ML18029A457

Incomplete Effluent & Waste Disposal Semiannual Rept, Supplemental Info,First Half 1983.

ML18029A457
Person / Time
Site:	Browns Ferry
Issue date:	06/30/1983
From:	TENNESSEE VALLEY AUTHORITY
To:
References
NUDOCS 8504090343
Download: ML18029A457 (33)

Text

1 V EFFLUENT AND >1ASTE DISPOSAL SEMIANNUAL REPORT SUPPLEMENTAL INFORMATION (CONTINUED)

FIRST 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.

0 Liquid effluents: sum of individual MPC ratios g 1 U

(ref. 10 CFR 20, Appendix B, note 1)

3. Average Energy - Not Applicable

4. Measurements and Approximations of Total Radioactivity a., b. & c. ission and Acti tion ases odines and art culates.

Airborne effluent gaseous activity is continuously monitored and recorded; additionally, grab samples are 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 exhau'st 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 concentr ations. 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.

I t Allowa'nce is made for a plus or minus one sigma counting error associated with gamma isotopic analyses. 'DESIGNATED ORIGIMII Ce"tifie6 B R

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EFFLUENT AND HASTE DISPOSAL SEMIANNUAL REPORT SUPPLEMENTAL INFORMATION (CONTINUED)

FIRST HALF 1983 II

4. Measurements and Approximations of Total Radioactivity (Continued)

d. i uid Effluent 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.

5. Batch ~a3I ue First Second

a. ~tutd Quarter Quarter

( 1) Number of batches released 126 102 Each (2) Total time period for batch releases 52952 38134 Minutes (3) Maximum time period for a batch release 1920 960 Minutes (4) Average time period for batch releases: 420.25 373.86 Minutes (5) Minimum time period for batch releases 20 70 Minutes (6) Average stream flow during period of release of effluent into a flowing stream1

b. gaseous None 1To be supplied by others.

EFFLUENTS AND WASTE DISPOSAL SEMIANNUAL REPORT FIRST HALF 1983 LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES First Second

~ni ~ua ~te ~ua ~te A. ission and ctivat on roducts

1. Total Releases (1) Curies 7.60E+00 2.57E+00 +1.50E+01

2. Average Diluted Conc. During Period uCi/ml '.58E-08 1.22E-08

3. Percent of Applicable Limit 3.80E+01 1 . 29E+01 0

B. ~itXum

1. Total Release Curies 1 . 17E+01 6.11E+00

2. Average Diluted Conc. During Period uCi/ml 3. 97E-08 2. 90E-08 ~+. OOE+00

3. Percent of Applicable Limit (3E-03 uCi/ml) 1.32E-03 9.67E-04 C. issolved and ntrained ases

1. Total Release Curies <1.54E+00 <1.70E-01 ~+.80E+00

2. Average Diluted Conc. Dur ing Period Uci/101 .<5.22E-09 <8.06E-10

3. Percent of Applicable Limit (6E-06 uCi/ml) <8.71E-02 <1.34E-02 D. ross A ha Radioactivit

1. Total Release Cur ies 8. 05E-05 5. 05E-04 +1. 70E+00 E. Volume of Waste Re ease (before dilution) Liters 1.25E+07 8.45E+06 ~+ . 00E+00 F. o ume of Di ution Water for Period Liters 2.95E+11 2.11E+11 +1 . 00E+00

( 1)Based on pre-release analyses which are not decay corrected.

EFFLUENT AND HASTE DISPOSAL SEMIANNUAL REPORT LIQUID RELEASES FOR FIRST HALF 1983 BATCH MODE First Second soto e ~ua ~te gu~ater Strontium-89(3) 5.31E-03 2.25E-03 2~ Strontium-90(3) 1.21E-03 5.27E-04 3 ~ Cesium-134 <5.90E-02 <9. 83E-02 Cesium-137 <7.60E>>02 <1.16E-01 5~ Iodine-131 <5. 14E-02 <1.83E-02 6 ~ Cobalt-58 <2. 61E-03 <1.13E-03 7 ~ Cobal t-60 <3.35E-02 5.80E>>02 8 ~ Ir on-59 <3.70E-03 <1. 37E-03

9. Zinc-65 <7.60E-02 8.35E-02 10 'anganese-54 <4.47E-03 <3.03E-03

11. Chr'omium-51 <1.49E-02 <1. 36 E-02 12 ~ Zirconium-Niobium-95 < 4. 56E-03 <4.02E-03 13 ~ Molybde nun-99 < 3. 07E-03 <1. 45E-03 14 'echnetium-99m <3.07E-03 <1.45E-03 15 ~ Barium-Lanthanum-140 <6.40E-03 <8.11E-04 16 ~ Cerium-141( 2) <1.26E-02 <2.10E-02

17. Sodium-124 <1.20E-02 <3.63E-02 18 'luorine-18 <1.21E-03 <4.41E-04 ota for Period <3.71E-01 <4. 61E-01 (1) Quantities listed are in cur ies.

