PRELIMINARY SURVEY OF BRIDGEPORT BRASS COMPANY … · PRELIMINARY SURVEY OF BRIDGEPORT BRASS...
Transcript of PRELIMINARY SURVEY OF BRIDGEPORT BRASS COMPANY … · PRELIMINARY SURVEY OF BRIDGEPORT BRASS...
PRELIMINARY SURVEY OF
BRIDGEPORT BRASS COMPANY
SEYMOUR, CONNECTICUT
Work performed by the
Health and Safety Research Division Oak Ridge National Laboratory
Oak Ridge, Tennessee 37830
March 1980
OAK RIDGE NATIONAL LABORATORY operated by
UNION CARBIDE CORPORATION for the
DEPARTMENT OF ENERGY as part of the
Formerly Utilized Sites-- Remedial Action Program
BRIDGEPORT BRASS COMPANY SEYMOUR, CONNECTICUT
At the request of the Department of Energy (then ERDA), a preliminary
survey was performed at the Bridgeport Brass Company in Seymour,
Connecticut (Fig. 1) on January 26, 1977, to assess the radiological
status of those facilities used under Atomic Energy Commission (AEC)
contract during the period 1962 through 1964. Mr. Edwin F. Rich, Plant
Engineer, provided information about the project and identified those
areas utilized in the project. Contract work involved the developmental
process of cold-forming (extrusion) of natural uranium metal, associated
storage, and laboratory support. This operation was moved to the site
from the Company's Havens Laboratory, Bridgeport, Connecticut, in 1962.
Present Use of Facilities
From information contained in ERDA records and that obtained during
the survey, the extrusion operations were conducted in a portion of only
one building (area approximately 30 x 100 ft). An adjacent area of
similar size was used for uranium and general storage, machine shop,
cutting and grinding room, and laboratory hood area (Fig. 2). The area
is now a printing plant with associated offices., warehousing, etc.,
owned by National Distillers and Chemical Corporation. Bridgeport Brass
Company is a subsidiary of this company. It was determined that the
Health and Safety Laboratory (HASL) conducted a radiological survey of
the facility in 1964 when the project terminated (report attached).
Results of Preliminary Survey
The preliminary survey was conducted by H. W. Dickson and M. T. Ryan
of the Oak Ridge National Laboratory and W. T. Thornton of the DOE/Oak
Ridge Operations Office (then ERDA). A survey was conducted in the
former Dynapak Extrusion Area, in an adjacent area used for uranium
storage (see Fig. Z), in a space formerly used for offices, and in an
area above the former office area (see Fig. 3). The survey consisted of
gamna-ray exposure-rate measurements 1 m above the floor surface,
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beta-gamma dose-rate measurements 1 cm above the surface, and direct
alpha radiation measurements made at contact with the surface.
Garmna-ray measurements in the former extrusion area (Fig. 2)
resulted in a maximum reading of 9 uR/hr 1 m above the surface. The
maximum beta-gamma dose rate 1 cm from the surface in that area was 0.6
mrad/hr, and the maximum gamma-ray exposure rate was 50 uR/hr 1 cm from
the surface. The maximum direct alpha radiation measured was 300 dpm/lOO cm2.
In the former storage area just outside the extrusion plant, the following
maximum readings were observed: 6 uR/hr gatmna-ray exposure rate 1 m
above the surface, 0.20 mrad/hr beta-gamma, and 30 pR/hr gamma-ray
exposure rate at 1 cm from the surface. No alpha activity above back-
ground was detected in this area. In the former office area (now print
shop) (Fig. 3), the following maximum readings were observed: 8 uR/hr
gannna-ray exposure rate at 1 m above the surface, 1.75 mrad/hr beta-
gama, and 130 uR/hr gamma-ray exposure rate at 1 cm from the surface.
The corresponding direct alpha radiation measured at this point
in concrete floor) was 180 dpm/lOO cm2. All measurements made
second level of the facility were at background levels.
An effort was made to confirm radiation levels presented i
(crack
on the
na
report of a survey conducted by A. J. Breslin, former HASL, October 21,
1964 (see attached report). Most of the current measurements were found
to be in agreement with those in the 1964 survey and within existing
Nuclear Regulatory Commission guidelines for unrestricted use. However,
in one area, radiation levels were found to approach or exceed these
guidelines. Because of this, some additional measurements should be
taken at this site.
