45

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

23 Uranium Refineries This section presents data for the following two facilities

bull a uranium refining facility in Blind River (Section 231) bull a uranium conversion facility in Port Hope (Section 232)

Graphs indicate the following average doses at each facility from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Note on data for uranium refineries

1 Doses from photons from external sources are measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay and lung counting Historically while these internal doses have been measured they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

231 Blind River Refinery

Cameco Corporation owns and is licensed to operate a uranium refinery in Blind River Ontario The facility which began operating in 1983 converts uranium ore concentrate to uranium trioxide The uranium trioxide is shipped to Camecorsquos uranium conversion facility in Port Hope Ontario where it is processed into uranium dioxide (for use in the fabrication of fuel for nuclear reactors in Canada) or uranium hexafluoride (exported for enrichment and fabrication into fuel for nuclear power reactors around the world)

Figures 245ndash248 present dose information for the Blind River refinery from 2001 to 2007

46

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 245 Average Dose Trends for the Blind River Refinery (Based on Non-Zero Results)

0

05

1

15

2

25

Year

Figure 246 Average Dose Trends for the Blind River Refinery (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

47

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 247 Collective Dose Trends for the Blind River Refinery

0

50

100

150

200

250

300 C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 248 Distribution of Effective Doses Among All Workers at the Blind River Refinery

0

20

40

60

80

100

120

140

160

180

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

48

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

232 Port Hope Conversion Facility

Cameco Corporation owns and is licensed to operate a uranium conversion facility in Port Hope Ontario The facility processes uranium trioxide received from the refinery in Blind River into uranium dioxide and uranium hexafluoride

Figures 249ndash252 present dose information for the Port Hope uranium conversion facility from 2001 to 2007

Figure 249 Average Dose Trends for the Port Hope Conversion Facility (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

49

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 250 Average Dose Trends for the Port Hope Conversion Facility (Based on All Monitoring Results)

0

01

02

03

04

05

06

07

08

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 251 Collective Dose Trends for the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

50

000-0

009

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 252 Distribution of Effective Doses Among All Workers at the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

400

450

500

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

51

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

24 Fuel Fabrication Facilities This section presents data for three nuclear fuel fabrication facilities

bull Two facilities owned and operated by General Electric Canada Inc (Section 241) bull One facility in Port Hope operated by Zircatec Precision Industries (Section 242)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average doses

Notes on data for fuel fabrication facilities

1 Effective doses for the three facilities are composed of the following reported components bull dose from photons (labelled on the charts as ldquoexternalrdquo) bull doses from internal intakes of uranium dust (long-lived radioactive dust) from

uranium in air concentrations (for General Electricrsquos Toronto facility only)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components photon doses and doses from long-lived radioactive dust

241 General Electric Nuclear Fuel Facilities

General Electric Canada Inc operates two nuclear fuel facilities in Ontario

bull At the Toronto facility uranium dioxide pellets are produced from natural or depleted uranium dioxide powder

bull At the Peterborough facility uranium dioxide fuel bundles are created from the pellets produced at the Toronto facility

Figures 253ndash256 present dose information for General Electric Canada Incrsquos fuel fabrication facilities from 2001 to 2007 Graphs do not distinguish between the doses received at the Peterborough facility versus those at the Toronto facility

52

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 253 Average Dose Trends for the General Electric Fuel Facility (Based on Non-Zero Results Only)

0

05

1

15

2

25

3

35

Long Lived Radioactive Dust External Effective

Year

Figure 254 Average Dose Trends for the General Electric Fuel Facility (Based on All Monitoring Results)

0

05

1

15

2

25

3

Long Lived Radioactive Dust External Effective

Year

Dos

e (m

Sv)

Dos

e (m

Sv)

53

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 255 Collective Dose Trends for the General Electric Fuel Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Long Lived Radioactive Dust External

Year

Figure 256 Distribution of Effective Doses among all Workers at the General Electric Fuel Facility

0

10

20

30

40

50

60

70

80

90

100

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

54

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

242 Zircatec Nuclear Fuel Facility

Zircatec Precision Industries Inc operates a nuclear fuel facility in Port Hope Ontario where it makes fuel pellets from uranium dioxide powder received from Port Hopersquos uranium conversion facility The nuclear fuel facility also manufactures fuel bundles for nuclear reactors in Canada

Notes on data for the Zircatec nuclear fuel facility

1 Graphs indicate the following data bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of average effective doses

2 Doses from photons from external sources were measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay Historically although these internal doses have been measured and submitted to the CNSC they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

Figures 257ndash260 present dose information for the Zircatec nuclear fuel facility from 2001 to 2007

Figure 257 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on Non-Zero Results)

0

05

1

15

2

25

3

35

Effe

ctiv

e D

ose

(mS

v)

Year

55

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 258 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

18

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 259 Collective Dose Trends for the Zircatec Nuclear Fuel Facility

0

50

100

150

200

250

300

350

400

450

500

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

56

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 260 Distribution of Effective Doses Among All Workers at the Zircatec Nuclear Fuel Facility

300

Num

ber o

f Wor

kers

250

200

150

100

50

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

57

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

25 Research and Radioisotope Production Facilities This section presents dose information for the following research and radioisotope production facilities from 2001 to 2007

bull Chalk River Laboratories and Whiteshell Laboratories (Section 251) bull A radioisotope production facility operated by MDS Nordion (Section 252) bull The Tri-University Meson Facility (TRIUMF) (Section 253)

Note on data for research and radioisotope production facilities

1 Graphs indicate the following data for each facility bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of effective doses

251 Chalk River Laboratories and Whiteshell Laboratories

Atomic Energy of Canada Limited (AECL) owns and is licensed to operate Chalk River Laboratories and Whiteshell Laboratories

Situated in Renfrew County on the south shore of the Ottawa River the Chalk River Laboratories site hosts the National Research Universal Reactor along with numerous other facilities occupying some 160 buildings in an area of approximately 40 km2 Activities consist of radioisotope production for nuclear medicine testing and development of structural materials in support of power reactor operations fuel fabrication research and radioactive waste management and storage

The Whiteshell Laboratories site is located approximately 10 km west of Pinawa Manitoba and 100 km northeast of Winnipeg on the east bank of the Winnipeg River AECL established the laboratories for nuclear research and testing during the early 1960s and has since discontinued operations which are being decommissioned under a licence from the CNSC

Figures 261ndash264 present dose information for Chalk River Laboratories and Whiteshell Laboratories from 2001 to 2007

Notes on data for Chalk River Laboratories and Whiteshell Laboratories

1 Effective doses are composed of the following reported components bull external doses5 (from both photon and neutron doses) bull tritium doses

Due to issues with AECLrsquos in-house dosimetry management system neutron doses were not reported separately to the NDR during the reporting period As a result external doses from photons and neutrons were totaled The reporting discrepancy has since been rectified

58

5

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of external (photon and neutron) and tritium doses Intakes of other radionuclides occasionally occur and these radionuclides are not included here because their associated doses are very small For this reason certain collective doses in this report may have values slightly lower than the sum of their respective components as listed

Figure 261 Average Dose Trends for Chalk River and Whiteshell Laboratories (Non-Zero Results Only)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Tritium External Effective

Year

59

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 262 Average Dose Trends for Chalk River and Whiteshell Laboratories (All Monitoring Results)

000

020

040

060

080

100

120

Dos

e (m

Sv)

Tritium External Effective

Year

Figure 263 Collective Dose Trends for Chalk River and Whiteshell Laboratories

0

500

1000

1500

2000

2500

3000

3500

Col

lect

ive

Dos

e (p

erso

n- m

Sv)

External Tritium

Year

60

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 264 Distribution of Effective Doses Among All Workers at Chalk River and Whiteshell Laboratories

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

3500

3000

2500

2000

1500

1000

500

Dose (mSv)

61

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

252 MDS Nordion (Nuclear Substance Processing Facility and Canadian Irradiation Centre)

MDS Nordion owns and operates a nuclear substance processing facility in Ottawa Ontario where it processes unsealed radioisotopes and manufactures sealed radiation sources In operation since the early 1970s the facility was purchased by Nordion International in 1991

In cooperation with the Universiteacute du Queacutebecrsquos Institut Armand-Frappier MDS Nordion also operates the Canadian Irradiation Centre which conducts various irradiation services which include training testing and development The centre is located in Laval Quebec on the Universiteacute du Queacutebec campus

Figures 265ndash268 present dose information for MDS Nordionrsquos Ottawa nuclear substance processing facility and for the Canadian Irradiation Centre from 2001 to 2007

Notes on data for MDS Nordionrsquos nuclear substance processing facility and the Canadian Irradiation Centre

1 Doses from photons from external sources were measured and reported to the NDR MDS Nordion also has a routine thyroid monitoring program very occasionally small recordable doses of radiation have occurred from thyroid uptake of iodine The resulting doses have not been historically submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided

Figure 265 Average Dose Trends for MDS Nordion (Based on Non-Zero Results)

0

05

1

15

2

25

Effe

ctiv

e D

ose

(mS

v)

Year

62

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 266 Average Dose Trends for MDS Nordion (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

Figure 267 Collective Dose Trends for MDS Nordion

0

100

200

300

400

500

600

700

800

Year

63

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 268 Distribution of Effective Doses Among All Workers at MDS Nordion

0

5 0

1 0 0

1 5 0

2 0 0

2 5 0

3 0 0

3 5 0

4 0 0

4 5 0

5 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

64

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

253 Tri-University Meson Facility

The Tri-University Meson facility (TRIUMF) is situated in Vancouver on the campus of the University of British Columbia TRIUMF which began operating in the early 1970s with one cyclotron now has two cyclotrons and associated laboratories for research and radioisotope production The laboratory provides research facilities for Canadian and international users and also produces radioisotopes which are used by medical facilities and by a commercial organization (MDS Nordion) MDS Nordion staff also work at the TRIUMF site however MDS Nordion oversees this work and has its own radiation protection program

Figures 269ndash272 present dose information for the TRIUMF facility from 2001 to 2007 Please note that data sets do not distinguish between doses received by TRIUMF staff and MDS Nordion staff who work on the site as the data for these two groups was submitted collectively to the NDR for the reporting period shown Future data for each group will be submitted separately to the NDR

Note on data for TRIUMF

1 Effective doses are composed of the following reported components bull doses from photons (labeled as ldquoexternalrdquo in the charts) bull neutron doses

Figure 269 Average Dose Trends for TRIUMF (Non-Zero Results Only)

000

020

040

060

080

100

120

140

160

Dos

e (m

Sv)

Neutrons External Effective

Year

65

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 47: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 240 Distribution of Effective Doses Among All Workers at the Cigar Lake Operation

0

200

400

600

800

1000

1200

1400

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

42

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

226 Rabbit Lake Operation

Cameco Corporation owns and operates mining facilities in Rabbit Lake located in north-eastern Saskatchewan Facilities include an underground mine four mined-out open-pit mines a mill and two tailings management facilities Mining and milling began in 1975

Figures 241ndash244 present dose information for the Rabbit Lake operation from 2001 to 2007

Figure 241 Average Dose Trends for the Rabbit Lake Operation (Based on Non-Zero Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

43

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 242 Average Dose Trends for the Rabbit Lake Operation (Based on All Monitoring Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

Figure 243 Collective Dose Trends for the Rabbit Lake Operation

0

200

400

600

800

1000

1200

1400

1600

1800

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Radon gas External Radon progeny Long-lived radioactive dust

Year

44

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

gt300

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 244 Distribution of Effective Doses Among All Workers at the Rabbit Lake Operation

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

900

800

700

600

500

400

300

200

100

0

Dose (mSv)

45

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

23 Uranium Refineries This section presents data for the following two facilities

bull a uranium refining facility in Blind River (Section 231) bull a uranium conversion facility in Port Hope (Section 232)

Graphs indicate the following average doses at each facility from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Note on data for uranium refineries

1 Doses from photons from external sources are measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay and lung counting Historically while these internal doses have been measured they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

231 Blind River Refinery

Cameco Corporation owns and is licensed to operate a uranium refinery in Blind River Ontario The facility which began operating in 1983 converts uranium ore concentrate to uranium trioxide The uranium trioxide is shipped to Camecorsquos uranium conversion facility in Port Hope Ontario where it is processed into uranium dioxide (for use in the fabrication of fuel for nuclear reactors in Canada) or uranium hexafluoride (exported for enrichment and fabrication into fuel for nuclear power reactors around the world)

Figures 245ndash248 present dose information for the Blind River refinery from 2001 to 2007

46

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 245 Average Dose Trends for the Blind River Refinery (Based on Non-Zero Results)

0

05

1

15

2

25

Year

Figure 246 Average Dose Trends for the Blind River Refinery (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

47

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 247 Collective Dose Trends for the Blind River Refinery

0

50

100

150

200

250

300 C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 248 Distribution of Effective Doses Among All Workers at the Blind River Refinery

0

20

40

60

80

100

120

140

160

180

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

48

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

232 Port Hope Conversion Facility

Cameco Corporation owns and is licensed to operate a uranium conversion facility in Port Hope Ontario The facility processes uranium trioxide received from the refinery in Blind River into uranium dioxide and uranium hexafluoride

Figures 249ndash252 present dose information for the Port Hope uranium conversion facility from 2001 to 2007

Figure 249 Average Dose Trends for the Port Hope Conversion Facility (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

49

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 250 Average Dose Trends for the Port Hope Conversion Facility (Based on All Monitoring Results)

0

01

02

03

04

05

06

07

08

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 251 Collective Dose Trends for the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

50

000-0

009

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 252 Distribution of Effective Doses Among All Workers at the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

400

450

500

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

51

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

24 Fuel Fabrication Facilities This section presents data for three nuclear fuel fabrication facilities

bull Two facilities owned and operated by General Electric Canada Inc (Section 241) bull One facility in Port Hope operated by Zircatec Precision Industries (Section 242)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average doses

Notes on data for fuel fabrication facilities

1 Effective doses for the three facilities are composed of the following reported components bull dose from photons (labelled on the charts as ldquoexternalrdquo) bull doses from internal intakes of uranium dust (long-lived radioactive dust) from

uranium in air concentrations (for General Electricrsquos Toronto facility only)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components photon doses and doses from long-lived radioactive dust

241 General Electric Nuclear Fuel Facilities

General Electric Canada Inc operates two nuclear fuel facilities in Ontario

bull At the Toronto facility uranium dioxide pellets are produced from natural or depleted uranium dioxide powder

bull At the Peterborough facility uranium dioxide fuel bundles are created from the pellets produced at the Toronto facility

Figures 253ndash256 present dose information for General Electric Canada Incrsquos fuel fabrication facilities from 2001 to 2007 Graphs do not distinguish between the doses received at the Peterborough facility versus those at the Toronto facility

52

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 253 Average Dose Trends for the General Electric Fuel Facility (Based on Non-Zero Results Only)

0

05

1

15

2

25

3

35

Long Lived Radioactive Dust External Effective

Year

Figure 254 Average Dose Trends for the General Electric Fuel Facility (Based on All Monitoring Results)

0

05

1

15

2

25

3

Long Lived Radioactive Dust External Effective

Year

Dos

e (m

Sv)

Dos

e (m

Sv)

53

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 255 Collective Dose Trends for the General Electric Fuel Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Long Lived Radioactive Dust External

Year

Figure 256 Distribution of Effective Doses among all Workers at the General Electric Fuel Facility

0

10

20

30

40

50

60

70

80

90

100

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

54

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

242 Zircatec Nuclear Fuel Facility

Zircatec Precision Industries Inc operates a nuclear fuel facility in Port Hope Ontario where it makes fuel pellets from uranium dioxide powder received from Port Hopersquos uranium conversion facility The nuclear fuel facility also manufactures fuel bundles for nuclear reactors in Canada

Notes on data for the Zircatec nuclear fuel facility

1 Graphs indicate the following data bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of average effective doses

2 Doses from photons from external sources were measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay Historically although these internal doses have been measured and submitted to the CNSC they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

Figures 257ndash260 present dose information for the Zircatec nuclear fuel facility from 2001 to 2007

Figure 257 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on Non-Zero Results)

0

05

1

15

2

25

3

35

Effe

ctiv

e D

ose

(mS

v)

Year

55

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 258 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

18

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 259 Collective Dose Trends for the Zircatec Nuclear Fuel Facility

0

50

100

150

200

250

300

350

400

450

500

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

56

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 260 Distribution of Effective Doses Among All Workers at the Zircatec Nuclear Fuel Facility

300

Num

ber o

f Wor

kers

250

200

150

100

50

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

57

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

25 Research and Radioisotope Production Facilities This section presents dose information for the following research and radioisotope production facilities from 2001 to 2007

bull Chalk River Laboratories and Whiteshell Laboratories (Section 251) bull A radioisotope production facility operated by MDS Nordion (Section 252) bull The Tri-University Meson Facility (TRIUMF) (Section 253)

Note on data for research and radioisotope production facilities

1 Graphs indicate the following data for each facility bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of effective doses

251 Chalk River Laboratories and Whiteshell Laboratories

Atomic Energy of Canada Limited (AECL) owns and is licensed to operate Chalk River Laboratories and Whiteshell Laboratories

Situated in Renfrew County on the south shore of the Ottawa River the Chalk River Laboratories site hosts the National Research Universal Reactor along with numerous other facilities occupying some 160 buildings in an area of approximately 40 km2 Activities consist of radioisotope production for nuclear medicine testing and development of structural materials in support of power reactor operations fuel fabrication research and radioactive waste management and storage

The Whiteshell Laboratories site is located approximately 10 km west of Pinawa Manitoba and 100 km northeast of Winnipeg on the east bank of the Winnipeg River AECL established the laboratories for nuclear research and testing during the early 1960s and has since discontinued operations which are being decommissioned under a licence from the CNSC

Figures 261ndash264 present dose information for Chalk River Laboratories and Whiteshell Laboratories from 2001 to 2007

Notes on data for Chalk River Laboratories and Whiteshell Laboratories

1 Effective doses are composed of the following reported components bull external doses5 (from both photon and neutron doses) bull tritium doses

Due to issues with AECLrsquos in-house dosimetry management system neutron doses were not reported separately to the NDR during the reporting period As a result external doses from photons and neutrons were totaled The reporting discrepancy has since been rectified

58

5

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of external (photon and neutron) and tritium doses Intakes of other radionuclides occasionally occur and these radionuclides are not included here because their associated doses are very small For this reason certain collective doses in this report may have values slightly lower than the sum of their respective components as listed

Figure 261 Average Dose Trends for Chalk River and Whiteshell Laboratories (Non-Zero Results Only)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Tritium External Effective

Year

59

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 262 Average Dose Trends for Chalk River and Whiteshell Laboratories (All Monitoring Results)

000

020

040

060

080

100

120

Dos

e (m

Sv)

Tritium External Effective

Year

Figure 263 Collective Dose Trends for Chalk River and Whiteshell Laboratories

0

500

1000

1500

2000

2500

3000

3500

Col

lect

ive

Dos

e (p

erso

n- m

Sv)

External Tritium

Year

60

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 264 Distribution of Effective Doses Among All Workers at Chalk River and Whiteshell Laboratories

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

3500

3000

2500

2000

1500

1000

500

Dose (mSv)

61

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

252 MDS Nordion (Nuclear Substance Processing Facility and Canadian Irradiation Centre)

MDS Nordion owns and operates a nuclear substance processing facility in Ottawa Ontario where it processes unsealed radioisotopes and manufactures sealed radiation sources In operation since the early 1970s the facility was purchased by Nordion International in 1991

In cooperation with the Universiteacute du Queacutebecrsquos Institut Armand-Frappier MDS Nordion also operates the Canadian Irradiation Centre which conducts various irradiation services which include training testing and development The centre is located in Laval Quebec on the Universiteacute du Queacutebec campus

Figures 265ndash268 present dose information for MDS Nordionrsquos Ottawa nuclear substance processing facility and for the Canadian Irradiation Centre from 2001 to 2007

Notes on data for MDS Nordionrsquos nuclear substance processing facility and the Canadian Irradiation Centre

1 Doses from photons from external sources were measured and reported to the NDR MDS Nordion also has a routine thyroid monitoring program very occasionally small recordable doses of radiation have occurred from thyroid uptake of iodine The resulting doses have not been historically submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided

Figure 265 Average Dose Trends for MDS Nordion (Based on Non-Zero Results)

0

05

1

15

2

25

Effe

ctiv

e D

ose

(mS

v)

Year

62

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 266 Average Dose Trends for MDS Nordion (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

Figure 267 Collective Dose Trends for MDS Nordion

0

100

200

300

400

500

600

700

800

Year

63

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 268 Distribution of Effective Doses Among All Workers at MDS Nordion

0

5 0

1 0 0

1 5 0

2 0 0

2 5 0

3 0 0

3 5 0

4 0 0

4 5 0

5 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

64

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

253 Tri-University Meson Facility

The Tri-University Meson facility (TRIUMF) is situated in Vancouver on the campus of the University of British Columbia TRIUMF which began operating in the early 1970s with one cyclotron now has two cyclotrons and associated laboratories for research and radioisotope production The laboratory provides research facilities for Canadian and international users and also produces radioisotopes which are used by medical facilities and by a commercial organization (MDS Nordion) MDS Nordion staff also work at the TRIUMF site however MDS Nordion oversees this work and has its own radiation protection program

Figures 269ndash272 present dose information for the TRIUMF facility from 2001 to 2007 Please note that data sets do not distinguish between doses received by TRIUMF staff and MDS Nordion staff who work on the site as the data for these two groups was submitted collectively to the NDR for the reporting period shown Future data for each group will be submitted separately to the NDR

Note on data for TRIUMF

1 Effective doses are composed of the following reported components bull doses from photons (labeled as ldquoexternalrdquo in the charts) bull neutron doses

Figure 269 Average Dose Trends for TRIUMF (Non-Zero Results Only)

000

020

040

060

080

100

120

140

160

Dos

e (m

Sv)

Neutrons External Effective

Year

65

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 48: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

226 Rabbit Lake Operation

Cameco Corporation owns and operates mining facilities in Rabbit Lake located in north-eastern Saskatchewan Facilities include an underground mine four mined-out open-pit mines a mill and two tailings management facilities Mining and milling began in 1975

Figures 241ndash244 present dose information for the Rabbit Lake operation from 2001 to 2007

Figure 241 Average Dose Trends for the Rabbit Lake Operation (Based on Non-Zero Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

43

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 242 Average Dose Trends for the Rabbit Lake Operation (Based on All Monitoring Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

Figure 243 Collective Dose Trends for the Rabbit Lake Operation

0

200

400

600

800

1000

1200

1400

1600

1800

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Radon gas External Radon progeny Long-lived radioactive dust

Year

44

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

gt300

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 244 Distribution of Effective Doses Among All Workers at the Rabbit Lake Operation

