ML19290B888
| ML19290B888 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 06/30/1979 |
| From: | CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML17174B224 | List:
|
| References | |
| FOIA-79-488 NUDOCS 7912140346 | |
| Download: ML19290B888 (17) | |
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g ATTACHMENT 1 EFFLUENT, WASTE DISPOSAL, AND POTENTIAL DOSES SEMIANNUAL REPORT January - June, 1979 Brunswick Steam Electric Plant l
1578 127 l
i
)
l
.m sm-4 e
1
1979 Supplemental Information Facility Brunswick Steam Electric Plant License Carolina Power & Light Co.
1.
Regulatory Limits a.
Fission & activation gases I Y S [1.5 Q, + 575 Q ] 1 1 quarterly reporting average y
I E y [45 Q,
+ 400 Q ] 1 1 quarterly reporting average y
I E S [2.8 Q, + 1160 Qy] 1 1 12 consecutive month average I E y[90 Q,
+ 800 Q ] 1112 consecutive month average y
b.
I-131 and Particulates with half-lives >8 days 6
7
[3.26 x 10 ] Q, + [3.74 x 10 ] Q, i l quarterly reporting average 6
[6.56 z 10 ] Q + [7.46 x 10 ) Q, i l 12 consecutive month average c.
Liquid effluents 20 Curies per calender quarter 40 Curies per 12 consecutive ronths 2.
16v4 mm Instantaneous Release Rates (10CFR20) a.
Fission & activation Gases IQ, [4.0 Ey + 0.23 IB] + Q, [35Ey + 92 ES] 1 1 b.
I-131 and Particulates with half-lives greater than eight days.
4
~
[3.7 x 10 ] Q, + D.8 x Eh 411 c.
Liquid Effluents values specified in 10CFR Part 20, Appendix B Table II, Column 2 for unrestricted areas 3.' Average Energy Stack Ey = 6.06E-01 May 38 - 4.35E-01 HeV Average Energy Ground Ey ='1.83E-01 MeV; ES = 2.60E-01 MeV 1578 128 1
4.
Hensurements and Approximations of Total Radioactivity Fission and activation gases a.
Analysis for specific radionuclides in representative grab samples.by gamma spectroscopy.
b.
Iodines Analysis for specific radionuclides collected on charcoal cartridges by gamma spectroscopy.
i 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 ca: h measurement used in calculating activity values were combined using the additive property of variance. The square root of 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.
Eatch Releases a.
Liquid 1.
Number of batch releases: 417 2.
Total time period for batch releases: 7.57E+04 minutes 3.
Enrhum time period for a batch release: 4335 minutes 4.
Average time period for batch release: 169 minutes 5.
Minimum time period for a batch release: 1 minute 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 5.
Mini =um time period for a batch release: not applicable
~
1578 129 2
m
%s) 6.
Abnormal Release
- a. Liquid 1.
Number of releases: None 2.
Total activity released: None b.
Caseous 1.
Number of releases: 1 i
i 2.
Total activity released:
12 mci (primarily activated corrosion l
products)
NOTE: This event resulted in a Technical Specification Violation.
A 30 day report was sub=itted to the U. S. Nuclear Regulatory Commission Region II office (
Reference:
CP&L letter to James P. O'Reilly, Director, Region II Office,! erial GD-79-1330 S
dated May 22, 1979).
Meteorological Data Durine Abnormal Release Date Time Wind Direction Wind Speed (oph)
Stability Class f
5/8/79 2045 ESE 7.9 D
5/8/79 2145 ESE 9.2 E
5/8/79 2245 ESE 5.0 E
5/8/79 2345 SE 4.6 E
5/9/79 0045 E
4.8 E
5/9/79 0145 ESE 5.4 E
5/9/79 0245 ESE 5.0 E
1578 130 8
e 3
EFFLUENT AND WASTE DISPOSAL SDiIANNUAL REPORT YEAR 1979 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Est.
Unit rotal I & II Ouarter I Ouarter II Error $
A.
Fission & activation gaser _
1.
Total release C1 1.66E+4 1.08E+4 1.25E+1 2.
Averane release rate for period uCi/ see 2.10E+~,
1.36E+3 3.
