ML19290B885
| ML19290B885 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 02/07/1978 |
| From: | CAROLINA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML17174B224 | List: |
| References | |
| FOIA-79-488 NUDOCS 7912140329 | |
| Download: ML19290B885 (19) | |
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ATTACHMENT 1 EFFLUENT, WASTE DISPOSAL, AND POTENTIAL DOSES SEMIANNUAL REPORT July - December 1977 Brunswick Steam Electric Plant February 7, 1978 1578 068 9 J e
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1977 Supplemental Information Facility Brunswick Steam Electric Plant License Carolina Power & Light Co.
- 1. Regulatory Limits
- a. Fission & activation gases I i 8 [0.72 Q, + 290 Qy] 11 quarterly average E 5 y ['? Q, + 200 () 11 quarterly average I E B [1.4 Q, + 580 () 11 12 month average IEy [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 >d days
[4.7 x 10 ]Q, + [7.2 x 10 ]Qy 11 quarterly average 5
(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. Maximum Permissible Concentrations
- a. Fission & activation Gases IQ, [4.0 ly + 0.23 ES] + Q [35Ey + 92 ES] 1 1
- b. Iodines and Particulates with half-lives greater than eight days.
6
[3.7 x 10'] Q, + [5.8 x 10 ] 11
- c. Liquid Effluents Values specified in 10CFR Part 20, Appendix B, Table II, Column 2 for unrestricted area.
- 3. Average Energy Stack fy = 5.93E-01 IIeV; YS = 4.30E-01 MeV Average Energy Ground Ey = 1.60E-01 MeV; ES = 2.40E-01 MeV 1578 069 1
l
- 4. Measurements and Approximations of Total Radioactivity
- a. Fission and activation gases Analysis for specific radionuclides in representative grab samples by gamma spectroscopy.
- b. Iodines Analysis for specific 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 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, i 5. Batch Releases
- a. Liquid
- 1. Number of batch releases: 537
- 2. Total time period for batch releases: 8.21E04 minutes l
- 3. Maximum time period for a batch release: 3115 minutes
- 4. Average time period for batch releases: 151.5 minutes
- 5. Minimum time period for a batch release: 0.1 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 lhh 4. Average time period for a batch release: not applicable
- 5. Minimum time period for a batch release: not applicable 2
i 1578 070
- 6. Abnormal Release
- a. Liquid
- 1. Number of releases: None
- 2. Total activity released: None
- b. Gaseous
- 1. Number of releases: None
- 2. Total activity released: None l
1578 071 O
3
TABLE LA EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (YEAR) 1977 CASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES Unit Quarter Quarter Est.Tctal III IV Error, %
A. Fission & activation gases l
C1 4.56E+04 4.79E+03 1.33E+01
- 1. Total release
- 2. Averate release rate for period uCi/ sec 5.80E+03 6.09E+C2 8.34E+00 2.46E+00
- 3. Percent of Technical anecification limit %
B. Iodines Ci 2.75E-01 5.17E-03 1.33E+01
- 1. Total iodine-131
- 2. AveraRe release rate for period uCi/see 3.50E-02 6.57E-04
- 3. Percent of technical specification limit % 6.88E+00 1. 29E-01 C. Particulates Particulates with half-lives > 8 days Ci 6.16E-02 2.10E-02 1.33E+01 1.