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

900

800

700

600

500

400

300

200

100

0

Dose (mSv)

45

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

23 Uranium Refineries This section presents data for the following two facilities

bull a uranium refining facility in Blind River (Section 231) bull a uranium conversion facility in Port Hope (Section 232)

Graphs indicate the following average doses at each facility from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Note on data for uranium refineries

1 Doses from photons from external sources are measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay and lung counting Historically while these internal doses have been measured they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

231 Blind River Refinery

Cameco Corporation owns and is licensed to operate a uranium refinery in Blind River Ontario The facility which began operating in 1983 converts uranium ore concentrate to uranium trioxide The uranium trioxide is shipped to Camecorsquos uranium conversion facility in Port Hope Ontario where it is processed into uranium dioxide (for use in the fabrication of fuel for nuclear reactors in Canada) or uranium hexafluoride (exported for enrichment and fabrication into fuel for nuclear power reactors around the world)

Figures 245ndash248 present dose information for the Blind River refinery from 2001 to 2007

46

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 245 Average Dose Trends for the Blind River Refinery (Based on Non-Zero Results)

0

05

1

15

2

25

Year

Figure 246 Average Dose Trends for the Blind River Refinery (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

47

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 247 Collective Dose Trends for the Blind River Refinery

0

50

100

150

200

250

300 C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 248 Distribution of Effective Doses Among All Workers at the Blind River Refinery

0

20

40

60

80

100

120

140

160

180

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

48

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

232 Port Hope Conversion Facility

Cameco Corporation owns and is licensed to operate a uranium conversion facility in Port Hope Ontario The facility processes uranium trioxide received from the refinery in Blind River into uranium dioxide and uranium hexafluoride

Figures 249ndash252 present dose information for the Port Hope uranium conversion facility from 2001 to 2007

Figure 249 Average Dose Trends for the Port Hope Conversion Facility (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

49

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 250 Average Dose Trends for the Port Hope Conversion Facility (Based on All Monitoring Results)

0

01

02

03

04

05

06

07

08

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 251 Collective Dose Trends for the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

50

000-0

009

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 252 Distribution of Effective Doses Among All Workers at the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

400

450

500

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

51

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

24 Fuel Fabrication Facilities This section presents data for three nuclear fuel fabrication facilities

bull Two facilities owned and operated by General Electric Canada Inc (Section 241) bull One facility in Port Hope operated by Zircatec Precision Industries (Section 242)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average doses

Notes on data for fuel fabrication facilities

1 Effective doses for the three facilities are composed of the following reported components bull dose from photons (labelled on the charts as ldquoexternalrdquo) bull doses from internal intakes of uranium dust (long-lived radioactive dust) from

uranium in air concentrations (for General Electricrsquos Toronto facility only)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components photon doses and doses from long-lived radioactive dust

241 General Electric Nuclear Fuel Facilities

General Electric Canada Inc operates two nuclear fuel facilities in Ontario

bull At the Toronto facility uranium dioxide pellets are produced from natural or depleted uranium dioxide powder

bull At the Peterborough facility uranium dioxide fuel bundles are created from the pellets produced at the Toronto facility

Figures 253ndash256 present dose information for General Electric Canada Incrsquos fuel fabrication facilities from 2001 to 2007 Graphs do not distinguish between the doses received at the Peterborough facility versus those at the Toronto facility

52

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 253 Average Dose Trends for the General Electric Fuel Facility (Based on Non-Zero Results Only)

0

05

1

15

2

25

3

35

Long Lived Radioactive Dust External Effective

Year

Figure 254 Average Dose Trends for the General Electric Fuel Facility (Based on All Monitoring Results)

0

05

1

15

2

25

3

Long Lived Radioactive Dust External Effective

Year

Dos

e (m

Sv)

Dos

e (m

Sv)

53

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 255 Collective Dose Trends for the General Electric Fuel Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Long Lived Radioactive Dust External

Year

Figure 256 Distribution of Effective Doses among all Workers at the General Electric Fuel Facility

0

10

20

30

40

50

60

70

80

90

100

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

54

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

242 Zircatec Nuclear Fuel Facility

Zircatec Precision Industries Inc operates a nuclear fuel facility in Port Hope Ontario where it makes fuel pellets from uranium dioxide powder received from Port Hopersquos uranium conversion facility The nuclear fuel facility also manufactures fuel bundles for nuclear reactors in Canada

Notes on data for the Zircatec nuclear fuel facility

1 Graphs indicate the following data bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of average effective doses

2 Doses from photons from external sources were measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay Historically although these internal doses have been measured and submitted to the CNSC they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

Figures 257ndash260 present dose information for the Zircatec nuclear fuel facility from 2001 to 2007

Figure 257 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on Non-Zero Results)

0

05

1

15

2

25

3

35

Effe

ctiv

e D

ose

(mS

v)

Year

55

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 258 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

18

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 259 Collective Dose Trends for the Zircatec Nuclear Fuel Facility

0

50

100

150

200

250

300

350

400

450

500

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

56

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 260 Distribution of Effective Doses Among All Workers at the Zircatec Nuclear Fuel Facility

300

Num

ber o

f Wor

kers

250

200

150

100

50

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

57

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

25 Research and Radioisotope Production Facilities This section presents dose information for the following research and radioisotope production facilities from 2001 to 2007

bull Chalk River Laboratories and Whiteshell Laboratories (Section 251) bull A radioisotope production facility operated by MDS Nordion (Section 252) bull The Tri-University Meson Facility (TRIUMF) (Section 253)

Note on data for research and radioisotope production facilities

1 Graphs indicate the following data for each facility bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of effective doses

251 Chalk River Laboratories and Whiteshell Laboratories

Atomic Energy of Canada Limited (AECL) owns and is licensed to operate Chalk River Laboratories and Whiteshell Laboratories

Situated in Renfrew County on the south shore of the Ottawa River the Chalk River Laboratories site hosts the National Research Universal Reactor along with numerous other facilities occupying some 160 buildings in an area of approximately 40 km2 Activities consist of radioisotope production for nuclear medicine testing and development of structural materials in support of power reactor operations fuel fabrication research and radioactive waste management and storage

The Whiteshell Laboratories site is located approximately 10 km west of Pinawa Manitoba and 100 km northeast of Winnipeg on the east bank of the Winnipeg River AECL established the laboratories for nuclear research and testing during the early 1960s and has since discontinued operations which are being decommissioned under a licence from the CNSC

Figures 261ndash264 present dose information for Chalk River Laboratories and Whiteshell Laboratories from 2001 to 2007

Notes on data for Chalk River Laboratories and Whiteshell Laboratories

1 Effective doses are composed of the following reported components bull external doses5 (from both photon and neutron doses) bull tritium doses

Due to issues with AECLrsquos in-house dosimetry management system neutron doses were not reported separately to the NDR during the reporting period As a result external doses from photons and neutrons were totaled The reporting discrepancy has since been rectified

58

5

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of external (photon and neutron) and tritium doses Intakes of other radionuclides occasionally occur and these radionuclides are not included here because their associated doses are very small For this reason certain collective doses in this report may have values slightly lower than the sum of their respective components as listed

Figure 261 Average Dose Trends for Chalk River and Whiteshell Laboratories (Non-Zero Results Only)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Tritium External Effective

Year

59

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 262 Average Dose Trends for Chalk River and Whiteshell Laboratories (All Monitoring Results)

000

020

040

060

080

100

120

Dos

e (m

Sv)

Tritium External Effective

Year

Figure 263 Collective Dose Trends for Chalk River and Whiteshell Laboratories

0

500

1000

1500

2000

2500

3000

3500

Col

lect

ive

Dos

e (p

erso

n- m

Sv)

External Tritium

Year

60

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 264 Distribution of Effective Doses Among All Workers at Chalk River and Whiteshell Laboratories

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

3500

3000

2500

2000

1500

1000

500

Dose (mSv)

61

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

252 MDS Nordion (Nuclear Substance Processing Facility and Canadian Irradiation Centre)

MDS Nordion owns and operates a nuclear substance processing facility in Ottawa Ontario where it processes unsealed radioisotopes and manufactures sealed radiation sources In operation since the early 1970s the facility was purchased by Nordion International in 1991

In cooperation with the Universiteacute du Queacutebecrsquos Institut Armand-Frappier MDS Nordion also operates the Canadian Irradiation Centre which conducts various irradiation services which include training testing and development The centre is located in Laval Quebec on the Universiteacute du Queacutebec campus

Figures 265ndash268 present dose information for MDS Nordionrsquos Ottawa nuclear substance processing facility and for the Canadian Irradiation Centre from 2001 to 2007

Notes on data for MDS Nordionrsquos nuclear substance processing facility and the Canadian Irradiation Centre

1 Doses from photons from external sources were measured and reported to the NDR MDS Nordion also has a routine thyroid monitoring program very occasionally small recordable doses of radiation have occurred from thyroid uptake of iodine The resulting doses have not been historically submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided

Figure 265 Average Dose Trends for MDS Nordion (Based on Non-Zero Results)

0

05

1

15

2

25

Effe

ctiv

e D

ose

(mS

v)

Year

62

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 266 Average Dose Trends for MDS Nordion (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

Figure 267 Collective Dose Trends for MDS Nordion

0

100

200

300

400

500

600

700

800

Year

63

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 268 Distribution of Effective Doses Among All Workers at MDS Nordion

0

5 0

1 0 0

1 5 0

2 0 0

2 5 0

3 0 0

3 5 0

4 0 0

4 5 0

5 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

64

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

253 Tri-University Meson Facility

The Tri-University Meson facility (TRIUMF) is situated in Vancouver on the campus of the University of British Columbia TRIUMF which began operating in the early 1970s with one cyclotron now has two cyclotrons and associated laboratories for research and radioisotope production The laboratory provides research facilities for Canadian and international users and also produces radioisotopes which are used by medical facilities and by a commercial organization (MDS Nordion) MDS Nordion staff also work at the TRIUMF site however MDS Nordion oversees this work and has its own radiation protection program

Figures 269ndash272 present dose information for the TRIUMF facility from 2001 to 2007 Please note that data sets do not distinguish between doses received by TRIUMF staff and MDS Nordion staff who work on the site as the data for these two groups was submitted collectively to the NDR for the reporting period shown Future data for each group will be submitted separately to the NDR

Note on data for TRIUMF

1 Effective doses are composed of the following reported components bull doses from photons (labeled as ldquoexternalrdquo in the charts) bull neutron doses

Figure 269 Average Dose Trends for TRIUMF (Non-Zero Results Only)

000

020

040

060

080

100

120

140

160

Dos

e (m

Sv)

Neutrons External Effective

Year

65

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 49: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 242 Average Dose Trends for the Rabbit Lake Operation (Based on All Monitoring Results)

000

050

100

150

200

250

300

350

Dos

e (m

Sv) Long-lived radioactive dust

Radon progeny External Effective Radon gas

Year

Figure 243 Collective Dose Trends for the Rabbit Lake Operation

0

200

400

600

800

1000

1200

1400

1600

1800

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Radon gas External Radon progeny Long-lived radioactive dust

Year

44

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

gt300

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 244 Distribution of Effective Doses Among All Workers at the Rabbit Lake Operation

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

900

800

700

600

500

400

300

200

100

0

Dose (mSv)

45

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

23 Uranium Refineries This section presents data for the following two facilities

bull a uranium refining facility in Blind River (Section 231) bull a uranium conversion facility in Port Hope (Section 232)

Graphs indicate the following average doses at each facility from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Note on data for uranium refineries

1 Doses from photons from external sources are measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay and lung counting Historically while these internal doses have been measured they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

231 Blind River Refinery

Cameco Corporation owns and is licensed to operate a uranium refinery in Blind River Ontario The facility which began operating in 1983 converts uranium ore concentrate to uranium trioxide The uranium trioxide is shipped to Camecorsquos uranium conversion facility in Port Hope Ontario where it is processed into uranium dioxide (for use in the fabrication of fuel for nuclear reactors in Canada) or uranium hexafluoride (exported for enrichment and fabrication into fuel for nuclear power reactors around the world)

Figures 245ndash248 present dose information for the Blind River refinery from 2001 to 2007

46

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 245 Average Dose Trends for the Blind River Refinery (Based on Non-Zero Results)

0

05

1

15

2

25

Year

Figure 246 Average Dose Trends for the Blind River Refinery (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

47

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 247 Collective Dose Trends for the Blind River Refinery

0

50

100

150

200

250

300 C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 248 Distribution of Effective Doses Among All Workers at the Blind River Refinery

0

20

40

60

80

100

120

140

160

180

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

48

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

232 Port Hope Conversion Facility

Cameco Corporation owns and is licensed to operate a uranium conversion facility in Port Hope Ontario The facility processes uranium trioxide received from the refinery in Blind River into uranium dioxide and uranium hexafluoride

Figures 249ndash252 present dose information for the Port Hope uranium conversion facility from 2001 to 2007

Figure 249 Average Dose Trends for the Port Hope Conversion Facility (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

49

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 250 Average Dose Trends for the Port Hope Conversion Facility (Based on All Monitoring Results)

0

01

02

03

04

05

06

07

08

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 251 Collective Dose Trends for the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

50

000-0

009

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 252 Distribution of Effective Doses Among All Workers at the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

400

450

500

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

51

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

24 Fuel Fabrication Facilities This section presents data for three nuclear fuel fabrication facilities

bull Two facilities owned and operated by General Electric Canada Inc (Section 241) bull One facility in Port Hope operated by Zircatec Precision Industries (Section 242)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average doses

Notes on data for fuel fabrication facilities

1 Effective doses for the three facilities are composed of the following reported components bull dose from photons (labelled on the charts as ldquoexternalrdquo) bull doses from internal intakes of uranium dust (long-lived radioactive dust) from

uranium in air concentrations (for General Electricrsquos Toronto facility only)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components photon doses and doses from long-lived radioactive dust

241 General Electric Nuclear Fuel Facilities

General Electric Canada Inc operates two nuclear fuel facilities in Ontario

bull At the Toronto facility uranium dioxide pellets are produced from natural or depleted uranium dioxide powder

bull At the Peterborough facility uranium dioxide fuel bundles are created from the pellets produced at the Toronto facility

Figures 253ndash256 present dose information for General Electric Canada Incrsquos fuel fabrication facilities from 2001 to 2007 Graphs do not distinguish between the doses received at the Peterborough facility versus those at the Toronto facility

52

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 253 Average Dose Trends for the General Electric Fuel Facility (Based on Non-Zero Results Only)

0

05

1

15

2

25

3

35

Long Lived Radioactive Dust External Effective

Year

Figure 254 Average Dose Trends for the General Electric Fuel Facility (Based on All Monitoring Results)

0

05

1

15

2

25

3

Long Lived Radioactive Dust External Effective

Year

Dos

e (m

Sv)

Dos

e (m

Sv)

53

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 255 Collective Dose Trends for the General Electric Fuel Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Long Lived Radioactive Dust External

Year

Figure 256 Distribution of Effective Doses among all Workers at the General Electric Fuel Facility

0

10

20

30

40

50

60

70

80

90

100

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

54

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

242 Zircatec Nuclear Fuel Facility

Zircatec Precision Industries Inc operates a nuclear fuel facility in Port Hope Ontario where it makes fuel pellets from uranium dioxide powder received from Port Hopersquos uranium conversion facility The nuclear fuel facility also manufactures fuel bundles for nuclear reactors in Canada

Notes on data for the Zircatec nuclear fuel facility

1 Graphs indicate the following data bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of average effective doses

2 Doses from photons from external sources were measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay Historically although these internal doses have been measured and submitted to the CNSC they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

Figures 257ndash260 present dose information for the Zircatec nuclear fuel facility from 2001 to 2007

Figure 257 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on Non-Zero Results)

0

05

1

15

2

25

3

35

Effe

ctiv

e D

ose

(mS

v)

Year

55

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 258 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

18

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 259 Collective Dose Trends for the Zircatec Nuclear Fuel Facility

0

50

100

150

200

250

300

350

400

450

500

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

56

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 260 Distribution of Effective Doses Among All Workers at the Zircatec Nuclear Fuel Facility

300

Num

ber o

f Wor

kers

250

200

150

100

50

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

57

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

25 Research and Radioisotope Production Facilities This section presents dose information for the following research and radioisotope production facilities from 2001 to 2007

bull Chalk River Laboratories and Whiteshell Laboratories (Section 251) bull A radioisotope production facility operated by MDS Nordion (Section 252) bull The Tri-University Meson Facility (TRIUMF) (Section 253)

Note on data for research and radioisotope production facilities

1 Graphs indicate the following data for each facility bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of effective doses

251 Chalk River Laboratories and Whiteshell Laboratories

Atomic Energy of Canada Limited (AECL) owns and is licensed to operate Chalk River Laboratories and Whiteshell Laboratories

Situated in Renfrew County on the south shore of the Ottawa River the Chalk River Laboratories site hosts the National Research Universal Reactor along with numerous other facilities occupying some 160 buildings in an area of approximately 40 km2 Activities consist of radioisotope production for nuclear medicine testing and development of structural materials in support of power reactor operations fuel fabrication research and radioactive waste management and storage

The Whiteshell Laboratories site is located approximately 10 km west of Pinawa Manitoba and 100 km northeast of Winnipeg on the east bank of the Winnipeg River AECL established the laboratories for nuclear research and testing during the early 1960s and has since discontinued operations which are being decommissioned under a licence from the CNSC

Figures 261ndash264 present dose information for Chalk River Laboratories and Whiteshell Laboratories from 2001 to 2007

Notes on data for Chalk River Laboratories and Whiteshell Laboratories

1 Effective doses are composed of the following reported components bull external doses5 (from both photon and neutron doses) bull tritium doses

Due to issues with AECLrsquos in-house dosimetry management system neutron doses were not reported separately to the NDR during the reporting period As a result external doses from photons and neutrons were totaled The reporting discrepancy has since been rectified

58

5

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of external (photon and neutron) and tritium doses Intakes of other radionuclides occasionally occur and these radionuclides are not included here because their associated doses are very small For this reason certain collective doses in this report may have values slightly lower than the sum of their respective components as listed

Figure 261 Average Dose Trends for Chalk River and Whiteshell Laboratories (Non-Zero Results Only)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Tritium External Effective

Year

59

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 262 Average Dose Trends for Chalk River and Whiteshell Laboratories (All Monitoring Results)

000

020

040

060

080

100

120

Dos

e (m

Sv)

Tritium External Effective

Year

Figure 263 Collective Dose Trends for Chalk River and Whiteshell Laboratories

0

500

1000

1500

2000

2500

3000

3500

Col

lect

ive

Dos

e (p

erso

n- m

Sv)

External Tritium

Year

60

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 264 Distribution of Effective Doses Among All Workers at Chalk River and Whiteshell Laboratories

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

3500

3000

2500

2000

1500

1000

500

Dose (mSv)

61

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

252 MDS Nordion (Nuclear Substance Processing Facility and Canadian Irradiation Centre)

MDS Nordion owns and operates a nuclear substance processing facility in Ottawa Ontario where it processes unsealed radioisotopes and manufactures sealed radiation sources In operation since the early 1970s the facility was purchased by Nordion International in 1991

In cooperation with the Universiteacute du Queacutebecrsquos Institut Armand-Frappier MDS Nordion also operates the Canadian Irradiation Centre which conducts various irradiation services which include training testing and development The centre is located in Laval Quebec on the Universiteacute du Queacutebec campus

Figures 265ndash268 present dose information for MDS Nordionrsquos Ottawa nuclear substance processing facility and for the Canadian Irradiation Centre from 2001 to 2007

Notes on data for MDS Nordionrsquos nuclear substance processing facility and the Canadian Irradiation Centre

1 Doses from photons from external sources were measured and reported to the NDR MDS Nordion also has a routine thyroid monitoring program very occasionally small recordable doses of radiation have occurred from thyroid uptake of iodine The resulting doses have not been historically submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided

Figure 265 Average Dose Trends for MDS Nordion (Based on Non-Zero Results)

0

05

1

15

2

25

Effe

ctiv

e D

ose

(mS

v)

Year

62

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 266 Average Dose Trends for MDS Nordion (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

Figure 267 Collective Dose Trends for MDS Nordion

0

100

200

300

400

500

600

700

800

Year

63

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 268 Distribution of Effective Doses Among All Workers at MDS Nordion

0

5 0

1 0 0

1 5 0

2 0 0

2 5 0

3 0 0

3 5 0

4 0 0

4 5 0

5 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

64

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

253 Tri-University Meson Facility

The Tri-University Meson facility (TRIUMF) is situated in Vancouver on the campus of the University of British Columbia TRIUMF which began operating in the early 1970s with one cyclotron now has two cyclotrons and associated laboratories for research and radioisotope production The laboratory provides research facilities for Canadian and international users and also produces radioisotopes which are used by medical facilities and by a commercial organization (MDS Nordion) MDS Nordion staff also work at the TRIUMF site however MDS Nordion oversees this work and has its own radiation protection program

Figures 269ndash272 present dose information for the TRIUMF facility from 2001 to 2007 Please note that data sets do not distinguish between doses received by TRIUMF staff and MDS Nordion staff who work on the site as the data for these two groups was submitted collectively to the NDR for the reporting period shown Future data for each group will be submitted separately to the NDR

Note on data for TRIUMF

1 Effective doses are composed of the following reported components bull doses from photons (labeled as ldquoexternalrdquo in the charts) bull neutron doses

Figure 269 Average Dose Trends for TRIUMF (Non-Zero Results Only)

000

020

040

060

080

100

120

140

160

Dos

e (m

Sv)

Neutrons External Effective

Year

65

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 50: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

gt300

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 244 Distribution of Effective Doses Among All Workers at the Rabbit Lake Operation

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

900

800

700

600

500

400

300

200

100

0

Dose (mSv)

45

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

23 Uranium Refineries This section presents data for the following two facilities

bull a uranium refining facility in Blind River (Section 231) bull a uranium conversion facility in Port Hope (Section 232)

Graphs indicate the following average doses at each facility from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Note on data for uranium refineries

1 Doses from photons from external sources are measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay and lung counting Historically while these internal doses have been measured they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

231 Blind River Refinery

Cameco Corporation owns and is licensed to operate a uranium refinery in Blind River Ontario The facility which began operating in 1983 converts uranium ore concentrate to uranium trioxide The uranium trioxide is shipped to Camecorsquos uranium conversion facility in Port Hope Ontario where it is processed into uranium dioxide (for use in the fabrication of fuel for nuclear reactors in Canada) or uranium hexafluoride (exported for enrichment and fabrication into fuel for nuclear power reactors around the world)

Figures 245ndash248 present dose information for the Blind River refinery from 2001 to 2007

