ML19290B886
| ML19290B886 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 08/08/1978 |
| From: | CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML17174B224 | List: |
| References | |
| FOIA-79-488 NUDOCS 7912140332 | |
| Download: ML19290B886 (20) | |
Text
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ATTACl&fE!!T 1
'
.
EFFLUEllT, UASTE DISPCSAL, A!!D POTCiTIAL DOSES SCIIA!E;UAL REPORT January - June 1978 , Brunswick Steam Electric Plant ,
.
August 8, 1978 ., i
.
.
.
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.
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.
1573 087
,
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9
.
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. .*. . . .
1978 Supplemental Information Facility Brunsuick Steam Electric Plant License Carolina Power & Light Co.
- 1. Regulatory Limits
- a. Fission 6. activation gases E E 6 [0.72 Q, + 290 Q ] 11 quarterly average E E y [22 Q, + 200 Q v ] 11 quarterly average E 5 8 [1.4 Q, + 580 Q ] 11 12 month average I I y [45 Q, + 400 Q )y 11 12 month average
- b. Iodine-131 via gaseous releases 4 Curies per quarter ,
8 Curies per 12 months
- c. Particulates, half-lives >8 days -
5 7 [4.7 x 10 ]Q, + [7.2 x 10 ]( 11 quarterly average 5 8 [9.3 x 10 ]Q, + [1.5 x 10 ] 1 1 12 month average
- d. Liquid effluents 20 Curies per quarter 40 Curies per 12 months
- 2. Maxinum Permissible Concentrations s
- a. Fission & act'ivation Gases
'
IQ, [4.0 Iy + 0.23 E8] + Q [35Ey + 92 E8] $ 1 b. Iodines and Particulates with half-lives greater than eight days. 6 [3.7 x 10 ] Q, + [5.8 x 10 ) iy
- c. Liquid Effluents
' .
Values specified in 10CFR Part 20, Appendix B, Table II, Column 2 for unrestricted area.
- 3. Average Energy Stack .
Ey = 6.06E-01 !!cV; ES = 4.35E-01 MeV
.\verar,e Ener;.y Cround
- 4 Ey = 1.83E-01 !!eV; E3 = 2.60E-01 licV 1578 088 G5 j 1 c.
"
. .
. .' . ..
1-
- 4. Measurements and Approximations of Total Radioactivity
- a. Fission and activation gases Analysis for specific radionuclides in representative grab samples by ga:ma spectroscopy.
- b. Iodines
_ Analysis for s'pecific radionuclides collected on charcoal cartridges by gamma spectroscopy.
- c. Particulates Analysis for specific radionuclides collected on filter papers by gamma spectroscopy.
.
- d. Liquid effluents Analysis for specific radionuclides by individual releases by gamma spectroscopy.
Relative variance for each measurement used in calculating activity values l were combined using the additive property of variance. The square root of l
.
the combined variance was extracted to obtain an estimate of the standard deviation of the multistep process. The standard deviation was used to evaluate the error in the calculated activities at the 95% confidence level.
- 5. Batch Releases -
- a. Liquid
'
- 1. Number of batch releases: 280
.
- 2. Total time period for batch releases: 3.52E+04 minutes s
- 3. Maximum time period for a batch release: 2025 minutes
,
- 4. Average time period for batch releases:
.
126 minutes
- 5. Minimum time period for a batch release: 6 minutes
- 6. Average stream flow during periods of release of effluent into a flowing stream: not applicable b.
.
Gaseous *
>
- 1. Number of batch releases: none '
- 2. Total time period for a batch release: not applicable -
3. Maximum time period for a batch release: not applicable
- 4. Average time period for a batch release: not applicable l
,
- 5. Minimum tiue period for a batch release: not applicable -l
'
.
-Jj 1578 089 4,
. . __
. .'. . . . -
- 6. Abnormal Release
- a. Liquid
- 1. Number of releases: None
.
- 2. Total activity released: None
- b. Caseous
- 1. Number of releases: None
- 2. Total activity released: None
-
e G G e B 1578 090
.
O S g e e
%
3
' '
, . .. . . .
TABLE 1A EFFLUENT AND WASTE DISPOSAL SDiIANNUAL REPORT YEAR 1978 CASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Est. Unit rotal
- Ouarter I Quarter II Error, A. Fission & activation gases
- 1. Total release C1 1. 63E+04 2.07E+04 6.79E+(
'
- 2. Average release rate for period uCi/ see 1.93E+03 2.55E+03 I
- 3. Perecat of Technical Specification limit % 1.10E+01 1.10E+01
.
B. Iodines .
,
- 1. Total iodine-131 Ci 8.36E-02 7.72E-02 8.00E+(
~
- 2. Average release rate for period uCi/ see 9.87E-03 9.51E-03
- 3. Percent of Technical Suecification limit % 2.09E+00 1.93E+00
- c. Particulates
- 1. Particulates with half-lives of 8 days C1 2.07E-02 1.59E-02 8.~ 00E+f
- 2. Average release rate for ceriod uCi/ see 2.44E-03 1.96E-03
'
- 3. Percent of Technical Seeeffication limit % 1.39E+01 1.23E+01
.
