Text

Semiannual Environ Rept,Jul-Dec 1978.
	ML19290B887
Person / Time
Site:	Brunswick
Issue date:	12/31/1978
From:	; CAROLINA POWER & LIGHT CO.
To:	;
Shared Package
ML17174B224	List: ML17174B223; ML19290B882; ML19290B883; ML19290B884; ML19290B885; ML19290B886; ML19290B887; ML19290B888; ML19290B889; ML19290B890; ML19290B891;
References
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ATTACHMENT 1

.9 Y, EFFLUENT, WASTE DISPOSAL, AND POTENTIAL DOSES SEMIANNUAL REPORT r

July - December 1978 Brunswick Steam Electric Plant 0

0 o

I

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157.8 107 i.

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5 l

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. .- . . . 1978 Suppio.. utal Inform.ition Facility "rm . ick .Ste.v. Cl.:ctric Plant 1.icence Carn!!na Po cr I. Li::ht Cc.

1. Regulatory Limitr. *

a. Fission & activation cases E i B [0.72 Q, + 290 Qy ] 11 quarterly average E 5 Y [22 Q + 200 Qy ) 1 1 quarterly average 3,E 5 8 [1.4 Q, + 580 Qy ] 1 1 12 month average sI E Y [45 Q, + 400 Q ] 11 12 mor.th average

b. Iodine-131 via gaseous releases .

. . >+

4 Curies per quarter ,

8 Curies per 12 months 'jf;

c. Particulates, half-lives >8 days 5 7

[4,7 x 10 ]Q, + [7.2 x 10 ]Q 11 quarterly average 5 8 -

[9.3 x 10 ]Q, + [1.5 x 10 ]( 11 12 month average

d. Liquideff5uents 20 Curies per quarter 40 Curies per 12 months

2. }!axinus Permissibic Concentrations

a. ~ Fission & act'ivation Cases IQ, [4.0 Ey + 0.23 ES] + Q [35Ey + 92 E8] 1 1

b. Iodines and Particulates with half-lives greater than eight days.

6

[3.7 x IQ ] Q, +. [5.8 x 10 ) ,y

c. Liquid' Effluents ,

Values specified in 10CFR Part 20, Appendix D Tabic II, Column 2 for unrestricted area. -

3. Average Encrpy Stack Yy . f.34E-g itcy; E3 4.oiE-ggrey ,

Avera',e Eni'r;v Crounst ' ,

Yy = 5.fo0E-l : ley; 23 = I.4 6(-l }[ey ,

1 15_/8 108 c:

,,,4. }!casurements and Apprur.imations of Total Radioactivity

a. Fission and activation r,ancs Analysis for crecific radionuclides in representative grab sampic.s by gar.=a pectroscopy.

b. Iodines

Analysis for specific radionuclides collected on charcoal cartridges by gamma spectroscopy.

c. Particulates .

Analysis for specific radionuclides collected on filter papers by Samma spectroscopy.

d. Liquid effluents Analysis for spccific radionuclides by individual releases by gacma spectroscopy. . -

Relative variance for each measurement used in calculating activity values were combined using the additive proper,ty of variance. The square roet of the conbined deviation of thevariance multistep was extracted to obtain an estimate of the stand.nd process.

The standard deviation was used to evaluate the error in,the calculated activities at the 95% confidence les.el.

5. Batch Releases

a. Liquid

1.

Number of batch releases: 30S

2. Total time period for batch releases:4.3'I6+'Isminutes

3. Itaximum time period for a batch release:3.SJE+3 minutes -

4. Average time period for batch releases:193E4 a minutes

5. l!1nimum time period for a batch release:0 5 minutes 6.

Average stream flow during periods of release of effluent into a flowing stream: not applicabic .

b. Cascous

. 1. Number of batch relcases: none

2. Total time period for a batch release: not applicable - .

3. !!aximum time period for a batch release: not applicabic

4. , Averge time period for a batch release: not applicable

5. !!1nimum tiue period for a batch re'1 case: not applicabic -

6. Abnormal Eclesse '

'l

s. Liquid -

l 1.

Number of releases: None

2. Total setivity released: Nonc

b. Caseous , ,

1. Number of releases: None 2._ Total activity released: None ;

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__ __ _ _ _ _ __ __ ._-_ - -- . _ . - - .- ,..mm TABL).lA EFFLUENT AND WASTE DISPOSAL SDiIANNUAL RTEORT YEAR 1978 CASEOUS EFFLUENTS-SLW.ATION OF ALL RELEASES Est.

Unit rotal "

Quarter III Quarter r/ ErrorJ A. Fission & activation gases (o.745*0

1. Total release Ci 2.42 E 4 3.02 E 4 '

2. Average release rate for period uCi/ see 2. 9 8 E+3 3. 75 E+3

3. Percent of Technical Specification Ifmit % 1.16 7 ' 1.15 E+1 -

B. Todines

1. Total iodine-131 Ci 9. 3C E-2 4.07 E-2 8.0E*0

2. Average release rate for period uCi/cee 1.15 E-2 5.07 E-3

3. Percent of Technical Soecification limit % 2.33 E+0 1.02 E+0 r

c. Particulates !

