ML18029A469

Effluent & Waste Disposal Semiannual Report/Supplemental Info,Second Half 1983. W/840302 Ltr

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~

0 33

+ Q~

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. Tr i tium (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 O.OOO>>~

I PgR ADQCV.

PDR R

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. Iodines: 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 Id n s nd P cu s Airborne effluent gaseous activity is continuously monitored and recorded; grab samples ar e taken and analyzed monthly to determine 'dditionally, 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 Fourth

a. ~Luud QuueC Quut~

( 1) Number of batches released 83 148 Each (2) Total time period for batch releases 32933 57207 Minutes (3) Maximum time period for a batch release 1515 Minutes (4) Average time period for batch releases 396.78 386.53 Minutes (5) Minimum time period for batch releases 169.8 60 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 Third Fourth

~n ~u~ ~u ~Frrrr A. t r

1. Total Releases (1) Curies 6. 96E-01 ., 1.90E+00 +1.50E+01

2. Average Diluted Conc. During Period uCi/ml 5.80E-09 6.58E-09

3. Percent of Applicable Limit 3.48E 00 9.50E+00 B

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

1. Total Release Curies (4.13E-02 1.86E-01. ~+ .80&00

2. Average Diluted Conc. During Period uCi/ml 3.44E-10 6.44E-10 Percent of Applicable Limit (6E-06 uCi/ml) 5.74E-03 1.07E-02 D. s 1 h a c

1. Total Release Curies 2.36E-04 1.44E-04 +1.70&01 E. ume of Wa te e eas (before dilution) Liters 6.00&06 1.48E+07 +5.00E+00 F. oumeofD u 1 e f P Li.ters 1.20E+11 2.89E+11 +1.00E+01 (1/Based on pre-release anal'yses which are not decay corrected.

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT LIQUID. RELEASES FOR SECOND HALF 1983 BATCH MDE Third (1) Four th (1)

~steno ~ua ~te Quur~e

1. Strontium-89(3) 4.21E-03 1.33E-03

2. Strontium-90( 3) 1.20E"03 6 '9E-04 II 3 ~ Cesium-134 1.60E-01 4.79E-Ol Cesium-137 1 ~ 93E-01 5 '6E-01 5 ~ Iodine-131 6 '4E-03 1 '6E-02 6 ~ Cobalt-58 2.79E-04 3 '0E-04 I

Cobalt-60 4.24E-02 7 '5E-02 I

8. Iron-59 MDA MDA

9. Zinc-65 8.79E-02 4 '5E-01 10 'anganese-54 1 ~ 76E-03 3 '7E-03 Chromium-51 4 '5E-03 2.66E-03 12 'irconium-Niobium-95 7 '1E-04 5.86L-04 13 'olybdenun-99 1.76E-03 2 71E-04

~

14. Technetium-99m 1 .76E-03 2.71E-04

15. Barium-Lanthanum-140 MDA 1 '8E-04 16 ~ Cerium-141( 2) 3. 41E-02 1 '2E-01

17. Sodium-124 5 '4E-02 2 '4E<<02

18. Fluorine-18 ( MDA ( MDA

~ 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 ~

EFFLUENT AND MASTE DISPOSAL SEMIANNUAL REPORT LIQUID RELEASES FOR SECOND HALF 1983 BATCH MODE Third(1) Fourth( 1)