- 4. Cross alpha radioactivity Ci 7.13E-06 7.86E-07
.
I D. . Tritits
- 1. Total release Ci 2.03E+00 1.60E+00 1.23E+
__
- 2. Aversee release rate for period uCi/ see 2.40E-01 1.97E-01
-
;
*3. Percent of Technical Soecification limit % 4.34E-02 3.47E-02
- Based on 10 CFR 20 App. 3 limit of 4E-05uci/mi for H3 submersion in an unrestricted area.
,
'
i578 00 .
.
~_
. .*. . . .
TABLE IB
=
YEAR 1978 EFFLUENT AND k'ASTE DISPOSAL SD!I/.NNUAL REPORT T CASEOUS EFFLUENTS-ELEVATED RELEASE
<
,
Continuous Mode Batch Mode Quarter II Quarter Ouarter N::clides Released
- Unit Quarter I .
- 1. Fission eases '
krypton-85 Ci <MDA <MDA krvoton-85m Ci 6.63E + 02 7.32E + O2 kr nton-S7 l Ci 1.28E + 03 1.35E + 03 kryoton-88 Ci 9.54E + O2 9.70E + O2 xenon-133 C1 2.80E + 03 5.53E + 03 xenon-l'S C1 2.52E + 03 2.73E + 03 xenon-135m Ci 1.06E + 03 1.38E + 03 ' xenon-138 C1 2.33E + 03 3.39E + 03 arcon-41 Ci 2.03E + 02 2.86E + O2 xenon-133m Ci 7. 74 E + 01 1.68E + O2 unidentified Ci 8.07E + 02 1.12E + 03 Total for Period Ci 1.27E + 04 1.77E + 04 2 .- Iodines iodine-131 Ci n ,, t- _ot , g e t- _n,
'
iodine-132 Ci 3.89E -09 3.77E - 02 iodine-133 C1 1.62E._-01 6.51E - 02 iodino-135 ' Ci 1.66E -01 6.90E 02 Total for Period Ci 4.50E -01 2.48E - 01 *
.
- 3. Particulates strontium-89 C1 3. 53E - 04 < dD A strontium-90 Ci 9.69E - 06 < MDA cesium-134 i Ci < MDA i 2.41E - 05 cesium-137 I Ci 6.95E - 05 1.09E - 04 barium-lanthanum-1.40 C1 3.07E - 03 1.22E - 03 cobalt-58 Ci 1 2.61E - 05 3.03E - 05 '
cobalt-60 Ci 6.54E - 05 5.98E - 05 chromium-51 Ci 5.52E - 05 3.56E - 04 i circonitet-nf o bium-95 Ci < MDA < MDA .
'
Eine-65 C1 3.55E - 06 1.53E - 07
.
iron-59 Ci 6.43E - 05 5.21E - 06 l mancanese-54 Ci 1.13E - 04 6.47E - - iodine-131 C1 3. 7 6E - 05 2.35E - 05 + cerium-139 Ci 2.44E - 04 6.77E ~05
- cerium-144 Ci < MDA < MDA Yttrium-88 Ci 4MDA < MDA unidentified C1 3.29E - 04 1.57E - 04 Total for l'oried C1 4.44E - 03 2.12E - 03 1578 092
.
. .
.
~
. .
'
. . .
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TABLE IC GTLUENT AND 'n'ASTE DISPOSAL SDiIANNUAL REPORT TEAg* 1978 GASEOUS EFFLUENTS-CROUND LEVEL RELEASES , 1
* .
Continuous Mode Estch Mode Nuclides Released - Unit Quarter I Quarter II Ouarter Quarter l
- 1. Fission stases krypton-85 Ci <MDA <MDA krypton-85m Ci <MDA <MDA l krypton-87 Ci <MDA <MDA krypton-88 Ci <MDA <MDA xenon-133 Ci 1.02E + 03 1.39E + 03 xenon-135 C1 2.32E + 03 1.36E + 03 xenon-135m Ci <MDA <MDA xenon-138 Ci <MDA <MDA argon-41 Ci <MDA <MDA xenon-133m Ci 4.80E + 01 7.75E + 01 i ;
Ci unidentified C1 2.34E + O2 1.92E + O2 ' Total for Period C1 3.62E + 03 3.02E + 03
- 2. Iodines iodine-131 C1 4.00E - 04 6.01E - 04 iodine-132 C1 3.22E 06 <MDA iodine-133 Ci 6.24E - 03 2.78E - 04 iodine-135 Ci 8.80E - 06 <MDA -
- Total for Period Ci 6.65E - 03 8.79E - 04 l 1
- 3. Particulates strontium-89 C1 2.10E - 05 4fDA strontium-90 Ci 3.83E - 06 4fDA cesium-134 Ci 2.73E - 06 7.39E -06 cesium-137 Ci 6.17E - 05 4.23E -05 ,I barium-lanthanum-140 Ci <MDA <MDA cobalt-58 Ci 9.15E - 04 5.52E -04 '
cobalt-60 Ci 3.38E - 03 9.67E -04 chromium-51 Ci 6.35E - 03 8.89E -03 zirconium-niobium-95 Ci 9.57E - 06 2.07E -06 zine-65 Ci 6.39E - 04 1.43E -04 ! 1ron-59 Ci 6.09E - 04 7.23E -04 ' manganese-54 ci 2./d5 - 03 1. 39E -03 lodine-131 Ci 9.61t - 03 9.39E -05 ' ' cerium-139 Ci 'MA *MDA > cerium-144 Ci *MDA <MDA _ vttrium-88 Ci <MDA <MDA . I cesium-136 Ci <MDA <MDA _ tin-117m Ci <MDA <MDA
'
antimonv-124 C1 3.54E -06 <MDA cobalt-57 Ci 41DA <MDA j cadmium-109 C1 1.49E - 06 <MDA
'
l unidentified C1 1. 21E - 03 1.02E -03 _
"
-_
Total for Period C1 1.63E - 02 1. 3 AE -0? h/d II3
PE
. . _ _ _ _ _ _ . _ _ _ _ . _
,
y ! _
.