uCi/sec 7.83E-03 2.67E-03
- 2. Average elease rate for period 4.00E+01 1.65E+01
- 3. Percent of technical specification limit %
C1 4.48E-05 2.07E-05
- 4. Gross alpha radioactivity -
D. Tritium C1 2.57E+00 1.47E+00 1.45E+01
- 1. Total release
- 2. Averace release rate for period uti/see 3.26E-01 1.87E-01
% 6.28E+00 2.59E+00
- 3. Percent of technical specification limit e
1578 072
TABLE IB EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (YEAR) 1977 GASEOUS EFFLUENTS-ELEVATED RELEASE Continuous Mode Batch Mode III IV Nuclides Released Unit Quarter Quarter Quarter Quarter
- 1. Fission gases krypton-85 C1 <MDA <MDA krypton-85m Ci 2.22E+03 3. 63 E+02 krypton-87 Ci 5.47E+03 2.17E+02 krypton-88 Ci 5.24E+03 1.05E+02 xenon-133 C1 1 17E+04 <MDA xenon-135 C1 1.02E+04 1.54E+02 xenon-135m C1 2.88E+03 1.26E+02 xenon-138 C1 4.16E+03 7.85E+02 argon-41 C1 2.13E+02 4. llE+02 xenon-133m C1 2.03E+02 <MDA Ci unidentified C1 4.77E+03 2.43E+02 Total.for period Ci 4.23E+04 1.83E+03 1
- 2. Iodines iodine-13; C1 2.15E-01 3.73E-03 iodine-133 C1 1.32E-01 1.43E-02 iodine-135 C1 3.63E-02 2.39E-02 Total for Period C1 3.83E-01 4.19E-02
- 3. Particulates strontium-89 l Ci 5.16E-03 4.22E-04 strontium-90 Ci 5.52E-05 8.46E-06 cesium-134 Ci 6.95E-05 1.29E-05 cesium-137 C1 2.90E-04 6.81E-05 barium-lanthanum-140 C1 1.03E-02 9.15E-04 cobalt-53 Ci 1.12E-05 1.84E-04 cobalt-60 C1 3.75E-05 4.56E-04 chromium-51 C1 9.11E-05 2.29E-04 zi rr oniu m-niob ium-95 C1 <MDA <MDA zine-65 Ci <MDA 9.05E-05 iron-59 Ci 3.57E-06 7.69E-05 mancanese-54 Ci 7.18E-05 4.81E-04 iodin e-131 Ci 6.10E-04 4.97E-06 cerium-139 Ci 8.13E-04 2.24E-04 cerium-144 ci 1.40E-05 <MDA yttrium-88 Ci 4.76E-04 <MDA Ci Ci Ci unidene4* fed C1 2.39E-03 4.22E-04 Total for period C1 1.80E-02 3.17E-03 1578 073
- * - - TABLE 1C
. -EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REFORT (YEAR) 1977 CASEOUS EFFLUENTS- CROUND-LEVEL RELLEES 0
Continuous Mode. Batch Mode III IV o
Nuclides Released Unit Quarter Quarter Quarter Quarter
- 1. Fission cases krypton-85 C1 <MDA ,
<MDA krypton-S5m ,
Ci '
<MDA <MDA krypten-87 C1 '
<MDA. i <MIW krypton-SS Ci i <MDA <MDA xenon-133 C1 1.07E+03 1.37E+03 xenon-135 C1 2.19E+03 1.17E+03 xenon-135m Ci <MDA <MDA xenon-138 Ci <MDA <MDA argon-41 Ci <MDA '
, <MDA xenon-133m Ci 2.74E+01 7.40E+01 C1 unidentified '
Ci 4.37E+02 3.93E+02 l Total.for period l Ci I 3.29E+03 l 2.96E+03 l l
- 2. Iodines iod ine- 131 C1 1 6.02E-02 Il.44E-03 I iodine-133 Ci 1.32E-02 1.63E-04 iodine-135 C1 3.66E-02 <MDA Total for Period Ci 1.10E-01 l1.60E-03
- 3. Particulates strontium-S9 i Ci l1.90E-04 6.91E-06 strontium-90 t ci '2.43E-05 ,5.04E-06 cesium-134 i C1 7.63E-05 l1.28E-05 cesium-137 i Ci 1 4.49E-04 l8.12E-05 barium-lanthanum-140 i Ci '
<MDA '
<MDA s cobalt-58 C1 4.54E-03 2.00E-03 cobalt-60 '
C1 7.59E-03 13.90E-03 l l
chromium-51 Ci 1.71E-02 15.05E-03 zirconium-niobium-95 Ci 6.65E-05 i3.07E-05 zinc-65 C1 2.61E-03 1.24E-03 .