Percent of Technical Soecification limit 8.08E+0 4.35E+0 B.
Iodines 1.
Total iodine-131 Ci 4.71E-3 7.43E-3 1.24E+
2.
Average release rate for period uci/see 5.97E-4 9.42E-4 3.
Percent of Technical Soecification limit 8.03E-1 5.83E-1
(
C.
Particulates 1.
Particulates with half-lives of > 8 days C1 3.75E-2 3.74r-7 1.24E+
2.
Average release rate for period uCi/sec 4.76E-3 4.11E-3 3.
Percent of Technical Scecification'11mit 1.46E+1 1.14 E+1 4.
Cross alpha radioactivity Ci 8.90E-7 9.91E-7 D.
Tritium 1.
Total release C1 1.24E+0 1.79E+0 1.59E+1 2.
Average release rate for period uCi/see 1.57E-1 2.27E-1
- 3.
Percent of Technien1 Soecification limie 3.79E-3 2.12E-2
- Baced on 10 CFR 2_0 App. B limit of 4E-05uci/ml for H3 submersion in an unrestricted area.
~
1578 131
TABLE IB EFFLUENT AND WASTE DISPOSAL SDlIANNUAL REPORT YEAR E GASEOUS EFFLUENTS-ELEVATED RELEASE Continuous Mode Batch Mode Nuclides Released Unit Quarter T Ouarter II Ouarter Quarter!
11.
Tission gases kryoton-85 Ci
<MDA
<MDA o
krypton-85m Ci 5.71E+2 1.58E+2 krypton-87 Ci 1.11E+3 4.60E+2 krypton-88 C1 1.05E+3 3.10E+2 xenon-133 C1 3.42E+3 1.19E+3 xenon-135 C1 2.73E+3 2.76E+3 xenon-135m C1 3.11E+2 7.36E+2 xenon-138 Ci 4.80E+2 1.077+1 arron-41 C1 4.36E+1 4.23r+?
xenon-133m Ci 1.33E+2 7.10E+1 unidentified Ci 1.24E+3 8.98E+2 Total for Period C1 1.11E+4 8.08E+3 2.
Iodines iodine-131 Ci 3.30E-3 6.79E-3 iodine-132 C1 2.62E-3 1.55E-2 iodine-133 Ci 6.17E-3 1.72E-1 iodine-135 C1 1.09E-3 4.78E-2 Total for Period Ci 1.32E-2 2.42E-1 3.
Particulates strontium-89 l
C1 3.49E-4 1.66E-3.
C1 4.17F-6 9.19E-7 cesium-134 Ci 1.67F-s 1.0??-4 cesium-137 Ci 7.71E-s
?.sAr-4 barium-lanthanum-140 Ci 1.1?r-1 1.osv-1 cobalt-58 Ci 1
1.01r-4 9.54r-4 cobalt-60 C1 L
1.nAr 1 1.4nv-1
}
chromium-51 Ci s.497-4 1.74r-4
=irconium-niobium-95 '
C1 1.81E-7
<MD.A zine-65 C1 1.21E-4 1.44r-4 antimonv-122 Ci 1.17E-6
<sm A iron-59 Ci 4.2SE-4 2.71E-4 mancanese-54 C1 1.60E-3 1.68E-3 iodine-131 C1 1.42E-5 5.43E-5 cerium-139 Ci 4.17E-4 2.29E-5 cerium-144 Ci
<MDA
<MDA yttrium-88 Ci 4.87E-6
<MDA antimony-122 Ci
<MDA 8.80E-6 h
unidentified Ci 7.54E-4 1.01E-3 11 Total for Period Ci 6.83E-3 9.19E-3 1578 132
y b
TABLE 1C EFFLUEhT AND WASTE DISPOSAL SEMIANNUAL REPORT YEAR 1979 CASEOUS EFFLUENTS-CROUND LEVEL PILEASES Continuous Mode Batch Mode Nuclides Released Unit Quarter T Quarter II Ouarter Ouart e-1.