46

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 245 Average Dose Trends for the Blind River Refinery (Based on Non-Zero Results)

0

05

1

15

2

25

Year

Figure 246 Average Dose Trends for the Blind River Refinery (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

47

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 247 Collective Dose Trends for the Blind River Refinery

0

50

100

150

200

250

300 C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 248 Distribution of Effective Doses Among All Workers at the Blind River Refinery

0

20

40

60

80

100

120

140

160

180

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

48

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

232 Port Hope Conversion Facility

Cameco Corporation owns and is licensed to operate a uranium conversion facility in Port Hope Ontario The facility processes uranium trioxide received from the refinery in Blind River into uranium dioxide and uranium hexafluoride

Figures 249ndash252 present dose information for the Port Hope uranium conversion facility from 2001 to 2007

Figure 249 Average Dose Trends for the Port Hope Conversion Facility (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

49

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 250 Average Dose Trends for the Port Hope Conversion Facility (Based on All Monitoring Results)

0

01

02

03

04

05

06

07

08

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 251 Collective Dose Trends for the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

50

000-0

009

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 252 Distribution of Effective Doses Among All Workers at the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

400

450

500

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

51

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

24 Fuel Fabrication Facilities This section presents data for three nuclear fuel fabrication facilities

bull Two facilities owned and operated by General Electric Canada Inc (Section 241) bull One facility in Port Hope operated by Zircatec Precision Industries (Section 242)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average doses

Notes on data for fuel fabrication facilities

1 Effective doses for the three facilities are composed of the following reported components bull dose from photons (labelled on the charts as ldquoexternalrdquo) bull doses from internal intakes of uranium dust (long-lived radioactive dust) from

uranium in air concentrations (for General Electricrsquos Toronto facility only)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components photon doses and doses from long-lived radioactive dust

241 General Electric Nuclear Fuel Facilities

General Electric Canada Inc operates two nuclear fuel facilities in Ontario

bull At the Toronto facility uranium dioxide pellets are produced from natural or depleted uranium dioxide powder

bull At the Peterborough facility uranium dioxide fuel bundles are created from the pellets produced at the Toronto facility

Figures 253ndash256 present dose information for General Electric Canada Incrsquos fuel fabrication facilities from 2001 to 2007 Graphs do not distinguish between the doses received at the Peterborough facility versus those at the Toronto facility

52

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 253 Average Dose Trends for the General Electric Fuel Facility (Based on Non-Zero Results Only)

0

05

1

15

2

25

3

35

Long Lived Radioactive Dust External Effective

Year

Figure 254 Average Dose Trends for the General Electric Fuel Facility (Based on All Monitoring Results)

0

05

1

15

2

25

3

Long Lived Radioactive Dust External Effective

Year

Dos

e (m

Sv)

Dos

e (m

Sv)

53

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 255 Collective Dose Trends for the General Electric Fuel Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Long Lived Radioactive Dust External

Year

Figure 256 Distribution of Effective Doses among all Workers at the General Electric Fuel Facility

0

10

20

30

40

50

60

70

80

90

100

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

54

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

242 Zircatec Nuclear Fuel Facility

Zircatec Precision Industries Inc operates a nuclear fuel facility in Port Hope Ontario where it makes fuel pellets from uranium dioxide powder received from Port Hopersquos uranium conversion facility The nuclear fuel facility also manufactures fuel bundles for nuclear reactors in Canada

Notes on data for the Zircatec nuclear fuel facility

1 Graphs indicate the following data bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of average effective doses

2 Doses from photons from external sources were measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay Historically although these internal doses have been measured and submitted to the CNSC they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

Figures 257ndash260 present dose information for the Zircatec nuclear fuel facility from 2001 to 2007

Figure 257 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on Non-Zero Results)

0

05

1

15

2

25

3

35

Effe

ctiv

e D

ose

(mS

v)

Year

55

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 258 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

18

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 259 Collective Dose Trends for the Zircatec Nuclear Fuel Facility

0

50

100

150

200

250

300

350

400

450

500

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

56

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 260 Distribution of Effective Doses Among All Workers at the Zircatec Nuclear Fuel Facility

300

Num

ber o

f Wor

kers

250

200

150

100

50

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

57

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

25 Research and Radioisotope Production Facilities This section presents dose information for the following research and radioisotope production facilities from 2001 to 2007

bull Chalk River Laboratories and Whiteshell Laboratories (Section 251) bull A radioisotope production facility operated by MDS Nordion (Section 252) bull The Tri-University Meson Facility (TRIUMF) (Section 253)

Note on data for research and radioisotope production facilities

1 Graphs indicate the following data for each facility bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of effective doses

251 Chalk River Laboratories and Whiteshell Laboratories

Atomic Energy of Canada Limited (AECL) owns and is licensed to operate Chalk River Laboratories and Whiteshell Laboratories

Situated in Renfrew County on the south shore of the Ottawa River the Chalk River Laboratories site hosts the National Research Universal Reactor along with numerous other facilities occupying some 160 buildings in an area of approximately 40 km2 Activities consist of radioisotope production for nuclear medicine testing and development of structural materials in support of power reactor operations fuel fabrication research and radioactive waste management and storage

The Whiteshell Laboratories site is located approximately 10 km west of Pinawa Manitoba and 100 km northeast of Winnipeg on the east bank of the Winnipeg River AECL established the laboratories for nuclear research and testing during the early 1960s and has since discontinued operations which are being decommissioned under a licence from the CNSC

Figures 261ndash264 present dose information for Chalk River Laboratories and Whiteshell Laboratories from 2001 to 2007

Notes on data for Chalk River Laboratories and Whiteshell Laboratories

1 Effective doses are composed of the following reported components bull external doses5 (from both photon and neutron doses) bull tritium doses

Due to issues with AECLrsquos in-house dosimetry management system neutron doses were not reported separately to the NDR during the reporting period As a result external doses from photons and neutrons were totaled The reporting discrepancy has since been rectified

58

5

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of external (photon and neutron) and tritium doses Intakes of other radionuclides occasionally occur and these radionuclides are not included here because their associated doses are very small For this reason certain collective doses in this report may have values slightly lower than the sum of their respective components as listed

Figure 261 Average Dose Trends for Chalk River and Whiteshell Laboratories (Non-Zero Results Only)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Tritium External Effective

Year

59

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 262 Average Dose Trends for Chalk River and Whiteshell Laboratories (All Monitoring Results)

000

020

040

060

080

100

120

Dos

e (m

Sv)

Tritium External Effective

Year

Figure 263 Collective Dose Trends for Chalk River and Whiteshell Laboratories

0

500

1000

1500

2000

2500

3000

3500

Col

lect

ive

Dos

e (p

erso

n- m

Sv)

External Tritium

Year

60

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 264 Distribution of Effective Doses Among All Workers at Chalk River and Whiteshell Laboratories

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

3500

3000

2500

2000

1500

1000

500

Dose (mSv)

61

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

252 MDS Nordion (Nuclear Substance Processing Facility and Canadian Irradiation Centre)

MDS Nordion owns and operates a nuclear substance processing facility in Ottawa Ontario where it processes unsealed radioisotopes and manufactures sealed radiation sources In operation since the early 1970s the facility was purchased by Nordion International in 1991

In cooperation with the Universiteacute du Queacutebecrsquos Institut Armand-Frappier MDS Nordion also operates the Canadian Irradiation Centre which conducts various irradiation services which include training testing and development The centre is located in Laval Quebec on the Universiteacute du Queacutebec campus

Figures 265ndash268 present dose information for MDS Nordionrsquos Ottawa nuclear substance processing facility and for the Canadian Irradiation Centre from 2001 to 2007

Notes on data for MDS Nordionrsquos nuclear substance processing facility and the Canadian Irradiation Centre

1 Doses from photons from external sources were measured and reported to the NDR MDS Nordion also has a routine thyroid monitoring program very occasionally small recordable doses of radiation have occurred from thyroid uptake of iodine The resulting doses have not been historically submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided

Figure 265 Average Dose Trends for MDS Nordion (Based on Non-Zero Results)

0

05

1

15

2

25

Effe

ctiv

e D

ose

(mS

v)

Year

62

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 266 Average Dose Trends for MDS Nordion (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

Figure 267 Collective Dose Trends for MDS Nordion

0

100

200

300

400

500

600

700

800

Year

63

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 268 Distribution of Effective Doses Among All Workers at MDS Nordion

0

5 0

1 0 0

1 5 0

2 0 0

2 5 0

3 0 0

3 5 0

4 0 0

4 5 0

5 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

64

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

253 Tri-University Meson Facility

The Tri-University Meson facility (TRIUMF) is situated in Vancouver on the campus of the University of British Columbia TRIUMF which began operating in the early 1970s with one cyclotron now has two cyclotrons and associated laboratories for research and radioisotope production The laboratory provides research facilities for Canadian and international users and also produces radioisotopes which are used by medical facilities and by a commercial organization (MDS Nordion) MDS Nordion staff also work at the TRIUMF site however MDS Nordion oversees this work and has its own radiation protection program

Figures 269ndash272 present dose information for the TRIUMF facility from 2001 to 2007 Please note that data sets do not distinguish between doses received by TRIUMF staff and MDS Nordion staff who work on the site as the data for these two groups was submitted collectively to the NDR for the reporting period shown Future data for each group will be submitted separately to the NDR

Note on data for TRIUMF

1 Effective doses are composed of the following reported components bull doses from photons (labeled as ldquoexternalrdquo in the charts) bull neutron doses

Figure 269 Average Dose Trends for TRIUMF (Non-Zero Results Only)

000

020

040

060

080

100

120

140

160

Dos

e (m

Sv)

Neutrons External Effective

Year

65

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 51: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

23 Uranium Refineries This section presents data for the following two facilities

bull a uranium refining facility in Blind River (Section 231) bull a uranium conversion facility in Port Hope (Section 232)

Graphs indicate the following average doses at each facility from 2001 to 2007

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Note on data for uranium refineries

1 Doses from photons from external sources are measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay and lung counting Historically while these internal doses have been measured they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

231 Blind River Refinery

Cameco Corporation owns and is licensed to operate a uranium refinery in Blind River Ontario The facility which began operating in 1983 converts uranium ore concentrate to uranium trioxide The uranium trioxide is shipped to Camecorsquos uranium conversion facility in Port Hope Ontario where it is processed into uranium dioxide (for use in the fabrication of fuel for nuclear reactors in Canada) or uranium hexafluoride (exported for enrichment and fabrication into fuel for nuclear power reactors around the world)

Figures 245ndash248 present dose information for the Blind River refinery from 2001 to 2007

46

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 245 Average Dose Trends for the Blind River Refinery (Based on Non-Zero Results)

0

05

1

15

2

25

Year

Figure 246 Average Dose Trends for the Blind River Refinery (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

47

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 247 Collective Dose Trends for the Blind River Refinery

0

50

100

150

200

250

300 C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 248 Distribution of Effective Doses Among All Workers at the Blind River Refinery

0

20

40

60

80

100

120

140

160

180

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

48

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

232 Port Hope Conversion Facility

Cameco Corporation owns and is licensed to operate a uranium conversion facility in Port Hope Ontario The facility processes uranium trioxide received from the refinery in Blind River into uranium dioxide and uranium hexafluoride

Figures 249ndash252 present dose information for the Port Hope uranium conversion facility from 2001 to 2007

Figure 249 Average Dose Trends for the Port Hope Conversion Facility (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

49

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 250 Average Dose Trends for the Port Hope Conversion Facility (Based on All Monitoring Results)

0

01

02

03

04

05

06

07

08

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 251 Collective Dose Trends for the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

50

000-0

009

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 252 Distribution of Effective Doses Among All Workers at the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

400

450

500

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

51

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

24 Fuel Fabrication Facilities This section presents data for three nuclear fuel fabrication facilities

bull Two facilities owned and operated by General Electric Canada Inc (Section 241) bull One facility in Port Hope operated by Zircatec Precision Industries (Section 242)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average doses

Notes on data for fuel fabrication facilities

1 Effective doses for the three facilities are composed of the following reported components bull dose from photons (labelled on the charts as ldquoexternalrdquo) bull doses from internal intakes of uranium dust (long-lived radioactive dust) from

uranium in air concentrations (for General Electricrsquos Toronto facility only)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components photon doses and doses from long-lived radioactive dust

241 General Electric Nuclear Fuel Facilities

General Electric Canada Inc operates two nuclear fuel facilities in Ontario

bull At the Toronto facility uranium dioxide pellets are produced from natural or depleted uranium dioxide powder

bull At the Peterborough facility uranium dioxide fuel bundles are created from the pellets produced at the Toronto facility

Figures 253ndash256 present dose information for General Electric Canada Incrsquos fuel fabrication facilities from 2001 to 2007 Graphs do not distinguish between the doses received at the Peterborough facility versus those at the Toronto facility

52

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 253 Average Dose Trends for the General Electric Fuel Facility (Based on Non-Zero Results Only)

0

05

1

15

2

25

3

35

Long Lived Radioactive Dust External Effective

Year

Figure 254 Average Dose Trends for the General Electric Fuel Facility (Based on All Monitoring Results)

0

05

1

15

2

25

3

Long Lived Radioactive Dust External Effective

Year

Dos

e (m

Sv)

Dos

e (m

Sv)

53

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 255 Collective Dose Trends for the General Electric Fuel Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Long Lived Radioactive Dust External

Year

Figure 256 Distribution of Effective Doses among all Workers at the General Electric Fuel Facility

0

10

20

30

40

50

60

70

80

90

100

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

54

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

242 Zircatec Nuclear Fuel Facility

Zircatec Precision Industries Inc operates a nuclear fuel facility in Port Hope Ontario where it makes fuel pellets from uranium dioxide powder received from Port Hopersquos uranium conversion facility The nuclear fuel facility also manufactures fuel bundles for nuclear reactors in Canada

Notes on data for the Zircatec nuclear fuel facility

1 Graphs indicate the following data bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of average effective doses

2 Doses from photons from external sources were measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay Historically although these internal doses have been measured and submitted to the CNSC they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

Figures 257ndash260 present dose information for the Zircatec nuclear fuel facility from 2001 to 2007

Figure 257 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on Non-Zero Results)

0

05

1

15

2

25

3

35

Effe

ctiv

e D

ose

(mS

v)

Year

55

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 258 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

18

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 259 Collective Dose Trends for the Zircatec Nuclear Fuel Facility

0

50

100

150

200

250

300

350

400

450

500

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

56

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 260 Distribution of Effective Doses Among All Workers at the Zircatec Nuclear Fuel Facility

300

Num

ber o

f Wor

kers

250

200

150

100

50

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

57

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

25 Research and Radioisotope Production Facilities This section presents dose information for the following research and radioisotope production facilities from 2001 to 2007

bull Chalk River Laboratories and Whiteshell Laboratories (Section 251) bull A radioisotope production facility operated by MDS Nordion (Section 252) bull The Tri-University Meson Facility (TRIUMF) (Section 253)

Note on data for research and radioisotope production facilities

1 Graphs indicate the following data for each facility bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of effective doses

251 Chalk River Laboratories and Whiteshell Laboratories

Atomic Energy of Canada Limited (AECL) owns and is licensed to operate Chalk River Laboratories and Whiteshell Laboratories

Situated in Renfrew County on the south shore of the Ottawa River the Chalk River Laboratories site hosts the National Research Universal Reactor along with numerous other facilities occupying some 160 buildings in an area of approximately 40 km2 Activities consist of radioisotope production for nuclear medicine testing and development of structural materials in support of power reactor operations fuel fabrication research and radioactive waste management and storage

The Whiteshell Laboratories site is located approximately 10 km west of Pinawa Manitoba and 100 km northeast of Winnipeg on the east bank of the Winnipeg River AECL established the laboratories for nuclear research and testing during the early 1960s and has since discontinued operations which are being decommissioned under a licence from the CNSC

Figures 261ndash264 present dose information for Chalk River Laboratories and Whiteshell Laboratories from 2001 to 2007

Notes on data for Chalk River Laboratories and Whiteshell Laboratories

1 Effective doses are composed of the following reported components bull external doses5 (from both photon and neutron doses) bull tritium doses

Due to issues with AECLrsquos in-house dosimetry management system neutron doses were not reported separately to the NDR during the reporting period As a result external doses from photons and neutrons were totaled The reporting discrepancy has since been rectified

58

5

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of external (photon and neutron) and tritium doses Intakes of other radionuclides occasionally occur and these radionuclides are not included here because their associated doses are very small For this reason certain collective doses in this report may have values slightly lower than the sum of their respective components as listed

Figure 261 Average Dose Trends for Chalk River and Whiteshell Laboratories (Non-Zero Results Only)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Tritium External Effective

Year

59

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 262 Average Dose Trends for Chalk River and Whiteshell Laboratories (All Monitoring Results)

000

020

040

060

080

100

120

Dos

e (m

Sv)

Tritium External Effective

Year

Figure 263 Collective Dose Trends for Chalk River and Whiteshell Laboratories

0

500

1000

1500

2000

2500

3000

3500

Col

lect

ive

Dos

e (p

erso

n- m

Sv)

External Tritium

Year

60

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 264 Distribution of Effective Doses Among All Workers at Chalk River and Whiteshell Laboratories

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

3500

3000

2500

2000

1500

1000

500

Dose (mSv)

61

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

252 MDS Nordion (Nuclear Substance Processing Facility and Canadian Irradiation Centre)

MDS Nordion owns and operates a nuclear substance processing facility in Ottawa Ontario where it processes unsealed radioisotopes and manufactures sealed radiation sources In operation since the early 1970s the facility was purchased by Nordion International in 1991

In cooperation with the Universiteacute du Queacutebecrsquos Institut Armand-Frappier MDS Nordion also operates the Canadian Irradiation Centre which conducts various irradiation services which include training testing and development The centre is located in Laval Quebec on the Universiteacute du Queacutebec campus

Figures 265ndash268 present dose information for MDS Nordionrsquos Ottawa nuclear substance processing facility and for the Canadian Irradiation Centre from 2001 to 2007

Notes on data for MDS Nordionrsquos nuclear substance processing facility and the Canadian Irradiation Centre

1 Doses from photons from external sources were measured and reported to the NDR MDS Nordion also has a routine thyroid monitoring program very occasionally small recordable doses of radiation have occurred from thyroid uptake of iodine The resulting doses have not been historically submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided

Figure 265 Average Dose Trends for MDS Nordion (Based on Non-Zero Results)

0

05

1

15

2

25

Effe

ctiv

e D

ose

(mS

v)

Year

62

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 266 Average Dose Trends for MDS Nordion (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

Figure 267 Collective Dose Trends for MDS Nordion

0

100

200

300

400

500

600

700

800

Year

63

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 268 Distribution of Effective Doses Among All Workers at MDS Nordion

0

5 0

1 0 0

1 5 0

2 0 0

2 5 0

3 0 0

3 5 0

4 0 0

4 5 0

5 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

64

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

253 Tri-University Meson Facility

The Tri-University Meson facility (TRIUMF) is situated in Vancouver on the campus of the University of British Columbia TRIUMF which began operating in the early 1970s with one cyclotron now has two cyclotrons and associated laboratories for research and radioisotope production The laboratory provides research facilities for Canadian and international users and also produces radioisotopes which are used by medical facilities and by a commercial organization (MDS Nordion) MDS Nordion staff also work at the TRIUMF site however MDS Nordion oversees this work and has its own radiation protection program

Figures 269ndash272 present dose information for the TRIUMF facility from 2001 to 2007 Please note that data sets do not distinguish between doses received by TRIUMF staff and MDS Nordion staff who work on the site as the data for these two groups was submitted collectively to the NDR for the reporting period shown Future data for each group will be submitted separately to the NDR

Note on data for TRIUMF

1 Effective doses are composed of the following reported components bull doses from photons (labeled as ldquoexternalrdquo in the charts) bull neutron doses

Figure 269 Average Dose Trends for TRIUMF (Non-Zero Results Only)

000

020

040

060

080

100

120

140

160

Dos

e (m

Sv)

Neutrons External Effective

Year

65

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 52: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 245 Average Dose Trends for the Blind River Refinery (Based on Non-Zero Results)

0

05

1

15

2

25

Year

Figure 246 Average Dose Trends for the Blind River Refinery (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

47

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 247 Collective Dose Trends for the Blind River Refinery

0

50

100

150

200

250

300 C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 248 Distribution of Effective Doses Among All Workers at the Blind River Refinery

0

20

40

60

80

100

120

140

160

180

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

48

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

232 Port Hope Conversion Facility

Cameco Corporation owns and is licensed to operate a uranium conversion facility in Port Hope Ontario The facility processes uranium trioxide received from the refinery in Blind River into uranium dioxide and uranium hexafluoride

Figures 249ndash252 present dose information for the Port Hope uranium conversion facility from 2001 to 2007

Figure 249 Average Dose Trends for the Port Hope Conversion Facility (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

49

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 250 Average Dose Trends for the Port Hope Conversion Facility (Based on All Monitoring Results)

0

01

02

03

04

05

06

07

08

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 251 Collective Dose Trends for the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

50

000-0

009

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 252 Distribution of Effective Doses Among All Workers at the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

400

450

500

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

51

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

24 Fuel Fabrication Facilities This section presents data for three nuclear fuel fabrication facilities

bull Two facilities owned and operated by General Electric Canada Inc (Section 241) bull One facility in Port Hope operated by Zircatec Precision Industries (Section 242)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average doses

Notes on data for fuel fabrication facilities

1 Effective doses for the three facilities are composed of the following reported components bull dose from photons (labelled on the charts as ldquoexternalrdquo) bull doses from internal intakes of uranium dust (long-lived radioactive dust) from

uranium in air concentrations (for General Electricrsquos Toronto facility only)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components photon doses and doses from long-lived radioactive dust

241 General Electric Nuclear Fuel Facilities

General Electric Canada Inc operates two nuclear fuel facilities in Ontario

bull At the Toronto facility uranium dioxide pellets are produced from natural or depleted uranium dioxide powder

bull At the Peterborough facility uranium dioxide fuel bundles are created from the pellets produced at the Toronto facility

Figures 253ndash256 present dose information for General Electric Canada Incrsquos fuel fabrication facilities from 2001 to 2007 Graphs do not distinguish between the doses received at the Peterborough facility versus those at the Toronto facility

52

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 253 Average Dose Trends for the General Electric Fuel Facility (Based on Non-Zero Results Only)

0

05

1

15

2

25

3

35

Long Lived Radioactive Dust External Effective

Year

Figure 254 Average Dose Trends for the General Electric Fuel Facility (Based on All Monitoring Results)

0

05

1

15

2

25

3

Long Lived Radioactive Dust External Effective

Year

Dos

e (m

Sv)

Dos

e (m

Sv)

53

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 255 Collective Dose Trends for the General Electric Fuel Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Long Lived Radioactive Dust External