iron-59 C1 2.21E-03 1.44E-03
-,nenneso-54 cf 5.97E-03 3.86E-03 foa4,g-111 C1 2.70E-03 3.16E-04 '
cerium-139 Ci 3.83E-06 '
<MDA cerium-144 Ci 1.70E-05 '
<MDA J vttrium-88 C1 7.78E-06 <MDA cesium-136 cf 7.015'-06 11 <MDA tin-ll7m Ci 1.30E-06 <MDA .
antimony-124 Ci <MDA 1.69E-05 a cobalt-57 '
Ci <MDA 2.60E-07 unidentified Ci 5.80E-03 2.38E-03 a h Total for Period Ci 4.36E-02 ,1.79E-02 1578 074
TABLE 2A EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (YEAR) 1977
.. LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Unit Quarter Quarter Est. Total III IV Error, %
A. Fissionaid activation products
- 1. Total release (not including C1 -2.17E400 ' l.77E+00- 1.15E+01 tritium, cases, alpha)
- 2. Average diluted concentreMon uC1/ml 2.57E-08 2 . 50E- during period
% 1.09E+01 8.85E+00
- 3. Percent of applicable limit B. Tritium
- 1. Total release Ci 3.06E+00 2.17E+00 1.33E+01
- 2. Average diluted concentration uCi/ml 3.62E-08 3.24E-08 during period
- 3. Percent of apolicable limit % 1.21E-03 1.08E-03 C. Dissolved and entrained cases
- 1. Total release C1 1.02E-01 9.52E-03 1.15E+01
- 2. Average diluted concentration uC1/ml 1.21E-09 1.34E-10 during period I 3. Percent of aoolicable limit % 4.02E-02 4.47E-03 D. Gross aloha radioactivity
- 1. Total release Ci 9.45E-05 1.68E-04 1.22E+01 E. Volume of waste released (prior to liters 1. 36E+07- 1.-76E+07 - 5.66E+00 dilution)
F. Volume of dilution water used liters 8.45E+10 7.09E+10 1.10E+01-during period 1578 075
TABLE 2B EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (YEAR) 1977 LIQUID EFFLUENTS Batch Mode Continuouw Mode
- III IV
' Nuclides Released Unit Quarter Quarter Quarter Quarter
, iodine-133 Ci 1.35E-02 3.82E-04 iodine-132 l Ci 5.64E-08 16.96E-07 l antimony-122 l Ci 2.29E-03 13.00E-03 l
. antimony-124 i Ci I3.38E-04 11. 83E-03 1 I cobalt-57 i Ci j4.92E-07 !8.53E-05 i cesium-136 Ci ll.19E-03 14.37E-04 cesium-138 '
Ci l1.62E-03 l <MDA cerium-144 l Ci !2.68E-03 <MDA yttrium-91m l Ci !7.17E-07 7.78E-07 tellurium-129m i Ci l2.60E-04 i <MDA i strontium-85 l Ci i3.71E-05 i <MDA l niobium-97m Ci ll.34E-04 <MDA I l zirconium-97 Ci i1.40E-04 ! <MDA l l tin-113 Ci ll.73E-05 i <MDA i I tin-117m '
Ci l 7.21E-05 1 <MDA I
- indium-113m Ci l2.65E-05 1 <MDA l barium-139 Ci !5.98E-04 i <MDA cerium-139 Ci l l .16E-04 1.04E-05 strontium-91 l Ci l5.76E-05 <MDA technitium-101 l Ci i2.03E-04 <MDA l tellurium-132 i Ci l1.83E-06 i <MDA i tungsten-187 Ci I <MDA j2.15E-04 i continued on Table 2B-1 Ci l l l
. Dissolved and Entrained Bases krypton-85 Ci l9.22E-03 <MDA krypton-85m Ci 1.89E-04 <MDA argon-41 Ci 6.32E-03 2.01E-03 xenon-131m C1 1.57E-03 <MDA xenon-133 Ci 7.55E-02 6.50E-03 xenon-135 Ci '
