Radiation protection Program for the future SINOP Nuclear ... · Chapter 1 General information on...

Radiation protection Program

for the future SINOP Nuclear Power StationA contribution from the experience of ENGIE

nuclear power stations

Ankara, 20/11/2015

Pierre DOUMONT

Group Senior Vice President

Nuclear Safety & Radiation Protection

RADKOR

National

Radiation Protection

CongressAnkara Turkey

CONTENTS

Chapter 1 General information on ENGIE Nuclear Fleet

Chapter 2Management commitment & leadership in

Radiation Protection

Chapter 3

Chapter 4

Chapter 5

Chapter 6

Chapter 7

Chapter 8

People training & qualification in radiation protection

Control of external exposure

Control of radioactive contamination

Control of radioactive materials

Radiation monitoring and equipment

Evaluation & improvement of radiation protection

results

General information on

ENGIE Nuclear Fleet

General information on ENGIE Nuclear Fleet

19/11/2015 4

Doel

Tihange

2015 – Radkor Congress Ankara - P.Doumont - ENGIE

20/11/2015 2015 - French-Turkish Conference on Nuclear Energy - P.Doumont - ENGIE 5

1. Tihange 1 - 962 MW



1

2

3


12

3

4

1. Doel 1 - 433 MW

2. Doel 2 - 433 MW

3. Doel 3 - 1006 MW

4. Doel 4 - 1008 MW

Management commitment &

leadership in Radiation Protection

Radiation protection & Nuclear Safety Culture

—Radiation Protection is a part of the Nuclear Safety

—Commitment of the management for a strong Nuclear Safety culture

—Clear vision of the Radiation Protection strategy

—Radiation Protection = process taking part to the integrated management

system of SINOP (as Health & Safety, Nuclear Safety, etc)

—Radiation Protection :program needs to be compliant with the applicable

regulation

-

Management commitment & leadership in Radiation Protection

19/11/2015 2015 – Radkor Congress Ankara - P.Doumont - ENGIE 8

19/11/2015 9

UL

Ges.Rahm.-bed

EKK –

Aufbauorganisation

Geschäftsanweisun -

gen/ Konzernrichtlinien

Steuerungs -/ Prozessmodell

Prozessablaufstandards

Konzeptionelle Standards

Ausführungsstandards

General nuclear safety

culture principles

Safety culture is the core values and behaviors of the staff and the

organization that ensure that the nuclear safety has the overriding priority



Legal framework of radioprotection

19/11/2015 10

ICRP Recommandation

IAEA Basic Safety Standard

EURATOM Basic Safety Standard

National legislation



Leadership & Responsibilities

—Radiation Protection is the responsibility of the line management

—RP officer has an important role and is recognized as such in the organization

— Impact of any modification on the radiation protection results

Expectations and guidelines from Management

—Clear expectations regarding ALARA policy & practices

—Expectations to be defined for collective dose, individual limit,

hot spots management, rigourous housekeeping, Pre-job briefings,

reduction of contaminated zones, strong monitoring of staff contamination,

reduction of radioactive waste generation, etc

19/11/2015 11



Organisation, Resources and Staffing

—RP technicians needs to be integrated to operating teams;

— Intensive training program on theoretical topics but also strong practical

exercices based on operational experience, human simulator, preparation works

on mock-up devices, specific training for emergency situations on site and in

case of radiological incidents (accidental contamination or irradiation)

Monitoring & Evaluation of the RP Policy and Practices

—Definition of a set of KPI in compliance with WANO recommendations.

—Self assessments of results and practices, international benchmarking

programs.

Improvement of human factors

— Root cause analysis in case of deviations from RP expectations/rules

Decision making process

— Integration of RP in the work processes and the modifications processes


19/11/2015 122015 – Radkor Congress Ankara - P.Doumont - ENGIE

People training & qualification

in radiation protection

Set-up of Radiation Protection Program :

Two main IAEA references :

- Safety Standard Series NS-G-2.7: Radiation Protection & Radioactive

Waste management in the operation of Nuclear Power Plants

- Safety Guide RS-G-1.1 : Occupational Radiation Protection

Based on :

—Optimisation of protection

—Planning

—Training

—Monitoring of individuals and workplace

—Protective clothing & equipment

—Emergency plan

—Health surveillance

— …19/11/2015 14



Overall benefit.