*
. , .,
*
.
j TABLE 2A EFFLUENT AND WASTE DISPOSAL SIMIANNUAL REPORT TEAR __1978 i
-
-
LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES ;
; ;
,
-'
Unit Quarter Quarter Est. Total 2
. 1st 2nd Error, % g i :
A. Fission activation products 7 .
*1. Total release (not including j tritium, gases, alpha) Ci 4.28E-01 9.19E-01 9.10E+00 .
,
- 2. Average diluted concentration =
during period uCi/mi 1.68E-08 2.'13E-08 ' y
- 3. Percent of applicable limit % 2.14E+00 4. 60E+00
"
-
- 3. Tritium
- 1. Total release Ci 1.10E+00 6.70E+00 1.23E+01 I
$
- 2. Average diluted concentration >
during period uCi/mi 4.32E-08 1.55E-07 ;
- 3. Percent of applicable limit % 1.44E-03 5.17E-03 ;-
*
; c C. Dissolved and entrained gases -
q
- 1. Total release Ci 2.77E-03 2.17E-03 9.10E+00 =
2.
. .
'
4-E Average diluted concentration during period
.
uCi/mi 1.09E-10 5.02E-11 ' i. ( q
- 3. Percent of applicable limit % 3.62E-03 1.67E-03 i i
'
l 4 1- . g
). Cross alpha radioactivity ,
I h 4 Total release Ci 3.87E-05 3.23E-05 1.12E+01 f I i q 3
-
'
. A t.
Volume of waste released (prior to ! ! dilution ) liters 7.67E+06 6.88E+06 5.66E+00 i g 3 : =
. . 'I
! 1 8
;
- f. Volume of dilution water used - '
durinc period liters 2.55E+10 4.32E+10 1.10E+01 ! ij
,
I
.eIncludes Estimated Total Error ,
' '
1578 094 _ . . . . _ ._ . 1
s .
.
~~
.- . . . . 3 TABLE 2B EFFLUElir A!;D WASTE DISPOSAL SD1IANNUAL REPORT YEAR 1978 LIQUID EFFLUENTS Batch Mode Continuous Mode Quarter II Ouarter Ouarter__
Nuclides Reicased Unit Ouarter I
- iodine-133 C1 1.Rav - na A 7sv - nt iodine-132 Ci <MDA < MDA ahtimony-122 Ci 3.20E - 04 2.01E - 03 anticony-124 C1 2.06E - 04 1.45E - 04 cobalt-57 Ci < MDA < MDA
.
cesium-136 I Ci < MDA < MDA cesium-138 Ci <MDA < MDA
,
h cerium-144
'
Ci < MDA < MDA yttrium-91m Ci 8.83E - 05 4.7 7E - 05 te11urium-129m Ci < MDA < MDA strontium-85 C1 4.25E -07 5.83E - 05
.
niobium-97m C1 <MDA <MDA zirconium-97 Ci <MDA <MDA ti.n-113 Ci <MDA 3.38E - 06 tin-117m Ci <MDA 9.18E - 0'7 indium-113m Ci <MDA 5.19E - 06
.
.
barium-139 Ci <MDA <MDA cerium-139 Ci <MDA <MDA strontium-91 Ci <MDA <MDA technitium-101 C1 <MDA <MDA tellurium-132 C1 4.5/L - u) <MDA tungsten-187 Ci J.44c - v4 4.c46 -ud continued on Table 2B-1 Dissolved and Entrained Cases . krypton-85 Ci ~ 1.05E - 04 <MDA krypton-85m Ci < MDA <MDA argon-41 Ci 9.32E - 06 2.08E -04 Tenen-131m Ci < MDA <MDA
- xenen-133 C1 1.82E - 03 1.10E -03 renon-135 Ci 8.36E - 04 8.59E -04 Tots 1 for Period C1 2.77E - 03 2.17E -03
. 1578 095
. .
* . . . . ..