9.32E-03 2.01E-03 Total for Period Ci 1.02E-01 l9.52E-03 1578 076
- ~ ' ' ' '
TABLE 2B-1 EFFLUENI AND WASTE DISPOSAL SEMIANNUAL REPORT (YEAR) 1977 LIQUID EFFLUENTS Batch Mode Continuous Mode III IV Nuclides Released Unit Quarter Quarter Quarter Quarter strontium-89 C1 3.56E-06 1.77E-03 strontium-90 Ci 5.24E-07 6.30E-04
. cesium-134 Ci 6.33E-02 7.91E-02 cesium-137 C1 1.30E-01 1.98E-01 iodine-131 C1 3.97E-01 1.64E-02 cobalt-58 C1 1.06E-01 1.24E-01 cobalt-60 C1 1.41E-01 2.53E-01 iron-59 i Ci 8.53E-02 1.10E-01 zine-65 i C1 4.30E-02 5.94E-02 manganese-54 l C1 2.64E-01 4.15E-01 chromium-51 l C1 4.80E-01 2.64E-01 zirconium-niobium-95 Ci 2.83E-03 4.77E-03 molybdenum-99 Ci 1.02E-02 1. 50 E-03 technetium-99m Ci 1.04E-02 1.77E-03 barium-lanthanum-140 C1 2.10E-04 0.00 E400 cerium-141 C1 1.13E-05 8.33E-07 fluorine-18 Ci 1.21E-02 1.38E-07 sodium-24 C1 1.65E-01 2.98E-02 nancaqese-56 Ci 1.04E-03 8.07E-04 cooper-64 C1 2.87E-02 1.99E-02 arsenic-76 Ci 8.36E-03 4.19E-03 niobium-97 Ci 0.00E+00 1.13E-04 unidentified C1 2.00E-01 1.61E-01 Total for period (above) l Ci l 2.17 E+00 l 1. 7 7 E+00 l 1578 077
O MINIMUM DETECTABLE ACTIVITIES (uCi/ml)
- 1. For Liquid and Noble Gas Releases Ar-41 2.21E-06 Ba-139 8.92E-09 Ce-144 1.96E-07 Cs-138 2.26E-09 In-133m 3.69E-09 Kr-85 5.69E-06 Kr-87 4.76E-09 Nb-97m 2.49E-08 Sr-85 2.23E-08 Tc-101 1.80E-09 Te-129m 4.99E-07 Te-132 1.74E-09 Kr-85m 2.81E-08 Kr-88 5.34E-09 Sn-113 2.40E-09 Sn-117m 2.35E-09 Xe-133 6.08E-09 Xe-133m 1.13E-07 Xe-135m 2.73E-09 Zr-97-Nb-97 2.60E-08
- 2. For Iodine and Particulate Gas Releases Ba-La-140 3.45E-14 Ce-139 7.10E-15 Ce-144 5.49 E-14 Cu-57 5.65E-15 Cs-136 9.59E-15 I-135 3. 45 E-14 Sb-124 2.29E-14 Sn-117m 6.70E-15 .
Y-88 1.20E-14 Zn-65 3.66E-14 0 "/ 3, Zr-97-Nb-97 2.32E-14 i cJ 7 8
. . . TABLE 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (YEAR) 1977 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. Solid Waste Shipped Offsite for Burial or Disposal (Not irradiated fuel)
- 1. Type of waste Unit 6-month Est. Total period Error, %
- a. Spent resins, filter sludges, evaporated m3 7. 39EM2 bottoms, etc. C1 2.04E+03 1. 50E+01
- b. Dry compressible vaste, contaminated mJ 3.76E+02 equip, etc. Ci 1.51E+01 2.00E+01
- c. Irradiated components, control m3 0.00E+00 rods, etc. Ci 0.00E+00 0.00E+00 m3 0.00E+00 Ci 0.00E+00 0.00E+00
- d. Other (describe)
- 2. Esticate of major nuclide co= position (by type of vaste)
~
- a. + b. chromium-51 % 4. 31E+'31 manganese-54 % 2.37E+01 iron-59 % 6.2SE+00 cobalt-58 % 7.21E+00 cobalt-60 % 1.53E+01 zine-65 % 2.88E+00 cesium-137 % 1.43E+00
- c. N/A %
- d. N/A %
- 3. Solid Waste Disposition Number of Shioments Mode of Trensoortation Destination 124 Sole Use Chem. Nuclear Systems, Inc.