JUSTIFICATION

ALARA

(As Low As

Reasonably

Achievable)

principle.

OPTIMISATION

Dose limits

prescribed by Safety

Authority.

IAEA limit for workers:

20 mSv per 12 gliding

months

IAEA limit for public:

1 mSv per 12 gliding

months

LIMITATION

19/11/2015 16



19/11/2015 17

Simulation school



19/11/2015 18

Simulation school

VALVES AND PIPINGS

MECHANICAL DEVICE FOR

REMOTE OPENING AND

CLOSING OF CHANNEL HEADS

OF STEAM GENERATORS



19/11/2015 19

Simulation school

Learning to dress and undress people

before & after working in radioactive areas


Application of the ALARA principle

Preparation of an activity :

— IDENTIFICATION of the risk of high radiological exposure

— QUANTITATIVE EVALUATION of the identified risk

— ANALYSIS and DETERMINATION of prevention and protection measures

— MONITORING of working conditions

— ADAPTATION of prevention and protection measures

— EVALUATION and RECORDINGS

RE-EVALUATION based on the evolution of the organisation, qualifications,

feedback, results of the registration, individual and collective dosimetry data, etc.



3 types of ALARA jobs :

• ALARA 1: net collective dose between 0.1 and 0.5 man-mSv

Normal surveillance

• ALARA 2: net collective dose between 0.5 and 5 man-mSv

Idem ALARA 1 + Use of Preparation forms

Additional RP inspections

• ALARA 3: net collective dose greater than 5 man-mSv

The job can’t start

Approval of the ALARA committee needed

Use of preparation forms

Dosimetry monitoring on specific ALARA job’s form

HOLD POINT if 75% of the estimated collective dose is reached





Duration of

exposure

Ambient

doserate

MAINTENANCECARE

Individual

doseX = # agentsX

Collective

dose=

Dose limits

ALARA

- primary chemistry

- material choice

- shielding

- training

- communication

- distance

- preparation- choice of contractor/method

- ergonomy

- etc.



SOURCEDose rate &

contamination

TIME

DISTANCE

SHIELDING

&

protective

clothes

MONITORING



Passive dose meter

Personal OSL/TLD/film dose

meter (beta/gamma and

neutron if needed)

Active dose meter

Electronic dose meter with alarm

(beta/gamma)

TLD : thermoluminescent dosimeter.

OSL : Optically Stimulated Luminescence.

Main avantages OSL :

• OSL can be reread multiple times;

• they are also insensible to warmth and humidity.


19/11/2015 26

Controlled area access



19/11/2015 27

Subdivision of controlled areas.

VERY HIGH RADIATION

INTENSITY > 1000 µSv/h

HIGH RADIATION

INTENSITY > 200 µSv/h

IONISING RADIATION

> 20 µSv/h

LOW DOSE RATE

≤ 20 µSv/h


How to reach good RP performances?Distance

19/11/2015 28

SOURCEDose rate &

contamination

TIME

DISTANCE

SHIELDING

&

protective

clothes

MONITORING



19/11/2015 29

Irradiation monitoring



19/11/2015 30

Tele dose rate meter and tele dosimetry.

Use of safe zones while waiting in the controlled area is written in the

ALARA procedure.


Control of radioactive

contamination


19/11/2015 32

Controlled area cleanliness : IMPORTANCE OF HOUSEKEEPING

Level of contamination % of rooms in

Tihange

% of rooms in Doel

< 0.4 Bq/cm2 99 % 99 %

0.4 Bq/cm2 < < 4 Bq/cm2 0.1 % 1 %

> 4 Bq/cm2 0.9 % 0 %

Avoiding contamination of the

workers requires a high level of

monitoring and of housekeeping

in the operating areas.