~so~o ~u~e (~u~e e o e u d o u d

1. Xenon-133 2. 16E-02 5.6 4E-02

2. Xenon-135 1.41E-02 4.22E-02

3. Iodine-133 6.76E-03 8.97E-03 Cesium-136 MDA MDA 5, Manganese-56 MDA MDA

6. Antimony-122 MDA MDA

7. Antimony-124 MDA MDA

8. Copper-64 MDA 4:77E-03

9. Arsenic-76 MDA

10. Arsenic-74 MDA - < MDA

11. Iodine-135 MDA 3.22E-03

12. Bromine-82 MDA MDA

13. Sil ver-110m 1.09E-03 2.26E-03

14. Antimony-125 1.18E-04 2 '5E-03

15. Samariam-153 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)

Third Fourth

1. Type of Waste n t ~u>p~

a. Spent resin, filter sludges, m3 224.73 180.1 etc. Ci 1345 694.24

b. Dry compressible waste 817H drums 1730 (12975 ft ) 668 (5010 ft )

contaminated equip., etc. Ci 287.0 79 05

c. Irradiated Components, control rods, etc. NA NA NA

d. Other (describe) Boxes Boxes 338 (28411 ft ) 240 (22888 ft )

Ci 20.7 24.64

2. Estimate of major nuclide composition (by type of waste) rte ou te

a. 1. Chromium-51 16.13 (217 / 1345) 16.28 (113 / 694)

2. Zinc-65 39.33 (529 / 1345) 46.60 (323.7/ 694)

3. Iodine-131 0.33 (4.48/ 1345) 0.90 (6.21/ 694)

4. Cesium-137 13.01 (175 / 1345) 9.82 (68.13/ 694)

5. Cesium-134 11.30 (152 / 1345) 8.52 (59.10/ 694)

6. Cobalt-58 0.88 (11.8/ 1345) 0.72 (5.27/ 694)

7. Cobalt-60 9.22 (124 / 1345) 8.15 (56 .54/ 694)

8. Zirconium-95 0.20 (2.68/ 1345) 0.15 ( 1.10/ 694)

9. Niobium-95 0.07 (.926/ 1345) 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) ou

a. 10. Lanthanun>>140 0.10 (1.40/ 1345) 0.02 (0.109/ 694)

11. Antimony-124 0.01 (0.190/1345) 0.00 (0.0/ 694)

12. Strontium-90 0.01 ( 0.192/1345) 0.01 (0.082/ 694)

13. Manganese-50 1.09 (14;7/ 1345) 1.12 (7.8 / 694)

14. Silver-110M 2 53 (34 0/ 1345) 1.97 (13.68/ 694)

15. Iron-59 0.05 (0.728/1345) 0.11, (0.80/ 694)

16. Other Nuclides 5 73 (77 12/1345) 4.98 (34.57/ 694)

b. 1. Chromium-51 7.63 (21.9/ 287) 25.63 420.25/ 79)

2. Zinc-65 72.12 (207 / 287) 42.37 (33.48/ 79)

3. Iodine-131 0.86 (2.48/ 287) 0.59 (0.46/ 79)

4. Cesium-137 5.89 (16.9/ 287) 6.98 (5.51/ 79)

5. Cesium-134 4.01 (11.5/ 287) 6.15 (4.86/ 79)

6. Cobal t-58 0.46 (1.31/ 287) 0.49 (0.387/ 79)

7. Cobal t-60 6.31 (18.1/ 287) 6.32 (4.99/ 79)

8. Zirconium-95 0. 17 ( 0.494/287) 0.15 (0.119/ 79)

9. Niobium-95 0.08 (0.236/34.1) 0.53 (0 423/ 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 0.54 (1.54/ 287) 0.03 (0.024/ 79)

11. Antimony-124 0.02 (0.712/ 187) 0.0 (0.0 / 79)

12. Strontium-90 0.25 (0.715/ 287) 0.008 (0.006/ 79)

13. Manganese-54 0.78 (2.23/ 287)

'I 1.0 (0 79/ '79)

14. Sil ver-110M 0.82 (2.34/ 287) 2.03 (1.6 / 79)

15. Iron-59 0.05 (0.150/ 287) 0.28 (0.221/ 79)

16. Other Nuclides 0.58 (1.67/ 287) '.45 (5.883/ 79)

c. Irradiated Components, Control Rods, etc. None

d. 1. Chromium-51 16.23 (3.36 / 20.7) 9.74 (2.397 / 24.6)