(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.

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT FIRST HALF 1983 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS A. Solid Waste Shipped Off-Site for burial or disposal (not irradiated fuel)

First Second

1. Type of Waste n t ~ear te Queer te

a. Spent resin, filter sludges,, m3 173.05 250.5 evaporator bottoms, etc. Ci 1886 2226

b. Dry compressible waste 817H drums 408(3060 ft ) 846(6345 ft )

contaminated equip., etc. Ci 34.1 298.1

c. Irradiated Components, control rods, etc.

d. Other (describe) Boxes Boxes 30(2890.5 ft ) 248(20434.8ft Ci 0.245 1.9

2. Estimate of ma)or nuclide composition (by type of waste)

First Second

/nit quarter ~ear te

a. 1. Chromium-51 12.57 (237 / 1886) 14.33 (319 / 2226)

2. Zinc-65 29.59 (558 / 1886) 26.59 (592 / 2226)

3. Iodine-131 9.86 (186 / 1886) 4.04 ( 89 / 2226)

4. Cesium-137 17.13 (323 / 1886) 20.26 (451 / 2226)

5. Cesium-134 16.22 (306 / 1886) 18.28 (407 / 2226)

6. Cobalt-58 0.47 ( 8.77/ 1886) 0.70 ( 15 / 2226)

7. Cobalt-60 7.00 (132 / 1886) 8.85 (197 / 2226)

8. Zirconium-95 0.50 ( 9.48/ 1886) 0.35 (7.69/ 2226)

9. Niobium-95 0.42 (7.98/ 1886) 0.04 (0.94/ 2226)

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT LIQUID RELEASES FOR FIRST HALF 1983 BATCH MODE First1 Second1 soto e ~ua ~te ~ua ~te thers ot e uired for e Guide

1. Xenon-133 1.52E+00 < 1 . 47E-01

2. Xenon-135 3. OOE-01 <2.32E-02

3. Iodine-133 <3.69E-02 <3.89E-03

4. Cesium-136 <2.74E-03 <1.69E-03

5. Manganese-56 <9.44E-04 <1.75E-04

6. Antimony-122 <7.85E-03 <4. 13E-03

7. Antimony-124 <2.27E-03 <1.06F 03

8. Copper-64 < 1 . 90E-02 <2. 15E-02

9. Arsenic-76 <2. 16E-02 <2.24F 02

10. Arsenic-74 <3. 1 8E-03 <1.70E-03

11. Iodine-135 <8.82E-03'3

<4.05E-03

12. Bromine-82 93E-03 <2.39E-03

13. Silver-110m <1.28E-02 <1.77E-03

14. Antimony-125 <6.41E-03 < 1 . 32E-03

15. Samariam-153 <3.63E-03 <2. 11E-03 1Quantities listed are in curies.

~ e '

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT FIRST HALF 1983 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS (CONTINUED)

2. Estimate of major nuclide composition (by type of waste) (Continued),

First Second

~u t . Quarter ~ua ~te

a. 10. Lanthanun-140 2.05 (38.7/ 1886) 2.01 (44.7/ 2226)

11. Antimony-120 0. 03 ( 0.635/1886) 0.04 ( 0.88/ 2226)

12. Strontium-90 0. 01 ( 0. 142/1886) 0.01 (0.25/ 2226)

13. Manganese-54 0.74 (13.9/ 1886) 1.03 (22.9/ 2226)

14. Silver-110M 1.20 ( 22.7/ 1886) 1.50 ( 33.3/ 2226) "

15. Iron-59 0.0,8 (1.52/ 1886) 0.13 (2.79/ 2226)

16. Other Nuclides 2.08 (39.2/ 1886) 1.98 (44.09/2226)

b. 1. Chromium-51 10.67 (3.64/ 34.1) 11.87 (35.39/298.1)

