ML18029A469
| ML18029A469 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 12/31/1983 |
| From: | Jones G TENNESSEE VALLEY AUTHORITY |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| NUDOCS 8504100514 | |
| Download: ML18029A469 (37) | |
Text
EFFLUENT AND MASTE DISPOSAL SEMIANNUAL REPORT SUPPLEMENTAL INFORMATION SECOND HALF 1983 1.
Regulator Limits a.
Fission and Activation Gases:
( 1)
Instantaneous-Q~
0.13
+
<?
1.46 Q1
= release rate from building exhaust vents in Ci/sec.
Q2
= release rate from main stack in Ci/sec.
(2)
Quarterly - ~ 0.10 Ci/sec.
as average b.
h c. Iodines and particulates, half-. lives )8 days
( 1)
Instantaneous-Q~
+
Q~
0 33 44 Q3
= release rate from building exhaust vents in uCi/sec.
Q4
= release rate from main stack in uCi/sec.
(2)
Quarterly - +0.80 mCi/sec as average d.
Liquid effluent:
1 x 10-7 uCi/ml (ref.
10 CFR 20, Appendix B, note 3C, Table II, column 2).
e.
Tritium (1)
Liquid - ~.OE-3 uCi/cc (ref.
10 CFR.20, Table II, column 2).
(2)
Airborne +2.0E-7 uCi/ml (ref.
10 CFR 20, Table I, column 2).
8804i005i4 BSi23i I
PgR ADQCV. O.OOO>>~
R PDR
P
~
~
~
EFFLUENT AND HASTE DISPOSAL SEMIANNUAL REPORT SUPPLEMENTAL INFORMATION (CONTINUED)
SECOND HALF 1983 2.
Maximum Permissible Concentration a.
Fission and Activation Gases:
Not Applicable b.
Not Applicable c.
Particulates, half-lives >8 days:
Not Applicable d.
Liquid effluents:
sum of individual MPC ratios g 1
( ref.
10 CFR 20, Appendix B, note 1)
\\
3.
Average Energy - Not Applicable Measurements and Approximations of Total Radioactivity a.,
b.
& c.
F ss n
d A t n
G s s I d n s nd P
cu s
Airborne effluent gaseous activity is continuously monitored and recorded;
'dditionally, grab samples ar e taken and analyzed monthly to determine specific radionuclide activity concentrations.
Stack and building vent effluent flow rates are calculated once a shift based on the configuration of operating exhaust fans.
The flow rate data is consolidated weekly to determine the volume of "airborne effluents released from the plant.
Charcoal and particulate samples are taken and analyzed at least weekly to determine specific activity concentrations.
The total activity released from the plant is then calculated by taking weekly activity concentration values and multiplying them by the weekly airborne effluent volume.
Allowance is made for a plus or minus one sigma counting error associated with gamma isotopic analyses.
I
'i
EFFLUENT AND MASTE DISPOSAL SEMIANNUAL REPORT SUPPLEMENTAL INFORMATION (CONTINUED)
SECOND HALF 1983 Measurements and Approximations of Total Radioactivity (Continued)
Gross
- beta, gamma and total gamma istopic activity concentrations are determined on each batch of liquid,effluent prior to release.
The total curie content of a released batch is determined by multiplying the highest of the above three activity concentrations by the total volume discharged.
The total activity released during a month is then determined by summing the activity content of each batch discharged during the month.
Allowance is made for plus or minus one sigma counting error associated with the total gamma isotopic analyses.
a Third a.
~Luud QuueC Fourth Quut~
( 1)
Number of batches released (2)
Total time period for batch releases (3)
Maximum time period for a batch release (4)
Average time period for batch releases (5)
Minimum time period for batch releases 83 32933 396.78 169.8 148 Each 57207 1515 Minutes Minutes 60 Minutes 386.53 Minutes (6)
Average stream flow during period of release of effluent into a flowing stream1--
b.
~sou None 1To be supplied by others.
EFFLUENTS AND WASTE DISPOSAL SEHIANNUAL REPORT SECOND HALF 1983 LIQUID EFFLUB1TS - SUMMATION OF ALL RELEASES A.
t r
Third Fourth
~n
~u~
~u
~Frrrr 1.
Total Releases (1) 2.
Average Diluted Conc. During Period Curies
- 6. 96E-01
., 1.90E+00
+1.50E+01 uCi/ml 5.80E-09 6.58E-09 B
3.