Year

Figure 256 Distribution of Effective Doses among all Workers at the General Electric Fuel Facility

0

10

20

30

40

50

60

70

80

90

100

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

54

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

242 Zircatec Nuclear Fuel Facility

Zircatec Precision Industries Inc operates a nuclear fuel facility in Port Hope Ontario where it makes fuel pellets from uranium dioxide powder received from Port Hopersquos uranium conversion facility The nuclear fuel facility also manufactures fuel bundles for nuclear reactors in Canada

Notes on data for the Zircatec nuclear fuel facility

1 Graphs indicate the following data bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of average effective doses

2 Doses from photons from external sources were measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay Historically although these internal doses have been measured and submitted to the CNSC they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

Figures 257ndash260 present dose information for the Zircatec nuclear fuel facility from 2001 to 2007

Figure 257 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on Non-Zero Results)

0

05

1

15

2

25

3

35

Effe

ctiv

e D

ose

(mS

v)

Year

55

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 258 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

18

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 259 Collective Dose Trends for the Zircatec Nuclear Fuel Facility

0

50

100

150

200

250

300

350

400

450

500

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

56

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 260 Distribution of Effective Doses Among All Workers at the Zircatec Nuclear Fuel Facility

300

Num

ber o

f Wor

kers

250

200

150

100

50

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

57

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

25 Research and Radioisotope Production Facilities This section presents dose information for the following research and radioisotope production facilities from 2001 to 2007

bull Chalk River Laboratories and Whiteshell Laboratories (Section 251) bull A radioisotope production facility operated by MDS Nordion (Section 252) bull The Tri-University Meson Facility (TRIUMF) (Section 253)

Note on data for research and radioisotope production facilities

1 Graphs indicate the following data for each facility bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of effective doses

251 Chalk River Laboratories and Whiteshell Laboratories

Atomic Energy of Canada Limited (AECL) owns and is licensed to operate Chalk River Laboratories and Whiteshell Laboratories

Situated in Renfrew County on the south shore of the Ottawa River the Chalk River Laboratories site hosts the National Research Universal Reactor along with numerous other facilities occupying some 160 buildings in an area of approximately 40 km2 Activities consist of radioisotope production for nuclear medicine testing and development of structural materials in support of power reactor operations fuel fabrication research and radioactive waste management and storage

The Whiteshell Laboratories site is located approximately 10 km west of Pinawa Manitoba and 100 km northeast of Winnipeg on the east bank of the Winnipeg River AECL established the laboratories for nuclear research and testing during the early 1960s and has since discontinued operations which are being decommissioned under a licence from the CNSC

Figures 261ndash264 present dose information for Chalk River Laboratories and Whiteshell Laboratories from 2001 to 2007

Notes on data for Chalk River Laboratories and Whiteshell Laboratories

1 Effective doses are composed of the following reported components bull external doses5 (from both photon and neutron doses) bull tritium doses

Due to issues with AECLrsquos in-house dosimetry management system neutron doses were not reported separately to the NDR during the reporting period As a result external doses from photons and neutrons were totaled The reporting discrepancy has since been rectified

58

5

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of external (photon and neutron) and tritium doses Intakes of other radionuclides occasionally occur and these radionuclides are not included here because their associated doses are very small For this reason certain collective doses in this report may have values slightly lower than the sum of their respective components as listed

Figure 261 Average Dose Trends for Chalk River and Whiteshell Laboratories (Non-Zero Results Only)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Tritium External Effective

Year

59

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 262 Average Dose Trends for Chalk River and Whiteshell Laboratories (All Monitoring Results)

000

020

040

060

080

100

120

Dos

e (m

Sv)

Tritium External Effective

Year

Figure 263 Collective Dose Trends for Chalk River and Whiteshell Laboratories

0

500

1000

1500

2000

2500

3000

3500

Col

lect

ive

Dos

e (p

erso

n- m

Sv)

External Tritium

Year

60

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 264 Distribution of Effective Doses Among All Workers at Chalk River and Whiteshell Laboratories

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

3500

3000

2500

2000

1500

1000

500

Dose (mSv)

61

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

252 MDS Nordion (Nuclear Substance Processing Facility and Canadian Irradiation Centre)

MDS Nordion owns and operates a nuclear substance processing facility in Ottawa Ontario where it processes unsealed radioisotopes and manufactures sealed radiation sources In operation since the early 1970s the facility was purchased by Nordion International in 1991

In cooperation with the Universiteacute du Queacutebecrsquos Institut Armand-Frappier MDS Nordion also operates the Canadian Irradiation Centre which conducts various irradiation services which include training testing and development The centre is located in Laval Quebec on the Universiteacute du Queacutebec campus

Figures 265ndash268 present dose information for MDS Nordionrsquos Ottawa nuclear substance processing facility and for the Canadian Irradiation Centre from 2001 to 2007

Notes on data for MDS Nordionrsquos nuclear substance processing facility and the Canadian Irradiation Centre

1 Doses from photons from external sources were measured and reported to the NDR MDS Nordion also has a routine thyroid monitoring program very occasionally small recordable doses of radiation have occurred from thyroid uptake of iodine The resulting doses have not been historically submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided

Figure 265 Average Dose Trends for MDS Nordion (Based on Non-Zero Results)

0

05

1

15

2

25

Effe

ctiv

e D

ose

(mS

v)

Year

62

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 266 Average Dose Trends for MDS Nordion (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

Figure 267 Collective Dose Trends for MDS Nordion

0

100

200

300

400

500

600

700

800

Year

63

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 268 Distribution of Effective Doses Among All Workers at MDS Nordion

0

5 0

1 0 0

1 5 0

2 0 0

2 5 0

3 0 0

3 5 0

4 0 0

4 5 0

5 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

64

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

253 Tri-University Meson Facility

The Tri-University Meson facility (TRIUMF) is situated in Vancouver on the campus of the University of British Columbia TRIUMF which began operating in the early 1970s with one cyclotron now has two cyclotrons and associated laboratories for research and radioisotope production The laboratory provides research facilities for Canadian and international users and also produces radioisotopes which are used by medical facilities and by a commercial organization (MDS Nordion) MDS Nordion staff also work at the TRIUMF site however MDS Nordion oversees this work and has its own radiation protection program

Figures 269ndash272 present dose information for the TRIUMF facility from 2001 to 2007 Please note that data sets do not distinguish between doses received by TRIUMF staff and MDS Nordion staff who work on the site as the data for these two groups was submitted collectively to the NDR for the reporting period shown Future data for each group will be submitted separately to the NDR

Note on data for TRIUMF

1 Effective doses are composed of the following reported components bull doses from photons (labeled as ldquoexternalrdquo in the charts) bull neutron doses

Figure 269 Average Dose Trends for TRIUMF (Non-Zero Results Only)

000

020

040

060

080

100

120

140

160

Dos

e (m

Sv)

Neutrons External Effective

Year

65

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 53: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 247 Collective Dose Trends for the Blind River Refinery

0

50

100

150

200

250

300 C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 248 Distribution of Effective Doses Among All Workers at the Blind River Refinery

0

20

40

60

80

100

120

140

160

180

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

48

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

232 Port Hope Conversion Facility

Cameco Corporation owns and is licensed to operate a uranium conversion facility in Port Hope Ontario The facility processes uranium trioxide received from the refinery in Blind River into uranium dioxide and uranium hexafluoride

Figures 249ndash252 present dose information for the Port Hope uranium conversion facility from 2001 to 2007

Figure 249 Average Dose Trends for the Port Hope Conversion Facility (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

49

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 250 Average Dose Trends for the Port Hope Conversion Facility (Based on All Monitoring Results)

0

01

02

03

04

05

06

07

08

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 251 Collective Dose Trends for the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

50

000-0

009

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 252 Distribution of Effective Doses Among All Workers at the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

400

450

500

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

51

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

24 Fuel Fabrication Facilities This section presents data for three nuclear fuel fabrication facilities

bull Two facilities owned and operated by General Electric Canada Inc (Section 241) bull One facility in Port Hope operated by Zircatec Precision Industries (Section 242)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average doses

Notes on data for fuel fabrication facilities

1 Effective doses for the three facilities are composed of the following reported components bull dose from photons (labelled on the charts as ldquoexternalrdquo) bull doses from internal intakes of uranium dust (long-lived radioactive dust) from

uranium in air concentrations (for General Electricrsquos Toronto facility only)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components photon doses and doses from long-lived radioactive dust

241 General Electric Nuclear Fuel Facilities

General Electric Canada Inc operates two nuclear fuel facilities in Ontario

bull At the Toronto facility uranium dioxide pellets are produced from natural or depleted uranium dioxide powder

bull At the Peterborough facility uranium dioxide fuel bundles are created from the pellets produced at the Toronto facility

Figures 253ndash256 present dose information for General Electric Canada Incrsquos fuel fabrication facilities from 2001 to 2007 Graphs do not distinguish between the doses received at the Peterborough facility versus those at the Toronto facility

52

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 253 Average Dose Trends for the General Electric Fuel Facility (Based on Non-Zero Results Only)

0

05

1

15

2

25

3

35

Long Lived Radioactive Dust External Effective

Year

Figure 254 Average Dose Trends for the General Electric Fuel Facility (Based on All Monitoring Results)

0

05

1

15

2

25

3

Long Lived Radioactive Dust External Effective

Year

Dos

e (m

Sv)

Dos

e (m

Sv)

53

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 255 Collective Dose Trends for the General Electric Fuel Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Long Lived Radioactive Dust External

Year

Figure 256 Distribution of Effective Doses among all Workers at the General Electric Fuel Facility

0

10

20

30

40

50

60

70

80

90

100

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

54

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

242 Zircatec Nuclear Fuel Facility

Zircatec Precision Industries Inc operates a nuclear fuel facility in Port Hope Ontario where it makes fuel pellets from uranium dioxide powder received from Port Hopersquos uranium conversion facility The nuclear fuel facility also manufactures fuel bundles for nuclear reactors in Canada

Notes on data for the Zircatec nuclear fuel facility

1 Graphs indicate the following data bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of average effective doses

2 Doses from photons from external sources were measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay Historically although these internal doses have been measured and submitted to the CNSC they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

Figures 257ndash260 present dose information for the Zircatec nuclear fuel facility from 2001 to 2007

Figure 257 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on Non-Zero Results)

0

05

1

15

2

25

3

35

Effe

ctiv

e D

ose

(mS

v)

Year

55

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 258 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

18

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 259 Collective Dose Trends for the Zircatec Nuclear Fuel Facility

0

50

100

150

200

250

300

350

400

450

500

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

56

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 260 Distribution of Effective Doses Among All Workers at the Zircatec Nuclear Fuel Facility

300

Num

ber o

f Wor

kers

250

200

150

100

50

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

57

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

25 Research and Radioisotope Production Facilities This section presents dose information for the following research and radioisotope production facilities from 2001 to 2007

bull Chalk River Laboratories and Whiteshell Laboratories (Section 251) bull A radioisotope production facility operated by MDS Nordion (Section 252) bull The Tri-University Meson Facility (TRIUMF) (Section 253)

Note on data for research and radioisotope production facilities

1 Graphs indicate the following data for each facility bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of effective doses

251 Chalk River Laboratories and Whiteshell Laboratories

Atomic Energy of Canada Limited (AECL) owns and is licensed to operate Chalk River Laboratories and Whiteshell Laboratories

Situated in Renfrew County on the south shore of the Ottawa River the Chalk River Laboratories site hosts the National Research Universal Reactor along with numerous other facilities occupying some 160 buildings in an area of approximately 40 km2 Activities consist of radioisotope production for nuclear medicine testing and development of structural materials in support of power reactor operations fuel fabrication research and radioactive waste management and storage

The Whiteshell Laboratories site is located approximately 10 km west of Pinawa Manitoba and 100 km northeast of Winnipeg on the east bank of the Winnipeg River AECL established the laboratories for nuclear research and testing during the early 1960s and has since discontinued operations which are being decommissioned under a licence from the CNSC

Figures 261ndash264 present dose information for Chalk River Laboratories and Whiteshell Laboratories from 2001 to 2007

Notes on data for Chalk River Laboratories and Whiteshell Laboratories

1 Effective doses are composed of the following reported components bull external doses5 (from both photon and neutron doses) bull tritium doses

Due to issues with AECLrsquos in-house dosimetry management system neutron doses were not reported separately to the NDR during the reporting period As a result external doses from photons and neutrons were totaled The reporting discrepancy has since been rectified

58

5

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of external (photon and neutron) and tritium doses Intakes of other radionuclides occasionally occur and these radionuclides are not included here because their associated doses are very small For this reason certain collective doses in this report may have values slightly lower than the sum of their respective components as listed

Figure 261 Average Dose Trends for Chalk River and Whiteshell Laboratories (Non-Zero Results Only)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Tritium External Effective

Year

59

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 262 Average Dose Trends for Chalk River and Whiteshell Laboratories (All Monitoring Results)

000

020

040

060

080

100

120

Dos

e (m

Sv)

Tritium External Effective

Year

Figure 263 Collective Dose Trends for Chalk River and Whiteshell Laboratories

0

500

1000

1500

2000

2500

3000

3500

Col

lect

ive

Dos

e (p

erso

n- m

Sv)

External Tritium

Year

60

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 264 Distribution of Effective Doses Among All Workers at Chalk River and Whiteshell Laboratories

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

3500

3000

2500

2000

1500

1000

500

Dose (mSv)

61

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

252 MDS Nordion (Nuclear Substance Processing Facility and Canadian Irradiation Centre)

MDS Nordion owns and operates a nuclear substance processing facility in Ottawa Ontario where it processes unsealed radioisotopes and manufactures sealed radiation sources In operation since the early 1970s the facility was purchased by Nordion International in 1991

In cooperation with the Universiteacute du Queacutebecrsquos Institut Armand-Frappier MDS Nordion also operates the Canadian Irradiation Centre which conducts various irradiation services which include training testing and development The centre is located in Laval Quebec on the Universiteacute du Queacutebec campus

Figures 265ndash268 present dose information for MDS Nordionrsquos Ottawa nuclear substance processing facility and for the Canadian Irradiation Centre from 2001 to 2007

Notes on data for MDS Nordionrsquos nuclear substance processing facility and the Canadian Irradiation Centre

1 Doses from photons from external sources were measured and reported to the NDR MDS Nordion also has a routine thyroid monitoring program very occasionally small recordable doses of radiation have occurred from thyroid uptake of iodine The resulting doses have not been historically submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided

Figure 265 Average Dose Trends for MDS Nordion (Based on Non-Zero Results)

0

05

1

15

2

25

Effe

ctiv

e D

ose

(mS

v)

Year

62

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 266 Average Dose Trends for MDS Nordion (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

Figure 267 Collective Dose Trends for MDS Nordion

0

100

200

300

400

500

600

700

800

Year

63

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 268 Distribution of Effective Doses Among All Workers at MDS Nordion

0

5 0

1 0 0

1 5 0

2 0 0

2 5 0

3 0 0

3 5 0

4 0 0

4 5 0

5 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

64

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

253 Tri-University Meson Facility

The Tri-University Meson facility (TRIUMF) is situated in Vancouver on the campus of the University of British Columbia TRIUMF which began operating in the early 1970s with one cyclotron now has two cyclotrons and associated laboratories for research and radioisotope production The laboratory provides research facilities for Canadian and international users and also produces radioisotopes which are used by medical facilities and by a commercial organization (MDS Nordion) MDS Nordion staff also work at the TRIUMF site however MDS Nordion oversees this work and has its own radiation protection program

Figures 269ndash272 present dose information for the TRIUMF facility from 2001 to 2007 Please note that data sets do not distinguish between doses received by TRIUMF staff and MDS Nordion staff who work on the site as the data for these two groups was submitted collectively to the NDR for the reporting period shown Future data for each group will be submitted separately to the NDR

Note on data for TRIUMF

1 Effective doses are composed of the following reported components bull doses from photons (labeled as ldquoexternalrdquo in the charts) bull neutron doses

Figure 269 Average Dose Trends for TRIUMF (Non-Zero Results Only)

000

020

040

060

080

100

120

140

160

Dos

e (m

Sv)

Neutrons External Effective

Year

65

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 54: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

232 Port Hope Conversion Facility

Cameco Corporation owns and is licensed to operate a uranium conversion facility in Port Hope Ontario The facility processes uranium trioxide received from the refinery in Blind River into uranium dioxide and uranium hexafluoride

Figures 249ndash252 present dose information for the Port Hope uranium conversion facility from 2001 to 2007

Figure 249 Average Dose Trends for the Port Hope Conversion Facility (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

49

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 250 Average Dose Trends for the Port Hope Conversion Facility (Based on All Monitoring Results)

0

01

02

03

04

05

06

07

08

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 251 Collective Dose Trends for the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

50

000-0

009

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 252 Distribution of Effective Doses Among All Workers at the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

400

450

500

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

51

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

24 Fuel Fabrication Facilities This section presents data for three nuclear fuel fabrication facilities

bull Two facilities owned and operated by General Electric Canada Inc (Section 241) bull One facility in Port Hope operated by Zircatec Precision Industries (Section 242)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average doses

Notes on data for fuel fabrication facilities

1 Effective doses for the three facilities are composed of the following reported components bull dose from photons (labelled on the charts as ldquoexternalrdquo) bull doses from internal intakes of uranium dust (long-lived radioactive dust) from

uranium in air concentrations (for General Electricrsquos Toronto facility only)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components photon doses and doses from long-lived radioactive dust

241 General Electric Nuclear Fuel Facilities

General Electric Canada Inc operates two nuclear fuel facilities in Ontario

bull At the Toronto facility uranium dioxide pellets are produced from natural or depleted uranium dioxide powder

bull At the Peterborough facility uranium dioxide fuel bundles are created from the pellets produced at the Toronto facility

Figures 253ndash256 present dose information for General Electric Canada Incrsquos fuel fabrication facilities from 2001 to 2007 Graphs do not distinguish between the doses received at the Peterborough facility versus those at the Toronto facility

52

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 253 Average Dose Trends for the General Electric Fuel Facility (Based on Non-Zero Results Only)

0

05

1

15

2

25

3

35

Long Lived Radioactive Dust External Effective

Year

Figure 254 Average Dose Trends for the General Electric Fuel Facility (Based on All Monitoring Results)

0

05

1

15

2

25

3

Long Lived Radioactive Dust External Effective

Year

Dos

e (m

Sv)

Dos

e (m

Sv)

53

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 255 Collective Dose Trends for the General Electric Fuel Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Long Lived Radioactive Dust External

Year

Figure 256 Distribution of Effective Doses among all Workers at the General Electric Fuel Facility

0

10

20

30

40

50

60

70

80

90

100

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

54

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

242 Zircatec Nuclear Fuel Facility

Zircatec Precision Industries Inc operates a nuclear fuel facility in Port Hope Ontario where it makes fuel pellets from uranium dioxide powder received from Port Hopersquos uranium conversion facility The nuclear fuel facility also manufactures fuel bundles for nuclear reactors in Canada

Notes on data for the Zircatec nuclear fuel facility

1 Graphs indicate the following data bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of average effective doses

2 Doses from photons from external sources were measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay Historically although these internal doses have been measured and submitted to the CNSC they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

Figures 257ndash260 present dose information for the Zircatec nuclear fuel facility from 2001 to 2007

Figure 257 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on Non-Zero Results)

0

05

1

15

2

25

3

35

Effe

ctiv

e D

ose

(mS

v)

Year

55

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 258 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

18

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 259 Collective Dose Trends for the Zircatec Nuclear Fuel Facility

0

50

100

150

200

250

300

350

400

450

500

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

56

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 260 Distribution of Effective Doses Among All Workers at the Zircatec Nuclear Fuel Facility

300

Num

ber o

f Wor

kers

250

200

150

100

50

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

57

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

25 Research and Radioisotope Production Facilities This section presents dose information for the following research and radioisotope production facilities from 2001 to 2007

bull Chalk River Laboratories and Whiteshell Laboratories (Section 251) bull A radioisotope production facility operated by MDS Nordion (Section 252) bull The Tri-University Meson Facility (TRIUMF) (Section 253)

Note on data for research and radioisotope production facilities

1 Graphs indicate the following data for each facility bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of effective doses

251 Chalk River Laboratories and Whiteshell Laboratories

Atomic Energy of Canada Limited (AECL) owns and is licensed to operate Chalk River Laboratories and Whiteshell Laboratories

Situated in Renfrew County on the south shore of the Ottawa River the Chalk River Laboratories site hosts the National Research Universal Reactor along with numerous other facilities occupying some 160 buildings in an area of approximately 40 km2 Activities consist of radioisotope production for nuclear medicine testing and development of structural materials in support of power reactor operations fuel fabrication research and radioactive waste management and storage

The Whiteshell Laboratories site is located approximately 10 km west of Pinawa Manitoba and 100 km northeast of Winnipeg on the east bank of the Winnipeg River AECL established the laboratories for nuclear research and testing during the early 1960s and has since discontinued operations which are being decommissioned under a licence from the CNSC

Figures 261ndash264 present dose information for Chalk River Laboratories and Whiteshell Laboratories from 2001 to 2007

Notes on data for Chalk River Laboratories and Whiteshell Laboratories

1 Effective doses are composed of the following reported components bull external doses5 (from both photon and neutron doses) bull tritium doses

Due to issues with AECLrsquos in-house dosimetry management system neutron doses were not reported separately to the NDR during the reporting period As a result external doses from photons and neutrons were totaled The reporting discrepancy has since been rectified

58

5

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of external (photon and neutron) and tritium doses Intakes of other radionuclides occasionally occur and these radionuclides are not included here because their associated doses are very small For this reason certain collective doses in this report may have values slightly lower than the sum of their respective components as listed

Figure 261 Average Dose Trends for Chalk River and Whiteshell Laboratories (Non-Zero Results Only)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Tritium External Effective

Year

59

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 262 Average Dose Trends for Chalk River and Whiteshell Laboratories (All Monitoring Results)

000

020

040

060

080

100

120

Dos

e (m

Sv)

Tritium External Effective

Year

Figure 263 Collective Dose Trends for Chalk River and Whiteshell Laboratories

0

500

1000

1500

2000

2500

3000

3500

Col

lect

ive

Dos

e (p

erso

n- m

Sv)

External Tritium

Year

60

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 264 Distribution of Effective Doses Among All Workers at Chalk River and Whiteshell Laboratories

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

3500

3000

2500

2000

1500

1000

500

Dose (mSv)

61

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

252 MDS Nordion (Nuclear Substance Processing Facility and Canadian Irradiation Centre)

MDS Nordion owns and operates a nuclear substance processing facility in Ottawa Ontario where it processes unsealed radioisotopes and manufactures sealed radiation sources In operation since the early 1970s the facility was purchased by Nordion International in 1991