TABLE 2B-1 EFFLUENT AND WASTE DISPOSAL SDiIAWJAL REPORT TEAR E LIQUID EFFLUDiTS __
-
Batch Mode Continuous Mode
,
Nuclides Released Unit Quarter I Ouarter II Ounrter Quarter strontium-89 C1 1.68E - 04 <MDA strontium-90 Ci 9.58E - 05 <MDA cesium-134 Ci 2.56E - 02 3.14E - 02 cesium-137 Ci 7.35E - 02 7.80E - 02 iodine-131 C1 1.57E - 04 1.05E - 02 cobalt-58 Ci 1 1 91E -702 l 2.97E - 02 cobalt-60 Ci 3.4JE - 04 6.05E - 02 iron-59 . C1 1.adt - 04 2.97E - 02 zine-65 C1 1.u46 - uz d.Jbt - 04 maneanese-54 Ci 6.99E - 02 9.20E - 02 chromium-51 Ci ' 7.02E - 02 1 1. 05 E - 01
.
zirconium-uiobium-95 Ci 7 nny -n, 2.19E - 03 molybdenum-99 Ci s sar _ 04 3.13E - 04 technetium-99m Ci I.20E - 04 1.43E - 03 barim -lanthanun-140 C1 <MDA 1.00E - 05 , cerium-141 Ci i 1.126 - 06 e 9fDA , i
.
fluorine-16 C1 4.90E -03
~
2.03E - 02 sodium-24 C1 2.63E 02 3.66E - 01 maneanese-56 C1 1.74E - 03 < MDA copper-64 C1 1.09E - 02 < MDA arsenic-76 Ci 2 06E - 03 3.84E - 03 niobium-97 Ci 6.JJL - 04 <MDA neotunium-239 Ci '+ 53h - U4 *MDA stroatium-92 C1 1.12E - 04 < MDA
. _ s,Lilver-110m C1 5.19E - 04 < MDA
_ nickel-65 Ci < MDA 1.16E - 05
.
unidentified Ci ' 3.57E - 02 7.66E - 02
-
-Total for oeriod (above) i C1 4.28E - 01 9.19E - 01
.
m 1578 096
.
J
- . . - - --
,._ --
MINIMUM DETECTABLE ACTIVITIES (uCi/ml)
- 1. For Liquid Releases 2. For Gaseous Releases Ag-110m 2.65E-08 Ar-41 2.51E-08 Ba-139 1.41E-07 Kr-85 5.68E-06 Ba-140,La-140 1.17E-07 Kr-85m 2.50E-08 Ce-139 3.88E-08 Kr-87 3.50E-08 Ce-141 5.81E-03 Kr-88 5.55E-08 Co-57 3*. 49E-08 Ze-135m 2.71E-08 .
Ca-72 1.23E-07 Xe-138 5.92E-08 ! I-132 3.38E-08 In-113m 4.26E-08 ! Kr-85 1.02E-05 i Mn-56 2.79E-08 [ Ni-65 6.33E-08 3. For Particulates and Iodines ? Np-239 3.43E-07 i Sc-46 2.84E-08 Cd-109' ' $.24 E-13 ! Sn-113 2.77E' 08 Ce-139 1.93E-14 Sn-117m 3.71E-08 Ce-144 1.32E-13 Sr-85 4. 04E-08 Co-57 1.78E-14 Sr-92 3.71E-08 Cs-134 1.37E-14 Te-132 5.17E-08 Cs-136 1. 60E-14 Y-91 1.99E-05 Sb-124 2.70E-14 Y-91m 5.05E-08 Sn-117m 1.66E-14 - Zr-95,Nb-95 8.12E-08 Y-88 1.14E-14 t Zr-95,Nb-95 3.77E-14 I I-132 2.87E-14 l
'
. I-135 5.81E-14
.
e
.
1573 097
.
[ %
. .- . . .
.
. .
,
. .. . ,. :_. T BLE 3 ,
,, ,
. EFFLUENT AND WASTE DISPOSAL SEMI ANNUAL REPORT (YEAR) /978 '
.
SOLID WASTE AND IRRADIATED FUEL SHIPMENTS .
-
, .
A. SOLID WASTE SHIPPED OFFSITE FOR DURIAL OR DISPOSAL (Notirradiated fuel) , , ,
,
unis konm Est. tow I. Type of waste Period Err or. %
- a. Spent resins, fdter sludges evaporator m' 5.10 E 01 bottoms. etc. CI 5.24 E02 1 50 E 01 '
- b. Dry compresuble waste, contsmmated m' 2.73 E 05 equip. etc. C1 1.54 E 01 2.00 E01 1.63 E01
,
- c. Irradiated components, control m' rods, etc. Ci 7.43 CO21.50 E01
- d. Other (desenbe) m' O.00 E0C Cl 0.00 E000 00Eco .
- 2. Estimate of maior nuclide composition (by type of waste) I
!
- a. & b. CR-51 4 5.99 E01 i MN-54 e 2.04 E01' FE-59 c; 6 J1E-01 .