Percent of Applicable Limit 3.48E 00 9.50E+00 1.
Total Release Curies 4.90E+00 '.28E'+00
+5.00E+00 2.
Average Diluted Conc. During Period uCi/ml 4.08E-08 3.22E-08 3.
Percent of Applicable Limit
.(3E-03 uCi/nl) 1.36E-03 1.07E-03 C.
ss n
En ained D.
1.
Total Release 2.
Average Diluted Conc.
Period Percent of Applicable (6E-06 uCi/ml) s 1 h a
c During Limit Curies (4.13E-02 1.86E-01.
~+.80&00 uCi/ml 3.44E-10 6.44E-10 5.74E-03 1.07E-02 E.
1.
Total Release ume of Wa te e eas Curies 2.36E-04 1.44E-04
+1.70&01 (before dilution)
F.
oumeofD u
1 e f P
Liters 6.00&06 Li.ters 1.20E+11 1.48E+07
+5.00E+00 2.89E+11
+1.00E+01 (1/Based on pre-release anal'yses which are not decay corrected.
~steno EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT LIQUID.RELEASES FOR SECOND HALF 1983 BATCH MDE Third (1)
~ua ~te Four th (1)
Quur~e 14.
Technetium-99m 15.
Barium-Lanthanum-140 16
~
Cerium-141( 2) 17.
Sodium-124 1.
Strontium-89(3) 2.
Strontium-90( 3)
II 3 ~
Cesium-134 Cesium-137 5 ~
~
Cobalt-58 Cobalt-60 8.
Iron-59 9.
Zinc-65 10 'anganese-54 Chromium-51 12 'irconium-Niobium-95 13 'olybdenun-99 4.21E-03 1.20E"03 1.60E-01 1
4.24E-02 I
MDA 8.79E-02 1
~ 76E-03 4 '5E-03 7 '1E-04 1.76E-03 1.76E-03 MDA
- 3. 41E-02 5 '4E-02 1.33E-03 6 '9E-04 4.79E-Ol 5 '6E-01 1 '6E-02 3 '0E-04 7 '5E-02 MDA 4 '5E-01 3 '7E-03 2.66E-03 5.86L-04 2 ~ 71E-04 2.71E-04 1 '8E-04 1 '2E-01 2 '4E<<02
(
MDA Fluorine-18 18.
(
~ 75 (1)Quantities listed are in curies.
(2)Calculated by multiplying Cs134 by a factor of 0.2133.
(Established by ratio CE141/CS134 in March 1979).
A new ratio of 0.1570 was established in December 1982.
For conservatism, use of 0.2133 factor will continue.
(3)Predicted estimation of release.
0 J
~
~so~o EFFLUENT AND MASTE DISPOSAL SEMIANNUAL REPORT LIQUID RELEASES FOR SECOND HALF 1983 BATCH MODE Third(1)
~u~e Fourth( 1)
(~u~e e
o e
u d
o u d 1.
Xenon-133 2.
Xenon-135 3.
Iodine-133 Cesium-136 5,
Manganese-56 6.
Antimony-122 7.
Antimony-124
Copper-64 9.
Arsenic-76 10.
Arsenic-74 11.
Iodine-135 12.
Bromine-82 13.
Silver-110m 14.
Antimony-125 15.
Samariam-153 MDA MDA 4:77E-03 MDA MDA 1.09E-03 1.18E-04 3.22E-03 MDA 2.26E-03 2 '5E-03 MDA MDA MDA (1) Quantities listed are in curies.
EFFLUENT AND WASTE DISPOSAL SEHIANNUAL REPORT SECOND HALF 1983 SOLID WASTE AND IRRADIATED FUEL SHIEHENTS A.
'Solid Waste Shipped Off-Site for burial or disposal (not irradiated fuel) 1.
Type of Waste n t Third Fourth
~u>p~
a.
Spent resin, filter sludges, etc.
b.
Dry compressible waste contaminated equip., etc.
m3 224.73 Ci 1345 817H drums 1730 (12975 ft )
Ci 287.0 180.1 694.24 668 (5010 ft )
79 05 c.
Irradiated Components, control rods, etc.
d.
Other (describe)
Boxes NA Boxes Ci NA 338 (28411 ft )
20.7 NA 240 (22888 ft )
24.64 2.
Estimate of major nuclide composition (by type of waste) rte ou te a.
1.