In cooperation with the Universiteacute du Queacutebecrsquos Institut Armand-Frappier MDS Nordion also operates the Canadian Irradiation Centre which conducts various irradiation services which include training testing and development The centre is located in Laval Quebec on the Universiteacute du Queacutebec campus

Figures 265ndash268 present dose information for MDS Nordionrsquos Ottawa nuclear substance processing facility and for the Canadian Irradiation Centre from 2001 to 2007

Notes on data for MDS Nordionrsquos nuclear substance processing facility and the Canadian Irradiation Centre

1 Doses from photons from external sources were measured and reported to the NDR MDS Nordion also has a routine thyroid monitoring program very occasionally small recordable doses of radiation have occurred from thyroid uptake of iodine The resulting doses have not been historically submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided

Figure 265 Average Dose Trends for MDS Nordion (Based on Non-Zero Results)

0

05

1

15

2

25

Effe

ctiv

e D

ose

(mS

v)

Year

62

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 266 Average Dose Trends for MDS Nordion (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

Figure 267 Collective Dose Trends for MDS Nordion

0

100

200

300

400

500

600

700

800

Year

63

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 268 Distribution of Effective Doses Among All Workers at MDS Nordion

0

5 0

1 0 0

1 5 0

2 0 0

2 5 0

3 0 0

3 5 0

4 0 0

4 5 0

5 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

64

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

253 Tri-University Meson Facility

The Tri-University Meson facility (TRIUMF) is situated in Vancouver on the campus of the University of British Columbia TRIUMF which began operating in the early 1970s with one cyclotron now has two cyclotrons and associated laboratories for research and radioisotope production The laboratory provides research facilities for Canadian and international users and also produces radioisotopes which are used by medical facilities and by a commercial organization (MDS Nordion) MDS Nordion staff also work at the TRIUMF site however MDS Nordion oversees this work and has its own radiation protection program

Figures 269ndash272 present dose information for the TRIUMF facility from 2001 to 2007 Please note that data sets do not distinguish between doses received by TRIUMF staff and MDS Nordion staff who work on the site as the data for these two groups was submitted collectively to the NDR for the reporting period shown Future data for each group will be submitted separately to the NDR

Note on data for TRIUMF

1 Effective doses are composed of the following reported components bull doses from photons (labeled as ldquoexternalrdquo in the charts) bull neutron doses

Figure 269 Average Dose Trends for TRIUMF (Non-Zero Results Only)

000

020

040

060

080

100

120

140

160

Dos

e (m

Sv)

Neutrons External Effective

Year

65

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 55: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 250 Average Dose Trends for the Port Hope Conversion Facility (Based on All Monitoring Results)

0

01

02

03

04

05

06

07

08

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 251 Collective Dose Trends for the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

50

000-0

009

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 252 Distribution of Effective Doses Among All Workers at the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

400

450

500

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

51

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

24 Fuel Fabrication Facilities This section presents data for three nuclear fuel fabrication facilities

bull Two facilities owned and operated by General Electric Canada Inc (Section 241) bull One facility in Port Hope operated by Zircatec Precision Industries (Section 242)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average doses

Notes on data for fuel fabrication facilities

1 Effective doses for the three facilities are composed of the following reported components bull dose from photons (labelled on the charts as ldquoexternalrdquo) bull doses from internal intakes of uranium dust (long-lived radioactive dust) from

uranium in air concentrations (for General Electricrsquos Toronto facility only)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components photon doses and doses from long-lived radioactive dust

241 General Electric Nuclear Fuel Facilities

General Electric Canada Inc operates two nuclear fuel facilities in Ontario

bull At the Toronto facility uranium dioxide pellets are produced from natural or depleted uranium dioxide powder

bull At the Peterborough facility uranium dioxide fuel bundles are created from the pellets produced at the Toronto facility

Figures 253ndash256 present dose information for General Electric Canada Incrsquos fuel fabrication facilities from 2001 to 2007 Graphs do not distinguish between the doses received at the Peterborough facility versus those at the Toronto facility

52

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 253 Average Dose Trends for the General Electric Fuel Facility (Based on Non-Zero Results Only)

0

05

1

15

2

25

3

35

Long Lived Radioactive Dust External Effective

Year

Figure 254 Average Dose Trends for the General Electric Fuel Facility (Based on All Monitoring Results)

0

05

1

15

2

25

3

Long Lived Radioactive Dust External Effective

Year

Dos

e (m

Sv)

Dos

e (m

Sv)

53

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 255 Collective Dose Trends for the General Electric Fuel Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Long Lived Radioactive Dust External

Year

Figure 256 Distribution of Effective Doses among all Workers at the General Electric Fuel Facility

0

10

20

30

40

50

60

70

80

90

100

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

54

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

242 Zircatec Nuclear Fuel Facility

Zircatec Precision Industries Inc operates a nuclear fuel facility in Port Hope Ontario where it makes fuel pellets from uranium dioxide powder received from Port Hopersquos uranium conversion facility The nuclear fuel facility also manufactures fuel bundles for nuclear reactors in Canada

Notes on data for the Zircatec nuclear fuel facility

1 Graphs indicate the following data bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of average effective doses

2 Doses from photons from external sources were measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay Historically although these internal doses have been measured and submitted to the CNSC they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

Figures 257ndash260 present dose information for the Zircatec nuclear fuel facility from 2001 to 2007

Figure 257 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on Non-Zero Results)

0

05

1

15

2

25

3

35

Effe

ctiv

e D

ose

(mS

v)

Year

55

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 258 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

18

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 259 Collective Dose Trends for the Zircatec Nuclear Fuel Facility

0

50

100

150

200

250

300

350

400

450

500

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

56

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 260 Distribution of Effective Doses Among All Workers at the Zircatec Nuclear Fuel Facility

300

Num

ber o

f Wor

kers

250

200

150

100

50

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

57

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

25 Research and Radioisotope Production Facilities This section presents dose information for the following research and radioisotope production facilities from 2001 to 2007

bull Chalk River Laboratories and Whiteshell Laboratories (Section 251) bull A radioisotope production facility operated by MDS Nordion (Section 252) bull The Tri-University Meson Facility (TRIUMF) (Section 253)

Note on data for research and radioisotope production facilities

1 Graphs indicate the following data for each facility bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of effective doses

251 Chalk River Laboratories and Whiteshell Laboratories

Atomic Energy of Canada Limited (AECL) owns and is licensed to operate Chalk River Laboratories and Whiteshell Laboratories

Situated in Renfrew County on the south shore of the Ottawa River the Chalk River Laboratories site hosts the National Research Universal Reactor along with numerous other facilities occupying some 160 buildings in an area of approximately 40 km2 Activities consist of radioisotope production for nuclear medicine testing and development of structural materials in support of power reactor operations fuel fabrication research and radioactive waste management and storage

The Whiteshell Laboratories site is located approximately 10 km west of Pinawa Manitoba and 100 km northeast of Winnipeg on the east bank of the Winnipeg River AECL established the laboratories for nuclear research and testing during the early 1960s and has since discontinued operations which are being decommissioned under a licence from the CNSC

Figures 261ndash264 present dose information for Chalk River Laboratories and Whiteshell Laboratories from 2001 to 2007

Notes on data for Chalk River Laboratories and Whiteshell Laboratories

1 Effective doses are composed of the following reported components bull external doses5 (from both photon and neutron doses) bull tritium doses

Due to issues with AECLrsquos in-house dosimetry management system neutron doses were not reported separately to the NDR during the reporting period As a result external doses from photons and neutrons were totaled The reporting discrepancy has since been rectified

58

5

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of external (photon and neutron) and tritium doses Intakes of other radionuclides occasionally occur and these radionuclides are not included here because their associated doses are very small For this reason certain collective doses in this report may have values slightly lower than the sum of their respective components as listed

Figure 261 Average Dose Trends for Chalk River and Whiteshell Laboratories (Non-Zero Results Only)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Tritium External Effective

Year

59

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 262 Average Dose Trends for Chalk River and Whiteshell Laboratories (All Monitoring Results)

000

020

040

060

080

100

120

Dos

e (m

Sv)

Tritium External Effective

Year

Figure 263 Collective Dose Trends for Chalk River and Whiteshell Laboratories

0

500

1000

1500

2000

2500

3000

3500

Col

lect

ive

Dos

e (p

erso

n- m

Sv)

External Tritium

Year

60

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 264 Distribution of Effective Doses Among All Workers at Chalk River and Whiteshell Laboratories

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

3500

3000

2500

2000

1500

1000

500

Dose (mSv)

61

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

252 MDS Nordion (Nuclear Substance Processing Facility and Canadian Irradiation Centre)

MDS Nordion owns and operates a nuclear substance processing facility in Ottawa Ontario where it processes unsealed radioisotopes and manufactures sealed radiation sources In operation since the early 1970s the facility was purchased by Nordion International in 1991

In cooperation with the Universiteacute du Queacutebecrsquos Institut Armand-Frappier MDS Nordion also operates the Canadian Irradiation Centre which conducts various irradiation services which include training testing and development The centre is located in Laval Quebec on the Universiteacute du Queacutebec campus

Figures 265ndash268 present dose information for MDS Nordionrsquos Ottawa nuclear substance processing facility and for the Canadian Irradiation Centre from 2001 to 2007

Notes on data for MDS Nordionrsquos nuclear substance processing facility and the Canadian Irradiation Centre

1 Doses from photons from external sources were measured and reported to the NDR MDS Nordion also has a routine thyroid monitoring program very occasionally small recordable doses of radiation have occurred from thyroid uptake of iodine The resulting doses have not been historically submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided

Figure 265 Average Dose Trends for MDS Nordion (Based on Non-Zero Results)

0

05

1

15

2

25

Effe

ctiv

e D

ose

(mS

v)

Year

62

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 266 Average Dose Trends for MDS Nordion (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

Figure 267 Collective Dose Trends for MDS Nordion

0

100

200

300

400

500

600

700

800

Year

63

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 268 Distribution of Effective Doses Among All Workers at MDS Nordion

0

5 0

1 0 0

1 5 0

2 0 0

2 5 0

3 0 0

3 5 0

4 0 0

4 5 0

5 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

64

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

253 Tri-University Meson Facility

The Tri-University Meson facility (TRIUMF) is situated in Vancouver on the campus of the University of British Columbia TRIUMF which began operating in the early 1970s with one cyclotron now has two cyclotrons and associated laboratories for research and radioisotope production The laboratory provides research facilities for Canadian and international users and also produces radioisotopes which are used by medical facilities and by a commercial organization (MDS Nordion) MDS Nordion staff also work at the TRIUMF site however MDS Nordion oversees this work and has its own radiation protection program

Figures 269ndash272 present dose information for the TRIUMF facility from 2001 to 2007 Please note that data sets do not distinguish between doses received by TRIUMF staff and MDS Nordion staff who work on the site as the data for these two groups was submitted collectively to the NDR for the reporting period shown Future data for each group will be submitted separately to the NDR

Note on data for TRIUMF

1 Effective doses are composed of the following reported components bull doses from photons (labeled as ldquoexternalrdquo in the charts) bull neutron doses

Figure 269 Average Dose Trends for TRIUMF (Non-Zero Results Only)

000

020

040

060

080

100

120

140

160

Dos

e (m

Sv)

Neutrons External Effective

Year

65

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 56: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

000-0

009

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 252 Distribution of Effective Doses Among All Workers at the Port Hope Conversion Facility

0

50

100

150

200

250

300

350

400

450

500

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

51

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

24 Fuel Fabrication Facilities This section presents data for three nuclear fuel fabrication facilities

bull Two facilities owned and operated by General Electric Canada Inc (Section 241) bull One facility in Port Hope operated by Zircatec Precision Industries (Section 242)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average doses

Notes on data for fuel fabrication facilities

1 Effective doses for the three facilities are composed of the following reported components bull dose from photons (labelled on the charts as ldquoexternalrdquo) bull doses from internal intakes of uranium dust (long-lived radioactive dust) from

uranium in air concentrations (for General Electricrsquos Toronto facility only)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components photon doses and doses from long-lived radioactive dust

241 General Electric Nuclear Fuel Facilities

General Electric Canada Inc operates two nuclear fuel facilities in Ontario

bull At the Toronto facility uranium dioxide pellets are produced from natural or depleted uranium dioxide powder

bull At the Peterborough facility uranium dioxide fuel bundles are created from the pellets produced at the Toronto facility

Figures 253ndash256 present dose information for General Electric Canada Incrsquos fuel fabrication facilities from 2001 to 2007 Graphs do not distinguish between the doses received at the Peterborough facility versus those at the Toronto facility

52

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 253 Average Dose Trends for the General Electric Fuel Facility (Based on Non-Zero Results Only)

0

05

1

15

2

25

3

35

Long Lived Radioactive Dust External Effective

Year

Figure 254 Average Dose Trends for the General Electric Fuel Facility (Based on All Monitoring Results)

0

05

1

15

2

25

3

Long Lived Radioactive Dust External Effective

Year

Dos

e (m

Sv)

Dos

e (m

Sv)

53

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 255 Collective Dose Trends for the General Electric Fuel Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Long Lived Radioactive Dust External

Year

Figure 256 Distribution of Effective Doses among all Workers at the General Electric Fuel Facility

0

10

20

30

40

50

60

70

80

90

100

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

54

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

242 Zircatec Nuclear Fuel Facility

Zircatec Precision Industries Inc operates a nuclear fuel facility in Port Hope Ontario where it makes fuel pellets from uranium dioxide powder received from Port Hopersquos uranium conversion facility The nuclear fuel facility also manufactures fuel bundles for nuclear reactors in Canada

Notes on data for the Zircatec nuclear fuel facility

1 Graphs indicate the following data bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of average effective doses

2 Doses from photons from external sources were measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay Historically although these internal doses have been measured and submitted to the CNSC they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

Figures 257ndash260 present dose information for the Zircatec nuclear fuel facility from 2001 to 2007

Figure 257 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on Non-Zero Results)

0

05

1

15

2

25

3

35

Effe

ctiv

e D

ose

(mS

v)

Year

55

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 258 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

18

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 259 Collective Dose Trends for the Zircatec Nuclear Fuel Facility

0

50

100

150

200

250

300

350

400

450

500

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

56

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 260 Distribution of Effective Doses Among All Workers at the Zircatec Nuclear Fuel Facility

300

Num

ber o

f Wor

kers

250

200

150

100

50

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

57

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

25 Research and Radioisotope Production Facilities This section presents dose information for the following research and radioisotope production facilities from 2001 to 2007

bull Chalk River Laboratories and Whiteshell Laboratories (Section 251) bull A radioisotope production facility operated by MDS Nordion (Section 252) bull The Tri-University Meson Facility (TRIUMF) (Section 253)

Note on data for research and radioisotope production facilities

1 Graphs indicate the following data for each facility bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of effective doses

251 Chalk River Laboratories and Whiteshell Laboratories

Atomic Energy of Canada Limited (AECL) owns and is licensed to operate Chalk River Laboratories and Whiteshell Laboratories

Situated in Renfrew County on the south shore of the Ottawa River the Chalk River Laboratories site hosts the National Research Universal Reactor along with numerous other facilities occupying some 160 buildings in an area of approximately 40 km2 Activities consist of radioisotope production for nuclear medicine testing and development of structural materials in support of power reactor operations fuel fabrication research and radioactive waste management and storage

The Whiteshell Laboratories site is located approximately 10 km west of Pinawa Manitoba and 100 km northeast of Winnipeg on the east bank of the Winnipeg River AECL established the laboratories for nuclear research and testing during the early 1960s and has since discontinued operations which are being decommissioned under a licence from the CNSC

Figures 261ndash264 present dose information for Chalk River Laboratories and Whiteshell Laboratories from 2001 to 2007

Notes on data for Chalk River Laboratories and Whiteshell Laboratories

1 Effective doses are composed of the following reported components bull external doses5 (from both photon and neutron doses) bull tritium doses

Due to issues with AECLrsquos in-house dosimetry management system neutron doses were not reported separately to the NDR during the reporting period As a result external doses from photons and neutrons were totaled The reporting discrepancy has since been rectified

58

5

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of external (photon and neutron) and tritium doses Intakes of other radionuclides occasionally occur and these radionuclides are not included here because their associated doses are very small For this reason certain collective doses in this report may have values slightly lower than the sum of their respective components as listed

Figure 261 Average Dose Trends for Chalk River and Whiteshell Laboratories (Non-Zero Results Only)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Tritium External Effective

Year

59

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 262 Average Dose Trends for Chalk River and Whiteshell Laboratories (All Monitoring Results)

000

020

040

060

080

100

120

Dos

e (m

Sv)

Tritium External Effective

Year

Figure 263 Collective Dose Trends for Chalk River and Whiteshell Laboratories

0

500

1000

1500

2000

2500

3000

3500

Col

lect

ive

Dos

e (p

erso

n- m

Sv)

External Tritium

Year

60

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 264 Distribution of Effective Doses Among All Workers at Chalk River and Whiteshell Laboratories

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

3500

3000

2500

2000

1500

1000

500

Dose (mSv)

61

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

252 MDS Nordion (Nuclear Substance Processing Facility and Canadian Irradiation Centre)

MDS Nordion owns and operates a nuclear substance processing facility in Ottawa Ontario where it processes unsealed radioisotopes and manufactures sealed radiation sources In operation since the early 1970s the facility was purchased by Nordion International in 1991

In cooperation with the Universiteacute du Queacutebecrsquos Institut Armand-Frappier MDS Nordion also operates the Canadian Irradiation Centre which conducts various irradiation services which include training testing and development The centre is located in Laval Quebec on the Universiteacute du Queacutebec campus

Figures 265ndash268 present dose information for MDS Nordionrsquos Ottawa nuclear substance processing facility and for the Canadian Irradiation Centre from 2001 to 2007

Notes on data for MDS Nordionrsquos nuclear substance processing facility and the Canadian Irradiation Centre

1 Doses from photons from external sources were measured and reported to the NDR MDS Nordion also has a routine thyroid monitoring program very occasionally small recordable doses of radiation have occurred from thyroid uptake of iodine The resulting doses have not been historically submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided

Figure 265 Average Dose Trends for MDS Nordion (Based on Non-Zero Results)

0

05

1

15

2

25

Effe

ctiv

e D

ose

(mS

v)

Year

62

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 266 Average Dose Trends for MDS Nordion (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

Figure 267 Collective Dose Trends for MDS Nordion

0

100

200

300

400

500

600

700

800

Year

63

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 268 Distribution of Effective Doses Among All Workers at MDS Nordion

0

5 0

1 0 0

1 5 0

2 0 0

2 5 0

3 0 0

3 5 0

4 0 0

4 5 0

5 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

64

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

253 Tri-University Meson Facility

The Tri-University Meson facility (TRIUMF) is situated in Vancouver on the campus of the University of British Columbia TRIUMF which began operating in the early 1970s with one cyclotron now has two cyclotrons and associated laboratories for research and radioisotope production The laboratory provides research facilities for Canadian and international users and also produces radioisotopes which are used by medical facilities and by a commercial organization (MDS Nordion) MDS Nordion staff also work at the TRIUMF site however MDS Nordion oversees this work and has its own radiation protection program

Figures 269ndash272 present dose information for the TRIUMF facility from 2001 to 2007 Please note that data sets do not distinguish between doses received by TRIUMF staff and MDS Nordion staff who work on the site as the data for these two groups was submitted collectively to the NDR for the reporting period shown Future data for each group will be submitted separately to the NDR

Note on data for TRIUMF

1 Effective doses are composed of the following reported components bull doses from photons (labeled as ldquoexternalrdquo in the charts) bull neutron doses

Figure 269 Average Dose Trends for TRIUMF (Non-Zero Results Only)

000

020

040

060

080

100

120

140

160

Dos

e (m

Sv)

Neutrons External Effective

Year

65

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 57: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

24 Fuel Fabrication Facilities This section presents data for three nuclear fuel fabrication facilities

bull Two facilities owned and operated by General Electric Canada Inc (Section 241) bull One facility in Port Hope operated by Zircatec Precision Industries (Section 242)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average doses

Notes on data for fuel fabrication facilities

1 Effective doses for the three facilities are composed of the following reported components bull dose from photons (labelled on the charts as ldquoexternalrdquo) bull doses from internal intakes of uranium dust (long-lived radioactive dust) from

uranium in air concentrations (for General Electricrsquos Toronto facility only)

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components photon doses and doses from long-lived radioactive dust

241 General Electric Nuclear Fuel Facilities

General Electric Canada Inc operates two nuclear fuel facilities in Ontario

bull At the Toronto facility uranium dioxide pellets are produced from natural or depleted uranium dioxide powder

bull At the Peterborough facility uranium dioxide fuel bundles are created from the pellets produced at the Toronto facility

Figures 253ndash256 present dose information for General Electric Canada Incrsquos fuel fabrication facilities from 2001 to 2007 Graphs do not distinguish between the doses received at the Peterborough facility versus those at the Toronto facility

52

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 253 Average Dose Trends for the General Electric Fuel Facility (Based on Non-Zero Results Only)

0

05

1

15

2

25

3

35

Long Lived Radioactive Dust External Effective

Year

Figure 254 Average Dose Trends for the General Electric Fuel Facility (Based on All Monitoring Results)

0

05

1

15

2

25

3

Long Lived Radioactive Dust External Effective

Year

Dos

e (m

Sv)

Dos

e (m

Sv)

53

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 255 Collective Dose Trends for the General Electric Fuel Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Long Lived Radioactive Dust External

Year

Figure 256 Distribution of Effective Doses among all Workers at the General Electric Fuel Facility

0

10

20

30

40

50

60

70

80

90

100

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

54

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

242 Zircatec Nuclear Fuel Facility

Zircatec Precision Industries Inc operates a nuclear fuel facility in Port Hope Ontario where it makes fuel pellets from uranium dioxide powder received from Port Hopersquos uranium conversion facility The nuclear fuel facility also manufactures fuel bundles for nuclear reactors in Canada

Notes on data for the Zircatec nuclear fuel facility

1 Graphs indicate the following data bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of average effective doses

2 Doses from photons from external sources were measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay Historically although these internal doses have been measured and submitted to the CNSC they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

Figures 257ndash260 present dose information for the Zircatec nuclear fuel facility from 2001 to 2007

Figure 257 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on Non-Zero Results)

0

05

1

15

2

25

3

35

Effe

ctiv

e D

ose

(mS

v)

Year

55

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 258 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

18

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 259 Collective Dose Trends for the Zircatec Nuclear Fuel Facility

0

50

100

150

200

250

300

350

400

450

500

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

56

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 260 Distribution of Effective Doses Among All Workers at the Zircatec Nuclear Fuel Facility