1. Particulates tiith half-lives of 8 days ci 4.36 E-2 3.19E-2 8. 0E +0

2. Average release rate for period uCi/ see 5.38 E-3 3.97E-3

, 3. Percent of Technical S eeffication limit % 2.67 E+1 1.97E+1

4. Cross alpha radioactivity ci 1.10 E-6 6.49 E-7 D. Tritium 4 23 E+ g

1. Total release Ci 3.46 E+0 2.94 E+0.__

2. Average release rate for period uCi/ sec 4.30 E-1 3.66 E-1

3. Percent of Technical Soecification Ifmit % 1.01 E-2 9.22 E . l

Based on 10 CFR 20 App. B limit of 4E-05u::i/ml for H3 submersion in an unrestricted area.

?00RORMM.

is78 Ili i

TABLE IB EFFLUENT AND WASTE DISPOSAL SEMIANNUAL RF. PORT YEAR 1978 CASEOUS EFII.UENIS-ELEVATED RELEASE Continuous Mode Batch Mode i

Fuelides Released Unit Ouarter III Quarter IV Ouarter Quarter

31. Fission gases krvnton-85 Ci 4MDA 4 MDA l 1

krypton-85m C1 1.13 E+3 1.70 E+3 krypton-87 C1 2. 27 E+3 3.03 E+3 krypton-88 Ci 2.07 E+3 3.06 E+3 xenon-133 Ci 6.12 E+3 7. 21 E+3 xenon-135 C1 4.84 E+3 7.37 E+3

~

xenon-133m Ci 1. 51 E+3 8.39 E+2 xenon-138 Ci 2.44 E+3 1.62 E+3 argon-41 Ci 1.07 E+2 1 25 E+2 xenon-133m C1 1. 68 E+2 2.23 E+2 Ci l unidentified Ci 1.40 E+3 1.71 E+3 ,

Total for Period Ci 2.20 E+4 2.69 E+4 l

2. Iodines iodine-131 Ci 8.41 E-2 3.91 E-2 l iodine-132 Ci 1.58 E-2 1.56 E-2 c 5.34 E-2 3.90 E-2 iodine-133 Ci iodine-135 Ci 4.25 E-2 3.07 E-2 i Total for Period C1 1.96 E-1 1.24 E-1

. 3. Particult.tes strontiu=-89 '

Ci 7.84 E-4 1.24 E A strontium-90 Ci 6. 21 E-6 3. 29 E-5

^

c esiim-134 Ci 6.64 E-5 1.78 E-5 cesium-137 C1 1.44 E-4 1.47 E-4 barium-lanthsnu=-140 Ci . 23 E-3 1.35 E-2 .

cobalt-58 Ci ' 62 E-4

. 7.78 E-6 cobalt-60 Ci '

2.03 E-4 4.07 E-5 chremium-51 Ci 9.29 E-3 1.50 E-4 zirconium-niobium-95 Ci < MDA d!DA zine-65 Ci 1.68 E-5 < MDA Ci iron-59 Ci 5.31 E-5 3.70 E-5 maneanese-54 Ci .

3.34 E-4 8.41 E-5 iodine-131 Ci 1.16 E-4 3.35 E-4 cerium-139 Ci 8.62 E-5 2.90 E-3 cerium-144 C1 < MDA < MDA

t yttrium-88 Ci 1. 01 E -6 2.09 E-4 rhodium-106 Ci 1.70 E-5 4 MDA strontium-91 Ci 1.07 E-4 < MDA f

Ci subtotal 1.74 E-2 unidentified C1 1. 01 E -3 1.40E-3 l Total for Period C1 1.36 E-2 1.88E-1 l 15.78 112

- TABLE IC YEAR 1978 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT .

CASEQUS EFFLUENTS-CROUND LEVEL RELEASES

, DDROREg Continuous Mode Batch Mode Quarter III Quarter IV Quarter Quarter Huelides Released Unit

1. Fission eases 4MDA krypten-85 Ci 4 MDA Ci 4 MDA 4 @A krypton-85m 4MDA krypton-87 Ci 4 MDA Ci (MDA < MDA krypton-88 2.90 E+3 xenon-133 Ci 1. 88 E+3 Ci 1.40 E+2 1.13 E+2 xenon-135 4 MDA Ci 4 MDA xenon-135m 4 MDA Ci 4MDA xenon-138 4.MDA argon-41 Ci < MDA Ci 3. 68 E+1 3.69 E+1 xenon-133m l Ci I Ci 1.40 E+2 2.07 E+2 unidentified 2.20 E+3 3.26 E+3 Total for Period C1

2. Iodines '

7.68 E-3 1.11 E-3 y __

Ci iodine-131 < MDA C1 4.MDA iodine-132 4.88 E-4 iodine-133 C1 6.36 E-4 8 Ci e MDA 4 MDA iodine-135 1. 60 E-3 Total for Period Ci 8.32 E-3

3. Parciculates 1.98 E-5 6.24 E-5

- strontium-69 J Ci Ci 7.53 E-6 1. 3 8 E - 5 strontfun-90 2.07 E-3 1.63 E-4 Ci cesium-134 2.98 E-3 3.01 E-4.