2. Zinc-65 37.54 (12.8/ 34.1) 44 95 (133 99/298-1)

3. Iodine-131 16.77 (5.72/ 34.1) 3.31 (9.87/298 1)

~

4. Cesium-137 10.65 (3.63/ 34.1) 13.31 (39.68/298.1)

5. Cesium-13 4 9.33 (3.18/ 34.1) 10.26 (30.58/298.1)

6. Cobalt-58 '

0.16 (0.0542/34.1) 0.74 (2.2 / 298 1)

~

7. Cobalt-60 5. 54 ( 1.89/34. 1) 9. 91 (29.53/298. 1)

8. Zirconium-95 0.75 (0.255/34.1) 0.40 ( 1.18/298.1)

9. Niobium-95 0. 21 ( 0. 0708/34. 1) 0.61 (1.83/298.1)

~

~

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EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT FIRST HALF 1983 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS (CONTINUED)

2. Estimate of ma)or nuclide compositon (by type of waste) (continued)

First Second

~ui ~uarte ~uarte

b. 10. Lanthanum-140 3.67 (1.25/34.1) 0.85 (2.53/298.1)

11. Antimony-124 0.04 (0.0130/34 1) F 0.06 (0.19/298.1)

12. Strontium-90 0.003 ( 9 77E-4/34 1) 0. 01 ( 0. 04/298. 1)

13. Manganese-54 0.43 (0 '45/34 ') 1.11 (3.30/298.1)

14. Silver-1 10M 0.63 ( 0.215/34 1)

~ 1.27 (3.78/298. 1)

15. Iron-59 p 0.10 (0.0335/34.1) 0.25 (0.76/298.1)

I

16. Other Nuclides 3.52 ( 1.20/34.1) 1.11 (3.32/298.1)

c. Irradiated Components, Control Rods, etc. None

d. 1. Chromium-51 $ 9.96 (2.44E-2/0.245) '.82 (0.15/ 1.9)

2. Zinc-65 24.49 (6.00E-2/0.245) 46.96 (0.90/ 1.9)

Iodine-131 22 12

~ (5.42E-2/0.245) 5.47 (0.10/ 1.9)

Cesium-137 12.82 (3.14E<<2/10.245) 12.32 (0.24/ 1.9) 5; Cesium-13 4 11.22 (2.75E-2/0.245) 9.54 (0.18/ 1.9)

6. Cobal t-58 0.22 (5.39E-4/0.245) 0.56 (0.01/ 1.9)

7. Cobalt-60 5.76 (1.41E-2/0.245) 9.04 (0.17/ 1.9)

8. Zirconium-95 1.04 (2.54E-3/0.245) 0.45 (0.01/ 1.9)

9. Niobium-95 0.25 (6.18E-4/0.245) 0.10 (0.02/ 1.9)

5 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT FIRST HALF 1983 SOLID WASTE AND IRRADIATED FUEL SHIPMENTS (CONTINUED)

2. Estimate of major nuclide composition (by type of waste) (continued)

First Second gnat guarder ~ua ~te

d. 10. Lanthanun-140 $ 5.31 (1.30E-2/0.245) 2.39 (0.05/ 1.9)

11. Antimony-124 $ 0. 04 ( 9. 94E-5/0.245) 0.04 ( 0.0008/1.9)

12. Strontium-90 $ 0.004 (8.72E-6/0.245) 0. 01 ( 0. 0002/1. 9)

13. Manganese-54 $ 0. 47 ( 1. 16E-3/0.245) 1.04 (0.02/ 1.9)

14. Silver-110M 0.62 (1.52E-3/0.245) 1.02 (0.02/ 1.9)

15. Iron-59 0.12 (2.88E-4/0.245) 0.18 (0.0034/1.9)

16. Other Nuolides $ 5.47 (1.34E-2/0.245) 2.65 (0.05/ 1.9)

3. Solid Waste Disposition umber of hi ments iode f ans o tatio est nation First Second

~ua ~te ~uar er 42 57 Sole Use Truck Bar nwell, SC 2 23 Sole Use Truck Richland, WA a

B. r adiated uel hi ments (disposition) um e of hi ments de of T ans o tat st at o First Second

~ear te ~ua ter NA NA NA NA

( 1)Combination box/drum shipments on these dates.

'( 1)Combination of irradiated components, regular boxes and drums shipped.