,
Co-57 e 2.03E-02 y CO-58 % h 5.48 EOC' s CO-60 4 7 16 E00 : CU-64 4 2.66 E0C 2N-65 4 2.81 EOC I-131 % 1.14E-01 NB-95 n 1.BOE-01 CS-134 4 1.89E-Q1 *
~
CS-137 q 3.93E-01
- c. ER-95 4 3.04 E03
-
hd-93 e 3.04 E01 MN-54 <* 7.84 EOC CO-58 e 2.08 E.QC CO-60 % 1. E _3N-65 9 RA1 EO IN-113M 1 3.03 E0
- d. None 4 n.nn End f
.
- 3. Solid Waste Disposition ,
Number of Shipments Mode of Transportation Destination .
'
132 Sole Use Vehicle Cham-Nuclear Systems, Inc. j Barnwell, SC - g B. IPRADIATED FUEL SHIPMENTS (Disposition) . g.1 Number of Shipments Mode of Transportation Destination g
'
0 N/A -
.N/A
. .
. .
-
i.3i.ie ' 1578 098
.
...
_ . _ . _ . _ _ _ _ _ _ g . .
'un . -- .. . . . y E
SHOPELIllE SEDIMEtlT DCSE AT CAtlAL, t1PEM/6 MOS. CHILD TEEtt ADULT ,,
- 1. 1. 6 E-5 -
E- 3. 3 - {ff E 80F/ .
,
E
-
HOTE: LIO.UID EFFLUEtlT D tT A ~ URS UCCD Ill THESE DOSE CALCULATI0tlS _ DOSE DUE TO EATIrlG FISH CAUGHT Ill DISCHARGE CAtlAL, MREt1/6 110S CHILD TEEH ADULT , 80tlE 5.61E-05 4.65E-05 4.52E-05 LIVEP o.34E-05 1.11E-04 1.10E-04 HHOLN BODY 6.52E-05 4.38E-05 5.28E-05 THYR 51D 5.55E-06 5.66E-06 e.06E-Oo 2.63E-05 2.e,.E-05 FIDilEy 2.10E-05 LUtlG 1.49E-05 1.91E-05 1.e4E-05 GI-LLI 7.7SE-05 2.17E-04 3.06E-04
-
=
,
tt0TE: LIOUID EFFLUEtiT DATA USED Itl FISH DOSd CALCULATI0tlS I-131 IllHALATI0tt DOSE AT WORST POIllT Oil SITE SOUllDARY, MREM /6 MOS -
-
IllFRtIT CHILD TEEll ADlJLT B0llE 4.32E-06 5.4?E-06 4.03E-06 2.87E-06 _ LIVER 5.05E-06 5.47E-06 5.59E-06 4.07E-06 MHOLE BODY 2.23E-06 3.10E-06 3.00E-06 2.33E-06 THYROID 1.69E-03 1.85E-03 1.67E-03 1.36E-03 KIDilEY 5.89E-06 0.9?E-06 9'56E-06
. 6.97E-06 LUllG 0.00E+00 0.00E+00 0.00E+00 0.00E+00 i GI-LLI 1.20E-0? 3.23E-07 7.30E-07 7.15E-07 {
;. -
TOTAL IllHALATI0tl DOSE AT WORST POIllT Oil SITE BOUllDARY, MREM /6 MOS ,
.
- IllFAtlT CHILD TEEN ADULT- ' ,
B0llE 3.35E-05 6.16E-05 5.66E-05 4.77E-05 LIVER 1.99E-04 3.32E-04 3.74E-04 3.56E-04 .
- WHOLE BODY 1.75E-04 3.05E-04 3.40E-04 3.33E-04
- THYROID 3.86E-03 4.30E-03 3.63E-03 2.88E-03 KIDilEY 1.83E-04 3.14E-04 3.54E-04 3.41E-04 .
LUHG 2.41E-03 3.61E-03 4.59E-03 3.25E-03 .; GI-LLI 1.82E-04 3.37E-04 4.76E-04 4.90E-04 :j**
-
,
Il0TE: GASEOUS EFFLUEllT DAT A USED Ill IllHALATI0tl DOSE CALCULATI0lls , 3001DRBlK ~
-
_ __ . 1R78 099 a
"
.- . . ,
g _g3: D05E DOE TO DPlitt.lHG (11LL. MFEM.~6 M03 INF Att i tHILD TEEH " ADULT BONE 0. ME-0 3 1.46E-03 6.03E-04 3.32E-04 LIVER 3.60E-03 1.47E-03 S.44E-04 4.75E-04 MHOLE BODY 1.58E-03 0.36E-04 4.54E-04 2.72E-04 THYPOID 1.18E+00 4.56E-01 2.46E-01 1.56E-01 iIDHEY 4.20E-0? 2.42E-03 1.45E-03 8.15E-04
'
LUNG 0.00E+00 0.00E+00 0.00E+00 0.00E+00 GI-LLI 1.28E-84 1.31E-04 1.67E-04 1.25E-04 TOTAL DOSE DUE TO DF IttKING HILK. MFEM/6 MOS INFANT CHILD TEEH ADULT B0tlE 4.96E-03 2.75E-03 1.19E-03 6.37E-04 LIVER 7.33E-03 3.54E-03 2.16E-03 1.26E-03 MHOLE BODY 3.04E-03 1.94E-03 1.10E-03 7.29E-04 THYR 01D 1.20E+00 4.94E-01 2.50E-01 1.58E-01 iIDHEY 5.65E-03 3.57E-03 2.21E-03 1.29E-03 LUttG 3.36E-04 2.06E-04 1.33E-04 S.66E-05 GI-LLI 2.27E-03 6.91E-04 9.14E-04 7.62E-04
-
D03E5 EVALURTED FOR STEVENS' FARM ( MK-;35 ).