cesium-137 Ci Ci 1.55 E-6 4 MDA barium-lanthanum-140 4.16 E-4 l Ci 5.62 E' 4

- I cobalt-58 2.07 E-3 1.05 E-3 l C1 cobalt-60 1. 56 E-2 7.46 E-3 J chromium-51 C1 Ci -c MDA 9.25 E-6 zirconiu=-niobiu=-95 3.08 E-4 1.06 E-4 C1 zine-65 4.63 E-4 2.~a8 E-4 Ci iron-59 1. 80 E-3 1.36 E-3 mancanese-54 Ci C1 1.12 E-3 1.81 E-4 iodine-131 <.MDA 2.7I E-5 cerium-139 Ci Ci 2.42 E-4 < MDA eerium-144 ; eMDA 8.19 E-4 yttrium-88 Ci 4 MDA I Ci < MDA cesium-136 < MDA I Ci < MDA tin-117m 5.47 E-6 Ci < MDA anti->nv-124 4 MDA cohalt-57 Ci 1.97 E-6 Ci 5.20 E-4 2.34 E-6 h cadmium-109 9.68E-4 unidentified C1 2. 22 E-3 3.00 E-2 1.31E-2 Total for Period l Ci 1578 113

TABLE 2A EFFLUENT AND WASTE DISPOSAL SEAIANNUAL REPORT YEAR 1o79 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Unit Quarter Quarter Est. Total 1 & 11 III IV Error, %

A. Fission activation products

. *1. Total release (not including tritium, gases, alpha) Ci 9.72 E-1 1.16E+0 9.10 E+0

2. Average diluted concentration during period uCi/ml 1.98 E-8 1.86E-8 l

3. Percent of applicable limit % 3. 89 E+1 4.64E+1 B. Tritium

1. Total release Ci 2.79 E+0 3.54 E+0 1. 23 E+01

2. Average diluted concentration during period uCi/mi s 67 v.9 s gn v g e 3. Percent of apolicable limit % 1.89 E-3 1. 89 E-3 C. Dissolved and entrained gases

1. Total release Ci 3.79 E-2 1.17 E-2 9.10 E+0

. 2. Average diluted concentration during period uCi/ml 7.70 E-10 1.88 E-10

3. Percent of applicable limit % 2.57 E-4 6.27 E-3

) .

% Gross aloha radioactivity Total release Ci 1.73 E-5 6.45 E-5 1.12 E+01 k .

?

E. Volume of vaste released (prior to c dilution ) liters 6. 66 E+6 8. 01 E+6 5.66 E40 9

i -

J

, F. Volume of dilution water used durine period liters 4.9 2 E+10! 6. 23 E+10 1.10 E+1

[

Includ s Estimated Total Error -

- 1576 114

rr

. .' .. TABLE 2B -

EFFLUENT AND WASTE DISPOSAL SDtIANNUA1 REPORT YEAR 1978 ,

LIQUID EFFLUENTS k Batch Mode Continuous Mode ;

t Nuclides Released Unit Quarter TTT Quarter Tv Ouarter Quarter _ [

iodine-134 Ci 4MDA 5.45 E-5 8 iodine-133 . C1 1. 77 E-3 2.90 E-6 iodine-132 Ci < MDA < MDA ' '

ant L.ony-12 2 C1 1.45 E-3 1.05 E-3 IJ antimony-124 Ci 8.62 E-5 2.89 E-4 -

c cobalt-57 Ci <MDA 4MDA -

.y cesium-136 Ci 4MDA 4MDA

. cesium-138 Ci <MDA 4 MDA cerium-144 Ci sMDA 4MDA :

yttrium-91m C1 2.27 E-5 2.22 E-3 j[

tellurium-129m Ci < MDA 4MDA strontium-85 Ci < MDA < MDA niobium-97m C1 4MDA <MDA i -

zirconium-97 C1 4MDA < MDA 1 tin-113 Ci <MDA 4MDA !

tin-117m Ci < MDA eMDA i indium-113m C1 < MDA I 4MDA

{

__ barium-139 Ci 9.15 E-5 4MDA 1 cerium-139 Ci 1.95 E-5 4MDA '

strontium-91 Ci 9. 23 E-5 7.83 E-4 l .;

technitium-101 C1 4 MDA 4 MDA Ii te11urium-132 Ci < MDA < MDA T tungsten-187 Ci < MDA i

<. MDA (

continued on Table 2B-1 < MDA <MDA a i

f bissolvedand'EntrainedBases t

_ krypton-85 Ci RMDA <MDA

_ krypton-85m Ci 4MDA < MDA

_ arRon-41 C1 2.80 E-3 3.55 E-3

_ xenon-131m C1 3. 58 E-3 4MDA

- xenon-133 C1 2.04 E-2 3.75 E-3' I xenon-135 Ci 7.83 E-3 4.37 E-3 yeqoq- 133 n l Ci 3.28 E-3 4MDA b

__ Total forEiod Ci 3.79 E-2 1.17 E-2 ?{

11 3 k

. 1578 ,

- ' ** TABLE 2B-1 I

EFFLUE!Tr AND WASTE DISPOSAL SDiIANliUAL REPORT YEAR 1978

' LIQUID EFFLUDITS Batch Mode continuous Mode Nuclides Released Unit Ouarter III QuarterIV Ouarter Quarter strontium-89 Ci 9.38 E-4 1.34 E-3 strontium-90 Ci 5.20 E-5 2. 92 E-4 '

cesius-134 Ci 1.96 E-2 1.16 E-2 cesium-137 Ci 3.87 E-2 1.99 E-2 l iodine-131 C1 1.90 E-2 1. 73 E-3 cobalt-58 I Ci I3.89 E-2 4.91 E-2 cobalt-60 Ci 8.52 E-2 1.70 E-1 1ron-59 Ci 4.12 E-2 6.40 E-2 zine-65 Ci 1.20 E-2 2.07 E-2 e.antanese-54 Ci 1.30 E-1 2.46 E-1 chromium-51 C1 3.37 E-1 4.38 E-1 zirconium-niobium-95 i Ci : 1.16 E-3 7.11 E-4 I colyMenum-99 C1 2.60 E-4 5. 74 E-5 l technetium-90m C1 4.81 E-3 5.45 E-4 barium-lant.hanum-140 Ci MDA MDA cerium-141 ,