Fission cases-kryoton-85 Ci
<MDA
<MDA krypton-85m Ci
<MDA
<MDA krypton-87 Ci
<MDA
<MDA krypton-88 Ci
<MDA
<MDA xenon-133 Ci 5.75E+2 4.51E+2 xenon-135 Ci 4.24E+3 1.86E+3 xenon-135m Ci
<MDA 6.25E+1 xenon-138 Ci
<MDA
<MDA arcon-41 Ci
<MDA
<MDA xenon-133m Ci 3.44E+1
<MDA unidentified Ci 6.06E+2 2.96E+2 Total for Period Ci 5.46E+3 2.67E+3 2.
Iodines iodine-131 Ci 1.41E-3 6.38E-4 iodine-132 C1 4.77E-5
<MDA iodine-133 C1 2.13E-4 4.05E-3 fodine-135 C1
<MDA
<MDA Total for Period C1 1.67E-3 4.69E-3
~
3.
Particulates strontium-89 C1 1.08E-5 1.04E-5 strontium-90 C1 2.84E-6 7.31E-6 cesium-134 C1 1.58E-5 3.73E-5 cesium-137 C1 4.49E-5 7.73E-5 barium-lanthanum-140 Ci
<MDA
<MDA cobalt-58 Ci 1.68E-3 1.65E-3 cobalt-60 Ci 5.10E-3 5.93E-3 chromium-51 Ci 1.36E-2 6.43E-3 zirconium-niobium-95 Ci 4.87E-6 1.89E-5 zine-65 Ci 6.14E-4 9.28E-4 iron-59 C1 1.68E-3 2.80E-3 mancanese-54 Ci 4.46E-3 2.58E-3 iodine-131 Ci 6.20E-5 5.82E-5 cerium-139 C1 2.03E-7
<MDA cerium-144 Ci
<MDA
<MDA vttriu=-88 I
Ci 5. 2 0 e-1 ()
oma cesium-136 Ci
<MDA
<tm A tin-117m Ci
<MDA 1.22E-5 antimony-124 Ci 5.43E-6 2.32E-5 cobalt-57 C1
<MDA 1.23E-5 unidentified C1 3.38 E-3 2.58E-3 Total for Period Ci 3.07E-2 2.32E-2 1 r7n 7
i J/O JJ
TABLE 2A a
EFFLUENT AND WASTE DISPOSAL SDiIANNUAL REPORT TEAR 1979 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Unit Quarter Quarter Est. Total 1 & II 1st 2nd Error, %
- h. Fission activation products
- 1.
Total release (not including tritium, cases, alpha )
Ci 6.73E-1 1.73E+0' 1.45E+1
~
2.
Average diluted concentration during period uCi/ml 1.05E-8 2.72E-8 3.
Percent of neolicable limit 2.63E+1 6.96E+1 I
B.
Tritium 1.
Total release Ci 7.32E+0 5.18E+0 1.59E+1 2.
Average diluted concentration during period uCi/mi 1.58E-7 8.15E-8 3.
Percent of neolicable limit 5.27E-3 2.72E,
C.
Dissolved and entrained gases 1.
Total release Ci 2.45E-3 1.93E-2 1.45E+1 2.
Average diluted concentration during period uCi/mi 5.29E-11 3.04E-10 3.
Percent of applicable limit 1.76E-3 1.01E-2
'D.
Cross alpha radioactivity Total release ci 6.65E-5 1.72E-5 See attached note 3.
Volume of vaste released (prior to dilution )
liters 9.98E+6 1.35E+7 5.66E+0 F.
Volu=e of dilution water used durinn period liters 4.63E+10 6.36E+10 1.10E+1
- Includes Esti=ated Total Error
~
f578 134
NOTE ON ESTIMATED TOTAL ERROR IN GROSS ALPHA RADI0 ACTIVITY (FROM TABLE 2A)
It is difficult to obtain a counting error for gross alpha due to the extremely small amount of alpha activity present in the liquid effluent samples.
Only one monthly co=posite alpha analysis provides a sufficient number of counts to determine a reasonable counting error. This error combined with a sampling error resulted in an esticated total error of 70.2%.
Assuming thn worst possible case by taking the total curies released for both cuarters, addinc 70.2% of this to the total, and converting to pCi/ml, a concentration of 6.07E-9 uC1/ml is obtained. The value is well below the Environmental Technical Specifications monthly liquid composite minimum detectable concentration for gross alpha of 1.0E-7 pCi/ml.