300

Num

ber o

f Wor

kers

250

200

150

100

50

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

57

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

25 Research and Radioisotope Production Facilities This section presents dose information for the following research and radioisotope production facilities from 2001 to 2007

bull Chalk River Laboratories and Whiteshell Laboratories (Section 251) bull A radioisotope production facility operated by MDS Nordion (Section 252) bull The Tri-University Meson Facility (TRIUMF) (Section 253)

Note on data for research and radioisotope production facilities

1 Graphs indicate the following data for each facility bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of effective doses

251 Chalk River Laboratories and Whiteshell Laboratories

Atomic Energy of Canada Limited (AECL) owns and is licensed to operate Chalk River Laboratories and Whiteshell Laboratories

Situated in Renfrew County on the south shore of the Ottawa River the Chalk River Laboratories site hosts the National Research Universal Reactor along with numerous other facilities occupying some 160 buildings in an area of approximately 40 km2 Activities consist of radioisotope production for nuclear medicine testing and development of structural materials in support of power reactor operations fuel fabrication research and radioactive waste management and storage

The Whiteshell Laboratories site is located approximately 10 km west of Pinawa Manitoba and 100 km northeast of Winnipeg on the east bank of the Winnipeg River AECL established the laboratories for nuclear research and testing during the early 1960s and has since discontinued operations which are being decommissioned under a licence from the CNSC

Figures 261ndash264 present dose information for Chalk River Laboratories and Whiteshell Laboratories from 2001 to 2007

Notes on data for Chalk River Laboratories and Whiteshell Laboratories

1 Effective doses are composed of the following reported components bull external doses5 (from both photon and neutron doses) bull tritium doses

Due to issues with AECLrsquos in-house dosimetry management system neutron doses were not reported separately to the NDR during the reporting period As a result external doses from photons and neutrons were totaled The reporting discrepancy has since been rectified

58

5

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of external (photon and neutron) and tritium doses Intakes of other radionuclides occasionally occur and these radionuclides are not included here because their associated doses are very small For this reason certain collective doses in this report may have values slightly lower than the sum of their respective components as listed

Figure 261 Average Dose Trends for Chalk River and Whiteshell Laboratories (Non-Zero Results Only)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Tritium External Effective

Year

59

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 262 Average Dose Trends for Chalk River and Whiteshell Laboratories (All Monitoring Results)

000

020

040

060

080

100

120

Dos

e (m

Sv)

Tritium External Effective

Year

Figure 263 Collective Dose Trends for Chalk River and Whiteshell Laboratories

0

500

1000

1500

2000

2500

3000

3500

Col

lect

ive

Dos

e (p

erso

n- m

Sv)

External Tritium

Year

60

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 264 Distribution of Effective Doses Among All Workers at Chalk River and Whiteshell Laboratories

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

3500

3000

2500

2000

1500

1000

500

Dose (mSv)

61

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

252 MDS Nordion (Nuclear Substance Processing Facility and Canadian Irradiation Centre)

MDS Nordion owns and operates a nuclear substance processing facility in Ottawa Ontario where it processes unsealed radioisotopes and manufactures sealed radiation sources In operation since the early 1970s the facility was purchased by Nordion International in 1991

In cooperation with the Universiteacute du Queacutebecrsquos Institut Armand-Frappier MDS Nordion also operates the Canadian Irradiation Centre which conducts various irradiation services which include training testing and development The centre is located in Laval Quebec on the Universiteacute du Queacutebec campus

Figures 265ndash268 present dose information for MDS Nordionrsquos Ottawa nuclear substance processing facility and for the Canadian Irradiation Centre from 2001 to 2007

Notes on data for MDS Nordionrsquos nuclear substance processing facility and the Canadian Irradiation Centre

1 Doses from photons from external sources were measured and reported to the NDR MDS Nordion also has a routine thyroid monitoring program very occasionally small recordable doses of radiation have occurred from thyroid uptake of iodine The resulting doses have not been historically submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided

Figure 265 Average Dose Trends for MDS Nordion (Based on Non-Zero Results)

0

05

1

15

2

25

Effe

ctiv

e D

ose

(mS

v)

Year

62

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 266 Average Dose Trends for MDS Nordion (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

Figure 267 Collective Dose Trends for MDS Nordion

0

100

200

300

400

500

600

700

800

Year

63

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 268 Distribution of Effective Doses Among All Workers at MDS Nordion

0

5 0

1 0 0

1 5 0

2 0 0

2 5 0

3 0 0

3 5 0

4 0 0

4 5 0

5 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

64

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

253 Tri-University Meson Facility

The Tri-University Meson facility (TRIUMF) is situated in Vancouver on the campus of the University of British Columbia TRIUMF which began operating in the early 1970s with one cyclotron now has two cyclotrons and associated laboratories for research and radioisotope production The laboratory provides research facilities for Canadian and international users and also produces radioisotopes which are used by medical facilities and by a commercial organization (MDS Nordion) MDS Nordion staff also work at the TRIUMF site however MDS Nordion oversees this work and has its own radiation protection program

Figures 269ndash272 present dose information for the TRIUMF facility from 2001 to 2007 Please note that data sets do not distinguish between doses received by TRIUMF staff and MDS Nordion staff who work on the site as the data for these two groups was submitted collectively to the NDR for the reporting period shown Future data for each group will be submitted separately to the NDR

Note on data for TRIUMF

1 Effective doses are composed of the following reported components bull doses from photons (labeled as ldquoexternalrdquo in the charts) bull neutron doses

Figure 269 Average Dose Trends for TRIUMF (Non-Zero Results Only)

000

020

040

060

080

100

120

140

160

Dos

e (m

Sv)

Neutrons External Effective

Year

65

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 58: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 253 Average Dose Trends for the General Electric Fuel Facility (Based on Non-Zero Results Only)

0

05

1

15

2

25

3

35

Long Lived Radioactive Dust External Effective

Year

Figure 254 Average Dose Trends for the General Electric Fuel Facility (Based on All Monitoring Results)

0

05

1

15

2

25

3

Long Lived Radioactive Dust External Effective

Year

Dos

e (m

Sv)

Dos

e (m

Sv)

53

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 255 Collective Dose Trends for the General Electric Fuel Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Long Lived Radioactive Dust External

Year

Figure 256 Distribution of Effective Doses among all Workers at the General Electric Fuel Facility

0

10

20

30

40

50

60

70

80

90

100

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

54

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

242 Zircatec Nuclear Fuel Facility

Zircatec Precision Industries Inc operates a nuclear fuel facility in Port Hope Ontario where it makes fuel pellets from uranium dioxide powder received from Port Hopersquos uranium conversion facility The nuclear fuel facility also manufactures fuel bundles for nuclear reactors in Canada

Notes on data for the Zircatec nuclear fuel facility

1 Graphs indicate the following data bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of average effective doses

2 Doses from photons from external sources were measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay Historically although these internal doses have been measured and submitted to the CNSC they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

Figures 257ndash260 present dose information for the Zircatec nuclear fuel facility from 2001 to 2007

Figure 257 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on Non-Zero Results)

0

05

1

15

2

25

3

35

Effe

ctiv

e D

ose

(mS

v)

Year

55

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 258 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

18

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 259 Collective Dose Trends for the Zircatec Nuclear Fuel Facility

0

50

100

150

200

250

300

350

400

450

500

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

56

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 260 Distribution of Effective Doses Among All Workers at the Zircatec Nuclear Fuel Facility

300

Num

ber o

f Wor

kers

250

200

150

100

50

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

57

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

25 Research and Radioisotope Production Facilities This section presents dose information for the following research and radioisotope production facilities from 2001 to 2007

bull Chalk River Laboratories and Whiteshell Laboratories (Section 251) bull A radioisotope production facility operated by MDS Nordion (Section 252) bull The Tri-University Meson Facility (TRIUMF) (Section 253)

Note on data for research and radioisotope production facilities

1 Graphs indicate the following data for each facility bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of effective doses

251 Chalk River Laboratories and Whiteshell Laboratories

Atomic Energy of Canada Limited (AECL) owns and is licensed to operate Chalk River Laboratories and Whiteshell Laboratories

Situated in Renfrew County on the south shore of the Ottawa River the Chalk River Laboratories site hosts the National Research Universal Reactor along with numerous other facilities occupying some 160 buildings in an area of approximately 40 km2 Activities consist of radioisotope production for nuclear medicine testing and development of structural materials in support of power reactor operations fuel fabrication research and radioactive waste management and storage

The Whiteshell Laboratories site is located approximately 10 km west of Pinawa Manitoba and 100 km northeast of Winnipeg on the east bank of the Winnipeg River AECL established the laboratories for nuclear research and testing during the early 1960s and has since discontinued operations which are being decommissioned under a licence from the CNSC

Figures 261ndash264 present dose information for Chalk River Laboratories and Whiteshell Laboratories from 2001 to 2007

Notes on data for Chalk River Laboratories and Whiteshell Laboratories

1 Effective doses are composed of the following reported components bull external doses5 (from both photon and neutron doses) bull tritium doses

Due to issues with AECLrsquos in-house dosimetry management system neutron doses were not reported separately to the NDR during the reporting period As a result external doses from photons and neutrons were totaled The reporting discrepancy has since been rectified

58

5

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of external (photon and neutron) and tritium doses Intakes of other radionuclides occasionally occur and these radionuclides are not included here because their associated doses are very small For this reason certain collective doses in this report may have values slightly lower than the sum of their respective components as listed

Figure 261 Average Dose Trends for Chalk River and Whiteshell Laboratories (Non-Zero Results Only)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Tritium External Effective

Year

59

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 262 Average Dose Trends for Chalk River and Whiteshell Laboratories (All Monitoring Results)

000

020

040

060

080

100

120

Dos

e (m

Sv)

Tritium External Effective

Year

Figure 263 Collective Dose Trends for Chalk River and Whiteshell Laboratories

0

500

1000

1500

2000

2500

3000

3500

Col

lect

ive

Dos

e (p

erso

n- m

Sv)

External Tritium

Year

60

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 264 Distribution of Effective Doses Among All Workers at Chalk River and Whiteshell Laboratories

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

3500

3000

2500

2000

1500

1000

500

Dose (mSv)

61

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

252 MDS Nordion (Nuclear Substance Processing Facility and Canadian Irradiation Centre)

MDS Nordion owns and operates a nuclear substance processing facility in Ottawa Ontario where it processes unsealed radioisotopes and manufactures sealed radiation sources In operation since the early 1970s the facility was purchased by Nordion International in 1991

In cooperation with the Universiteacute du Queacutebecrsquos Institut Armand-Frappier MDS Nordion also operates the Canadian Irradiation Centre which conducts various irradiation services which include training testing and development The centre is located in Laval Quebec on the Universiteacute du Queacutebec campus

Figures 265ndash268 present dose information for MDS Nordionrsquos Ottawa nuclear substance processing facility and for the Canadian Irradiation Centre from 2001 to 2007

Notes on data for MDS Nordionrsquos nuclear substance processing facility and the Canadian Irradiation Centre

1 Doses from photons from external sources were measured and reported to the NDR MDS Nordion also has a routine thyroid monitoring program very occasionally small recordable doses of radiation have occurred from thyroid uptake of iodine The resulting doses have not been historically submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided

Figure 265 Average Dose Trends for MDS Nordion (Based on Non-Zero Results)

0

05

1

15

2

25

Effe

ctiv

e D

ose

(mS

v)

Year

62

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 266 Average Dose Trends for MDS Nordion (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

Figure 267 Collective Dose Trends for MDS Nordion

0

100

200

300

400

500

600

700

800

Year

63

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 268 Distribution of Effective Doses Among All Workers at MDS Nordion

0

5 0

1 0 0

1 5 0

2 0 0

2 5 0

3 0 0

3 5 0

4 0 0

4 5 0

5 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

64

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

253 Tri-University Meson Facility

The Tri-University Meson facility (TRIUMF) is situated in Vancouver on the campus of the University of British Columbia TRIUMF which began operating in the early 1970s with one cyclotron now has two cyclotrons and associated laboratories for research and radioisotope production The laboratory provides research facilities for Canadian and international users and also produces radioisotopes which are used by medical facilities and by a commercial organization (MDS Nordion) MDS Nordion staff also work at the TRIUMF site however MDS Nordion oversees this work and has its own radiation protection program

Figures 269ndash272 present dose information for the TRIUMF facility from 2001 to 2007 Please note that data sets do not distinguish between doses received by TRIUMF staff and MDS Nordion staff who work on the site as the data for these two groups was submitted collectively to the NDR for the reporting period shown Future data for each group will be submitted separately to the NDR

Note on data for TRIUMF

1 Effective doses are composed of the following reported components bull doses from photons (labeled as ldquoexternalrdquo in the charts) bull neutron doses

Figure 269 Average Dose Trends for TRIUMF (Non-Zero Results Only)

000

020

040

060

080

100

120

140

160

Dos

e (m

Sv)

Neutrons External Effective

Year

65

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 59: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

501-1

000

1001

-1500

gt 150

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 255 Collective Dose Trends for the General Electric Fuel Facility

0

50

100

150

200

250

300

350

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Long Lived Radioactive Dust External

Year

Figure 256 Distribution of Effective Doses among all Workers at the General Electric Fuel Facility

0

10

20

30

40

50

60

70

80

90

100

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

54

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

242 Zircatec Nuclear Fuel Facility

Zircatec Precision Industries Inc operates a nuclear fuel facility in Port Hope Ontario where it makes fuel pellets from uranium dioxide powder received from Port Hopersquos uranium conversion facility The nuclear fuel facility also manufactures fuel bundles for nuclear reactors in Canada

Notes on data for the Zircatec nuclear fuel facility

1 Graphs indicate the following data bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of average effective doses

2 Doses from photons from external sources were measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay Historically although these internal doses have been measured and submitted to the CNSC they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

Figures 257ndash260 present dose information for the Zircatec nuclear fuel facility from 2001 to 2007

Figure 257 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on Non-Zero Results)

0

05

1

15

2

25

3

35

Effe

ctiv

e D

ose

(mS

v)

Year

55

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 258 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

18

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 259 Collective Dose Trends for the Zircatec Nuclear Fuel Facility

0

50

100

150

200

250

300

350

400

450

500

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

56

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 260 Distribution of Effective Doses Among All Workers at the Zircatec Nuclear Fuel Facility

300

Num

ber o

f Wor

kers

250

200

150

100

50

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

57

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

25 Research and Radioisotope Production Facilities This section presents dose information for the following research and radioisotope production facilities from 2001 to 2007

bull Chalk River Laboratories and Whiteshell Laboratories (Section 251) bull A radioisotope production facility operated by MDS Nordion (Section 252) bull The Tri-University Meson Facility (TRIUMF) (Section 253)

Note on data for research and radioisotope production facilities

1 Graphs indicate the following data for each facility bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of effective doses

251 Chalk River Laboratories and Whiteshell Laboratories

Atomic Energy of Canada Limited (AECL) owns and is licensed to operate Chalk River Laboratories and Whiteshell Laboratories

Situated in Renfrew County on the south shore of the Ottawa River the Chalk River Laboratories site hosts the National Research Universal Reactor along with numerous other facilities occupying some 160 buildings in an area of approximately 40 km2 Activities consist of radioisotope production for nuclear medicine testing and development of structural materials in support of power reactor operations fuel fabrication research and radioactive waste management and storage

The Whiteshell Laboratories site is located approximately 10 km west of Pinawa Manitoba and 100 km northeast of Winnipeg on the east bank of the Winnipeg River AECL established the laboratories for nuclear research and testing during the early 1960s and has since discontinued operations which are being decommissioned under a licence from the CNSC

Figures 261ndash264 present dose information for Chalk River Laboratories and Whiteshell Laboratories from 2001 to 2007

Notes on data for Chalk River Laboratories and Whiteshell Laboratories

1 Effective doses are composed of the following reported components bull external doses5 (from both photon and neutron doses) bull tritium doses

Due to issues with AECLrsquos in-house dosimetry management system neutron doses were not reported separately to the NDR during the reporting period As a result external doses from photons and neutrons were totaled The reporting discrepancy has since been rectified

58

5

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of external (photon and neutron) and tritium doses Intakes of other radionuclides occasionally occur and these radionuclides are not included here because their associated doses are very small For this reason certain collective doses in this report may have values slightly lower than the sum of their respective components as listed

Figure 261 Average Dose Trends for Chalk River and Whiteshell Laboratories (Non-Zero Results Only)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Tritium External Effective

Year

59

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 262 Average Dose Trends for Chalk River and Whiteshell Laboratories (All Monitoring Results)

000

020

040

060

080

100

120

Dos

e (m

Sv)

Tritium External Effective

Year

Figure 263 Collective Dose Trends for Chalk River and Whiteshell Laboratories

0

500

1000

1500

2000

2500

3000

3500

Col

lect

ive

Dos

e (p

erso

n- m

Sv)

External Tritium

Year

60

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 264 Distribution of Effective Doses Among All Workers at Chalk River and Whiteshell Laboratories

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

3500

3000

2500

2000

1500

1000

500

Dose (mSv)

61

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

252 MDS Nordion (Nuclear Substance Processing Facility and Canadian Irradiation Centre)

MDS Nordion owns and operates a nuclear substance processing facility in Ottawa Ontario where it processes unsealed radioisotopes and manufactures sealed radiation sources In operation since the early 1970s the facility was purchased by Nordion International in 1991

In cooperation with the Universiteacute du Queacutebecrsquos Institut Armand-Frappier MDS Nordion also operates the Canadian Irradiation Centre which conducts various irradiation services which include training testing and development The centre is located in Laval Quebec on the Universiteacute du Queacutebec campus

Figures 265ndash268 present dose information for MDS Nordionrsquos Ottawa nuclear substance processing facility and for the Canadian Irradiation Centre from 2001 to 2007

Notes on data for MDS Nordionrsquos nuclear substance processing facility and the Canadian Irradiation Centre

1 Doses from photons from external sources were measured and reported to the NDR MDS Nordion also has a routine thyroid monitoring program very occasionally small recordable doses of radiation have occurred from thyroid uptake of iodine The resulting doses have not been historically submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided

Figure 265 Average Dose Trends for MDS Nordion (Based on Non-Zero Results)

0

05

1

15

2

25

Effe

ctiv

e D

ose

(mS

v)

Year

62

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 266 Average Dose Trends for MDS Nordion (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

Figure 267 Collective Dose Trends for MDS Nordion

0

100

200

300

400

500

600

700

800

Year

63

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 268 Distribution of Effective Doses Among All Workers at MDS Nordion

0

5 0

1 0 0

1 5 0

2 0 0

2 5 0

3 0 0

3 5 0

4 0 0

4 5 0

5 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

64

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

253 Tri-University Meson Facility

The Tri-University Meson facility (TRIUMF) is situated in Vancouver on the campus of the University of British Columbia TRIUMF which began operating in the early 1970s with one cyclotron now has two cyclotrons and associated laboratories for research and radioisotope production The laboratory provides research facilities for Canadian and international users and also produces radioisotopes which are used by medical facilities and by a commercial organization (MDS Nordion) MDS Nordion staff also work at the TRIUMF site however MDS Nordion oversees this work and has its own radiation protection program

Figures 269ndash272 present dose information for the TRIUMF facility from 2001 to 2007 Please note that data sets do not distinguish between doses received by TRIUMF staff and MDS Nordion staff who work on the site as the data for these two groups was submitted collectively to the NDR for the reporting period shown Future data for each group will be submitted separately to the NDR

Note on data for TRIUMF

1 Effective doses are composed of the following reported components bull doses from photons (labeled as ldquoexternalrdquo in the charts) bull neutron doses

Figure 269 Average Dose Trends for TRIUMF (Non-Zero Results Only)

000

020

040

060

080

100

120

140

160

Dos

e (m

Sv)

Neutrons External Effective

Year

65

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 60: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

242 Zircatec Nuclear Fuel Facility

Zircatec Precision Industries Inc operates a nuclear fuel facility in Port Hope Ontario where it makes fuel pellets from uranium dioxide powder received from Port Hopersquos uranium conversion facility The nuclear fuel facility also manufactures fuel bundles for nuclear reactors in Canada

Notes on data for the Zircatec nuclear fuel facility

1 Graphs indicate the following data bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of average effective doses

2 Doses from photons from external sources were measured and reported to the NDR However doses from internal intakes of uranium are measured through urine bioassay Historically although these internal doses have been measured and submitted to the CNSC they have not been submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided In the future both internal and external doses will be reported to the NDR

Figures 257ndash260 present dose information for the Zircatec nuclear fuel facility from 2001 to 2007

Figure 257 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on Non-Zero Results)

0

05

1

15

2

25

3

35

Effe

ctiv

e D

ose

(mS

v)

Year

55

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 258 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

18

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 259 Collective Dose Trends for the Zircatec Nuclear Fuel Facility

0

50

100

150

200

250

300

350

400

450

500

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

56

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 260 Distribution of Effective Doses Among All Workers at the Zircatec Nuclear Fuel Facility

300

Num

ber o

f Wor

kers

250

200

150

100

50

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

57

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

25 Research and Radioisotope Production Facilities This section presents dose information for the following research and radioisotope production facilities from 2001 to 2007

bull Chalk River Laboratories and Whiteshell Laboratories (Section 251) bull A radioisotope production facility operated by MDS Nordion (Section 252) bull The Tri-University Meson Facility (TRIUMF) (Section 253)

Note on data for research and radioisotope production facilities

1 Graphs indicate the following data for each facility bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of effective doses

251 Chalk River Laboratories and Whiteshell Laboratories

Atomic Energy of Canada Limited (AECL) owns and is licensed to operate Chalk River Laboratories and Whiteshell Laboratories

Situated in Renfrew County on the south shore of the Ottawa River the Chalk River Laboratories site hosts the National Research Universal Reactor along with numerous other facilities occupying some 160 buildings in an area of approximately 40 km2 Activities consist of radioisotope production for nuclear medicine testing and development of structural materials in support of power reactor operations fuel fabrication research and radioactive waste management and storage

The Whiteshell Laboratories site is located approximately 10 km west of Pinawa Manitoba and 100 km northeast of Winnipeg on the east bank of the Winnipeg River AECL established the laboratories for nuclear research and testing during the early 1960s and has since discontinued operations which are being decommissioned under a licence from the CNSC

Figures 261ndash264 present dose information for Chalk River Laboratories and Whiteshell Laboratories from 2001 to 2007

Notes on data for Chalk River Laboratories and Whiteshell Laboratories

1 Effective doses are composed of the following reported components bull external doses5 (from both photon and neutron doses) bull tritium doses

Due to issues with AECLrsquos in-house dosimetry management system neutron doses were not reported separately to the NDR during the reporting period As a result external doses from photons and neutrons were totaled The reporting discrepancy has since been rectified