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT FIRST HALF 1983 GASEOUS EFFLUENTS - SUMPTION OF ALL RELEASES First Second Summation of ll eleases ~nt ~na ter ~E~or ua teZ $ gy~

A. Fission and Activation Gases

1. Total Releases <1.46E+05 +7.60E+00 <9.19E+04 +7.60

2. Avg. release rate for period uCi/sec. <1.86E+04 <1. 17E+04

3. Percent of technical speoification limit <3.71E+01 2.34E+01 B. ~odines Total Iodine-131 1.00E-01 +1.22E+01 5.21E-02 +1.22

2. Avg. release rate for period uCi/sec. 1 .27E-02 6.63E-03

3. Percent of technical specification limit 3.19E+00 1.66E+00 I

1. Particulate with half-lives )8 days Ci <6.01E-02 +1.05E+01 <3.77E-02 +1

2. Avg. release rate for period uCi/sec.

.05'.80E-03

<7.65E-03

3. Percent of technical specification limit 1. 91E+00 1 .20E+00

4. Gross alpha radioactivity Ci <4.05E-09 <8.24E-07 D. Tritium

1. Total release Ci 1.22E+01 ~+.OOE+00 1 . 44E+01 ~+ .00i

2. Avg. release rate for period uCi/sec. 1.55E+00 1.83E+00

3. Percent of technical specification limit 2.86E+00 1.49E+00

4. Ground level releases 1.20E+01 1 .41E+01

5. Elevated release Ci 1 .76E+01 2.95E-01 (l) Reporting period - 181 days

EFFLUENT AND HASTE DISPOSAL SEMIANNUAL REPORT FIRST HALF 1983 GASEOUS EFFLUENTS - ELEVATED RELEASE First Second

~ua ~te (~ua ~te Krypton-85 Ci <1. 58E+03 < 1 . 21E-03 Krypton-85m Ci <2. 35E+04 < 9. 0 9E+03 Krypton-87 <8. 90E+03 <2.72E+03 Krypton-88 Ci <2. 07 E+04 <8.20E+03 Xenon-133 Ci <8.66E+04 < 1. 89E+04 Xenon-135 Ci <2. 06 E+02 <3. 45E+02 Xenon-135m Ci <5. 65E+02 <3.05E+04 Xenon-138 Ci <3.00E+03 <2.00E+04 Others (specify)

Argon-41 Ci <8.33E+01 <2.46E+02 Unidentified Ci NA NA ota for Period Ci <1.45E+05 <9.00E+04

2. ~ofnes Iodine-131 Ci 9.36E-02 5-21E-02 Iodine-133 Ci 3.28E-02 4.81E-03 Iodi ne-135 1.08-02 4.65E-03 otal for eriod Ci 1 . 37E-01 6. 16E-02

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT FIRST HALF 1983 GASEOUS EFFLUENTS ELEVATED RELEASE (Continued)

First Second nit ~ua ter ~ua ter 3.

Strontium-89 Ci 9 ~9E-05 3.68E-04 Strontium-90 Ci 9.27E-06 4.93E-06 Cesium-134 <7.51E-05 <4.64E-05 Cesium-137 <1.32E-04 <5.06E-05 Barium-140 Ci <6. 50E-04 <1.70E-04 Zirconium-95 Ci <2-62E-03 <3. 87E-03 Niobium-95 Ci <7 45E-05 <4.60E-05 CubaX+~58 Ci <1. 08E-04 <5. 18E-05 Manganese-54 Ci <1.74E-04 <7.28E-05 Zinc-65 Ci <1.53E-04 <1.01E-04 Iron-59 Ci '1.56E-04

<8.93E-05 Cobal t-60 Ci 6 . 82E-05 <8.19E-05 Others (specify)

Lanthanum-140 Ci <1. 25E-02 < 8. 57E-04 Total for Period Ci <1.68E-02 <5. 81E-03 Tritium Ci 1.76E-01 2.95E-01 (1) Predicted estimation of release 4

4

~ ~

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT FIRST HALF 1983 GASEOUS EFFLUENTS - GROUND LEUEL RELEASES First Second Un t quarter ~uar te u "'"

Krypton-85 <1.01E+00 <3. 03E+02 Krypton-85m Ci 2.16E+01 <4.10E+01 Krypton-87 <5. 42E+01 <1. 12E+02 Kr ypton-88 Ci <5.59E+01 <6.94E+01 Xenon-133 <1.55E+02 <2.56E+02 Xenon-135 <1.04E+02 <5.57E+01 Xenon-135m Ci <9.18E+01 <2.20E+02 Xenon-138 Ci <3.50E+02 <7.78E+02 Others (specify)