Barnwell, S. C.
B. Irradiated Fuel Shipments (Disposition)
Number of Shipments Mode of Transportation Destination 0 N/A N/A 1578 079 i
WORST CASE SITE DOSES RELATED TO AIRBORNE IODINE RELEASES Thyroid Dose due to Inhalation, mrem /6 Months at Worst Point on Site Boundary 1 Year Old 1.18E-01 4 Years Old 1.15E-01 14 Years Old 7.59E-02 Adult 1.02E-01 Thyroid Dose due to Milk Pathway, mrem /6 Months at Nearest Cow
- 1 Year Old 2.25E+01
- 4 Years Old 9.37E+00 14 Years Old 3.19E+00 Adult 2.52E+00 Thyroid Dose due to Eating Green Leafy Vegetables, mrem /6 Months at Worst Garden 1 Year Old 0.00E+00 4 Years Old 5.77E-01 14 Years Old 3.36E-01 Adult 3.55E-01
- There are no children of the 1-Year-Old or 4-Years-Old age group drinking milk from this cow.
According to data obtained from milk samples collected at this farm, the infant thyroid dose due to plant releases for the year 1977 is 2.45 mrem.
O A
1578 Ob'
S
SUMMARY
OF DOSES DUE TO LIQUID RELEASES Dose Due to Eating Fish Caught in Discharge Canal Whole Body 7.24E-05 mrem /6 months G.I. Tract 4.80E-04 nRem/6 months Thyroid 1.82E-04 mrem /6 months Bone 1.72E-02 mrem /6 months Shoreline Sediment Dose along Discharge Canal. 5.86E-05 mrem /6 months Ocean Swimming Dose 5.52E-06 mrem /6 months Radiological Impact on Man from direct radiation from the facility is negligible based on the results frem environmental TLD's.
1578 OlB1
AIR SUBMERSION SKIN DOSE, mrem /6 MONTHS .
Brunswick Steam Electric Plant July to December 31, 1977 Mi es Sector
.5 1.5 2.5 3.5 4.5 7.5 15 25 35 45 S 3.056E+00 7.272E-01 4.563E-01 3.551E-01 2.761E-01 1.611E-01 7.403 E-02 4.096E-02 2.757E-02 2.050E-02 SSW 2.520E+00 6.842E-01 5.001E-01 2.221E-01 3.006E-01 1.811E-01 8.521E-02 4.753E-02 3.209E-02 2.385E-02 SW 2.024E+00 3.983E-01 4.496E-01 3.363E-01 2.657E-01 1.571E-01 7.218E-02 3.981E-02 2.671E-02 1.977 E-02 WSW 1.809E+00 5.507E-01 L 918E-01 2.908E-01 2.283E-01 1.343E-01 6.188E-02 3.436E-02 2.320E-02 1.728E-02 W 1.246E+00 3.755E-01 2.735E-01 2.112E-01 1.112E-01 1.084E-01 6.019E-02 3.112E-02 2.198E-02 1.665E-02 WNW 9.377E-01 2.998E-01 2.209E-01 1.726E-01 1.409E-01 8.942E-01 1.023E-01 2.589E-02 1.787E-02 1.348E-02 NW 6.922E-01 3. 925 E-01 1.819E-01 1.446E-01 1.195E-01 7.762E-02 4.026 E-02 2.407E-02 1.694E-02 1.297E-02 NNW 5.338E-01 1. 869 E-01 9.651E-01 1.213F-01 7. 727 E-01 6.572E-02 3.383E-02 1.993 E-02 1.389E-02 1.057E-02 N 8.367E-01 3.209E-01 2.722E-01 2.211E-01 1.824E-01 1.146E-01 5.207E-02 3.078E-02 2.075E-02 1.539E-02 NNE 1.428E+00 4.035E-01 4.968E-01 3.863E-01 3.092E-01 1.472E-01 9.016E-02 4.580E-02 3.051E-02 2.246E-02 NE 1.667E+00 8.086E-01 6. 