Ci MDA MDA fluorine-18 Ci 6.06 E-3 6.71 E-3 11 sodium-24 C1 1.30 E-1 1.21 E-2 cantanese-56 Ci 6. 78 E-4 3.76 E-5 cooper-64 Ci 1.25 E-2 8.68 E-3 arsenic-7,6 Ci 9.67 E-3 2.58 E-4 niobium-97 Ci 1.81 E-5 3.56 E-3 stroncium-85 Ci MDA MDA nentunium-239 Ci MDA MDA strontium-92 C1 3.49 E-5 1.93 E-3 silver-110m Ci 1.20 E-5 1.79 E-3 nickel-65 Ci MDA MDA unidentified Ci 8.10 E-2 9.65E-2 Total for period (above) Ci 9.72 E-1 1.16E+0

1 MINIMUM DETECTABLE ACTIVITIES (uCi/ni)

.i

1. For Liquid Releases 2. For Gaseous Releases I-134 2.11E-8 Kr-85 4.91E-5 I-132 9.74E-9 Kr-85m 1.77E-8 Co-57 6.29E-9 Kr-87 5.16E-8 Cs-137 1.09E-8 Kr-88 3.96E-8 Ce-144 5.24E-8 Xe-135m 1.67E-7 -

Te-129m 3.65E-7 Ar-41 1.03E-7 {

Sr-85 - 2.37E-7 :

Nb-97m '

2.35E-8 Zr-97 2.24E-8 l Sn-113 1.83E-8 Sn-117m 7.22E-9 3. For Particulates und Iodines In-113m 2.81E-8 Ba-139 6.38E-8 Ba-140,La-140 6.16E-14

Ce-139 6.35E-9 Nb-95, Z- -95 1.76E-14 Tc-101 1.69E-8 Ce-139 ' 7.63E-15 -

Te-132 1.72E-8 Ce-144 6.80E-14 W-137 5.92E-8 Y-88 9.32E-15 Ba-140,La-140 5.92E-8 Cs-136 1.02E-14 ,

Ce-141 3.26E-8 Sn-117m 6.61E-15 ;

Np-239 1.46E-7 Sb-124 2.54E-14 Kr-85 5.89E-5 Co-57 9.35E-15 {'

Kr-85m 2.12E-8 Cd-109 7.50E-13 , j Ie-131m 9.49E-7 Ag-110m 1.08E-14 3 Ie-133m 1.78E-7 Zn-65 2.13E-14 0 Cs-138 Ni-65 2.05E-8 3.16E-8 Rh-106 6.50E-14 [

Sr-91 1.77E-14 !.

I-132 1.16E-14 '

I-135 2.82E-14 f I

t t

1

[

. I l

.y i

1578 117 .

. EFFLUENT AND WASTE DISPOS /.L SEMIANNUAf. UEPOP.T (Yl:.ilt) 5 SOLID WASTE AND IlmADIATED FUCL SilIPMENTS ,j A. ' Solid Waste Shipped Offsite for Eurial or Disposal (Not irradiotel fuel)

Unit 6-month Fut. T.Lal

1. Type of k*aste perio.1 l Error, '

a. Spent resins, filter sludges, evaporated m 7.51E02j ~~ ;

botto.s, etc. . Ci 8.24E02 ' l.50E01

b. Dry conpressible waste, contaminated m3 4.74E02 ,:

Ci 2.23E01 2.00E01 j, couin., etc. ~~

l h

c. Irradiated components, control mJ 3.90E-0j~1.50E01 rods, etc. C1 1.20E0li l

[

m3 0.00E00

d. Other (describe) Ci 0.00E00 0.00E00

2. Esti= ate of major nuclide composition (by type of waste)

A + B Cr-51 % 6.23E01 Mn-54 % 1.58E01 ,

Co-60 % 1.08E01 ___

Fe-59 % 4.07E00 ,

o Co-58 % 3.85E00 3 Zn-65 % 1.41E00 ,_j ~

Cs-134 % 6.79E-01 l

,_Cs-137 f-~ 4.80E-01 l I-131 % 2.51E-01 ; ,

r 1.79E-01 : ,

Nb-95 %

Zr-95 % 6.96E-02 ! t<

Sb-124 % 4.48E-02 ~~l l Sr-92 % 2.34E-Oi'-~~l 1 C Zr-95 - % 3.04E01 I i

Nb-95 % 3.04E01 --

I Co-60 g 1.78E01 Zn-65 % 8.53E00 7.84E00 t Mn-54 %

In-ll?n % 3.03E00 Co-58 % 2.08E00 :

D None % 0.00E00 , [

3. Solid Waste Disposition ,

v Number of Shipments Mode of Transoortation Destinacion .

n 168 Sole Use Vehicle Chem-Nuclear Systems, Inc.