19/11/2015 33

Application of the ALARA principle

Controlled area access



19/11/2015 34

Controlled area exit

Identification of the origin of the contamination

detected on a people at the exit of the controlled area

Immediate corrective actionBadge reader



19/11/2015 35

Individual contamination monitoring



19/11/2015 36

Contamination monitoring


Control of radioactive

materials


19/11/2015 38

Calibration stands

Specific place

for radioactive sources



19/11/2015 39

Waste Management facilities on site



19/11/2015 40

Control of transport materials



19/11/2015 41

Control of transport materials


Radiation monitoring and

equipment

At nuclear power plants, it is needed to monitor :

— Individual exposure (see chapter 4).

—Contamination of areas (see chapter 5).

—Radioactive releases.

—Radioactive materials (waste, clearance…).

—On-site monitoring :

• Ambiance dose rate,

• control of the pathways,

• control of the building roofs,

• control of groundwater,

• control of rain water…




19/11/2015 44

Contamination monitoring


Radiation monitoring and equipmentSite monitoring

19/11/2015 45

Radiation monitoring chain PIG (Particules, Iodine, Gas releases)

Ambiance dose rate measurement(TLD)

TLD : thermoluminescent dosimeter


Radiation monitoring and equipmentSite monitoring

19/11/2015 46

Contamination control of the pathways


Evaluation & improvement of

radiation protection results

How to reach good RP performances?

19/11/2015 48

SOURCEDose rate &

contamination

TIME

DISTANCE

SHIELDING

&

protective

clothes

MONITORING


How to reach good RP performances?Reduction of source term

19/11/2015 49

TIME

DISTANCE

SHIELDING

&

protective

clothes

MONITORING

SOURCEDose rate &

contamination


Primary chemistry

— Avoiding accumultation of stellites through appropriate choice of material (Co-58 vs Co-60).

— Good operation practices (e.g. Oxygenation of the primary water at the beginning of outage).

— Minimisation of the corrosion speed.

— Minimisation of the deposit of the corrosion products on the fuel elements.

— Preventive or curative Zinc injection

Integrity of the first barrier (fuel cladding)

— Robust fuel assembly design

— Foreign Material Exclusion strategy

Integrity of the second barrier (primary circuit)

Reduction of the filters’ mesh

With, in addition, the fundamental role of housekeeping practices.



Steam generators replacement :

Improve primary chemistry.

Use of materials inducing less doses.



Management of hot spots :

—Avoid the appearance of hot spots.

—Detection of hot spots.

—Signalization.

—Follow-up of hot spots

—Elimination of hot spots.


19/11/2015 52

Hot spot : contact dose rate

> 1000 µSv/h


Management of hot spots :


19/11/2015 53

Areas with red label are locked with key

Hot spotscontact dose rate > 1000 µSv/h


Cleanliness and housekeeping in controlled area



RP performancesReducing Time of exposure

19/11/2015 55

SOURCEDose rate &

contamination

DISTANCE

SHIELDING

&

protective

clothes

MONITORING

TIME


19/11/2015 56

Appropriate training

Pre-job briefings

Internal and external Return of EXperience (REX)

Supporting software program (SARA/ESTER) ALARA calculations

…

RP performancesReducing Time of exposure


How to reach good RP performances?Shielding & protective clothes

19/11/2015 57

SOURCEDose rate &

contamination

TIME

DISTANCE

SHIELDING

& protective

clothes

MONITORING


How to reach good RP performances?Shieldings


How to reach good RP performances?Protective clothes

19/11/2015 60

Protective clothing is required

whenever entering a working area

with a contamination risk

Protective clothing type must match

the type of risk ; eg :

simple overclothing for controlled

area.

breath protective clothing when

there is a risk of radioactivity

inhalation.