2. Zinc-65 63.77 (13.2 / 20.7) 59.6 (14.67 / 24.6)

3. Iodine-131 1,66 (0.344/ 20.7) 0.68 (0.166 / 24.6)

4. Cesium-137 7.78 (1.61 /'0.7) 8.72 (2.144 / 24.6)

5. Cesium-134 5.99 (1.24 / 20.7) 7.48 (1.841 / 24.6)

6. Cobal t-58 0.67 (0.138/ 20.7) 0.41 (0.10 / 24.6)

7. Cobal t-60 8,94 (1.85 / 20.7) 8.10 (1.98 / 24.6)

8. Zirconium-95 0,11 (0.0237/20.7) 0.002 (0.0006/ 24.6)

9. Niobium-95 0.02 ( 00327/20 7) 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 0.73 (0.152/ 20.7) 0.11 (0.027/ 24.6)

11. Antimony-124 0 04 ( 00749/20.7) 0.0 (0.0 / 24.6)

12. Strontium-90 '5 . 0.01 (.00222/ 20.7) 0.01 (0.002/24.6)

13. Manganese-54 0.97 (0.200/ 20.7) 0.88 (0.22 / 24.6)

14. Sil ver-110M 1.59 (0.329/ 20.7) 0.66 (0.163/ 24.6)

15. Iron-59 0 03 (.00609/ 20.7) 0.12 ( 0.029/ 24.6) 16 ~ Other Nuclides 3.22 (0.667/ 20.7) ,2.43 (0.60 / 24.6)

3. Solid Waste Dispositi.on u

Third e

Four th Mod nso o stnto

~u>~te (~u~e 41 Sole Use Tr uck Barnwell, SC Quatre< 27 Sole Use Truck Richland, WA d ue nt (disposition)

Nu of ode o ans o t t o est Third Fourth

~ua t~e NA NA NA NA

4 l

EFFLUENT AND MASTE DISPOSAL SEHIANNUAL REPORT SECOND HALF 1983 GASEOUS EFFLUENTS - SUMMATION OF ALL RELEASES Fourth u 0 e e Q<~

A. Fission and Activation Gases

1. Total Releases Ci 3.96& 04 <2.01E+05

2. Avg. release rate for period uCi/sec. 5.04E+03 <2.56'4

3. Percent of technical specification limit 1.01'1 5.11&-01 B. /~i~

1. Total Iodine-131 Ci 6.08E-03 1.29E-02

2. Avg. release rate for period uCi/sec. 7,74E 04 1.64E-03

3. Percent of technical specification limit 1.93E-01 4 ~ 10F 01 C. u ate

1. Particulate with half-lives )8 days Ci 8.14E-03 <5.69E-03

2. Avg. release rate for period uCi/sec. 1.04E-03 <7. 24E-04

3. Percent of technical specification limit 2.59E-01 1.81E-01 Gross alpha radioactivity ~ Ci <3.35E-06 <2.02E-04 D. ~tium

1. Total release Ci 1.16E+Ol 2.68E 00

2. Avg. release rate for period uCi/sec. 1.48E+00 3.41E-01

3. Percent of technical specification limit 1.27'0 3.68E-01 Ground level releases Ci 1.11Et01 2,59E+00

5. Elevated release Ci 5.47E-01 9.25E-02 V

(1) Repor ting period - 182 days

~ ~

EFPLUB/T AND MASTE DISPOSAL SEMIANNUAL REPORT SECOND HALF 1983 GASEOUS EFFLUENTS - ELEVATED RELEASE Third Fourth

~n Quu~e qua.~

Krypton-85 Ci 2.04'3 MDA Krypton-85m 5 .82'.03 1.71E+04 Krypton-87 Ci 3.20E+03 <1.35E+04 Krypton-88 Ci '1.07& 04 2.10E+04 Xenon-133 Ci 1 .54E+04 1.44E+05 Xenon-'135 Ci 8.19$ .02 4.65& 03