Barnwell, SC ,

t 1

B. Irradiated Fuel Shipments (Disposition)

Number of Shipments Mode of Transportation Destination 0 N/A N/A 1578 Ii8 '

SHORELINE SEDIMEllT DOSE AT CANAL, 11 REM /6 MOS.

I' CHILD TEEN ADULT UHOLE BODY 8.13E-07 3.89E-06 6.97E-07 SKIH 9.55E-07 4.57E-06 8.10E-07 LIQUID EFFLUEllT DATA USED IN SHORELIllE DOSE cal.CULATIONS

. DOSE DUE TO EATIllG FISH CAUGHT IN DISC!$PGE CCHAL. M:MM/ 6 11.X -

, CHILD TEEN ADULT

B0llE 2.84E-05 2.39E-05 2.35E-05

LIVER 5.71E-05 6.92E-05 6.85E-05 WHOLE BODY 2.75E-05 2.71E-05 2.81E-05 THYROID 4.41E-06 4.27E-06 4.57E-06 KIDHEY , 1.01E-05 1.30E-05 1.35E-05 LUllG 1.02E-05 1.32E-05 1.14E-05 GI-LLI 5.14E-05 1.44E-04 2.03E-04 LIOUID EFFLUEt4T DATA USED IN FISH DOSE CALULATI0 tis e DOSE DUE TO EATING GREEli LEAFY VEGS. FROM WORST GARDEll,. t1 REM /6 110S CHILD TEEtt ADULT B0tlE 1.42E-03 8.40E-04 9.71E-04 LIVER 1.21E-03 9.52E-04 1.08E-03 WHOLE BODY 4.04E-04 4.66E-04 8.14E-04

^

THYROID 7.79E-02 5.25E-02 6.52E-02 KIDHEY 7.09E-04 5.75E-04 6.48E-04 LUllG 1.24E-04 1.08E-04 1.13E-04 GI-LLI 1.97E-04 3.36E-04 5.19E-04 DOSES CALCULATED FROM GASEOUS EFFLUEt4T DATA DOSE DUE TO EATING PRODUCE FROM UORST GARDEN, MPEM/6 MOS CHILD TEEll ADULT BONE 1.65E-02 7.51E"03 4.78E-03 LIVER 1.43E-02 8.54E-03 5.25E-03 MHOLE BODY 3.95E-03 4.08E-03 4.20E-03 THYROID 7.51E-03 3.83E-03 2.60E-03 KIDHEY 4.76E-03 2.94E-03 1.84E-03 LUNG 1.83E-03 1.20E-03 6.80E-04 GI-LLI ,

1.51E-03 1.97E-03 1.72E-03 DOSES CALCULATED FROM GASEOUS EFFLUENT DATA D

DOSES CALCULATED FOR MAXIMUM EXPOSED INDTVIDUAL 1 19 1578

~P00R ORGINA _

I 131 DOSE DUE TO DRIHKIllG MILK, 11 REM /6 ' HOS IllFANT CHILD TEEN ADULT

<- B0llE 4.29E-03 2.05E-03 8.47E-04 4. 67E -04 LIVER 5.05E-03 2.07E-03 1.19E-03 6.67E-04 WHOLE BODY 2.22E-03 1.17E-03 6.37E-04 3.82E-04 THYROID 1.66E+00 6.83E-01 3.46E-01 2.19E-01 KIDi1EY 5.90E-03 3.39E-03 2.04E-03 1.14E 03 LUNG 0.00E+00 0.00E+00 0.00E+00 0.00EF00 GI-LLI 1.80E-04 1.84E-04 2.34E-04 1. 76E--0 4 TOTAL DOSE DUE TO DRIllKING MILK, MREM /6 110S

~

IltFANT CHILD T t: Ell ADULT E0t1E 5.60E-02 3.45E-02 1. 46E- 02 8.1.7E 03 LIVER 7.67E-02 3.99E-02 2.3SE-02 1.37E-02 UHOLE 80DY 9.58E-03 8.63E-03 9.92E-03 9.85E-03 THYROID 1.67E+00 .6.86E-01 3.47E-01 2.20E-01 KIDt1EY 2.56E-02 1.60E-02 9.87E-03 5.73E-03 LUHG 7.93E-03 4.59E-03 3.03E-03 1.57E 03 GI-LL{ 2.53E-03 1.20E-03 1.38E-03 1.12E-03 LOSES EVALUATED FOR STEVENS' FARM (MK-35)

'I-131 IllHALATIOtt DOSE AT WORST P0lllT 011 SITE BOUNDARY, 11 ret 1/6 INS g- INFRtlT CHILD TEEN ADULY BONE 3.67E-05 4.66E-05 3.43E-05 2.44E-05 LIVER 4.30E-05 4.66E-05 4.75E-05' 3.46E-05 MHOLE BODY 1.90E-05 2.64E-05 2.55E-05 1.98E-05 THYROID 1.44E-02 1.57E-02 1.42E-02 1.15E-02 KIDtlEY 5.01E-05 7.63E-05 8.13E-05 5.93E-05

. LUNG 0.00E+00 0.00E+00 0.00E+00 0.00E+00 GI-LLI 1.02E-06 2.75E-06 6.28E-06 6.08E-06 TOTAL IllHALAT10tl DOSE AT WORST POItiT ON SITE BOUl4DARY, MREM /6 I:03 -