Chromium-51 2.
Zinc-65 3.
Iodine-131 4.
Cesium-137 5.
Cesium-134 6.
Cobalt-58 7.
Cobalt-60 8.
Zirconium-95 9.
Niobium-95 16.13 (217 / 1345) 39.33 (529 / 1345) 0.33 (4.48/
1345) 13.01 (175 / 1345) 11.30 (152 / 1345) 0.88 (11.8/
1345) 9.22 (124 / 1345) 0.20 (2.68/
1345) 0.07
(.926/
1345) 16.28 (113 / 694) 46.60 (323.7/ 694) 0.90 (6.21/ 694) 9.82 (68.13/
694) 8.52 (59.10/ 694) 0.72 (5.27/ 694) 8.15 (56.54/ 694) 0.15
( 1.10/ 694) 0.56 (3.91/ 694)
EFFLUENT AND WASTE DISPOSAL $2GANNUAL REPORT SECOND HALF 1983 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS (CONTB1UED) 2.
Estimate of major nuclide composition (by type of waste)
(Continued) 12.
Strontium-90 13.
Manganese-50 14.
Silver-110M 15.
Iron-59 16.
Other Nuclides a.
10.
Lanthanun>>140 11.
Antimony-124 0.10 (1.40/
1345) 0.01 (0.190/1345) 0.01
( 0.192/1345) 1.09 (14;7/
1345) 2 53 (34 0/
1345) 0.05 (0.728/1345) 5 73 (77 12/1345) ou 0.02 (0.109/ 694) 0.00 (0.0/ 694) 0.01 (0.082/ 694) 1.12 (7.8 / 694) 1.97 (13.68/ 694) 0.11, (0.80/ 694) 4.98 (34.57/ 694) b.
1.
Chromium-51 2.
Zinc-65 3.
Iodine-131 4.
Cesium-137 5.
Cesium-134 6.
Cobal t-58 7.
Cobal t-60 8.
Zirconium-95 9.
Niobium-95 7.63 (21.9/ 287) 72.12 (207 / 287) 0.86 (2.48/ 287) 5.89 (16.9/ 287) 4.01 (11.5/ 287) 0.46 (1.31/ 287) 6.31 (18.1/ 287)
- 0. 17
( 0.494/287) 0.08 (0.236/34.1) 0.15 0.53 (0.119/ 79)
(0 423/ 79) 25.63 420.25/ 79) 42.37 (33.48/ 79) 0.59 (0.46/ 79) 6.98 (5.51/ 79) 6.15 (4.86/ 79) 0.49 (0.387/ 79) 6.32 (4.99/ 79)
~ 1
~
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SECOND HALF 1983 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS (CONTINUED) 2.
Estimate of ma)or nuclide compositon (by type of waste)
(continued) ou h
b.
10.
Lanthanum-140 11.
Antimony-124 12.
Strontium-90 13.
Manganese-54 14.
Silver-110M 15.
Iron-59 16.
Other Nuclides 0.54 (1.54/ 287) 0.02 0.25 0.78 0.82 (0.712/
187)
(0.715/ 287)
(2.23/ 287)
'I (2.34/ 287) 0.05 (0.150/ 287) 0.58 (1.67/ 287) 0.03 (0.024/ 79) 0.0 (0.0 / 79) 0.008 (0.006/ 79) 1.0 (0 79/ '79) 2.03 (1.6 / 79) 0.28 (0.221/ 79)
'.45 (5.883/ 79) d.
1.
Chromium-51 2.
Zinc-65 3.
Iodine-131 4.
Cesium-137 5.
Cesium-134 6.
Cobal t-58 7.
Cobal t-60 8.
Zirconium-95 9.
Niobium-95 16.23 (3.36 / 20.7) 63.77 (13.2 / 20.7) 1,66 (0.344/ 20.7) 7.78 (1.61 /'0.7) 5.99 (1.24 / 20.7) 0.67 (0.138/ 20.7) 8,94 (1.85 / 20.7) 0,11 (0.0237/20.7) 0.02
( 00327/20 7) c.
Irradiated Components, Control Rods, etc.
None 9.74 (2.397 / 24.6) 59.6 (14.67 / 24.6) 0.68 (0.166 / 24.6) 8.72 (2.144 / 24.6) 7.48 (1.841 / 24.6) 0.41 (0.10 / 24.6) 8.10 (1.98 / 24.6) 0.002 (0.0006/ 24.6) 0.008 (0.002 / 24.6)
0 I
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT 1
SECOND HALF 1983 SOLID WASTE AND IRRADIATED FUEL SHIFHENTS (CONTINUED) 2.