1578 135 e
e e
S
TABLE 2B EITLUENT AfD WASTE DISPOSAL SEMIAN1 MAL REPORT YEAR 1979 LIQUID EFFLUENTS Batch Hode Continuous Mode Nuclides Relesred Unit Ouarter I Ouarter II Ouarter Ouarter iodine-133 Ci 8.68E-4 7.86E-4 iod ine-132 Ci
<MDA
<MDA antimonv-122 Ci 7.29E-3 1.98E-2 antimony-124 Ci 1.00E-6 7.79E-5 cobalt-57 l Ci
<MDA
<MDA cesium-136 Ci
<MDA 1.86E-4 cesium-138 Ci
<MDA
<MDA cerium-144 Ci
<MDA
<MDA yttrium-91m Ci
<MDA 4.02E-4 tellurium-120m C1
<MDA
<MDA strontium-85 Ci
<MDA 7.39E-5 niobium-97m Ci l<MDA 4.32E-4 zirconium-97 Ci
<MDA 4.50E-4 tin-113 Ci
.<MDA 8.53E-6 tin-117m Ci
'<MDA
<MDA indium-113m Ci
<MDA 1.31E-5 barium-139 Ci
<MDA
<MDA cerium-139 Ci
<MDA
<MDA strontium-91 Ci
<MDA
<MDA technitiu=-101 Ci
<MDA
<MDA t ellurium-132 Ci
<MDA
<MDA tunesten-187 Ci
<MDA
<MDA continued on Table 2B-1 Dissolved and Entrained Bases krypton-85 f. _Ci 9fDA 1.83E-2 krypton-85m C1
<MDA iMDA argon-41 Ci 5.08E-4 4.81E-4 xenon-131m Ci
<MDA
<!GA xenon-133 Ci 1.53E-3 3.88E-5 xenon-135 Ci 4.13E-4 4.37E-4 Total for Period C1 2.45E-3
- 1. 93 E-2
, -, e mo ou
- - u.
c.
m-
-m
.._m.
__m TABLE 2B-1 8
EFFLUENT AND WASTE DISPOSAL SDiIANNUAL REPORT YEAR 1979.
LIQUID EFFLUENTS Batch Mode Continuous Mode Nucliden Released Unit Ouarter I Ouarter II Ouarter Ouarter strontium-89 Ci 2.96E-4 7.26E-5 strontium-90 Ci 2.02E-4 1.44E-5 cesium-134 Ci 5.55E-2 1.58E-1 cesium-137 C1 1.19E-1 2.49E-1 iodine-131 C1 4.12E-3 2.55E-3 I
cobalt-58 Ci 2.84E-2 3.85E-2 cobalt-60 C1 1.59E-1 1.79E-1 3
1ron-59 Ci 9.46E-3 1.59E-2 i
zine-65 Ci 7.47E-3 8.40E-3 i
mancanese-54 I Ci 1.46E-1 2.02E-1 I
i Ci 4.25E-2 5.15E-2 i
chromium-51 zirconium-niobium-95 Ci 2.49E-4 1.78E-3 mol ybd enum-99 Ci
<MDA
<MDA technetium-99m C1 1.24E-4 5.21E-4 barium-lanthanum-140 Ci
<MDA
<MDA I
cerium-141 1
Ci
<MDA
<MDA I
fluorine-IS Ci 7.52E-3 7.22E-2 I
sodium-24 Ci 2.94E-2 3.60E-1 I
mancanese-56 C1
<MDA 6.06E-4 I
copper-64 C1 2.50E-2 1.49E-1 arsenic-76 Ci 5.76E-5 3.88E-4 niobium-97 Ci 2.64E-4 6.60E-4 strontium-85 Ci
<MDA
<MDA nentunium-239 Ci
<MDA
<MDA strontium-92 Ci 2.78E-4 7.27E-5 s11ver-110m C1 1.43E-4
<MDA nickel-65 Ci
<MDA
<MDA mercury-203 Ci 4.76E-6 I <MDA
~
unidentified Ci 8.53E-2 2.19E-1 i
Total for period (above)
Ci 6.73E-1 1.73E+0 O
1578 137
s.