58

5

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of external (photon and neutron) and tritium doses Intakes of other radionuclides occasionally occur and these radionuclides are not included here because their associated doses are very small For this reason certain collective doses in this report may have values slightly lower than the sum of their respective components as listed

Figure 261 Average Dose Trends for Chalk River and Whiteshell Laboratories (Non-Zero Results Only)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Tritium External Effective

Year

59

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 262 Average Dose Trends for Chalk River and Whiteshell Laboratories (All Monitoring Results)

000

020

040

060

080

100

120

Dos

e (m

Sv)

Tritium External Effective

Year

Figure 263 Collective Dose Trends for Chalk River and Whiteshell Laboratories

0

500

1000

1500

2000

2500

3000

3500

Col

lect

ive

Dos

e (p

erso

n- m

Sv)

External Tritium

Year

60

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 264 Distribution of Effective Doses Among All Workers at Chalk River and Whiteshell Laboratories

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

3500

3000

2500

2000

1500

1000

500

Dose (mSv)

61

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

252 MDS Nordion (Nuclear Substance Processing Facility and Canadian Irradiation Centre)

MDS Nordion owns and operates a nuclear substance processing facility in Ottawa Ontario where it processes unsealed radioisotopes and manufactures sealed radiation sources In operation since the early 1970s the facility was purchased by Nordion International in 1991

In cooperation with the Universiteacute du Queacutebecrsquos Institut Armand-Frappier MDS Nordion also operates the Canadian Irradiation Centre which conducts various irradiation services which include training testing and development The centre is located in Laval Quebec on the Universiteacute du Queacutebec campus

Figures 265ndash268 present dose information for MDS Nordionrsquos Ottawa nuclear substance processing facility and for the Canadian Irradiation Centre from 2001 to 2007

Notes on data for MDS Nordionrsquos nuclear substance processing facility and the Canadian Irradiation Centre

1 Doses from photons from external sources were measured and reported to the NDR MDS Nordion also has a routine thyroid monitoring program very occasionally small recordable doses of radiation have occurred from thyroid uptake of iodine The resulting doses have not been historically submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided

Figure 265 Average Dose Trends for MDS Nordion (Based on Non-Zero Results)

0

05

1

15

2

25

Effe

ctiv

e D

ose

(mS

v)

Year

62

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 266 Average Dose Trends for MDS Nordion (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

Figure 267 Collective Dose Trends for MDS Nordion

0

100

200

300

400

500

600

700

800

Year

63

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 268 Distribution of Effective Doses Among All Workers at MDS Nordion

0

5 0

1 0 0

1 5 0

2 0 0

2 5 0

3 0 0

3 5 0

4 0 0

4 5 0

5 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

64

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

253 Tri-University Meson Facility

The Tri-University Meson facility (TRIUMF) is situated in Vancouver on the campus of the University of British Columbia TRIUMF which began operating in the early 1970s with one cyclotron now has two cyclotrons and associated laboratories for research and radioisotope production The laboratory provides research facilities for Canadian and international users and also produces radioisotopes which are used by medical facilities and by a commercial organization (MDS Nordion) MDS Nordion staff also work at the TRIUMF site however MDS Nordion oversees this work and has its own radiation protection program

Figures 269ndash272 present dose information for the TRIUMF facility from 2001 to 2007 Please note that data sets do not distinguish between doses received by TRIUMF staff and MDS Nordion staff who work on the site as the data for these two groups was submitted collectively to the NDR for the reporting period shown Future data for each group will be submitted separately to the NDR

Note on data for TRIUMF

1 Effective doses are composed of the following reported components bull doses from photons (labeled as ldquoexternalrdquo in the charts) bull neutron doses

Figure 269 Average Dose Trends for TRIUMF (Non-Zero Results Only)

000

020

040

060

080

100

120

140

160

Dos

e (m

Sv)

Neutrons External Effective

Year

65

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 61: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 258 Average Dose Trends for the Zircatec Nuclear Fuel Facility (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

18

Effe

ctiv

e D

ose

(mS

v)

Year

Figure 259 Collective Dose Trends for the Zircatec Nuclear Fuel Facility

0

50

100

150

200

250

300

350

400

450

500

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

56

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 260 Distribution of Effective Doses Among All Workers at the Zircatec Nuclear Fuel Facility

300

Num

ber o

f Wor

kers

250

200

150

100

50

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

57

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

25 Research and Radioisotope Production Facilities This section presents dose information for the following research and radioisotope production facilities from 2001 to 2007

bull Chalk River Laboratories and Whiteshell Laboratories (Section 251) bull A radioisotope production facility operated by MDS Nordion (Section 252) bull The Tri-University Meson Facility (TRIUMF) (Section 253)

Note on data for research and radioisotope production facilities

1 Graphs indicate the following data for each facility bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of effective doses

251 Chalk River Laboratories and Whiteshell Laboratories

Atomic Energy of Canada Limited (AECL) owns and is licensed to operate Chalk River Laboratories and Whiteshell Laboratories

Situated in Renfrew County on the south shore of the Ottawa River the Chalk River Laboratories site hosts the National Research Universal Reactor along with numerous other facilities occupying some 160 buildings in an area of approximately 40 km2 Activities consist of radioisotope production for nuclear medicine testing and development of structural materials in support of power reactor operations fuel fabrication research and radioactive waste management and storage

The Whiteshell Laboratories site is located approximately 10 km west of Pinawa Manitoba and 100 km northeast of Winnipeg on the east bank of the Winnipeg River AECL established the laboratories for nuclear research and testing during the early 1960s and has since discontinued operations which are being decommissioned under a licence from the CNSC

Figures 261ndash264 present dose information for Chalk River Laboratories and Whiteshell Laboratories from 2001 to 2007

Notes on data for Chalk River Laboratories and Whiteshell Laboratories

1 Effective doses are composed of the following reported components bull external doses5 (from both photon and neutron doses) bull tritium doses

Due to issues with AECLrsquos in-house dosimetry management system neutron doses were not reported separately to the NDR during the reporting period As a result external doses from photons and neutrons were totaled The reporting discrepancy has since been rectified

58

5

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of external (photon and neutron) and tritium doses Intakes of other radionuclides occasionally occur and these radionuclides are not included here because their associated doses are very small For this reason certain collective doses in this report may have values slightly lower than the sum of their respective components as listed

Figure 261 Average Dose Trends for Chalk River and Whiteshell Laboratories (Non-Zero Results Only)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Tritium External Effective

Year

59

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 262 Average Dose Trends for Chalk River and Whiteshell Laboratories (All Monitoring Results)

000

020

040

060

080

100

120

Dos

e (m

Sv)

Tritium External Effective

Year

Figure 263 Collective Dose Trends for Chalk River and Whiteshell Laboratories

0

500

1000

1500

2000

2500

3000

3500

Col

lect

ive

Dos

e (p

erso

n- m

Sv)

External Tritium

Year

60

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 264 Distribution of Effective Doses Among All Workers at Chalk River and Whiteshell Laboratories

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

3500

3000

2500

2000

1500

1000

500

Dose (mSv)

61

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

252 MDS Nordion (Nuclear Substance Processing Facility and Canadian Irradiation Centre)

MDS Nordion owns and operates a nuclear substance processing facility in Ottawa Ontario where it processes unsealed radioisotopes and manufactures sealed radiation sources In operation since the early 1970s the facility was purchased by Nordion International in 1991

In cooperation with the Universiteacute du Queacutebecrsquos Institut Armand-Frappier MDS Nordion also operates the Canadian Irradiation Centre which conducts various irradiation services which include training testing and development The centre is located in Laval Quebec on the Universiteacute du Queacutebec campus

Figures 265ndash268 present dose information for MDS Nordionrsquos Ottawa nuclear substance processing facility and for the Canadian Irradiation Centre from 2001 to 2007

Notes on data for MDS Nordionrsquos nuclear substance processing facility and the Canadian Irradiation Centre

1 Doses from photons from external sources were measured and reported to the NDR MDS Nordion also has a routine thyroid monitoring program very occasionally small recordable doses of radiation have occurred from thyroid uptake of iodine The resulting doses have not been historically submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided

Figure 265 Average Dose Trends for MDS Nordion (Based on Non-Zero Results)

0

05

1

15

2

25

Effe

ctiv

e D

ose

(mS

v)

Year

62

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 266 Average Dose Trends for MDS Nordion (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

Figure 267 Collective Dose Trends for MDS Nordion

0

100

200

300

400

500

600

700

800

Year

63

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 268 Distribution of Effective Doses Among All Workers at MDS Nordion

0

5 0

1 0 0

1 5 0

2 0 0

2 5 0

3 0 0

3 5 0

4 0 0

4 5 0

5 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

64

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

253 Tri-University Meson Facility

The Tri-University Meson facility (TRIUMF) is situated in Vancouver on the campus of the University of British Columbia TRIUMF which began operating in the early 1970s with one cyclotron now has two cyclotrons and associated laboratories for research and radioisotope production The laboratory provides research facilities for Canadian and international users and also produces radioisotopes which are used by medical facilities and by a commercial organization (MDS Nordion) MDS Nordion staff also work at the TRIUMF site however MDS Nordion oversees this work and has its own radiation protection program

Figures 269ndash272 present dose information for the TRIUMF facility from 2001 to 2007 Please note that data sets do not distinguish between doses received by TRIUMF staff and MDS Nordion staff who work on the site as the data for these two groups was submitted collectively to the NDR for the reporting period shown Future data for each group will be submitted separately to the NDR

Note on data for TRIUMF

1 Effective doses are composed of the following reported components bull doses from photons (labeled as ldquoexternalrdquo in the charts) bull neutron doses

Figure 269 Average Dose Trends for TRIUMF (Non-Zero Results Only)

000

020

040

060

080

100

120

140

160

Dos

e (m

Sv)

Neutrons External Effective

Year

65

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 62: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 260 Distribution of Effective Doses Among All Workers at the Zircatec Nuclear Fuel Facility

300

Num

ber o

f Wor

kers

250

200

150

100

50

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

57

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

25 Research and Radioisotope Production Facilities This section presents dose information for the following research and radioisotope production facilities from 2001 to 2007

bull Chalk River Laboratories and Whiteshell Laboratories (Section 251) bull A radioisotope production facility operated by MDS Nordion (Section 252) bull The Tri-University Meson Facility (TRIUMF) (Section 253)

Note on data for research and radioisotope production facilities

1 Graphs indicate the following data for each facility bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of effective doses

251 Chalk River Laboratories and Whiteshell Laboratories

Atomic Energy of Canada Limited (AECL) owns and is licensed to operate Chalk River Laboratories and Whiteshell Laboratories

Situated in Renfrew County on the south shore of the Ottawa River the Chalk River Laboratories site hosts the National Research Universal Reactor along with numerous other facilities occupying some 160 buildings in an area of approximately 40 km2 Activities consist of radioisotope production for nuclear medicine testing and development of structural materials in support of power reactor operations fuel fabrication research and radioactive waste management and storage

The Whiteshell Laboratories site is located approximately 10 km west of Pinawa Manitoba and 100 km northeast of Winnipeg on the east bank of the Winnipeg River AECL established the laboratories for nuclear research and testing during the early 1960s and has since discontinued operations which are being decommissioned under a licence from the CNSC

Figures 261ndash264 present dose information for Chalk River Laboratories and Whiteshell Laboratories from 2001 to 2007

Notes on data for Chalk River Laboratories and Whiteshell Laboratories

1 Effective doses are composed of the following reported components bull external doses5 (from both photon and neutron doses) bull tritium doses

Due to issues with AECLrsquos in-house dosimetry management system neutron doses were not reported separately to the NDR during the reporting period As a result external doses from photons and neutrons were totaled The reporting discrepancy has since been rectified

58

5

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of external (photon and neutron) and tritium doses Intakes of other radionuclides occasionally occur and these radionuclides are not included here because their associated doses are very small For this reason certain collective doses in this report may have values slightly lower than the sum of their respective components as listed

Figure 261 Average Dose Trends for Chalk River and Whiteshell Laboratories (Non-Zero Results Only)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Tritium External Effective

Year

59

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 262 Average Dose Trends for Chalk River and Whiteshell Laboratories (All Monitoring Results)

000

020

040

060

080

100

120

Dos

e (m

Sv)

Tritium External Effective

Year

Figure 263 Collective Dose Trends for Chalk River and Whiteshell Laboratories

0

500

1000

1500

2000

2500

3000

3500

Col

lect

ive

Dos

e (p

erso

n- m

Sv)

External Tritium

Year

60

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 264 Distribution of Effective Doses Among All Workers at Chalk River and Whiteshell Laboratories

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

3500

3000

2500

2000

1500

1000

500

Dose (mSv)

61

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

252 MDS Nordion (Nuclear Substance Processing Facility and Canadian Irradiation Centre)

MDS Nordion owns and operates a nuclear substance processing facility in Ottawa Ontario where it processes unsealed radioisotopes and manufactures sealed radiation sources In operation since the early 1970s the facility was purchased by Nordion International in 1991

In cooperation with the Universiteacute du Queacutebecrsquos Institut Armand-Frappier MDS Nordion also operates the Canadian Irradiation Centre which conducts various irradiation services which include training testing and development The centre is located in Laval Quebec on the Universiteacute du Queacutebec campus

Figures 265ndash268 present dose information for MDS Nordionrsquos Ottawa nuclear substance processing facility and for the Canadian Irradiation Centre from 2001 to 2007

Notes on data for MDS Nordionrsquos nuclear substance processing facility and the Canadian Irradiation Centre

1 Doses from photons from external sources were measured and reported to the NDR MDS Nordion also has a routine thyroid monitoring program very occasionally small recordable doses of radiation have occurred from thyroid uptake of iodine The resulting doses have not been historically submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided

Figure 265 Average Dose Trends for MDS Nordion (Based on Non-Zero Results)

0

05

1

15

2

25

Effe

ctiv

e D

ose

(mS

v)

Year

62

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 266 Average Dose Trends for MDS Nordion (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

Figure 267 Collective Dose Trends for MDS Nordion

0

100

200

300

400

500

600

700

800

Year

63

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 268 Distribution of Effective Doses Among All Workers at MDS Nordion

0

5 0

1 0 0

1 5 0

2 0 0

2 5 0

3 0 0

3 5 0

4 0 0

4 5 0

5 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

64

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

253 Tri-University Meson Facility

The Tri-University Meson facility (TRIUMF) is situated in Vancouver on the campus of the University of British Columbia TRIUMF which began operating in the early 1970s with one cyclotron now has two cyclotrons and associated laboratories for research and radioisotope production The laboratory provides research facilities for Canadian and international users and also produces radioisotopes which are used by medical facilities and by a commercial organization (MDS Nordion) MDS Nordion staff also work at the TRIUMF site however MDS Nordion oversees this work and has its own radiation protection program

Figures 269ndash272 present dose information for the TRIUMF facility from 2001 to 2007 Please note that data sets do not distinguish between doses received by TRIUMF staff and MDS Nordion staff who work on the site as the data for these two groups was submitted collectively to the NDR for the reporting period shown Future data for each group will be submitted separately to the NDR

Note on data for TRIUMF

1 Effective doses are composed of the following reported components bull doses from photons (labeled as ldquoexternalrdquo in the charts) bull neutron doses

Figure 269 Average Dose Trends for TRIUMF (Non-Zero Results Only)

000

020

040

060

080

100

120

140

160

Dos

e (m

Sv)

Neutrons External Effective

Year

65

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 63: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

25 Research and Radioisotope Production Facilities This section presents dose information for the following research and radioisotope production facilities from 2001 to 2007

bull Chalk River Laboratories and Whiteshell Laboratories (Section 251) bull A radioisotope production facility operated by MDS Nordion (Section 252) bull The Tri-University Meson Facility (TRIUMF) (Section 253)

Note on data for research and radioisotope production facilities

1 Graphs indicate the following data for each facility bull average doses based on non-zero (positive) results bull average doses based on all monitoring results bull collective doses bull distribution of effective doses

251 Chalk River Laboratories and Whiteshell Laboratories

Atomic Energy of Canada Limited (AECL) owns and is licensed to operate Chalk River Laboratories and Whiteshell Laboratories

Situated in Renfrew County on the south shore of the Ottawa River the Chalk River Laboratories site hosts the National Research Universal Reactor along with numerous other facilities occupying some 160 buildings in an area of approximately 40 km2 Activities consist of radioisotope production for nuclear medicine testing and development of structural materials in support of power reactor operations fuel fabrication research and radioactive waste management and storage

The Whiteshell Laboratories site is located approximately 10 km west of Pinawa Manitoba and 100 km northeast of Winnipeg on the east bank of the Winnipeg River AECL established the laboratories for nuclear research and testing during the early 1960s and has since discontinued operations which are being decommissioned under a licence from the CNSC

Figures 261ndash264 present dose information for Chalk River Laboratories and Whiteshell Laboratories from 2001 to 2007

Notes on data for Chalk River Laboratories and Whiteshell Laboratories

1 Effective doses are composed of the following reported components bull external doses5 (from both photon and neutron doses) bull tritium doses

Due to issues with AECLrsquos in-house dosimetry management system neutron doses were not reported separately to the NDR during the reporting period As a result external doses from photons and neutrons were totaled The reporting discrepancy has since been rectified

58

5

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of external (photon and neutron) and tritium doses Intakes of other radionuclides occasionally occur and these radionuclides are not included here because their associated doses are very small For this reason certain collective doses in this report may have values slightly lower than the sum of their respective components as listed

Figure 261 Average Dose Trends for Chalk River and Whiteshell Laboratories (Non-Zero Results Only)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Tritium External Effective

Year

59

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 262 Average Dose Trends for Chalk River and Whiteshell Laboratories (All Monitoring Results)

000

020

040

060

080

100

120

Dos

e (m

Sv)

Tritium External Effective

Year

Figure 263 Collective Dose Trends for Chalk River and Whiteshell Laboratories

0

500

1000

1500

2000

2500

3000

3500

Col

lect

ive

Dos

e (p

erso

n- m

Sv)

External Tritium

Year

60

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 264 Distribution of Effective Doses Among All Workers at Chalk River and Whiteshell Laboratories

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

3500

3000

2500

2000

1500

1000

500

Dose (mSv)

61

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

252 MDS Nordion (Nuclear Substance Processing Facility and Canadian Irradiation Centre)

MDS Nordion owns and operates a nuclear substance processing facility in Ottawa Ontario where it processes unsealed radioisotopes and manufactures sealed radiation sources In operation since the early 1970s the facility was purchased by Nordion International in 1991

In cooperation with the Universiteacute du Queacutebecrsquos Institut Armand-Frappier MDS Nordion also operates the Canadian Irradiation Centre which conducts various irradiation services which include training testing and development The centre is located in Laval Quebec on the Universiteacute du Queacutebec campus

Figures 265ndash268 present dose information for MDS Nordionrsquos Ottawa nuclear substance processing facility and for the Canadian Irradiation Centre from 2001 to 2007

Notes on data for MDS Nordionrsquos nuclear substance processing facility and the Canadian Irradiation Centre

1 Doses from photons from external sources were measured and reported to the NDR MDS Nordion also has a routine thyroid monitoring program very occasionally small recordable doses of radiation have occurred from thyroid uptake of iodine The resulting doses have not been historically submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided

Figure 265 Average Dose Trends for MDS Nordion (Based on Non-Zero Results)

0

05

1

15

2

25

Effe

ctiv

e D

ose

(mS

v)

Year

62

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 266 Average Dose Trends for MDS Nordion (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

Figure 267 Collective Dose Trends for MDS Nordion

0

100

200

300

400

500

600

700

800

Year

63

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 268 Distribution of Effective Doses Among All Workers at MDS Nordion

0

5 0

1 0 0

1 5 0

2 0 0

2 5 0

3 0 0

3 5 0

4 0 0

4 5 0

5 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

64

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

253 Tri-University Meson Facility

The Tri-University Meson facility (TRIUMF) is situated in Vancouver on the campus of the University of British Columbia TRIUMF which began operating in the early 1970s with one cyclotron now has two cyclotrons and associated laboratories for research and radioisotope production The laboratory provides research facilities for Canadian and international users and also produces radioisotopes which are used by medical facilities and by a commercial organization (MDS Nordion) MDS Nordion staff also work at the TRIUMF site however MDS Nordion oversees this work and has its own radiation protection program

Figures 269ndash272 present dose information for the TRIUMF facility from 2001 to 2007 Please note that data sets do not distinguish between doses received by TRIUMF staff and MDS Nordion staff who work on the site as the data for these two groups was submitted collectively to the NDR for the reporting period shown Future data for each group will be submitted separately to the NDR

Note on data for TRIUMF

1 Effective doses are composed of the following reported components bull doses from photons (labeled as ldquoexternalrdquo in the charts) bull neutron doses

Figure 269 Average Dose Trends for TRIUMF (Non-Zero Results Only)

000

020

040

060

080

100

120

140

160

Dos

e (m

Sv)

Neutrons External Effective

Year

65

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 64: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

2 Collective dose data is presented in stacked bar graphs where total effective doses are the sum of their respective components of external (photon and neutron) and tritium doses Intakes of other radionuclides occasionally occur and these radionuclides are not included here because their associated doses are very small For this reason certain collective doses in this report may have values slightly lower than the sum of their respective components as listed

Figure 261 Average Dose Trends for Chalk River and Whiteshell Laboratories (Non-Zero Results Only)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Tritium External Effective

Year

59

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 262 Average Dose Trends for Chalk River and Whiteshell Laboratories (All Monitoring Results)

000

020

040

060

080

100

120

Dos

e (m

Sv)

Tritium External Effective

Year

Figure 263 Collective Dose Trends for Chalk River and Whiteshell Laboratories

0

500

1000

1500

2000

2500

3000

3500

Col

lect

ive

Dos

e (p

erso

n- m

Sv)

External Tritium

Year

60

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 264 Distribution of Effective Doses Among All Workers at Chalk River and Whiteshell Laboratories

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

3500

3000

2500

2000

1500

1000

500

Dose (mSv)

61

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

252 MDS Nordion (Nuclear Substance Processing Facility and Canadian Irradiation Centre)

MDS Nordion owns and operates a nuclear substance processing facility in Ottawa Ontario where it processes unsealed radioisotopes and manufactures sealed radiation sources In operation since the early 1970s the facility was purchased by Nordion International in 1991

In cooperation with the Universiteacute du Queacutebecrsquos Institut Armand-Frappier MDS Nordion also operates the Canadian Irradiation Centre which conducts various irradiation services which include training testing and development The centre is located in Laval Quebec on the Universiteacute du Queacutebec campus

Figures 265ndash268 present dose information for MDS Nordionrsquos Ottawa nuclear substance processing facility and for the Canadian Irradiation Centre from 2001 to 2007