Estimate o'f ma)or nuclide composition (by type of waste)
(continued) ou d.
10.
Lanthanun-140 11.
Antimony-124 12.
Strontium-90 13.
Manganese-54 14.
Silver-110M 15.
Iron-59 16 ~
Other Nuclides 3.
Solid Waste Dispositi.on 1.59 0 03 (0.329/ 20.7)
(.00609/ 20.7) 3.22 (0.667/ 20.7) 0.73 (0.152/ 20.7) 0 04
( 00749/20.7)
'5.
0.01
(.00222/ 20.7) 0.97 (0.200/ 20.7) 0.11 (0.027/ 24.6) 0.0 (0.0 / 24.6) 0.01 (0.002/24.6) 0.88 (0.22 / 24.6) 0.66 (0.163/ 24.6) 0.12
( 0.029/ 24.6)
,2.43 (0.60 / 24.6) u e
Third
~u>~te Four th
(~u~e Mod nso o
stnto d
ue Nu of 41 27 Sole Use Tr uck Sole Use Truck nt (disposition) ode o
ans o t t o
- Barnwell, SC
- Richland, WA est Third Quatre<
NA Fourth
~ua t~e NA NA NA
4l
EFFLUENT AND MASTE DISPOSAL SEHIANNUAL REPORT SECOND HALF 1983 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES u
0 e e Fourth Q<~
A.
Fission and Activation Gases 1.
Total Releases Ci 3.96& 04 2.
Avg. release rate for period uCi/sec.
5.04E+03
<2.01E+05
<2.56'4 3.
Percent of technical specification limit B. /~i~
1.
Total Iodine-131 Ci 2.
Avg. release rate for period uCi/sec.
3.
Percent of technical specification limit 1.01'1 6.08E-03 7,74E 04 1.93E-01 5.11&-01 1.29E-02 1.64E-03 4 ~ 10F 01 C.
u ate 1.
Particulate with half-lives )8 days Ci 8.14E-03 2.
Avg. release rate for period uCi/sec.
1.04E-03
<5.69E-03
<7. 24E-04 3.
Percent of technical specification limit Gross alpha radioactivity D.
~tium
~
Ci 2.59E-01
<3.35E-06 1.81E-01
<2.02E-04 1.
Total release Ci 1.16E+Ol 2.
Avg. release rate for period uCi/sec.
1.48E+00 2.68E 00 3.41E-01 3.
Percent of technical specification limit Ground level releases 5.
Elevated release Ci Ci 1.27'0 1.11Et01 5.47E-01 V
3.68E-01 2,59E+00 9.25E-02 (1)
Repor ting period 182 days
~
~
EFPLUB/T AND MASTE DISPOSAL SEMIANNUAL REPORT SECOND HALF 1983 GASEOUS EFFLUENTS - ELEVATED RELEASE Third
~n Quu~e Fourth qua.~
Krypton-85 Krypton-85m Krypton-87 Krypton-88 Xenon-133 Xenon-'135
. Xenon-135m Xenon-138 Others (specify)
At gon-41 Unidentified Ci Ci Ci Ci Ci Ci Ci Ci Ci 2.04'3 5.82'.03 3.20E+03
'1.07& 04 1.54E+04 8.19$.02 MDA MDA 8.94E+02 NA MDA 1.71E+04
<1.35E+04 2.10E+04 1.44E+05 4.65& 03 MDA MDA
<1.66B 02 NA o a o
e Ci 3.88&04
<2.00E+05 2.