MINIMUM DETECTABLE ACTIVITIES (uC1/ml) 1.
For Liquid Releases 2.
For Caseous Releases Ba-139 2.25E-8 Ar-41 5.90E-9 Ba-140, La-140 3.69E-8 Kr-85 3.68E-6 Ce-139 5.42E-9 Kr-85m 1.20E-8 Ce-141 8.30E-9 Kr-87 2.06E-8 Ce-144 5.94E-8 Kr-88 2.65E-8 Cs-136 4.72E-9 Xe-135m 1.19E-8 Cs-138 1.44E-8 Xe-138 2.53E-8 Co-57 8.91E-9 In-113m 5.64E-9 I-132 5.94E-9 Kr-85 8.05E-7 Kr-85m 5.98E-9 Mn-56 6.95E-9 Rg-203 6.61E-9 Mo-99 3.18E-8 Np-239 3.55E-8 Ni-65 3.15E-8 3.
For Particulates and Iodines IB-97n 4.46E-9 Ag-110m 8.40E-9 Sb-122 6.30E-15 Sr-85 5.62E-9 Sb-124 1.84E-14 Sr-91 1.74E-8 Ba-140, La-140 3.72E-14 Tc-101 4.58E-9 Te-129m 1.90E-7 Ce-139 6.64E-15 Te-132 4.96E-9 Ce-144 6.95E-14 Sn-113 3.66E-9 Cs-136 4.86E-15 Sn-117m 6.29E-9 CO-57 7.33E-15 W-187 2.28E-8 I-132 8.47E-15 Xe-131m 2.53E-7 I-135 2.92E-14 Y-91m 1.03E-8 Sn-117m 6.97E-15 Zr-97 4.65E-9 Y-88 9.61E-15 Zr-95, Nb-95 1.80E-14 O
\\38
- \\c,o nu O
e
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (YEAR)
SOLID WASTE AND IRRADIATED RTEL SHIPMENTS A.
Solid Waste Shipped Offsite for Burial or Disposal (Not irradiated fuel) 1.
Typeo5 Waste Unit.
6-month
.Est. Total period Error, %
Spent resins, filter sludges, evaporated m"
6.80E02 a.
bottoms, etc.
Ci 1.52E03 1.50E01*
b.
Dry compressible vaste, contaminated mJ J,.31E03 couip., etc.
Ci 3.87E01-2.00E01 c.
. Irradiated components, control mJ 0.00E00 rods, etc.
Ci 0.00E00 0.00E00 m3 0.00E00 d.
Other (describe) ci 0.00E00 0.00E00 2.
Estimate of major nuclide composition (by type f vaste)
A+B Mn-54 3.07E01 Co-60 2.61E01 Cr-51 1.94E01 Fe-59 6.34E00 Co-58 5.95E00 Cs-137 A.56E00 Cs-134 3.71E00 Zn-65 2.38E00 Sb-122 5.30E-01 Nb-95 1
2.14 E-01 C
None Z
D None 3.
Solid Waste Disposition Number of Shioments Mode of Transoortation Destination 207 Sole Use Vehicle CheENuclearSystems,Inc.
Barnwell, South Carolina
~
B.
Irradiated Fuel Shipments (Disposition)
. Number of Shioments Mode of Transportation Destination
~
g 0
N/A N/A 1578 139
~.
~iiORELINE SEDIMENT DOSE AT CANAL, MREM /6 MGS.
CHILD TEEN ADULT WHOLE BODY-2.66E-06 1.27E-05 2.2SE-06 SKIH 3.11E-06 1.49E-05 2.67E-06 LIQUID EFFLUENT DATA USED IN SHOPELINE LOSE CALCULATIONS-DOSE DUE TO EATING FISH CAUGHT IN DISCHARGE CAHAL: HREM/6 MOS CHILD TEEN ADULT BONE LIVER 5.66E-05 4.62E-05 4.43E-05 8.85E-05 1.05E-04
- 1. 03E~-04 NHOLE BODY 2.SOE-05 4.16E-05 5.96E-05 THYROID.