Notes on data for MDS Nordionrsquos nuclear substance processing facility and the Canadian Irradiation Centre

1 Doses from photons from external sources were measured and reported to the NDR MDS Nordion also has a routine thyroid monitoring program very occasionally small recordable doses of radiation have occurred from thyroid uptake of iodine The resulting doses have not been historically submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided

Figure 265 Average Dose Trends for MDS Nordion (Based on Non-Zero Results)

0

05

1

15

2

25

Effe

ctiv

e D

ose

(mS

v)

Year

62

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 266 Average Dose Trends for MDS Nordion (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

Figure 267 Collective Dose Trends for MDS Nordion

0

100

200

300

400

500

600

700

800

Year

63

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 268 Distribution of Effective Doses Among All Workers at MDS Nordion

0

5 0

1 0 0

1 5 0

2 0 0

2 5 0

3 0 0

3 5 0

4 0 0

4 5 0

5 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

64

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

253 Tri-University Meson Facility

The Tri-University Meson facility (TRIUMF) is situated in Vancouver on the campus of the University of British Columbia TRIUMF which began operating in the early 1970s with one cyclotron now has two cyclotrons and associated laboratories for research and radioisotope production The laboratory provides research facilities for Canadian and international users and also produces radioisotopes which are used by medical facilities and by a commercial organization (MDS Nordion) MDS Nordion staff also work at the TRIUMF site however MDS Nordion oversees this work and has its own radiation protection program

Figures 269ndash272 present dose information for the TRIUMF facility from 2001 to 2007 Please note that data sets do not distinguish between doses received by TRIUMF staff and MDS Nordion staff who work on the site as the data for these two groups was submitted collectively to the NDR for the reporting period shown Future data for each group will be submitted separately to the NDR

Note on data for TRIUMF

1 Effective doses are composed of the following reported components bull doses from photons (labeled as ldquoexternalrdquo in the charts) bull neutron doses

Figure 269 Average Dose Trends for TRIUMF (Non-Zero Results Only)

000

020

040

060

080

100

120

140

160

Dos

e (m

Sv)

Neutrons External Effective

Year

65

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 65: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 262 Average Dose Trends for Chalk River and Whiteshell Laboratories (All Monitoring Results)

000

020

040

060

080

100

120

Dos

e (m

Sv)

Tritium External Effective

Year

Figure 263 Collective Dose Trends for Chalk River and Whiteshell Laboratories

0

500

1000

1500

2000

2500

3000

3500

Col

lect

ive

Dos

e (p

erso

n- m

Sv)

External Tritium

Year

60

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 264 Distribution of Effective Doses Among All Workers at Chalk River and Whiteshell Laboratories

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

3500

3000

2500

2000

1500

1000

500

Dose (mSv)

61

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

252 MDS Nordion (Nuclear Substance Processing Facility and Canadian Irradiation Centre)

MDS Nordion owns and operates a nuclear substance processing facility in Ottawa Ontario where it processes unsealed radioisotopes and manufactures sealed radiation sources In operation since the early 1970s the facility was purchased by Nordion International in 1991

In cooperation with the Universiteacute du Queacutebecrsquos Institut Armand-Frappier MDS Nordion also operates the Canadian Irradiation Centre which conducts various irradiation services which include training testing and development The centre is located in Laval Quebec on the Universiteacute du Queacutebec campus

Figures 265ndash268 present dose information for MDS Nordionrsquos Ottawa nuclear substance processing facility and for the Canadian Irradiation Centre from 2001 to 2007

Notes on data for MDS Nordionrsquos nuclear substance processing facility and the Canadian Irradiation Centre

1 Doses from photons from external sources were measured and reported to the NDR MDS Nordion also has a routine thyroid monitoring program very occasionally small recordable doses of radiation have occurred from thyroid uptake of iodine The resulting doses have not been historically submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided

Figure 265 Average Dose Trends for MDS Nordion (Based on Non-Zero Results)

0

05

1

15

2

25

Effe

ctiv

e D

ose

(mS

v)

Year

62

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 266 Average Dose Trends for MDS Nordion (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

Figure 267 Collective Dose Trends for MDS Nordion

0

100

200

300

400

500

600

700

800

Year

63

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 268 Distribution of Effective Doses Among All Workers at MDS Nordion

0

5 0

1 0 0

1 5 0

2 0 0

2 5 0

3 0 0

3 5 0

4 0 0

4 5 0

5 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

64

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

253 Tri-University Meson Facility

The Tri-University Meson facility (TRIUMF) is situated in Vancouver on the campus of the University of British Columbia TRIUMF which began operating in the early 1970s with one cyclotron now has two cyclotrons and associated laboratories for research and radioisotope production The laboratory provides research facilities for Canadian and international users and also produces radioisotopes which are used by medical facilities and by a commercial organization (MDS Nordion) MDS Nordion staff also work at the TRIUMF site however MDS Nordion oversees this work and has its own radiation protection program

Figures 269ndash272 present dose information for the TRIUMF facility from 2001 to 2007 Please note that data sets do not distinguish between doses received by TRIUMF staff and MDS Nordion staff who work on the site as the data for these two groups was submitted collectively to the NDR for the reporting period shown Future data for each group will be submitted separately to the NDR

Note on data for TRIUMF

1 Effective doses are composed of the following reported components bull doses from photons (labeled as ldquoexternalrdquo in the charts) bull neutron doses

Figure 269 Average Dose Trends for TRIUMF (Non-Zero Results Only)

000

020

040

060

080

100

120

140

160

Dos

e (m

Sv)

Neutrons External Effective

Year

65

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 66: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

0

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 264 Distribution of Effective Doses Among All Workers at Chalk River and Whiteshell Laboratories

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Num

ber o

f Wor

kers

3500

3000

2500

2000

1500

1000

500

Dose (mSv)

61

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

252 MDS Nordion (Nuclear Substance Processing Facility and Canadian Irradiation Centre)

MDS Nordion owns and operates a nuclear substance processing facility in Ottawa Ontario where it processes unsealed radioisotopes and manufactures sealed radiation sources In operation since the early 1970s the facility was purchased by Nordion International in 1991

In cooperation with the Universiteacute du Queacutebecrsquos Institut Armand-Frappier MDS Nordion also operates the Canadian Irradiation Centre which conducts various irradiation services which include training testing and development The centre is located in Laval Quebec on the Universiteacute du Queacutebec campus

Figures 265ndash268 present dose information for MDS Nordionrsquos Ottawa nuclear substance processing facility and for the Canadian Irradiation Centre from 2001 to 2007

Notes on data for MDS Nordionrsquos nuclear substance processing facility and the Canadian Irradiation Centre

1 Doses from photons from external sources were measured and reported to the NDR MDS Nordion also has a routine thyroid monitoring program very occasionally small recordable doses of radiation have occurred from thyroid uptake of iodine The resulting doses have not been historically submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided

Figure 265 Average Dose Trends for MDS Nordion (Based on Non-Zero Results)

0

05

1

15

2

25

Effe

ctiv

e D

ose

(mS

v)

Year

62

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 266 Average Dose Trends for MDS Nordion (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

Figure 267 Collective Dose Trends for MDS Nordion

0

100

200

300

400

500

600

700

800

Year

63

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 268 Distribution of Effective Doses Among All Workers at MDS Nordion

0

5 0

1 0 0

1 5 0

2 0 0

2 5 0

3 0 0

3 5 0

4 0 0

4 5 0

5 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

64

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

253 Tri-University Meson Facility

The Tri-University Meson facility (TRIUMF) is situated in Vancouver on the campus of the University of British Columbia TRIUMF which began operating in the early 1970s with one cyclotron now has two cyclotrons and associated laboratories for research and radioisotope production The laboratory provides research facilities for Canadian and international users and also produces radioisotopes which are used by medical facilities and by a commercial organization (MDS Nordion) MDS Nordion staff also work at the TRIUMF site however MDS Nordion oversees this work and has its own radiation protection program

Figures 269ndash272 present dose information for the TRIUMF facility from 2001 to 2007 Please note that data sets do not distinguish between doses received by TRIUMF staff and MDS Nordion staff who work on the site as the data for these two groups was submitted collectively to the NDR for the reporting period shown Future data for each group will be submitted separately to the NDR

Note on data for TRIUMF

1 Effective doses are composed of the following reported components bull doses from photons (labeled as ldquoexternalrdquo in the charts) bull neutron doses

Figure 269 Average Dose Trends for TRIUMF (Non-Zero Results Only)

000

020

040

060

080

100

120

140

160

Dos

e (m

Sv)

Neutrons External Effective

Year

65

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 67: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

252 MDS Nordion (Nuclear Substance Processing Facility and Canadian Irradiation Centre)

MDS Nordion owns and operates a nuclear substance processing facility in Ottawa Ontario where it processes unsealed radioisotopes and manufactures sealed radiation sources In operation since the early 1970s the facility was purchased by Nordion International in 1991

In cooperation with the Universiteacute du Queacutebecrsquos Institut Armand-Frappier MDS Nordion also operates the Canadian Irradiation Centre which conducts various irradiation services which include training testing and development The centre is located in Laval Quebec on the Universiteacute du Queacutebec campus

Figures 265ndash268 present dose information for MDS Nordionrsquos Ottawa nuclear substance processing facility and for the Canadian Irradiation Centre from 2001 to 2007

Notes on data for MDS Nordionrsquos nuclear substance processing facility and the Canadian Irradiation Centre

1 Doses from photons from external sources were measured and reported to the NDR MDS Nordion also has a routine thyroid monitoring program very occasionally small recordable doses of radiation have occurred from thyroid uptake of iodine The resulting doses have not been historically submitted to the NDR For the purposes of this report only the external component of the effective dose (as found in the NDR) is provided

Figure 265 Average Dose Trends for MDS Nordion (Based on Non-Zero Results)

0

05

1

15

2

25

Effe

ctiv

e D

ose

(mS

v)

Year

62

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 266 Average Dose Trends for MDS Nordion (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

Figure 267 Collective Dose Trends for MDS Nordion

0

100

200

300

400

500

600

700

800

Year

63

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 268 Distribution of Effective Doses Among All Workers at MDS Nordion

0

5 0

1 0 0

1 5 0

2 0 0

2 5 0

3 0 0

3 5 0

4 0 0

4 5 0

5 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

64

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

253 Tri-University Meson Facility

The Tri-University Meson facility (TRIUMF) is situated in Vancouver on the campus of the University of British Columbia TRIUMF which began operating in the early 1970s with one cyclotron now has two cyclotrons and associated laboratories for research and radioisotope production The laboratory provides research facilities for Canadian and international users and also produces radioisotopes which are used by medical facilities and by a commercial organization (MDS Nordion) MDS Nordion staff also work at the TRIUMF site however MDS Nordion oversees this work and has its own radiation protection program

Figures 269ndash272 present dose information for the TRIUMF facility from 2001 to 2007 Please note that data sets do not distinguish between doses received by TRIUMF staff and MDS Nordion staff who work on the site as the data for these two groups was submitted collectively to the NDR for the reporting period shown Future data for each group will be submitted separately to the NDR

Note on data for TRIUMF

1 Effective doses are composed of the following reported components bull doses from photons (labeled as ldquoexternalrdquo in the charts) bull neutron doses

Figure 269 Average Dose Trends for TRIUMF (Non-Zero Results Only)

000

020

040

060

080

100

120

140

160

Dos

e (m

Sv)

Neutrons External Effective

Year

65

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 68: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 266 Average Dose Trends for MDS Nordion (Based on All Monitoring Results)

0

02

04

06

08

1

12

14

16

Year

Figure 267 Collective Dose Trends for MDS Nordion

0

100

200

300

400

500

600

700

800

Year

63

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 268 Distribution of Effective Doses Among All Workers at MDS Nordion

0

5 0

1 0 0

1 5 0

2 0 0

2 5 0

3 0 0

3 5 0

4 0 0

4 5 0

5 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

64

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

253 Tri-University Meson Facility

The Tri-University Meson facility (TRIUMF) is situated in Vancouver on the campus of the University of British Columbia TRIUMF which began operating in the early 1970s with one cyclotron now has two cyclotrons and associated laboratories for research and radioisotope production The laboratory provides research facilities for Canadian and international users and also produces radioisotopes which are used by medical facilities and by a commercial organization (MDS Nordion) MDS Nordion staff also work at the TRIUMF site however MDS Nordion oversees this work and has its own radiation protection program

Figures 269ndash272 present dose information for the TRIUMF facility from 2001 to 2007 Please note that data sets do not distinguish between doses received by TRIUMF staff and MDS Nordion staff who work on the site as the data for these two groups was submitted collectively to the NDR for the reporting period shown Future data for each group will be submitted separately to the NDR

Note on data for TRIUMF

1 Effective doses are composed of the following reported components bull doses from photons (labeled as ldquoexternalrdquo in the charts) bull neutron doses

Figure 269 Average Dose Trends for TRIUMF (Non-Zero Results Only)

000

020

040

060

080

100

120

140

160

Dos

e (m

Sv)

Neutrons External Effective

Year

65

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 69: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

gt 200

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 268 Distribution of Effective Doses Among All Workers at MDS Nordion

0

5 0

1 0 0

1 5 0

2 0 0

2 5 0

3 0 0

3 5 0

4 0 0

4 5 0

5 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

64

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

253 Tri-University Meson Facility

The Tri-University Meson facility (TRIUMF) is situated in Vancouver on the campus of the University of British Columbia TRIUMF which began operating in the early 1970s with one cyclotron now has two cyclotrons and associated laboratories for research and radioisotope production The laboratory provides research facilities for Canadian and international users and also produces radioisotopes which are used by medical facilities and by a commercial organization (MDS Nordion) MDS Nordion staff also work at the TRIUMF site however MDS Nordion oversees this work and has its own radiation protection program

Figures 269ndash272 present dose information for the TRIUMF facility from 2001 to 2007 Please note that data sets do not distinguish between doses received by TRIUMF staff and MDS Nordion staff who work on the site as the data for these two groups was submitted collectively to the NDR for the reporting period shown Future data for each group will be submitted separately to the NDR

Note on data for TRIUMF

1 Effective doses are composed of the following reported components bull doses from photons (labeled as ldquoexternalrdquo in the charts) bull neutron doses

Figure 269 Average Dose Trends for TRIUMF (Non-Zero Results Only)

000

020

040

060

080

100

120

140

160

Dos

e (m

Sv)

Neutrons External Effective

Year

65

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 70: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

253 Tri-University Meson Facility

The Tri-University Meson facility (TRIUMF) is situated in Vancouver on the campus of the University of British Columbia TRIUMF which began operating in the early 1970s with one cyclotron now has two cyclotrons and associated laboratories for research and radioisotope production The laboratory provides research facilities for Canadian and international users and also produces radioisotopes which are used by medical facilities and by a commercial organization (MDS Nordion) MDS Nordion staff also work at the TRIUMF site however MDS Nordion oversees this work and has its own radiation protection program

Figures 269ndash272 present dose information for the TRIUMF facility from 2001 to 2007 Please note that data sets do not distinguish between doses received by TRIUMF staff and MDS Nordion staff who work on the site as the data for these two groups was submitted collectively to the NDR for the reporting period shown Future data for each group will be submitted separately to the NDR

Note on data for TRIUMF

1 Effective doses are composed of the following reported components bull doses from photons (labeled as ldquoexternalrdquo in the charts) bull neutron doses

Figure 269 Average Dose Trends for TRIUMF (Non-Zero Results Only)

000

020

040

060

080

100

120

140

160

Dos

e (m

Sv)

Neutrons External Effective

Year

65

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 71: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 270 Average Dose Trends for TRIUMF (All Monitoring Results)

000

020

040

060

080

100

120

140

Dos

e (m

Sv)

Neutrons External Effective

Year

Figure 271 Collective Dose Trends for TRIUMF

0

200

400

600

800

1000

1200

1400

Col

lect

ive

Dos

e (p

erso

n-m

Sv)

Neutrons External Effective

Year

66

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 72: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

000-0

009

001-5

0

501-1

000

1001

-1500

1501

-2000

2001

-3000

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 272 Distribution of Effective Doses Among All Workers at TRIUMF

0

1 0 0

2 0 0

3 0 0

4 0 0

5 0 0

6 0 0

7 0 0

8 0 0

9 0 0

N um

ber o

f W or

k ers

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

67

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 73: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

26 Tritium Light Source Production Facilities This section presents dose information for two tritium light source production facilities

bull Shield Source Incorporated (Section 261) bull SRB Technologies (Canada) Inc (Section 262)

Graphs indicate the following data for each facility

1 average doses based on non-zero (positive) results 2 average doses based on all monitoring results 3 collective doses 4 distribution of average effective doses

Notes on data for tritium light source production facilities

1 Total effective doses are equivalent to doses from tritium which is the sole radiological hazard at these facilities

261 Shield Source Incorporated

Shield Source Incorporated operates a facility in Peterborough Ontario where it uses tritium gas to manufacture self-luminescent light sources These are distributed throughout Canada the United States and the rest of the world Operations began in 1986

Figures 273ndash276 present dose information for Shield Source Incorporated from 2001 to 2007

68

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 74: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Effe

ctiv

e D

ose

(mS

v)

Effe

ctiv

e D

ose

(mS

v)

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 273 Average Dose Trends for Shield Source Incorporated (Based on Non-Zero Results)

0

01

02

03

04

05

06

Year

Figure 274 Average Dose Trends for Shield Source Incorporated (Based on All Monitoring Results)

0

01

02

03

04

05

06

Year

69

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 75: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

2001

2002

2003

2004

2005

2006

2007

000-0

009

001-5

0

gt 501

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 275 Collective Dose Trends for Shield Source Incorporated

0

1

2

3

4

5

6

7

8C

olle

ctiv

e E

ffect

ive

Dos

e (p

erso

n-m

Sv)

Year

Figure 276 Distribution of Effective Doses Among All Workers at Shield Source Incorporated

0

5

10

15

20

25

Num

ber o

f Wor

kers

2001 2002 2003 2004 2005 2006 2007

Dose (mSv)

70

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 76: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

262 SRB Technologies (Canada) Inc

During the reporting period SRB Technologies (Canada) Inc operated a facility in Pembroke Ontario using tritium in sealed tubes to manufacture self-luminescent light sources SRB Technologies did not process tritium for the majority of 2007 In mid-2008 SRB Technologies resumed processing tritium at its facility

Figures 277ndash280 present dose information for SRB Technologies (Canada) Inc from 2001 to 2007

Figure 277 Average Dose Trends for SRB Technologies (Canada) Inc (Based on Non-Zero Results)

0

02

04

06

08

1

12

Effe

ctiv

e D

ose

(mS

v)

Year

71

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 77: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

2001

2002

2003

2004

2005

2006

2007

2001

2002

2003

2004

2005

2006

2007

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 278 Average Dose Trends for SRB Technologies (Canada) Inc (Based on All Monitoring Results)

0

0 1

0 2

0 3

0 4

0 5

0 6

0 7

0 8

E ffe

c ti v

e D

os e

( m S

v )

Y ear

Figure 279 Collective Dose Trends for SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

Col

lect

ive

Effe

ctiv

e D

ose

(per

son-

mS

v)

Year

72

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 78: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

00

0-000

9

001-5

0

501-1

000

gt 100

1

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Figure 280 Distribution of Effective Doses Among All Workers at SRB Technologies (Canada) Inc

0

5

10

15

20

25

30

35

Num

ber o

f W or

k er s

2 0 0 1 2 0 0 2 2 0 0 3 2 0 0 4 2 0 0 5 2 0 0 6 2 0 0 7

Dose (mSv)

73

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 79: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Glossary all monitoring average dose average dose determined using the entire data set of dose readings As the zero readings are included in the data set the all monitoring average dose values will be less than or equal to the non-zero (positive) average dose values for the same facility For example if a data set of five effective doses was 0 0 13 16 and 22 (all measured in mSv) then the all monitoring average dose would be (0+0+13+16+22)5 = 10 mSv and the non-zero average dose would be (13+16+22)3 = 17 mSv

collective dose A total radiation dose incurred by a population

cyclotron a particle accelerator that causes a beam of charged particles to travel in a roughly circular path The particles are accelerated using a high frequency alternating voltage

dose limit a limit on radiation dose specified in the Radiation Protection Regulations

effective dose a measure of dose designed to reflect the amount of radiation detriment likely to result from the dose Measured in Sieverts (Sv) it is obtained by multiplying the equivalent dose to each tissue or organ by an appropriate tissue weighting factor and summing the products

licensee a person who is licensed to carry on an activity described in any of paragraphs 26(a) to (f) of the Nuclear Safety and Control Act

long-lived radioactive dust dust composed of Uranium-238 and its long-lived progeny such as U-234 Th-230 and Ra-226

milliSievert (mSv) one one-thousandth of a Sievert

National Dose Registry (NDR) Canadarsquos central repository for occupational radiation doses Managed by Health Canada it publishes annual reports on occupational dose information and trends according to job type

net radiological detriment The total harm that would eventually be experienced by an exposed person or group and their descendants as a result of their exposure to radiation

non-zero (positive) average dose average dose determined using the subset of data containing only the non-zero (positive) values The zero dose readings which include both zero and below measurable threshold readings are not included in this subset

nuclear energy worker a person who is required in the course of the personrsquos business or occupation in connection with a nuclear substance or nuclear facility to perform duties in such circumstances that there is a reasonable probability that the person may receive a dose of radiation that is greater than the prescribed limit for the general public

radiation energy in the form of waves or particles propagating through space

radon progeny the following radioactive decay products of radon 222 bismuth 214 lead 214

74

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 80: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

polonium 214 and polonium 218

Sievert the SI unit of dose which corresponds to the rem (1 Sv = 100 rem) It is the product of absorbed dose in units of Grays and the radiation weighting factor

tritium a radioactive form of hydrogen having an atomic mass number of three Tritium is produced during the normal operation of CANDU reactors

uranium ore concentrate U3O8 (also known as yellowcake) the product of an intermediate step in the processing of uranium ore

working level month the exposure that results from the inhalation of air containing one working level for 170 hours

working level means the concentration of radon progeny in 1 m3 of air that has a potential alpha energy of 208 x 10-5 Joules

75

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76

Page 81: Occucaptional Dose Data for Major Canadian Nuclear Facilities › pubs_catalogue › uploads › INFO_0775_e.p… · as “occupational dose”. This report provides an overview of

Occupational Dose Data for Major Canadian Nuclear Facilities 2001-2007

Bibliography Nuclear Safety and Control Act SOR2000-202

Protection Against Radon at Home and at Work ICRP Publication 65 International Commission on Radiation Protection (1994)

Radiation People and the Environment IAEAPIA75 04-00391 International Atomic Energy Agency (2004)

Radiation Protection Regulations SOR2000-203

76