~)~es Xodine-131 Xodine-133 Xodine-135 Tota fo e
Ci Ci 5.62E-03 1.24E-02 1.80E-02 1.13E-02
<1.34E-02 MDA
<2.47E-02
F
~
~
3 ~
EFFLUBIT AND >1ASTE DISPOSAL SEMIANNUAL REPORT SECOND HALF 1983 GASEOUS EFFLUENTS - ELEVATED RELEASE (Continued)
Third Four th
- gnn, Quy~~e Qu~~
Strontium-89 Strontium-90 Cesium-134 Cesium-137 Barium-140 Zirconium-95 Niobium-95 Cobal t-58 Manganese-50 Zinc-65 Iron-59 Cobal t-60 Ci Ci 2.64E-05 8.47E-06 Ci Ci Ci Ci MDA MDA MDA 3.76E-05 Ci Ci Ci MDA MDA MDA Ci MDA Ci '
MDA Ci 4'11E-05 2.82E-04 6.17E-07 MDA MDA MDA MDA MDA MDA
<].64E-04 MDA MDA MDA Others (specify)
Lanthanum-140 fo
@~tom (1)Predicted estimation of release Ci Ci Ci 3.51E-04 5.47E-01 MDA
<4.47E-04 9.25E-02
EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SECOND HALF 1983 GASEOUS EFFLUENTS - GRCUND LEVEL RELEASES Third
~n Fourth Qual f:ee Krypton-85 Krypton-85m Krypton-87 Krypton-80 Xenon-133 Xenon-135 Xenon-135m Xenon-138 Others ('pecify)
Ci MDA Ci MDA Ci MDA Ci MDA Ci
<'DA Ci Ci 3 59E+02 Ci 3.55E'+02 MDA MDA MDA MDA 4.24K 02 1.95E+02 MDA
'DA Argon-41 Unidentified Ci Ci NA MDA NA or e
Ci
- 7. 14&.02
<6.18&02 2.
~oops Iodine-131 Iodine-133 Iodine-135 fo Ci Ci 4.63E-04 1.04E-03 MDA 1.50E-03 1.62E-03
<1.43E-03 MDA
<3.05F 03
t P
EFFLURTS AND MASTE DISPOSAL SEMIANNUAL REPORT SECOND HALF 1983 GASEOUS EFFLUENTS - GRCUND LEVEL RELEASES (Continued)
Third Fourth
~n x
3.
Strontium-89 Strontium-90 Cesium-134 Cesium-137 Barium-140 Zirconium-95 Niobium-95 Cobalt-58 Manganese-50 Zinc-65 Iron-59 Cobalt-60 Others (specify)
Lanthanum-140 Ci Ci Ci Ci Ci Ci Ci Ci Ci 2.21F 03 2.42E-05 1.76E-04 5.24E-07 3.45E-04 4.60E-04 4.44E-05 5.36F 05
<5.73E-04
<7.15E-04 MDA MDA 1.23E-05 1.32E 04 1.20E-03 MDA 2.80E-03
<7.65E-06
<2.52E-03 MDA 1.41E-03 3.43E-05 MDA 3.19E-04 '1.26F 06'or Ci 7 79F 03
<5.25E-03 4,
g~~ura Predicted estimation of releases.
(1)
Ci 1.11& 01 2.59Et 00
I
Table 10 Browns Fer Nuclear Plant - Individual Doses From Gaseous Effluents Third uarter 1983
~EEfluen Noble gases
~Pa thwa T Air dose P Air dose Total body2 Skin~
Iodines/Particulates Guideline*
30 60 15 45 Point Hax. Exp.~
Hax. Exp.~
Residences Residences Dose Oalg mrad 0.34 mrad 0.10, mrem 0.16 mrem Bone (critical organ) 45 Real Pathway4 0.30 mrem Breakdown of Iodine Particulate Ex osures mrem Vegetable Ingestion Beef Ingestion5 Inhalation Ground Contamination Total Child 2.85 x 10 9.59 x 10 4
4.42 x 10
'.33 x 10 2
3.00 x 10 Adult 1.20 x 10 i 8.55 x 10 2.87 x 10 4
1.33 x 10 2
1.34 x 10 Pe ynnuq$ guide)ines are defined by Appendix I to 10 CFR 50.
+e mqgimqy exposure point 2.
Poop from air submersion.
3.
+e maximum exposure point 4.
Qeceptog is at 1750 meters Qy gyyiyqg exposure point is at 6100 meters in the W sector.
is at 7925 meters in the N sector.
in the NNW sector.
is at 1375 meters in the E sector.
36
Table ll Browns Fer Nuclear Plant - Individual Doses From Gaseous Effluents Fourth uarter 1983 Effluent
~Pathwa Noble gases T Air dose P Air dose Total body~
Skin~
Iodines/Particulates Guideline*
30 60 15 45 Point Hax. Exp.
Hax. Exp.