2.41E-06 2.33E-06 2.50E-06 KIDHEY 2.56E-05 3.14E-05 3.14E-05
~
LUNG 9.91E-06 1.27E-05 1.0SE-05 GI-LLI 4.31E-05 1.22E-04 1.73E-04 LIQUID EFFLUENT DATA USED I.H FISH DOSE CALULATIONS DOSE DUE TO EATING GREEN LEAFY VEGS. FROM WORST GARDENS MREfi/6MOS CHILD TEEN ADULT BONE 4.92E-04 3.12E-04 3.80E-04 LIVER 2.94E-04 2.46E-04 2.87E-04 WHOLE BODY 2.76E-04 2.00E-04 2.57E-04
. THYROID 1.21E-02 S.01E-03 9.89E-03 KIDHEY 1.41E-04 1.19E-04 1.41E-04 LUNG 4.02E-05 3.50E-05 4.26E-05 GI-LLI 3.69E-04 7.12E-04 1.18E-03 i
DOSES C_ALCULATED FROM GASEOUS EFFLUENT DATA DOSE DUE TO EATING PRODUCE FROM HORST CARDENs MREM /6 MOS j
CHILD TEEH ADULT' j
BONE 4.97E-03 2.52E-03 1.74E-03 i
LIVER 3.14E-03 1.99E-03 1.2SE-03 l
WHOLE BODY 3.40E-03 1.SSE-03 1.34E-03 I
- THYROID, 1.26E-03 6.72E-04 4.77E-04 i
KIDHEY 1.05E-03 6.87E-04 4.70E-04 LUNG 4.65E-04 3.00E-04 2.09E-04 i
GI-LLI 4.45E-03 6.50E-03 5.90E-03 l()h0SESCALCULATEDFROMGASEOUSEFFLUENTDATA t
DOSES CALCULATED FOR MAXIMUM EXPOSED INDIVIDUAL 1578 140.
l
I-131 DOSE DUE TO DRIl1KIllG' MILK, MREM /6 MOS IllFANT CHILD TEEN ADULT BONE 5.07E-04 2.43E-04 1.00E-04 5.52E-05 LIVER 5.97E-04 2.44E-04 1.40E-04 7.89E-05 WHOLE BODY 2.63E-04 1.39E-04 7.53E-05 4.52E-05 THYROID 1.96E-01
- 8. 08E-02 '" 4.09E-02 2.59E-02 KIDHEY 6.98E-04 4.01E-04 2.41E-04 1.35E-04 LUNG 0.00E+00 0.00E+00 0.00E+00 0.00E+00 GI-LLI 2.13E-05 2.17E-05 2.77E-05 2.08E-05 TOTAL DOSE DUE TO DRIHKIllG MILK, MREM /6 MOS Il1FANT CHILD TEEN ADULT BONE 3.97E-03 2.58E-03 1.19E-03 7.27E-04 LIVER 7.64E-03 4.19E-03 2.67E-03 1.59E-03 NHOLE BODY 3.21E-03 2.38E-03 1.37E-03 9.31E-04 THYROID 2.09E-01 8.60E-02 4.32E-02 2.72E 02
- KIDNEY, 3.69E-03 2.54E-03 1.66E-03 1.02E-03 LUNG 5.53E-04 3.36E-04 2.17E-04 1.40E-04 GI-LLI 4.44E-03 1.20E-03 1.67E-03 1.43E-03 a
DOSESEVALUATEDFORSTEVENS' FARM (MK-35{
1-131 INHALATION DOSE AT WORST POIllT 011 SITE BOUNDARY, MREM /6 MOS IllF AllT CHILD TEEN ADULT BONE 6.69E-06 8.49E-06 6.25E-06 4.45E-06 LIVER 7.83E-06 9.49E-06 8.67E-06 6.31E-06 WHOLE BODY 3.46E-06 4.81E-06 4.66E-06 3.61E-06 THYROID 2.62E-03 2.87E-03 2.58E-03 2.10E-03
(