540 E-01 5.135E-01 4.135E-01 2.465E-01 1.135E-01 6.173E-02 4.096E-02 3.007E-02 ENE 2.343E+00, 6.791E-01 5.280E-01 4.146E-01 3.374E-01 2.087E-01 9.938E-02 5.531E-02 3.720E-02 2.766E-02 E 2.030E+00 5.204E-01 3.819E-01 2.920E-01 1.335E-01 1.442E-01 6.938E-02 3.929E-02 2.680E-02 2.011E-02 ESE 2.275E+00 5. 342 E-01 3.652E-01 2.685E-01 2.118E-01 1.274E-01 6.094E-02 3.459E-02 2.366E-02 1.776E-02 SE 2.650E+00 6.171E-01 3.944E-01 2.773E-01 9.406E-01 1.217E-01 5.594E-02 3.108E-02 2.139E-02 1.606E-02
[}( SSE 4.463E+00 1.001E+00 6.403E-01 4.463E-01 3.386E-01 1.898E-01 8.447E-02 4.625E-02 3.181E-02 2.305E-02 N
Maximum Off-Site Air Submersion Skin Dose, mrem /6 Months 3.056E+00 CD Co N
AIR SUBMERSION W110LE BODY DOSE, mrem /6 MONTilS Brunswick Steam Electric Plant -
July to December 31, 1977 -
Miles Sector 2.5 3.5 4.5 7.5 15 25 35 45
,a 1.5 S 1.278E+00 2.548E-01 1.350E-01 8.921E-02 6.548E-02 3.493E-02 1.487 E-02 7.880E-03 5.262E-03 3.875E-03 SSW 1.055E+00 3.262E-02 1.156E-01 7.751E-02 5.743E-02 3.110E-02 1.342E-02 7.205E-03 4.783E-03 3.520E-03 SW 8.109E-01 3.106E-02 7.913E-01 6.142E-02 4.521E-02 2.414E-02 1.020E-02 5.404E-03 3.558E-03 2.604E-03 WSW 7.156 E-01 2.729E-02 8.096E-02 5.376E-02 3.953E-02 2.109E-02 8.643E-03 4.762E-03 3.147E-03 2.112E-03 W 4.914E-01 1.055E-01 5.599E-02 3.738E-02 2. 7 74 E-02 2.050E-02 6.663E-03 3.640E-03 2.439E-03 1.608E-03 WNW 3.517E-01 7.437E-02 3.935E-02 2 535E-02 1.959 E-02 1.075E-02 4. 715 E-03 2.584E-03 1.730E-03 1.281E-03 NW 2. 646 E-01 5.652E-02 3.034E-02 2.048E-02 1.539 E-02 8.611E-03 3.912E-03 1.018E-02 1.496E-03 1.122E-03 NNW 2.300E-01 5.136E-02 2.811E-02 1.917E-02 1.442E-02 8.071E-03 3.638E-03 1.060E-03 1.350E-03 1.004E-03 N 3.456E-01 7. 762 E-02 4.362E-02 3.007E-02 2.268E-02 1.257E-02 5.469E-03 2.922E-03 1.925E-03 1.408E-03 NME 5.673E-01 3.273E-02 7.348E-02 5.000E-02 3. 723 E-02 1.04CE-02 8.459E-03 4.443 E-03 2.903E-03 2.112 E-03 NE 7.065E-01 1.649E-01 9.425E-02 6.493E-02 4.563E-02 1.414E-02 1.136E-02 5.989E-03 3.918E-03 2.852E-03 ENE 9. 830 E-01 2.072E-01 1.134E-01 7.684E-02 5.738E-02 3.055E-02 1.360E-02 7.278E-03 4.812E-03 3.530E-03 E 8.503E-01 1.738E-01 9.340E-02 6.253E-02 1.187E-01 2.515E-02 1.089E-02 5.867E-03 3.903E-03 2.881E-03 ESE 9.527E-01 1.896E-01 1.006E-01 6.663E-02 4.909E-02 2.642E-02 1.140E-02 6.149E-03 4.096E-03 3.025E-03 SE 1.138E-01 ,2.154E-01 1.135E-01 6.652E-02 5.455E-02 2.901E-02 1.238E-02 6.655 E-03 4.431E-03 3.275E-03 SSE 1.858E+00 3. 640E-01 1.925E-01 1.268E-01 9.273E-02 4.920E-02 2.090E-02 1.119E-02 7.429E-03 5.478E-03 Maximum Off-Site Air Submersion Whole Body Dose, mrem /6 Months 1.278E+00 N
CO CD CO Lia
AIR SUBMERSION POPULATION DOSE (WHOLE BODY), Man Rem /6 MONTHS .