. Xenon-135m Ci MDA MDA Xenon-138 Ci MDA MDA Others (specify)

At gon-41 Ci 8.94E+02 <1.66B 02 Unidentified Ci NA NA o a o e Ci 3.88&04 <2.00E+05

2. ~)~es Xodine-131 Ci 5.62E-03 1.13E-02 Xodine-133 Ci 1.24E-02 <1.34E-02 Xodine-135 MDA Tota fo e 1.80E-02 <2.47E-02

F '

~

~

EFFLUBIT AND >1ASTE DISPOSAL SEMIANNUAL REPORT SECOND HALF 1983 GASEOUS EFFLUENTS - ELEVATED RELEASE (Continued)

Third Four th gnn, Quy~~e Qu~~

3 ~

Strontium-89 Ci 2.64E-05 2.82E-04 Strontium-90 Ci 8.47E-06 6.17E-07 Cesium-134 Ci < MDA MDA Cesium-137 Ci ' <, MDA MDA Barium-140 Ci 4'11E-05 MDA Zirconium-95 Ci MDA MDA Niobium-95 Ci MDA MDA Cobal t-58 Ci MDA MDA Manganese-50 Ci 3.76E-05 <].64E-04 Zinc-65 Ci MDA MDA Iron-59 Ci MDA MDA Cobal t-60 Ci MDA MDA Others (specify)

Lanthanum-140 Ci MDA fo Ci 3.51E-04 <4.47E-04

@~tom Ci 5.47E-01 9.25E-02 (1) Predicted estimation of release

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SECOND HALF 1983 GASEOUS EFFLUENTS - GRCUND LEVEL RELEASES Third Fourth

~n Qual f:ee Krypton-85 Ci < MDA MDA Krypton-85m Ci < MDA MDA Krypton-87 Ci < MDA MDA Krypton-80 Ci MDA MDA Xenon-133 Ci <'DA 4.24K 02 Xenon-135 Ci 3.55E'+02 1.95E+02 Xenon-135m Ci 3 59E+02 MDA

'DA Xenon-138 Ci Others ('pecify)

Argon-41 Ci MDA Unidentified Ci NA NA or e Ci 7. 14&.02 <6.18&02

2. ~oops Iodine-131 Ci 4.63E-04 1.62E-03 Iodine-133 1.04E-03 <1.43E-03 Iodine-135 MDA MDA fo Ci 1.50E-03 <3.05F 03

P t

EFFLURTS AND MASTE DISPOSAL SEMIANNUAL REPORT SECOND HALF 1983 GASEOUS EFFLUENTS - GRCUND LEVEL RELEASES (Continued)

Third Fourth

~n x 3.

Strontium-89 Ci 2.21F 03 2.42E-05 Strontium-90 Ci 1.76E-04 5.24E-07 Cesium-134 3.45E-04 <5.73E-04 Cesium-137 Ci 4.60E-04 <7.15E-04 Barium-140 Ci 4.44E-05 MDA Zirconium-95 Ci 5.36F 05 MDA Niobium-95 Ci 3.19E-04 '1.26F Cobalt-58 Ci 1.23E-05 Manganese-50 1.32E 04 <7.65E-06 Zinc-65 Ci 1.20E-03 <2.52E-0306'or Iron-59 Ci MDA MDA Cobalt-60 2.80E-03 1.41E-03 Others (specify)

Lanthanum-140 3.43E-05 < MDA Ci 7 79F 03 <5.25E-03 4, g~~ura Ci 1.11& 01 2.59Et 00 (1) Predicted estimation of releases.