KIDHEY 9.14E-06 1.39E-05 1.48E-05 1.08E-05 LUNG 0.00E+00 0.00E+00 0 00E+00 0.00E+00 GI-LLI 1.87E-07 5.01E-07 1.14E-06 1.11E-06 TOTAL. IllHALATION DOSE AT WORST POINT Oil SITE BOUliDARY, MREM /6 MOS IllFANT' CHILD TEEli ADULT BONE 6.08E-05 1.23E-04 1.19E-04 1.04E-04 LIVER 1.92E-04 3.17E-04 3.58E-04 3.31E-04 WHOLE BODY 1.59E-04 2.82E-04 3.09E-04 2.98E-04 THYROID 4.25E-03 4.71E-03 4.07E-03 3.26E-03 KIDHEY 1.58E-04 2.73E-04 3.08E-04 2.93E-04 1.01E-02, 7.00E-03
. LUNG 5.31E-03 7.90E-03 GI-LLI 1.82E-04 3.65E-04 6.27E-04 6.612-04 GASEOUS EFFLUENT DAT A USED Ill IllHALATIOli DOSE CALCULATIONS
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l DOSE FROM HOBLE GAS RELEASES-SKIH l
MREM /6 MOS RADIAL DISTANCE, MILES 0.5 1.5
- 2. 5 3.5 4.5 S
1.14E+00 4.31E-01 2.28E-01 1.53E-01 1.13E-01 SSW 1.07E+00 4.17E-01 2.27E-01 1.54E-01 1.15E-01 SW 6.71E-01 2.79E-01 1.55E-01 1.05E-01 7.80E-02 WSW 8.06E-01 3.41E-01 1.93E-01 1.34E-01 1.01E-01 W
7.75E-01 3.26E-01 1.86E-01 1.275-01 9.45E-02 NHW 7.55E-01 3.04E-01 1.67E-01 1.13E-01 8.40E-02 HH 6.77E-01 2.86E-01 1.66E-01 1.15E-01 8.63E-02 HHW 5.62E-01 2.38E-01 1.3SE-01 9.71E-02 7.35E-02 H
6.80E-01 2.80E-D1 1.61E-01 1.12E-01 8.50E-02 HNE S.82E-01 3.78E-01 2.21E-01 1.55E"01 1.17E-01 NE 1.09E+00 4.81E-01 2.79E-01 1.95E-01 1.46E-01 ENE 1.08E+00 4.33E-01 2.46E-01 1.71E-01 1.29E-01 E
1.51E+00 5.63E-01 3.01E-01 2.04E-01 1.52E-01 ESE 8.68E-01 3.39E-01 1.87E-01 1.27E-01 1.42E-01 SE 1.44E+00 5.34E-01 2.83E-01 1.91E-01 1.42E-01 SSE 1.82E+00 6.62E-01 3.45E-01 2.29E-01 1.69E-01 RADIAL DISTANCE: MILES 7.5 15.0 25.0 35.0 45.0 S
6.16E-02 2.67E-02 1.43E-02 9.56E-03' 7.0?E-03 SSW 6.30E-02 2.72E-02 1.45E-02 9.61E-03 7.07E-03 SW 4.24E-02 1.82E-02 9.75E-03 6.49E-03 4.80E-03 s
NSW 5.56E-02 2.41E-02 1.2SE-02 8.47E-03 6.21E-03 W
5.12E-02 2.16E-02 1.12E-02 7.33E-03 5.33E-03 WHW 4.58E-02 1.97E-02 1.06E-02 7.05E-03 5.21E-02 HW -
4.72E-02 T.00E-02 0
1.05E-02 6.87E-03 5.00E-03 MHW 4.14E-02
.83E-02 9.81E-03 6.51E-03 4.79E-03 H
4.76E-02 2.10E-02 1.13E-02 7.50E-03 5.52E-03 NME' 6.48E-02 2.80E-02 1.47E-02 9.65E-03 7.03E-03 HE 7.92E-02 3.33E-02 1.73E-02 1.12E-02 8.17E-03 EHE 7.19E-02 3.15E-02 1.69E-02 1.12E-02 8.23E-03 E
S.40E-02 3.69E-02 2.00E-02 1.34E-02 9.90E-03 ESE 5.22E-02 2.28E-02 1.23E-02 8.21E-03 9.09E-03 SE 7.76E-02 3.38E-02 1.83E-02 1.22E-02 9.09E-03 SSE 9.19E-02 3.98E-02 2.14E-02 1.43E-02 1.06E-02 N0&DQ
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