Argon-41 Ci <2. 29E+02 <6.02E+Ol Unidentified Ci NA Total for Period Ci <8.56 E+02 < 1 . 90E+03

2. ~ediuea Iodine-131 6 .59E-03 2.43E-06 Iodine-133 Ci <2. 08E-03 <3.81E-03 Iodine-135 Ci <8. 53E-03 < 1 . 59E-02 Total for Period Ci <1.72E-02 <1.97E-02

EFFLUENTS AND 11ASTE DISPOSAL SEHIANNUAL REPORT FIRST HALF 1983 4 GASEOUS EFFLUENTS - GROUND LEVEL RELEASES (Continued) uarter ua ter 3 l!"

Strontium-89 Ci 2. 82E-04 2.00E-04 Strontium-90 Ci 1 . 17E-04 5. 08E-05 Cesium-134 Ci <2.43E-03 <8.56E-04 Cesium-137 <2.51E-03 <9.34E-04 Barium-140 Ci 5.86E-03 6 .26 E-04 Zirconium-95 Ci <4.23E-03 <1.68E-03 Niobium-95 Ci <1.86E-03 < 1 . 77E-02 Cobalt-58 Ci <1.82E-03 <5.25E-04 Hanganese-54 Ci <1.83E-03 <5.70E-04 Zinc-65 < 5. 56 E-03 <2.75E-03 Iron-59 <5.04E-03 <1.14E-03 Cobalt-60 Ci 4.59E>>03 2.59E-03 Others (specify).

Lanthanum-140 Ci <7.18E-03 <2.29E-03 Total for Pe iod <4.33E-02 '3.19E-02

4. Tritium Ci 1.20E+Ol 1. 41E-01 (1) Predicted estimation of releases.

~j 0

4 ~

T)ble 10 llrowns Ferry Nucl<;)r I'lant - individual. Doses Fr<m) Gaseous Ef flu('.nLs I'irst f)uart( ) I98'3 f:.flluvnt I 1)Lhway Gu I d( 1 inc"'oint Dose N<>I>l< ~

I .">s<":

~

7 A<1'l<>s( ~

30 II~ . I:. 0.4 j mr.><l I.'.)x.

I3 A 1 f>O O. 45 Ii>> ')(I Vxp.'()

I'Ios('ot.a I hody2 15 si d en c( 0. 16 mrem Ski n2 Residences 0.24 mrem Ban('cri

>ALS l<><lines/I'arL iculat.( s a <>

4 Re;) 1 0.25 mr('m

')37 Lira organ) 1 Pa t.hway" 4h7

'>3>)

755 6 >> II) <;>k<l<>wn < H'>

743

>') 5>

Ch)ld Adult

>6

>It( getabl( lng( sL ian 2.2.'3 x 10 8.6:3 x IO

>(>(>

>7>>

<75 IIPPI 2.78 x 10 ') 1.98 x 10 IngesL)an'nE)al

)Lian 1.52 x 10 x 10 "

'>.53 Grour)<l Cont.aminaLion 2.60 x 10 2 2.60 x 10

'I'o t.a 1 2.53 x 10 1.15 x 10

""I'h( anna') I guidel ines ar( define<i by Appendix 1 Lo 10 CFR 50.

I . 'I'h< m;)ximum exposur( poinL is at. 5500 meters in the NW sert. or.

2. Dose from a ir subm<'rs ion.

3. Receptor is at. 4880 met.ers in Lhe SW sect. or.

4. It(('(I>t.or is at 1750 met.ers in the NNW sectar.

5. Beef ingest.ion dose is ralrulated at the site baundary at, 1575 meters i>> t,h( ESE sert, or.

Talrle 11 llrowrrs Ferry Nrrc1ear I'lant - Inrlivirlua I Doses From Gaseorrs I'.f flrrenLs Srrconrl err;rrtcr l983 I,"f fluerrL ~Pa Lhwa Gui de 1 i ne" Point. Dose Noble gases T Air. dose 30 Hax. Exp.r 0.48 mrarl P Air. dose 60 llax. Exp.2 0.42 mrarl Total bodyS Residence" 0.19 mrem Skins 45 Residence" 0.32 mrem I orli rros/I';r r t, I err I a Les Tlry roid Real 0.31 mrem (critical organ) Pathway" llrr ak<lowrr ol'orlirre/I'arL I err laLe I'.xposrrres (mrem)

Clri ld '<lu l t Vegetable Irrgestion 2.20 x 10 1.04 x 10 Heel'ngestiorr2 2.25 x l.0 2.11 x 10 1.78 x 10 2 8.89 x 10 s I nba 1 a t. ion 7.44 x 10 2 7.44 x 10 2 Ground Contamination Tota I 3.14 x 10 1.89 x 10 "Tire annual guirlelines are defined by Appendix I to 10 CFR 50.