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DYNAF’AK EXTRUSION AREA
‘!- 100’ T 300 dpm 0 in former extrusion areaa
(maximum) I 0.6 mrad/hr B/Y in'former extrusion areab
3d (maximum)
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50-uR/hr y in former extrusion areab (maximum)
9 pR/hr y in former extrusion areaC (maximumk .
!k is!
0.20 mrad/hr B/Y just outside
7 . .(maximum)
z extrusion area B
v,
3@wR/hr y just outside extrusion area (maximum) 1
s ci Y
6 pR/hr y just outside extrusion area (maximum)
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9 2i . 6 ii is
QAlpha activity over a loo-cm2 area. b Dose rate at 1 cm above the surface.
'Exposure rate at 1 m above the survace.
Fig. 2. Location and radiation levels inside the area once used for extrusion operations at the Bridgeport Brass Company site.
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OFFICE AREA (PRINT SHOP)
I 30’
DOWNSTAIRS
180 dpm a in former office areaa (maximum)
1.75 mrad/hr B/Y in former office areab (maximum)
0.13 mR/hr in former office arez maximum)
8 pR/hr in former office arei (maximum)
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STORAGE AREA
UPSTAIRS
All measurements upstairs were at the background level
'Alpha radiation over a lOO-cm2 area.
'Dose rate at 1 cm above the surface.
'Exposure rate at 1 m above the surface.
Fig. 3. Location and radiation levels inside the area used for office operations at the Bridgeport Brass Company site.
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John W. Ruth, Director Feed Materials DLvlston - OR
A. J. Bresiln, Director Health Protection Engineering Division, HAS, NY
CONTAAMXNATION SURW AT F”cTNE ME’IALS, INC., SEYMOUR,
Summary Accompanfed by Mr. A. GreUa of Inactive Met&, on Cktober 21, 1964, 1 vlaited the Seymour faduty, formerly occupied by Reactive Metals, to perform the survey requested in your telegram to Dr. 3arl8y dated Oc&ber 7. We inspected aU tooms that were related to XC contract activities and measured surhtce cxmtamlaation in tha following areas: machine shop, metai storage area, lab hood area, cutting and grIncUng room, and Dynapack &we& Afl rooms were frcs of process and office squ@znent and were cleaa In appearance. Local exhaust ventilation systems had been removed iran the process areas. The only ffxtures and equipment tn evidence wem itghtfng fLxture8, slectrb& gas and cxmpres3ed air sowlces, air conci.ltio.ning SyStems, and 4 few porrab~e fire f2?aingutshers.
In my judgment, the prvcoss areas have been ckaned of uranium contamina- tion satisfactorily and CSXI &a6 released for unrestricted use.
,’ _’ / ;_ sumw
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Following iucili~ decontamination by Reactive Metals, but prior to my visit, Mt. Greila had performed a detailed survey of floor contamlnatioq. EUa measurements were u&e on grid patterns est8bkh8d for each of the prokess
areas. His Sumwf results are shown in Flgwes 1 - 4.
My measurements wwe perfunned at hations seicctod randomly from the same grid patterns, awering about one-third of the locations included in his survey. (It should be noted that the kations were only approxhnately the same.) In addltfon, 1 measured contamination on a few surfaces above
the floor such as window sUls ond shelves. The results ~‘8 shoWn ln NgW8s 5 - 9. Numbers on the floor pkini3 Co~OSpOnd t0 thOS8 on ?iir, Gr8ik'S
diagrams. 7%~ circled numbers indicate locattons at which measurements were obtained.
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An EberUne PAC 1SA alpha surv8y meter and 8 Universal Atmics ,Model 9700 beta-garnna survey motet wera used for contact measurements. Suear SampLlag axWstsd ofrukblng a one inch &meter ftlterpaperuvetan awa of appK?tdmat~Ay IOOcm~.
Ihe bsta-gauma measuremnts are repxted in units of mlUlrad/frour. Any UZ&SlE8mor&t W - .05 -d/hour 1s Oqufvaknt to b!k%gfw.nd.
llZ8Um-i -to me r0ported directly 80 net alpha dislntegrations/1UO uquare cet2tim8tem.