Residences Residences Dose 0.39 mrad 0.85 mrad 0.14 mrem 0.24 mrem Thyroid (critical organ) 45 Real Pathway4 0.04 mrem Breakdown of Iodine/Particulate Ex osures (mrem)
Vegetable Ingestion Beef Ingestion Inhalation Ground Contamination Total Child 2.29 x 10 2
2.73 x 10
~
7.37 x 10
~
1.73 x 10 2
4a12 x 10 2
Adult 1.09 x 10
~
2.58 x 10
~
3.75 x 10
~
1.73 x 10
~
2.88 x 10 2
he annual guidelines are defined by Appendix I to 10 CFR 50.
1.
The maximum exposure point is at 6100 meters in the NW sector.
2.
Dose from air submersion.
3.
The maximum exposure point is at 4425 meters in the WNW sector.
4.
Receptor is at 3225 meters in the NW sector.
5.
The maximum exposure point is at 2275 meters in the NW sector.
37
Table 12 Gaseous Effluent Doses - Po ulation RFN 3RD QUARTI.P 1983 SUPINATION OF POPULATION DOSES INFANT LIVER CHILD TrE9 ADULT TOTALS INF ANT EONC CHILD TrfN ADULT TOTALS SU 4 NC 1 5 I0's SROUV9 IN<AL4TIni CnN WILV OEEF I NGCST ION VEG INGESTION 10E "
4 ~ 43C 91 2 ~ 82C fl I 31E 00 2
10
+00 1
61E 03 1
01C 9?
6 ~ 4QC 03 2 ~ 96C-02 4 ~ 77C-0?
3 ~ 72E-03
. 3 ~ 51r-C2 1 ~ 46E-GP 4 <1C-02 1 ~ 02r-01 3 ~ 90r 04 1 ~ 'TTE-03 4 ~ 40E-04 1 ~ 72E-03 3 <2f-03 0 ~ 00E+Cni 3 ~ 25E-04 1 ~ 66C-04 1 ~ DIE-"3 I ~ 59C-93 0 ~ 00F+99 2 ~ 33C-04 1 ~ 215-04 7 12C-0 ~
I 37f-93 7 ~ 19C-02 4 ~ 43L-Gl 2 ~ 62E 01 I ~ 3IC+GC 2 IOE400 lidlf G3 1 ~ Olf-02 6'0E 03 2 '6E-02 4 '7f.
C2 4 ~3IE-05 9 '0C 04 4il3C 04 1 ~ TSE 03 3 '4C~03 9 '9C-04 4 '4E-03 1 ~ 06E-03 4 'RE-03 1 ~ 01C 02 0 ~ OOE+CO 4 '+f 04 I ~ 62C-04 9 '6C 04 I 53E 03 Gi90Ei90 3 '2E-G3 1 ~ 55C-C3 9 ~ 24E-03 I ~ 43f CE TOTAL HAN-REH
'7'7C 02 4 'OE 91 3 ~ 04C Ol I 39C+00 2'6Ci 70 7 ~ 36C-92 4 ~ 62E 01 2 ~ 91E 01 1 ~ 3SC+00 2 ~ lff~ 00 bPN
- 4083 SUHHATION OP POPULATION DOSES INFAN'I THTROI 0 CHILD TE EN ADULT TOTALS INFANT TOTAL bODT CHILD 7FEN ADULT TOTALS 5VAHERSION 1 ~ 37E-01 8 53E-01 5 ~ 43E-01 2 ~ 51Et00 4 ~ 05K<00 GROUND 2 ~ 89E 03 1 ~ 80E 02 1 ~ 1SE 02 5 ~ 31E 02 8 ~ 54E 02 CON HILA 1 ~ 70E-02 4 ~ 36E-02 1 ~ 16E-02 4 ~ 39E-02 1 ~ 16E-01 bEEP INGESTION 0 ~ OOE>00 S ~ 43E-04 2 ~ 32E-04 1 ~ 42E-03 2 ~ 20E-03 VKG INGESTION 0 ~ DDE>00 5 '5K-03 2 '0E-03 1 '3K-02 2 '9E-02 INHALATION 2 ~ 95E-04 3 ~ 02E-03 1 ~ 14E-03 4 ~ 35E-03 8 ~ 81E-03 0 ~ ODK+OC 8 '2E-05 d 42E-05 5 '2K-04 d 87K-04 1 ~ 37C 01 8 ~ 53E 01 5 ~ 43K 01 2 ~ 51E400 4 ~ OSE+00 2.89E-03 1 ~ 80E-02 1 ~ 15E 02 5 ~ 31E-02 8+54K-02 2 ~ 81E-03 3 ~ 33E-02 1 ~ 06E-02 3 ~ 53E-02 8 ~ 21E-02 8 ~ 48E-05 4 ~ 13E-04 2 ~ 13E-04 1 ~ 20E-03 1 ~ 91E-03 0 ODE400 9 ~ 65E-05 8 89E-05 8 41E-04 1 ~ 03E-03 TOTAL HAN-REH 1 '7K-01 9'3K 01 5,d98-01 2 63K<00 4'8K<00
]+43K 01 9 'SE 01 SodSE 01 2 '1K<00 4 22E>00
Table 13 Li uid Effluent Doses Brovns Per Nuclear Plant Routine Releases
.Third Ouarter 1983
~ WEgt~jf GI TRACT icccc THYROID c cccccc ~
tt TOTAL'bODY:,
I YE ccccc siss '"
tcsc r
'T V
tHREH)&7" f '.:';.:
=
4 2E-03
~v P, q
AH R H:~',.>>
~
~
~
E c
c
~
-0 6 'E-OC 6 ~
5 'E-03
.4.2E-03
""i.i. 5 'E-03 k
~ ~
42E 03 fc Wr r
g>>Pry "A,XI.