I. The maxirnrrm exposure point is at 4800 meLers in the NW sector.

2. The maxirnrrrn exposure point is at. 1525 meters in the N sector.

3. Dose from air submersion.

4. Recept. or is at 1700 meters in the N sector.

36

,V<<<<"., <<.'.4<<<< ',lK'<<A l J<<%dr<< l<<<<d. <<,*.r/<<'.&<<,l'<<, 4, '.<<I<<<<<<Alt

Table 12 Gaseous Effluent Doses - Po ulation First Quarter 1983 LIY  :"Or.C INF ANT CHILi" t ~

CN TOtALS I'sF ANT Cr)L= TICN <<DVL I TO'IAL 4 a

SVBHERAT)ON S ION 1,44c.-01 9 ~ QOC-Cl 5 ~ 73C-01 2 ~ 65E~ 00 4 ~ 27i+00 I ~ 44. -Gl 9 ~ COC-Gl 5 ~ 73C-01 2 6SE "C 4 '7E~CO GROV> 0 5 24c.-03 3 ~ 27E-0? 2 ~ OBC-02 9 ~ 64C-0? ) ~ 55i-0) 44r Gl 3 '7E-02 2 '6E-02 9 '4E-02 I'iH<<L 5 ~ 72C-03 6 ~ 32i-G2 2 ~ 63E-02 8 ~ BOC-02 I o84 -Ol I ~ 94E 0 I 2 ~ 05C 03 F ~ 22E 04 2 ~ +OE 0 6 ~ 371 C3 CO<<H I LK 1 ~ 985-03 6 '4C-C3 I o9E-03 6."6c.-03 I ~ 73"-02 I ~ 55E-C3 6 56E-03 I 56E-03 5 '7C-03 ) ~ 54F-02 BE F INGEST ION 0 ~ OOE 00 2 '3C-03 1 13E-03 6 '2E-03 4 ~ 6:C-03 O.QCr QG ).AFE-03 6.76E-04 3.73i-03 6.27F-C3 YEG INGEStIGN 0 ~ OOE~ 00 I ~ 42E-03 7 '6i-04 3. 85E-03 6 OGC-03 O.QOr 00 3 16C-03 I ~ 36C-03 P 06E-03 1.26E-02 tOTAL HAN REH. I 58E-01 1 0)E 00 6 ~ 24L-0) 2 ~ 85L 00 4 ~ 64. 00 I 5)E-0) 9 ~ 47i-01 5~ .BC-01 2 ~ 77E OG 4 ~ 47E'CO Second Quarter 1983 INF

'l'HYROID CHILD TEE)."  :.".UL t TOTALS I NF AN T tOTAL BOOT err l1.o 'Tier,'DULT TGTALS SUBHCRS ION 5 ~ 65C-02 3 ~ 52E-Ol 2 ~ 24E-01 I ~ I 4C~ CQ 1 ~ 67C~(c. 5 ~ 65E 2 3 52E Ol 2~ 24E 01 I 04C+C9 I 67E+ CO GoQUND -7.37E-03 4.5. E-9? 2 ~ 92C-02 I. '5r-Cl 2. ) ir- 7 ~ 37r-03 4 ~ 59C-02 2 ~ 92E-02 I ~ 35C- 1 2 ~ 16C-91 I NIALAt ION 2 ~ 39i-03 2 ~ 44i" 02 9m44E-03 3 ~ 61C-"2 7~ 745- 2 I~ 9ir-C3 2 '3E-02 7 '4E-03 2 '4C-92 5 '3C-02 C54 H ILcc I 13E-Ql 2 9)E-Cl 7 ~ 72C-02 2 ~,?E-Ql 7~ 7 i-01 C3E- 94 I 74E-03 7.09E'-04 3 '8r -03 6.448-93 BCEF I'JGCS I ION G ~ OQE+QQ 3 22E<<03 I ~ 38C-Oc 8 ~ 431.-93 I ~ 3i". -02 O.OQC 09 2 '6E-04 I ~ 99C-04 I ~ 745-93 2.2)E-03 YCG I rrGEST IOrr 0 ~ OQE+ QO 3 ~ I BC-02 I ~ 36C-02 7 ~ 86C- 42 I ~ 24C nl 9 ~ QOC CO 3 BCE-04 2~ 27E-04 I 65E-03 2 ~ 27E-03 TOTAL CAth-RE') I BGE-01 7 ~ 48E-91 3 ~ 55E-91 l. 59C+ <<rr  ? rc7E ~ 09 6 ~ 62i-02 4 24C-0) 2 ~ 52E-Cl I 21r QQ I 96E QQ 1.44F.-01 = 1.44 x 10