Ihe smear meaauregsen~ were in a rather u cils/la/10(ic?n2.
narrow range of 2n to 90
u cii§~xz&l/100csn2. The single measurement 3n tie lab hood area was 3
Wth the exception of thr0e or four v&x85, the hta-gammu measurements did IMP etxce& backgrorntd, Z&e highest value ivos 0.5 miUrad/hour .
Agreement wit! Mr. GreIIa’s data is good and cestalnly within the limits of expected differences for this kind of survey0 Accorcilng to Mr. Grelta, the fked alpha vaIues llsted on hla survey sheets represent readings from a PAC 12% corrected fora 50 c/m !xwkground~ ‘Ibrefore, a more appropriate heading for his measurementu would be "XlBt counts/min/bOcm2.”
Iam not awareof anyAK stnndards for SutfaC8 axW%&WlOnwithwltich the sUnmy data .nay be compared. lbwmmr, the values are quite km and 4xwmlnly are halgniflc8nt with respect to any mod0 oi exposure that can be hypothesized. .
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k 8 pofnt of ruftmwe, these values are weU Mow the Umlta mentfoned i?l the nibport "Xeaith Protection Pmgmn Rsvirrrw of Speclal L:etalij Dsvekq- mont D0pzutmnt, bactfw rL!lMzJ~s, xno .a Sayuour, Connecteut - June 1'364' by WluaP A. Pryor imd aaynond L. xervfn.
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MACHINE SHOP
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18 20. 0 19 0 21
.
22 23. i4.
25. 26. -27 0 28
r.lr; -
.._ -
:
_Location 3 ’
: 4 8
13 15 1 5A( Top of Shelf) 19 21 21A (Window Siil) 28
,. .:. . .
. Fig. 5
Painted Concrete Floor
Contact Readins a c/m/60cmZ p-y mrad/hr
400 l . .03 400 .04 500 .02 800 .05 600 .05 100
900 -02 6500
,++.J l 5 r,rr
300 )
700 .03
Smear a-d/m/100cm2
20 20
90 . 80
70
.
30
HASL - October 19
._ ---.
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METALSTORAGE AREA
I 0 ? .2: $ ? 0 5A -
0 5 6 (ramp)
7 8
0 0 ‘9 .
8A
I
19 11
I 0 .l8 19 .I * . . .
0 20 21 22
\- 40' >-
Location 1
5
SA (Top ofrolldoor housing) .
8A(Ughtfixture) 100
9 . 700 . .03 80
13
17
18
20
.
Contact Readins Smeai iic/m/60cm2 3-y mrad/hr ad/m/lOOcm'
300 .02 40
'400 .02
300
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Fig. 6
Painted Concrete Floor
N
70
30
.60
400 .lO
400 .05
80
. 80
400 .08
500 .25 70 .
HASL -Oct. 1964
i -
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Fig. 7 CUTTING AND GRINDING ROOM
.
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'1 2 3 4 0
.O 13. .14
-(
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17 18 19 @
21 @ 23 24.
. &cation 4
5 8A (Window Sill) 11
. 13
16A (Window Sill) 20 . 22
.
,
Asphalt Tile Floor
.
.
Contact Reading . . Smear -a c/m/60cm2 0-v mradhr a d/m/100cm2
300 .04
200 .06 800 .05 . 200 .02 200 .04
200 .02 100 .04 300 .Ol
.
HASL - Oct. 196
Platform --1 -1 -y ;: yqij=QFg* .
Dynapack Base
N
0 ;s 9 .ul
4 0 w
Location 3 4 6A (Base) . 8A (Base) 8 B (Trench) 11 12
* l3
.
16A (Top Elect. Box) 17A (Step) 17B (Shelf) 17C (Office Roof)
18
Contact Reading p c/m/60cm2 P-Y mrad/hr a d/m/100cm2
100 .03 100 .Ol 20 u 400 0.4 7 2 200 .os %
300 .07 ii 100 .02 14
100 .03 250
F .O2 ?
. 250 .02 =r c
350 .02 z!a . 400 .03 gg 2
200 .03 2 . 02
200 .03 2 G