.
P00RORISINAL
,
DOSE DUE TO EATING GPEEH LEAFY VEGS. FROM HORST GARDEtt, MREM /6 MOS
- -
CHILD TEEN ADULT E'ONE 3.38E-04 2.01'E-04 2.T4E-04 . LIVER 2.95E-04 2.33E-04 2.63E-04 . WHOLE BODY 1.96E-04 1.43E-04 1.80E-04 THYPOID 6.46E-02 4.34E-02 5.39E-02 iIDHEY 3.61E-04 2.91E-04 3.26E-04 Lt.lHG 1.58E-05 1.37E-05 1.72E-05 ' GI-LLI 1.46E-04 2.70E-04 4.38E-04 e
!
E35E5 CALCULATED FROM GASEOUS EFFLUENT DATA !
..
DO5E DUE TO ERTING PRODUCE FPOM UOF5T GARDEH, MREM /6 MOS ! L CHILD TEEN ADULT ' (C BGHE 1.75E-03 9.00E-04 6.26E-04 I' LIVER 1.25E-03 7.35E-04 5.06E-04 i WHOLE BODY 1.17E-03 6.67E-04 4.89E-04 THYROID 6.04E-03 3.07E-03 2.08E-03 il KIDHEY 4.88E-04 3.15E-04 2.15E-04 g LUHG 2.03E-04 1.21E-04 9.32E-05 , GI-LLI 1.42E-03 2.04E-03 1.85E-03 { DOSES CALCULATED FROM GA5EOUS EFFLUENT DATA i-
DOSES CALCULATED FOR MAXIMUM E*,'P,0EED INDIVIDUAL 1578 100 .
.:
1
'
.,
. .
'
- . .
% . .
, . e m. -
*
.
.-
W 4
. . . . . . . _ _ . . -
, . - - - --
. --
.
AIR SUBMERSION DOSE AT WORST POINT OH SITE BOUNDARY = 1.15E+00 SKIH DOSE FROM HOBLE GAS RELEASES-SKIH MREM /6 MOS RADIAL DISTANCE, MILES 0.5 1.5 2.5 3.5 4.5 S 8.25E-01 3.49E-01 2.10E-01 1.49E-01 1.14E-01 RSW 6.53E-01 2.88E-01 1.77E-01 1.26E-01 9.61E-02 SH 5.52E-01 2.86E-01 1.95E-01 1.44E-01 1.11E-01 USW 4.90E-01 2.26E-01 1.50E-01 1.12E-~01 8.75E-02 W 4.60E-01 2.19E-01 1.40E-01 1.02E-01 7.78E-02 MHW 3.37E-01 1.50E-01 8.93E-02 6.40E-02 4.96E-02 HW 3.93E-01 1.77E-01 1.07E-01 7.74E-02 6.01E-02 NHu 3.59E-01 1.73E-01 1.13E-01 0.47E-02 6.70E-02 H 4.10E-01 2.11E-01 1.42E-01 1.06E-01 8.28E-02 HNI' 4.14E-01 2.20E-01 1.56E-01 1.19E-01 9.45E-02 HE 7.94E-01 3.96E-01 2.62E-01 1.94E-01 1.50E-01 ENE 7.64E-01 3.39E-01 2.19E-01 1.62E-01 1.26E-01 E 1.03E+00 4.19E-01 2.45E-01 1.72E-01 1.31E-01 ESE. 6.48E-01 2.66E-01 1.56E-01 1.11E-01 9.41E-02 SE . . 6.50E-01 2.85E-01 1.74E-01 1.24E-01 9.41E-02 SSE 7.08E-01 3.14E-01 1.93E-01 1.37E-01 1.03E-01 RADIAL DISTANCE, HILES 7.5 15.0 25< 0 35.0 45.0 R 6.34E-00
- 70E-02 1.39E-02 8.89E-03 6.35E-03 SSu 5.29E.-02 2.22E-02 1.13E-02 7.23E-03 5.18E-03 SW 6.14E-02 2.57E-02 1.30E-02 8.24E-03 5.86E-03 H$W 4.98E-02 2.15E-02 1.11E-02 7.10E-03 5.08E-03 W 4.322-02 1.83E-02 9.43E-03 6.06E-03 4.36E-03 UHW 2.89E-02 1.34E-02 7.47E-03 5.04E-03 3.74E-03 HW 3.49E-02 1.59E-02 8.65E-03 5.75E-03 4.22E-03 HHW 3.95E-02 1.82E-02 9.90E-03 6.57E-03 4.82E-03 H 4.74E-02 2.09E-02 1.iOE-02 7.18E-03 5.20E-03 HHE 5.47E-02 2.42E-02 1.26E-02 8.17E-O'3 5.89E-03 UE 3.48E-02 3.65E-02 1.88E-02 1.21E-02 8.62E-03 ENE 7.23E-02 3.20E-02 1.69E-02 1.11E-02 8.08E-03 E 7.29E-02 3.13E-02 1.63E-02 1.05E-02 7.53E-05 ESE
~
4.81E-02 2.14E-02 1.15E-02 7.58E-03 5.46E-03
,
'
5.29E-02 2.25E-02 1.17E-02 7.58E-03 5.46E-03 5.65E-02 2.35E-02 1.19E-02 7.59E-03 5.41E-03
-
1573 101
. - _ _ _
_ _ _ _ _ _ 4
-
.- . . . .