I Table 10 Browns Fer Nuclear Plant - Individual Doses From Gaseous Effluents Third uarter 1983

~EE fluen ~Pa thwa Guideline* Point Dose Noble gases T Air dose 30 Hax. Exp.~ Oalg mrad P Air dose 60 Hax. Exp.~ 0.34 mrad Total body2 15 Residences 0.10, mrem Skin~ 45 Residences 0.16 mrem Iodines/Particulates Bone 45 Real 0.30 mrem (critical organ) Pathway4 Breakdown of Iodine Particulate Ex osures mrem Child Adult Vegetable Ingestion 2.85 x 10 1.20 x 10 i Beef Ingestion5 9.59 x 10 4 8.55 x 10 Inhalation 4.42 x 10 2.87 x 10 4 Ground Contamination x 10 2 1.33 x 10 2

'.33 Total 3.00 x 10 1.34 x 10 Pe ynnuq$ guide)ines are defined by Appendix I to 10 CFR 50.

+e mqgimqy exposure point is at 6100 meters in the W sector.

2. Poop from air submersion.

3. +e maximum exposure point is at 7925 meters in the N sector.

4. Qeceptog is at 1750 meters in the NNW sector.

Qy gyyiyqg exposure point 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 Guideline* Point Dose Noble gases T Air dose 30 Hax. Exp. 0.39 mrad P Air dose 60 Hax. Exp. 0.85 mrad Total body~ 15 Residences 0.14 mrem Skin~ 45 Residences 0.24 mrem Iodines/Particulates Thyroid 45 Real 0.04 mrem (critical organ) Pathway4 Breakdown of Iodine/Particulate Ex osures (mrem)

Child Adult Vegetable Ingestion 2.29 x 10 2 1.09 x 10 ~

Beef Ingestion 2.73 x 10 ~ 2.58 x 10 ~

Inhalation 7.37 x 10 ~ 3.75 x 10 ~

Ground Contamination 1.73 x 10 2 1.73 x 10 ~

Total 4a12 x 10 2 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 LIVER EONC INFANT CHILD TrE9 ADULT TOTALS INF ANT CHILD TrfN ADULT TOTALS SU 4 NC 1 5 I 0's 10E " 4 ~ 43C 91 2 ~ 82C fl I 31E 00 2 10 +00 7~ 19C-02 4 ~ 43L-Gl 2 ~ 62E 01 I ~ 3IC+GC 2 IOE400 SROUV9 1 61E 03 1 01C 9? 6 ~ 4QC 03 2 ~ 96C-02 4 ~ 77C-0? lidlf G3 1 ~ Olf-02 6 '0E 03 2 '6E-02 4 '7f. C2 IN<AL4TIn i 3 ~ 72E-03 . 3 ~ 51r-C2 1 ~ 46E-GP 4 <1C-02 1 ~ 02r-01 4 ~ 3IE-05 9 '0C 04 4il3C 04 1 ~ TSE 03 3 '4C~03 CnN WILV 3 ~ 90r 04 1 ~ 'TTE-03 4 ~ 40E-04 1 ~ 72E-03 3 <2f-03 9 '9C-04 4 '4E-03 1 ~ 06E-03 4 'RE-03 1~ 01C 02 OEEF I NGCST ION 0~ 00E+Cni 3 ~ 25E-04 1 ~ 66C-04 1 ~ DIE-"3 I ~ 59C-93 0 ~ OOE+CO 4 '+f 04 I ~ 62C-04 9 '6C 04 I 53E 03 VEG INGESTION 0 ~ 00F+99 2 ~ 33C-04 1~ 215-04 7 12C-0 ~ I 37f-93 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 THTROI 0 TOTAL bODT INF AN'I CHILD TE EN ADULT TOTALS INFANT CHILD 7FEN ADULT TOTALS 5VAHERSION 1 ~ 37E-01 8 53E-01 5~ 43E-01 2~ 51Et00 4 ~ 05K<00 1 ~ 37C 01 8 ~ 53E 01 5~ 43K 01 2 ~ 51E400 4 ~ OSE+00 GROUND 2 ~ 89E 03 1 ~ 80E 02 1 ~ 1SE 02 5 ~ 31E 02 8 ~ 54E 02 2.89E-03 1 ~ 80E-02 1 ~ 15E 02 5 ~ 31E-02 8+54K-02 INHALATION 2 ~ 95E-04 3 ~ 02E-03 1 ~ 14E-03 4 ~ 35E-03 8 ~ 81E-03 2 ~ 81E-03 3 ~ 33E-02 1 ~ 06E-02 3~ 53E-02 8 ~ 21E-02 CON HILA 1 ~ 70E-02 4 ~ 36E-02 1 ~ 16E-02 4 ~ 39E-02 1 ~ 16E-01 8 ~ 48E-05 4~ 13E-04 2~ 13E-04 1 ~ 20E-03 1 ~ 91E-03 bEEP INGESTION 0 ~ OOE>00 S ~ 43E-04 2 ~ 32E-04 1 ~ 42E-03 2 ~ 20E-03 0 ODE400 9 ~ 65E-05 8 89E-05 8 41E-04 1 ~ 03E-03 VKG INGESTION 0 ~ DDE>00 5 '5K-03 2 '0E-03 1 '3K-02 2 '9E-02 0 ~ ODK+OC 8 '2E-05 d 42E-05 5 '2K-04 d 87K-04 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 GI TRACT THYROID c TOTAL 'bODY:,