Lgk bf PgMlJH IHSIYIOVAKREH) 2 'E-01 3 'E-03 Cr9E-02 C ~ SE 02 2'E-0
<~+@44 b E-02-!
v ~
lro TEHHESSEE RIVER.POPULATIOH,IHAN-REH) 2 ~ 2Ei01 1 ~ 1Et00 2 ~ OE+01 2r OEi01
~
irt-
~
3 ~ CEy01 2 ~ OEy01'
.c c i> t~ ~j,Qgtfi I
~
RECRERTIOH cia'VPAVic ~
- i'1)g~:i. i:
r r AW++VP+i'cr>>pi
'Pi Per.Pi q t g
~
~ r t>le-iQY)POPULATIO110(HAH R EH)
,'I)'e) IH llATER INDIVIDUAL-'rtMREH) 2 1E-01 6 'c-GC 1 ~ o E-01 5 ~ SE-OC 1
6E-01 5 'E-04 1 'E-01 c ~ 6E-04 1 ~ 6E-01-,.$1$>>$2i 2E 01'.EE-04
-'5"o 6.7E-OC
.rROPULAT ION (HAH Rck) r Cc r3 1.12-03 USE-04 1.1c 03 9 ~ bE-04 1,4E-03-',
IVi.- TOTAl. ':
A ~
MAXIMUM IHOIYIOVAL CH LO t",9=".)
2 ~ 6E-01 USE 02 7.3E-02 7.3E-02 3 ~ OE-01, 7>> 7E-02 C ~
TEHHESScc RIY.R POPULATION tHCN RPN)
= F 22>31
~ 4 c
1 ~ )c+nl 7.0bt01 I
~ ~
~
7 'c+01 3.co+01 2>01 0
<<2 1 02E 02 = 1.02 X 10
1
c Table 14 Li uid Effluent Doses Brogans Perry Nuclear Plant Routine Releases Pourth Ouarter 1983 5)
ST PLTliOOO CKAHPICH PAPER t t ~ttt t ~ttt t ~tt
~tttt k tttt I
tt ~t tt t ~ttt bO~H CI T(EACT THYROIO TOTAL SOOT LIVER SKIll
-A ~
tiAXIMUtl IN(EIYIEAUAL CKILO (HREH) 8 ~
HAXIHEJH IHOIYI UAL AGULT (HR(i4)
CD TENNESSEE RIVER POPULATION (HAtt-REH) 0 1 ~ 9C-G2 7 7E-04 7 22-03 7o 1E-03 1 ~ 2F;03 1
1E-G2 1 ~ 38-01 1 W-OZ 9 ~ 7E-02 4 'E"03 2 ~
E-
~ E-8.8E-03 1
2K-02 8.SK-03 5, 55 O~ I~E~ EE lt II~
FISK IHOESTION FROM K
AX 8
L H
H II V
5 IC L
HR 3.