e
.
.
P001ORl8iiEL
~
,. __ AIR SUBMERSI0ll DOSE AT WORST POINT OH SITE BOUtIDARY= 4.33E-01 T. BODY
'
DOSE FROM 110BLE GAS RELEASES-T. BODY MREM /6 MOS RADIAL DISTAllCE, MILES 0.5 1.5 2.5 3.5 4.5 S 3.15E-01 1.41E-01 8.93E-02 6.51E-02 5.03E-02
; SSW 2.49E-01 1.17E-01 7.59E-02 5.54E-02 4.26E-0* '
SW 2.17E-01 1.22E-01 8.78E-02 6.60E-02 5.14E-03 WSW 1.91E-01 9.52E-02 6.67E-02 5.10E-02 4.03E-02 W 1.80E-01 9.18E-02 6.20E-02 4.58E-09 3.55E-05 HHW - 1.34E-01 6.25E-02 3.90E-02 2.86E-03 2.24E-05
-; HH 1.57E-01 7.47E-02 4.73E-02 3.49E-09
- 75E-05
; HHH 1.4 1.e,1E-01 7.27E-02 5.01E-02 3.85E-03 308E-05 H 1E-01 9.04E-02 6.41E-02 4.87E-02 3.85E-0* -
HHP 1.e1E-01 9.42E-02 7.08E-02 5.52E-09 4.42E-05
, HE 3.10E-01 1.67E-01 1.17E-01 8.83E-05 6.93E-05 EllE 2.91E-01 1.38E-01 9.45E-02 7.16E-05 5.66E-05 E 3.92E-01 1.66E-01 1.02E-01 7.36E-03 5.67E-03 ESE, 2.48E-01 1.07E-01
,
, 6.57E-02 4.76E-02 4.20E-05 SE 2.52E-01 1.17E-01 7.50E-02 5.45E-0* 0E-05 SSE 2.73E-01 1.29E-01 8.37E-02 6.04E-03 4".'62E-03 4
RADIAL DISTAllCEs. MILES
.
7.5 15.0 25.0 35.0 45.0 S 2.84E-02 1.23E-02 6.41E-03 4.13E-03
- 96E-03 SSW 2.38E-02 1.02E-02 5.23E-03 3.37E-03 3.42E-03 SW 2.88E-02 1.22E-02 6.19E-03 3.94E-03 2.81E-03 USW .33E-02 1.02E-02 5.28E-03 3.40E-03
- 44E-03 W 2.00E-02 8.58E-03 4.45E-03 2.88E-03 3l08E-03 UNW 1.33E-02 6.31E-03 3.55E-03 2.41E-03 5.80E-03 HW 1.e2E-02 7.51E-03 4.13E-03 2.76E-03 2.03E-03 HHW 1.85E-02 8.64E-03 4.74E-03 3.16E-03 '
H 2.23E-02 9.96E-03 5.29E-03 3.46E-03 3.33E-O' 51E-03 HHy -.s9E-02
-
1.16E-02 6.09E-03 3.95E-03
- 85E-03 HE 3.96E-02 1.73E-02 8.97E-03 5.77E-03 [.14E-03 ENE g.30E-02 1.49E-02 7.94E-03 5.23E-03 3.83E-03 E .22E-02 1.41E-02 7.42E-03 4,83E-03 3.49E-03 E~ . 14E-02 9.75E-03 5.31E-03 3.52E-03 2.57E-03
,
g.40E-02 1.04E-02 5.44E-03 3.54E-03 2.57E-03 SW -.v6E-U2 1.08E-02 5.53E-03 3.53E-03 2.53E-03 1578 102
-
-
- - . - , .. . - . . . . . - , - - - - - - - -
. .
. .- ..