IllF ANT CHILD TEEN ADULT BONE 4.13E-04 7.42E-04 5.93E-04 4.53E-04 LIVER 7.05E-04 1.08E-03 1.18E-03 1.02E-03 WHOLE BODY 3.53E-04 6.46E-04 8.29E-04 8. 86E -04 THYROID 1.51E-02 1.6SE-02 1.51E-02 1.24E-02 KIDt4EY 4.49E-04 7.70E-04 8.59E-04 7.80E-04 LUNG 2.35E-03 3.50E-03 . 4~.36E-03 3.14E-03 GI-LLI 3.13E-04 5.66E-04 7.30E-04 7.37E-04 GASEOUS EFFLUEllT DATA USED IN IMHALATION DOSE CBLCULATI0lis n-'

1573 120

t' DOSE FROM NO3LE GAS RELEASES-SKIH MREM /6 MOS RADIAL DISTANCE, HILES 0.5 1.5 2.5 3.5 4.5

$ 5.47E-01 2.84E-01 1.96E-01 1.4SE-01 1.145 - :e i SSu 3.28E-01 2.99E-01 2.73E-01 2.25E-01 1.84E-?.

SW 3.70E-01 2.80E-01 2.24E-01 1.78E-01 1.45F 9:

HSW 3.10E-01 2.24E-01 1.79E-01 1.44E-01 1.13E-01 W 1.68E-01 1.22E-01 9.55E-02 7.69E-02 6.36E-02 WNW -

1.45E-01 1.01E-01 8.40E-02 6.93E-02 5.74E-0? .

NW 1.83E-01 1.06E-01 8.04E-02 6.64E-02 5. 60?-0'J NHW 1.58E-01' 1.18E-01 1.02E-01 8.65E-02 7.35E 02 H 1.65E-01 1.28E-01 1.06E-01 8.78E-02 7.31E-0?

HHE 2.02E-01 1.83E-01' 1.63E-01 1.36E-01 1.12E-01 NE 3.98E-01 3.63E-01 3.17E-01 2.59E-01 2.12E-01 ENE 2.60E-01 2.28E-01 2.09E-01 1.76E-01 1.47E-01 E 2.58E-01 1.70E-01 1. 4 6 E-0.1 1.23E-01 1.03E-01 ESE 2.00E-01 1.05E-01 7.69E-02 6.05E-02 5. 20E- 02 SE 2.56E-01 1.25E-01 8.65E-02 6.56E-02 5.20E-01

/~' SSE 4.48E-01 2.24E-01 1.54E-01 1.16E-01 9. 20E- 02 RADIAL DISTANCE, MILES 7.5 15.0 25.0 35.0 45.0 S 6.74E-02 3.03E-02 1.6?E-02 1.07E-02 7.?OE-03

. SSW 1.11E-01 5.10E-02 2.75E-02 1.82E 1. 33E- 01 SW 8.92E-02 4.36E-02 2.49E-02 1.70E-02 1.28E-02 I WSW 7.27E-02 3.50E-02 1.95E-02 1.31E-02 9.73E-03 ll W 4.07E-02 2.11E-02 1.26E-02 8.78E-03 6.68E-03 WHW 3.56E-02 1.72E-02 9.61E-03 6.49E-03 4.84E-03 HW 3.70E-02 1.95E-02 1.16E-02 8.05E-03 6.08E-03 HHW 4.79E-02 2.45E-02 1.42E-02 9.67E-03 7.22E-03 H 4.62E-02 2.31E-02 1.33E-02 9.17E-03 6.91E-03 NHE 6.81E-02 3.18E-02 1.73E-02 1.15E-02 8.4?E-U.<

, NE 1.28E-01 5.91E-02 3.18E-02 2.0SE-02 1.51E-02 i EHE 9.21E-02 4.46E-02 2.49E-02 1.67E-02 1. 23E- 0?

6.55E-02 E 3.28E-02 1.87E-02 1.27E-02 9.50E-03 ESE 3.04E-02 1.51E-02 8.77E-03 6.09E-03 4.22E-03 SE 3.10E-02 1.47E-02 8.27E-03 5.64E-03 4.22E-03 SSE 5.39E-02 2.45E-02 1.32E-02 8.67E-03 6.34E-03 e

P00ROR81WAl m8 m e

4 e e

r .

DOSE FROM HOSLE GAS RELEASES-T. 80DY MREM /6 MOS RADIAL DISTANCE, MILES 0.5 1.5 2.5 3.5 4.5

.S 2.08E-01 1.18E-01 8.60E-02 6.60E-02 5.24: 2.

SSW 1.30E-01 1.35E-01 1.28E-01 1.06E-01 8. 74 E - T?

SW 1.63E-01 1.20E-01 1.06E-01 8.51E-02 6.922 21 HSH 1.36E-01 1.04E-01 8.44E-02 6.86E-02 5.64 . J.

N ?.36E-02 . 5.66E-02 4. 52E -02 3.66E-02 3.04c-02 MHW 6.04E-02 4.55E-02 3.92E-02 3.27E-02 2. 72E -01 HH 7.91E-02 4.82E-02 3.76E-02 ?.13E-02 2.66E-02 HHH 6.64E-02 5.35E-02 4.77E-02 4.10E-02 3.50E-02 H 7.01E-02 5.87E-02 5.01E-02 4.1?E-02 3.;rE c HHE 8.58E-02 8.46E-02 7. 74E -02 6.47E-02 5. ..l ~.