~
Brunswick Steam Electric Plant July to December 31, 1977 Miles Sector
.5 1.5 2.5 3.5 4.5 7.5 15 25 35 45 S 6.39E-03 1.02E-02 9.41E-02 0 0 0 0 0 0 0 SSW 0 5.25E-03 2.38E-01 0 5.80E-03 0 0 0 0 0 SW 2.59E-02 1.99E-03 0 4.92E-04 0 0 0 0 0 0 WSW 0 1.83E-03 6.48E-04 1.72E-04 1.98E-04 3.65E-03 0 0 3.37E-03 4.80 E-03 W 3.93E-03 3.48E-03 8.96E-04 0 0 1.03E-03 8.42E-03 1.44E-02 1.22E-02 1.10E-02 tani 5.63E-03 5.95E-04 0 0 0 2.17E-03 6.39 E-03 4.53E-03 6. 23 E-03 1.81E-02 NW 2.12E-03 0 0 0 0 1.32E-03 7.74E-03 2.86E-02 5.39E-03 6.36E-03 NNW 4.60E-03 2.05E-04 0 0 0 1.23E-03 4.27E-03 3.78E-03 3.58E-03 3.44E-04 N 6.91E-03 0 0 0 0 1.14E-U3 5.29E-02 2. 97 E-02 7.09E-03 9.19 E-03 NNE O 5.24E-04 0 0 0 2.88E-03 4.39E-01 1.02E-01 8.42E-03 4.18E-03 NE O 3.30E-03 0 0 0 3.05E-02 0 0 4.78E-04 7.01E-03 ENE O 2.49E-03 0 0 0 2.40E-03 0 0 0 0 E O 2.78E-03 0 0 0 0 0 0 0 0 ESE O 3.98E-03 0 0 0 0 0 0 0 0 SE 4.10E-03 2.58E-03 0 0 0 0 0 0 0 0 SSE O 1.46E-03 0 0 0 0 0 0 0 0 N
CO CD CO
-4
1974 POPULATION DISTRIBUTION ,
Brunswick Steam Electric Plant July to December 31, 1977 Distance Miles Sector --
.5 1.5 2.5 3.5 4.5 7.5 15 25 35 45 S 5 40 697 0 0 0 0 0 0 0 SSW 0 161 2,058 0 101 0 0 0 0 0 SW 32 64 0 8 0 0 0 0 0 0 WSW 0 69 8 32 5 173 0 0 1,071 2,275 W 8 33 16 0 0 51 1,264 3,967 5,000 6,814 WNW 16 8 0 0 0 124 1,356 1,754 3,600 14,100 NW 8 0 0 0 0 153 1,979 2,407 3,600 5,670 NNW 20 4 0 0 0 153 1,173 3,570 2,652 3,427 N 20 0 0 0 0 91 9,690 10,180 3,682 6,528 NNE O 16 0 0 0 275 51,918 22,950 2,900 1,978 NE O 20 0 0 0 2,160 0 0 122 2,458 f.NE O 12 0 0 0 785 0 0 0 0 E O 16 0 0 0 0 0 0 0 0 ESE O 21 0 0 0 0 0 0 0 0 SE 36 12 0 0 0 0 0 0 0 0 SSE O 4 0 0 0 0 0 0 0 0 Ln N
CO CD CO LJ1