14' POPULATION INTEGRATED WHOLE BODY DOSE, MREM /6 MOS RADIAL DISTANCE, MILES 0.5 1.5 2.5 3.5 4.5 s 1.57E-03 5.64E-03 6.23E-02 0.00E+00 0.00E+00 , 55u 0.00E+00 1.88E-02 1.56E-01 0.00E+00 4.30E-03 : su 6.93E-03 7.83E-03 0.00E+00 5.28E-04 0.00E+00 uSW 0.00E+00 6.57E-03 5.34E-04 1.63E-03 2.02E-04 u 1.44E-03 3.03E-03 9.91E-04 0.00E+00- 0.00E+00 WHu 2.14E-03 5.00E-04 0.00E+00 0.00E+00 0.00E+00 HW 1.26E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 HHW 2.81E-03 2.91E-04 0.00E+00 0.00E+00 0.00E+00 H 3.22E-03 0.00E+00 0.00E+00 0.00E+00 0.00E+00 HHE 0.00E+00 1.51E-03 0.00E+00 0.00E+00 0.00E+00 NE 0.00E+00 3.35E-03 0.00E+00 0.00E+00 0.00E+00 EHE 0.00E+00 1.66E-03 0.00E+00 0.00E+00 0.00E+00 E 0.00E+00 2.66E-03 0.00E+00 0.00E+00 0.00E+00 ' ESE 0.00E+00 2.25E-03 0.00E+00 0.00E+00 0.00E+00 SE 9.07E-03 1.41E-03 0.00E+00 0.00E+00 0.00E+00 SSE 0.00E+00 5.18E-04 0.00E+00 0.00E+00 0.00E+00 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 0.00E+00 SSW 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 Sil 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 WSW 4.02E-03 0.00E+00 0.00E+00 3.64E-03 5.55E-03 W 1.02E-03 1.08E-02 1.77E-02 1.44E-02 1.41E-02 MHH 1.65E-03 8.56E-03 6.23E-03 8.68E-03 2.53E-02 HW 2.48E-03 1.49E-02 9.94E-03 9.93E-03 1.15E-02 -
'
HHW 2.83E-03 1.01E-02 1.69E-02 8.39E-03 7.98E N 2.03E-03 9.65E-02 5.39E-02 1.27E-02 1.64E-02 HHE 7.12E-03 6.01E-01 1.40E-01 1.15E-02 5.64E-03 NE 3.56E-02 0.00E+00 0.00E+00 7.04E-04 1.02E-02 EHE 2.59E-02 0.00E+00 0.00E+00 0.00E+00 0.00E+00 E 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 ESE 0.00E+00 0.00E+00 0.00E+00 Q.00E+00 0.00E+00 SE 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 SSE 0.00E+00 0.00E+00 0.00E+00 0.00E+00 0.00E+00 !
!
TOTAL POPULATION INTEGRATED WHOLE BODY DOSE = 1.60E+00 l
,
CASEQUS EFFLUENT DATA USED IN THESE DOSE CALCULATIONS 5
'
DOSES CALCULATED FOR MAXIMUM EXPOSED INDIVIDUALS . o
!<
1578 103 L
!
.
;
,
. .. - - . .
-
. . ..
.
.
.
.
I
-
i- . POPULATI0tl IllTEGRATED IllHALATI0tt DOSE Mall-RE!1/6 MOS OR THYROID MAH-REM /6 MOS IllF AllT CHILD TEEN t! HOLE BODY 3.76E-06 ADULT THYROID 6.95E-05 5.09E-05 2.30E-04 ., 9.06E-04 1.13E-02 6.73E-03 2.61E-02
-
.
-
. GASEOUS EFFLUEllT DATA USED Ill THESE DOSE CALCULATIONS
>
. ?00R DillGINA_ ! r
.
a' .
! 1 1573 104 .
!
1 - f : '
!
!
!
;
.
!
.
$
_ _ . _ . .
~
.
*1-
,
,, . .
- 1973 POPULATION DISTRIBUTION .
,
- c Brunswick Steam Electric Plant ,
;
January - June 1978 Distance Miles 4.5 7.5 15 25 35 45
.5 1.5 2.5 3.5 0 0 0 0 0 +0 0 S 5 40 697 101 0 0 0 0 0 SSW 0 161 2,058 0 8 0 0 0 0 0 0 SW 32 64 0 32 5 173 0 0 1,071 2,275 WSW 0 69 8 0 0 51 1,264 3,967 5,000 6,814 W 8 33 16 0 0 124 1,356 1,754 3,600 14,100 WNW 16 8 0 0 0 153 1,979 2,407 3,600 5,670 NW 8 0 0 0 0 153 1,173 3,570 2,652 3,427 inM 20 4 0 0 0 91 9,690 10,180 3,682 6,528 N 20 0 0 O 16 0 0 0 275 51,918 22,950 2,900 .1,978 NNE 0 0 0 2,160 0 0 122 2,458 NE O 20 -
0 0 785 0 0 0 0 ENE O 12 0 0 0 0 0 0 0 E O 16 0 0 0' O O O O ESE O 21 0 0 0 0 0 0 0 0 0 SE 36 12 0 0 0 0 0 0 0 0 SSE O 4 0 0
-
N
,
CO
*
.
- ,
LJ1 . . . . . ... . , . . . . ,,
. __
-
t}}