'" I YE

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tt ccccc siss tcsc r . -:$ $$

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r r AW++VP+i'cr>> pi 'Pi Per.Pi q tg

~ ~r t>le- i QY)POPULAT IO110(HAH R EH) 2 1E-01 1 ~

o E-01 1 6E-01 1 'E-01 1 ~ 6E-01-,.$ 1$ >>$ 2i 2E

,'I)'e) IH llATER INDIVIDUAL-'rtMREH) 6 'c-GC 5 ~ SE-OC 5 'E-04 c ~ 6E-04 -'5"o 6.7E-OC 01'.EE-04 r

.rROPULAT ION (HAH Rck) Cc r3 1.12-03 USE-04 1.1c 03 9 ~ bE-04 . -, 1,4E-03-',

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A~ MAXIMUM IHOIYIOVAL CH LO t",9=".) 2 ~ 6E-01 USE 02 7.3E-02 7.3E-02 3~ OE-01, - 7>> 7E-02

~ 4 c I ~ ~ ~

C ~ TEHHESScc RIY.R POPULATION tHCN RPN) = F 22>31 1 ~ )c+nl 7.0bt01 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 LIVER SKIll tt t bO~H

~

CI t ttt tt T(EACT~

THYROIO t t ~ ttt TOTAL SOOT t ~ ttt t ~ tt ~ tttt k tttt I

5) ST PLTliOOO CKAHPICH PAPER 0

'E"03 E- E-O~ I~E~

-A ~ tiAXIMUtl IN(EIYIEAUAL CKILO (HREH) 1 ~ 9C-G2 7 7E-04 7 22-03 4 2~ ~

8 ~ HAXIHEJH IHOIYI UAL AGULT (HR(i4) 7o 1E-03 1 ~ 2F;03 1 1E-G2 8.8E-03 1 2K-02 8.SK-03 1 ~ 38-01 W-OZ 7E-02 5, 55 EE lt CD TENNESSEE RIVER POPULATION (HAtt-REH) 1 9 ~

II~ FISK IHOESTION K AX FROM 8 L H H II V 5 IC L HR 5 '0-01 8 'E-03 1 ~ 18-01 151K-or 6.2E-01 1 "IE-01

3. MAXIMUM IH IVICUAL AOULT (H".CH) I ~ SC-01 3 'E-02 5 OK-01 5,0E-01 6 'E-O 5 'E-01 P ' HAH R H) 4.5K+01 2 ~ SE<00 4 'E+01 4 'E401 ~