HE 1.69E-01 1.68E-01 1.50E-01 1.24E-01 1. A ;: ~:

EHE 1.04E-01 1.03E-01 9.80E-02 8.35E-02 7 01 C - G

/~'

E 9.60E-02 7.24E-02 6.63E-02 5.66E-02 4.?;3-A' ESE 7.39E-02 4.31E-02 3.35E-02 2.69E-02 2. iniE - Y_

SE 9.59E-02 5.12E-02 3.73E-02 2.89E-02 2 . 3.5. i . 1 SSE 1.70E-01 9.24E-02 6.69E-02 5.17E-02 4.1 <E .:2

. RADIAL DISTANCE, HILES

. 7.5 15.0 25.0 35.0 45.0 S 3.08E-02 1.40E-02 7.56E-03 5.00E-03 3.66v.-ai s SSH 5.28E-02 2.44E-02 1.32E-02 8.75E-03 6. 4. J Su 4.28E-02 ~ 2.10E-02 1.20E-02 8.22E-03 6.116 T.

USH 3'.49E-02 1.68E-02 9.42E-03 6.34E-03 4.Tn_ .

W 1.95E-02 1.02E-02 6.06E-03 4.24E-03 . . 2:8i .

NHW 1.70E-02 8.23E-03 4.62E-03 3.13E-03 2. 3:;E -.. i NH 1.77E-02. 9.37E-03 5.58E-03. 3. 88E -03 2. 9 4 2 -?i NHW 2.292-02 1.18E-02 6.82E-03 4.66E-03 3. 49L al N 2.21E-02 1.11E-02 6.43E-03 4.43E-03 3.3 E-03 HHE 3.27E-02 1.53E-02 8.36E-03 5.56E-03 4.09E-01 HE 6.15E-02 2.85E-02 1.53E-02 1.01E-02 7.30E-05 EHE 4.40E-02 2.14E-02 1.20E-02 8.03E-03 5.94E-'03 E 3.08E-02 1.55E-02 8.93E-03 6.09E-03 4.55E-05 ESE 1.39E-02 7.03E-03 4.12E-03 2.88E-03 1. 992 -r:1 SE 1.40E-02 6.76E-03 3.85E-03 -2.64E-03 1' . 9 9 E - 0 .-

-SSE 2.45E-02 1.13E-02 6.12E-03 4.05E-03 2.97E-02 O-P90RORPAAL ms m.

r 2

\

POPULATION INTEG- WHOLE EZ DOSE, MREM /6 1105 i

RAI: : J STRHCE ' ES o 0.5 1.5 2.5 3.5 4.5 S 1.04E-03 4.72E-02 =.99E-02 3.00E+00 u. out e00

.( SSl4 0.00E+00 2.17E ,02 .43E-01 1.00E+00 A.? :: A3 s SH 5.21E-03 8.34E-0? 00E+00 : .stC 04 0.OuE:01 li . WSW y

0.00E+00 7.15E-0? .c5E 04 '.20E 03 ?. RPE -04

' s, eve-04 1.87E 03 ? ';E 04

. . d:00 0 . T ". : 0 unu 9.e,/E-04 3.64E-04 ;0E500 .00EFOO 0. 00E ( NW 6.32E-04 0.00E+00 .?0E+00 1.00E+00 0.00EC.0

NHN 1.33E-03 2.14E-04 00E+00 ~.00E+00 0.00Ei>0 t

' H 1.40E-03 0.00E+00 10E+00 i.00E+00 0. 00E- 00 I HilE . 0.00E+00 1.35E-05 30E+00 1.00EE00 0.00E+00 NE -

0.0cc+00 3.35E-03 00E+00 ).00E+00 0.00E+00

[ EllE 0.00EF00 1. 24E -03 30E+00

.00E+00 0.00E+00 E O. C OE + 00 1.16E-0? 00E+00 3.00E400 0. 00E 4 0 :'

i ESE 0.00E>00 9.05E-04 d ' 30E+00 3.00E+00 0.00E&OO SE 3.45E-03 6.14E -04 30E+00 1.00E+00 0.00EFOO SSE 0.00Es00 3.70E-04 00E+00 !.00E+00 0.00EF~0 RAD:; : 1TRitCE. ':.ES 7.5 15.0 .5. 0 35.0 45.0 r'

S 0.00E+00 0.00E+00 00E+00 1.00E+00 0.00E+oo SSW 0.00E+00 0.00E+00 : 30E+00 1.00E+00 0.00E+00 SW 0.00E+00 0.00E+00 : 20E+00 .00E+00 0.00E>00 USW 6.04E-03 0.00E+00 :20E+00 E.79E-03 1. 0?E- 02 N 9.96E-04 1.23E-02 140E-02 1.12E-02 2.2eE-01 uuW 2.11E-03 1.12E-02 :.10E-03 . 13E-02 3.29E-02 HW 2.70E-03 1.85E-02 .34E-02 . 40E-02 1.6iE 02' It'tW 3.51E-03 1.38E-02 L14E-02 :.24E-02 1. 0 E - >.4 2