MAXIMUM IH IVICUAL AOULT (H".CH)
P HAH R H) 5'0-01 8 'E-03 I ~ SC-01 3'E-02 4.5K+01 2 ~ SE<00 1 ~ 18-01 5 OK-01 4 'E+01 5,0E-01 4 'E401
~
6 'E-O 7 1E401 151K-or 6.2E-01 1 "IE-01 5 'E-01 4 ~ 1E+01 A
ti AT EtHEELER LAKE 8ELO'N SFN A ~
SHi)RELINE INGIVIOUAl (HR t')
ttAt Rt 8 ~
IN-RATER IHQIVIOtJAL (tEREH) 3 'E-02 1 ~ 4E-01 1 ~ Gt-03 5.4E-d'2 3.0E-1 ~ 2E-01 1 ~ 1E"01 8 'E-04 7'E-34 1 'E-01 8 ~ SE"04 1 ~ 1E-01
" ASK-01 7 'E-04
'K-03 PQPULATICN (HAN R
K)
C ~ >ABOVE-J'tATER IHOIYIJUAL (HRLH)
PCPULATIOH (HAtt-REH)
~ ~
~
~r
<<),Jjf
'IV~. TOTAL
~~
A '~MAXIMUM INOIVIOUAL CKILO (HREH)
VCRl,INAXANUN IHOIVIOUAL AOULI HA~N N
E RIVER POPULATIOtf (MAN RcH 5 'C-04 3 'C 04 3'E-4 5
EEVEE.~-e ac-1 ~ 3E-03 1 <<OE-03 8 ~ 8E-04 5 6C-01 4 'E-02 1 ~ 5E-01
- 4. 3E=61 7.CE.=02 3'.
4 'K>01 2 'K+00 4 'E>01 1 ~ 1E "03
~
-.'AI. VE"
-.-.-"P 5 X)W&W",
'-g.
'1 'E-01m, i5A
- 4 ~ 2E<TTT~~
~
t
~
9.3E-04 '
Nt. 1 ~ 3E 03
~
~
~,
Wo <<5.r.
6 7E-01
~1 ~ 4K 01.
I 7 ~ 2K<01-
~ 2K>01 l.9E-02 = l.9 x lO
~ >
Table 15 Browns Fer Nuclear Plant - Five-Year Summa of Quarterl Doses-
~ ~
L Air Submersion Li uid Effluents Year uarter Air-Y (mrad)
Air-P (mrad)
Skin Total Body (mrem)
(mrem)
Haximum Organ Total Body (mrem)
(mrem)
Naximum Organ (mrem) 1979 1980 1981 1982 1983 1
2 3
4 1a 2b 3
4 1
2 3
4 1
2 3
4 1
2 3
4 1.44
.79 1.94 2.25
.35
.39
.40
.93 1.97
.28
.15
.09
.11
.33
.27
.19
.47
.48
.18
.39 5.01 7.00 12.90 16.00
.44
.48
.52 1.09 2.11
~ 35
.19
.12
.16
.52
.35
.23
.45
~ 42
.34
.85 2.24 2.49 4.36 5.65
.31
.33
.31
.64 1.40
.23
.11
.09
~.09
.23
.37
.20
.24
.32
.16
.24
.89
.51 1.19 1.27
.21
.22
.21
.45
.96
.15
.07
.06
.07
.17
.27
.13
.16
.19
.10
.14
.10 Thyr.
.09 Thyr.
.26 Thyr.
.14 Thyr.
.11 Thyr.
1.19 Bone
.07 Thyr.
.08 Thyr.
.09 Bone
.98 Bone
.14 Bone
.08 Thyr.
.13 Bone
.11 Bone
.24 Bone
.16 Bone
~ 25 Bone
.31 Thyr.
.30 Bone
.04 Thyr.
.02
.02
.04
.06
.05
.03
.09
.15
.07
.21
-23
.05
.11
.06
.10
.07
.07
.09
.25
.54
. 13 GI Tract
.07 GI Tract
.04 Thyr.
.06 Thyr.
.03 Thyr.
.01 Thyr.
.11 Liver
.19 Liver
.10 Liver
.25 Liver
.28 Liver
.06 Liver
.13 Liver
.07 Liver
.12 Liver
.08 Liver
.09 Liver
.11 Iiver
.33 I.iver
.73 Liver a Plant procedures were revised in early 1980 for determining more realistically Kr-85 releases via the plant b gaseous effluent release points.
Prior to the third quarter of 1980 the liver was not considered in liquid dose analyses' Note:
All calculated doses are below limits specified in Appendix I to 10 CFR 50.
4
'