7 1E401 4 ~ 1E+01 A ti AT EtHEELER LAKE 8ELO'N SFN A~ SHi)RELINE INGIVIOUAl (HR t') 3 'E-02 5.4E-d'2 3.0E-

" ASK-01 ttAt Rt 1 ~ 4E-01 1 ~ 2E-01 1 ~ 1E"01 1 'E-01 1 ~ 1E-01

'E-34 'E-04 ' 'K-03 IN-RATER IHQIVIOtJAL (tEREH) Gt-03 8 'E-04 7 8 ~ SE"04 7 8 ~

PQPULATICN (HAN R K) 1 ~

5 'C-04 3 'C 04 3 'E- 4 ~ t ~

C ~ >ABOVE-J'tATER IHOIYIJUAL (HRLH)

PCPULATIOH (HAtt-REH) 1 ~

5 EEVEE.~-e 3E-03 1 <<OE-03 ac- 8~ 8E-04 1 ~ 1E "03 9.3E-04 ' Nt. 1 ~ 3E 03

~ ~

• r~~

~

~

~ -.'AI. VE" Wo

~,

<<5.r.

'IV ~ . TOTAL

<<),J jf -.-.-"P 5 X)W&W",

'-g.

~~ A '~MAXIMUM INOIVIOUAL CKILO (HREH) 5 6C-01 4 'E-02 1 ~ 5E-01 '1 'E-01m, 6 7E-01 ~1 ~ 4K 01.

4. 3E=61 7.CE.=02 3'. I VCRl,INAXANUN IHOIVIOUAL AOULI HA~N i5A N E RIVER POPULATIOtf (MAN RcH 4 'K>01 2 'K+00 4 'E>01  ; 4 ~ 2E<TTT~~ 7 ~ 2K<01- '

~ 2K>01 l.9E-02 = l.9 x lO

~>

~ ~

L Table 15 Browns Fer Nuclear Plant - Five-Year Summa of Quarterl Doses-Air Submersion Li uid Effluents Air-Y Air-P Skin Total Body Haximum Organ Total Body Naximum Organ Year uarter (mrad) (mrad) (mrem) (mrem) (mrem) (mrem) (mrem) 1979 1 1.44 5.01 2.24 .89 .10 Thyr. .02 . 13 GI Tract 2 .79 7.00 2.49 .51 .09 Thyr. .02 .07 GI Tract 3 1.94 12.90 4.36 1.19 .26 Thyr. .04 .04 Thyr.

4 a

2.25 16.00 5.65 1.27 .14 Thyr. .06 .06 Thyr.

1980 1 .35 .44 .31 .21 .11 Thyr. .05 .03 Thyr.

2b .39 .48 .33 .22 1.19 Bone .03 .01 Thyr.

3 .40 .52 .31 .21 .07 Thyr. .09 .11 Liver 4 .93 1.09 .64 .45 .08 Thyr. .15 .19 Liver 1981 1 1.97 2.11 1.40 .96 .09 Bone .07 .10 Liver 2 .28 ~ 35 .23 .15 .98 Bone .21 .25 Liver 3 .15 .19 .11 .07 .14 Bone -23 .28 Liver 4 .09 .12 .09 .06 .08 Thyr. .05 .06 Liver 1982 1 .11 .16 ~

.09 .07 .13 Bone .11 .13 Liver 2 .33 .52 .23 .17 .11 Bone .06 .07 Liver 3 .27 .35 .37 .27 .24 Bone .10 .12 Liver 4 .19 .23 .20 .13 .16 Bone .07 .08 Liver 1983 1 .47 .45 .24 .16 ~ 25 Bone .07 .09 Liver 2 .48 ~ 42 .32 .19 .31 Thyr. .09 .11 Iiver 3 .18 .34 .16 .10 .30 Bone .25 .33 I.iver 4 .39 .85 .24 .14 .04 Thyr. .54 .73 Liver a

Plant procedures were revised in early 1980 for determining more realistically Kr-85 releases via the plant gaseous effluent release points.

b 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

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