1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 2013 2014

EEX 2,843 0,685 2,544 0,988 0,849 2,432 1,099 1,194 1,243 1,213 1,149 0,86 1,103 0,925 0,961 1,059 0,716 0,76 0,618

EBL-CNT 0,514 0,229 0,463 0,211 0,211 0,384 0,323 0,289 0,277 0,258 0,223 0,187 0,236 0,178 0,181 0,208 0,161 0,194 0,198

0

0,5

1

1,5

2

2,5

3

3,5

4

Co

lle

cti

ve

do

se

(H

Sv)

Evaluation of RP results at Electrabel ENGIECollective Radiation Exposure

19/11/2015 61

Steam generator replacement :

CNT1, CNT3, CNT2

Evolution of the collective doses (HSv) : Electrabel Tihange and contractors


Evolution of the collective doses (HSv) : Electrabel Doel and contractors


19/11/2015 62

1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 2013 2014

EEX 4,8 4,179 3,828 5,45 3,385 2,592 2,542 1,343 1,523 1,373 1,129 0,797 1,21 0,998 1,187 1,141 1,129 0,786 1,107 1,213 0,866 1,143 1,334 0,324 0,813

EBL-KCD 1,035 0,915 0,742 0,515 0,566 0,546 0,511 0,417 0,421 0,335 0,3 0,276 0,307 0,27 0,231 0,237 0,279 0,192 0,294 0,286 0,21 0,271 0,278 0,125 0,168

0

1

2

3

4

5

6

7

Do

se c

ollecti

ve (

HS

v) Steam generators

replacement :

•KCD1 : 2009

•KCD2 : 2004

•KCD3 : 1993

•KCD4 : 1997


Evaluation of RP results at Electrabel ENGIEIndividual doses

19/11/2015 63

Evolution of the individual doses (HSv) : Electrabel Tihange and contractors

1996 1997 1998 1999 2000 2001 2002 2003 2004 2005 2006 2007 2008 2009 2010 2011 2012 2013 2014

Average (mSv) 0,945 0,602 0,942 1,151 0,787 0,774 0,735 0,666 0,581 0,581 0,525 0,399 0,409 0,447 0,315 0,339 0,291

0

0,2

0,4

0,6

0,8

1

1,2

1,4

Avera

ge

ind

ivid

uald

ose (

HS

v)


Evolution of the individual doses (mSv) : Electrabel Doel and contractors

Evaluation of RP results at Electrabel ENGIEIndividual doses

19/11/2015 64

1990

1991

1992

1993

1994

1995

1996

1997

1998

1999

2000

2001

2002

2003

2004

2005

2006

2007

2008

2009

2010

2011

2012

2013

2014

EBL-KCD 0,9 0,8 0,6 0,4 0,5 0,4 0,4 0,4 0,4 0,3 0,3 0,3 0,3 0,3 0,3 0,3 0,3 0,2 0,3 0,2 0,2 0,29 0,3 0,14 0,19

EEX 1,7 1,5 1,4 1,5 1,3 1,0 0,8 0,6 0,9 0,7 0,6 0,4 0,7 0,6 0,5 0,6 0,6 0,4 0,5 0,4 0,3 0,51 0,54 0,14 0,35

-

0,20

0,40

0,60

0,80

1,00

1,20

1,40

1,60

1,80

Avera

ge i

nd

ivid

ual d

oses (

mS

v)


Collective Radiation Exposure (average Doel and Tihange)


19/11/2015 65

0,0

0,2

0,4

0,6

0,8

1,0

1,2

1,4

Valu

e -

3y [

H.S

v]

Below WorstQuartile

Between Medianand Worst Quartile

Between Best andMedian Quartile

Above BestQuartile

Doel

Tihange


Top 5 tasks with most dose during outage


19/11/2015 66

0 5 10 15 20

Servitudes

Mechanics

Thermal insulation

Heating

Valves

Services


19/11/2015 67

Thanks foryour attention


Radiation protection Program for the future SINOP Nuclear ... · Chapter 1 General information on...

Documents

Transcript of Radiation protection Program for the future SINOP Nuclear ... · Chapter 1 General information on...