'N 2.01E-03 1.08E-01 . 54 E-02 :.63E-02 Ht4E 9.00E-03 7.96E-01 2.10E -41 ttE

. 32E-01 . 61E-02 S.09E-00 1.33E-01 0.00E+00 2.00E+00 . 23E-03 Et4E 3.45E-02 0.00E+00 1.?9E 02 100E+00 2.00E400 0.00E+00 E 0.00E+00 0.00E+00 3.00E+00 I.00E+00 ESE B.00E+00 0.00E+00 0.00Ein0 SE 0.00E+00 0.00E&OO

. DOE +00 ?.00E+00 0.0iE.00 1.00E+00 1.00E+00 0.00EF00 SSE 0.00E+00 0.00E+00 :. 00E+00 :.00E+00 0.00E+00 TOTAL POPULRTION INTEGRATED WHOLE EZ^ DOSE = 1.;:E+00 GRSEQUS EFFLUENT DRTR USED IN THEEE ::3E CALC __; IGHS DOSES CRLCULATED FOR 11RXIMUM EXP :E :NDIVI:.C_2*

L^ -

P00R ORIGIM

" 78 i e

v

O POPULATION INTEGRATED WHOLE BODY DOSE, t1 REM /6 (105 RADIAL DISTANCE, MILES 0.5 1.5 2.5 3.5 4.5

' S 1.04E-03 4.72E-03 5.99E-02 0.00E+00 SSW 0.00E+00 0.001.>00 2.17E-02 2.63E-01 0.00E+00 9. 8 " -i.:

b SW 5.21E-03 8.34E /03 0.00E+00 6.01E 04 0. 0 0E : S.'

' ~ HSW 0.00E+00 7.15E-03 6.i5E-04 ?.20E 03 9. :-#E - 0 4 H *. 09E-04 1.87E 03 7.2]E 04 0.. 4:00 0 . . /. ~. O UHW 9.67E-04 3. 64E- 04 0.00Et00 0.00EF00 0.00E %-

HW 6.32E-04 0.00E+00 0.00E+00 0.00E+00 0.00E+'.e HHW 1.33E-03 2.14E-04 0.00E+00 0.00E+00 0.00EtJO H 1.40E-03 0.00E+00 0.00E+00 0.00E+00 0.00E-00 MHE. 0.00E+00 1.35E-03 0.00E+00 0.00EF00 0.00E+00 HE 0.00E+00 3.35E-03 0.00E+00 0.00E+00 0.00E+00 EHE 0.00EF00 1.24E-03 0.00E+00 0.00E+00 0.00E+00 0.00C+00 E 1.16E-03 0.00E+00 0.00E400 0.00E*03 ESE 0.00E+00 9.0$E-04 0.00E+00 0.00E+00 SE 3.45E-03 6.14 E'-04 0.00E+00 0.00E+00 0.00E+00 0.00E:-00 SSE 0.00E+00 3.70E-04 0.00E+00 0.00E+00 0.00EFC0 RADIAL DISTANCE, MILES 7.5 15.0 25.0 35.0 45.0

("

S 0.00E+00 0.00E+00 0.00E+00 0.00E+00 SSW 0.00E+00 0.00E+00 0.00r.+eo 0.00E+00 0.00E+00 0.00E+00 SW 0.00E+00 0.00E+00 0.00E+00 0.00E+00 USW 6.04E-03 0.00E+00 0.00EiOO 0.00E+00 6.79E-03 1.0?E-02 W 9.96E-04 1.2SE-02 2.40E-02 2.12E-02 UHW 2.11E-03 1.12E-02 2.2eE-02 8.10E-03 1.13E-02 3.29E-92 HW 2.70E-03 1.85E-02 1.34E-02 1.40E-02 3.51E-03 1. 67E -02

'N'1H 1.38E-02 2.44E-02 1.24E-02 1. ?0E -a2 N 2.01E-03 1.0SE-01 6.54E-02 1.63E-02 HNE 9.00E-03 7.96E-01 2.18E -n1 1.92E-01 1.61E-02 S.09E-0' HE 1.33E-01 0.00E+00 0.00E+00 1.23E-03 EME 3.45E-02 0.00E+00 1.79E~02 0.00E+00 0.00E400 0.00E+00 E 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ESE 0.00E+00 0.00E+00 0.AGEtae 0.00E+00 0.00E+00 0.07E.00 SE 0.00E+00 0.00E+00 0.00E+00 0.00E+00 SSE 0.00E+00 0.00E+00 0.00EF00 0.00E+00 0.00E+00 0.00E+00 TOTAL POPULATIGH INTEGRATED WHOLE BODY DOSE = 2.13E+00 GASEOUS EFFLUENT DATA USED IN THESE DOSE CALCULATIONS DOSES CALCULATED FOR MAXIMUM EXPOSED INDIVIDUALS N

P03 DHl8ML .

W

. .s ..

POPULATI0li IllTEGRAIED IllHALATIOll DOSE Mall-REM /6 MOS OR THYROID 11All-REM /6 l10s IllFANT CHILD TEEli ADULT 11 HOLE BODY 6.06E-04 1. 22E- 02 1.05E-02 5.32E-02 THYROID 8.06E-02 1.00E+00 6.16E-01 2.43E*00 GASEOUS EFFLUE!1T DAT A USED IN i:iFsE T C'EE cal.CUI.ATI0lls DOSES C ALCULATED FOR 11 AXIL 1UM E:-:PD :ED IUDIVIDUALS

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ML19290B887

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