A

Table 13 Li uid Effluent Doses Browns Kerr Nuclear Plant Routine Releases Pptt f GI T=::. Thv&GIO TOTtL ROOT LIVEP SK I 'I Io I ATER IMGCST IOlt AT PL YVCOO CH'P I Gt, P>>PER 4

U ~ S ~

a A~ "' I "UH I'eO I VIDUAL CHIT.O I YRC'4) 5C-03 I ~ 4 -02 9 ~ MAXIMUM IhOI V)DU L ADULT IMRC ') I 6L'-03 I ~ 2C-03 ).6C-C3 I ~ 2E-G3

c. TEt.ttcssEc R IvER popULATIGU IYAtt-REH) 2. 4E-02 v TE-92 Ie 11 ~ F ISH Ii)GEST I 0)t FROM

'WHEELER LAKE BELO" SF" C ~

MAX IHUH TEA'SSEE I:TOI VIOL'AL Ctll LO IHPCH)

6. YAXI..UY It:OIvIDUAL AOULT lrRCY)

R lvr" +OPULATIOU IHt tt-RrH) r>.5r-02 4

4

~

~

3j, 02 9E+CG 6 ~ 4 E-4'P C

5:5E=~6.6C-C2 C+00 6r=

7.6E+00

.5:

I ~ 2C-0?

E r'--'oiE~C 111 ~ >>

CRCATIOA'HEELER LA<E 84LOV iFV A ~ SHCRf L ICE It)OI v OU-'L

~ I YRC Y) I ~ 6C-0? I 7r-02

~

POPO' I I Oh; (HAlt-Rr

~

?+5C-62 2 ~ 2 2 2e O'02 2 2E- 0'2 I ~ 9E-02 2.7E-02 "f-04 'C-04 8 ~ I" CATER I "DIVIDUAL lHRrr)

T'OPU' IGX I H A'-RE, Pi 04 5.4C-~5 c ~ I 2 ~

-15 ~:z=v~

2 2 ~

~

4r E - 5 C~ A80V -I'ATER

~ I'i IVIOUAL IAPCH)

PCi JL T IC'I IHAt'CY) I~ 4C 04

~ ~

".1E-6<

. ~ 7L-05 2:6E~C ITIC-04 r..-

9 'E-05

~;a.-lc 1..4E-04 IV ~ TOTAL

".AX I "U". IiOIV: ~ 'L CHILO l "FE") " (..I - f" '.--' -G2 I lC=~'C 2.FE-02 2 'E-02

- 1'4U-'0

. ~ MAXI>UH IVOIVI >>-L AotJLT IYPC .) ~ ~ 6 2 C ~ TE i ~ ESSEE RIV'CPULAT Ctt l A't ~ RC ') 4 ~ 9E~ 0; 4.2C~GQ 4.5Ei(0 7 ~ 6E i'3 4 5E~GO 3.5E-03 = 3.5 x 10 S

a 3 >E-03 - 3.5 x 10 B Table 14 Li uid Effluent Doses Browns Ferry iVuclear Plant Routine Releases Second uarter 1983 80"E Gl T66 ACt THYROID TOtAL BOOT LIVER SKIN I ~ (:ATFR I VGEST'10tl AT U~S ~ PLY'6(OOD-Cl AHP ION I'APCR a

6(AXIHUH INDIVIDUAL CHILD (HREH) 3 ~ IC-G3 3 'E-G4 4 'C-C3 7.5C-04 3 'E-03 USE-04 B. YAxlrUr. INDlvIOVAL ADVLt (..RCH) l. 3r 03 5 'E-04 3.1C-G3 I ~ 3L-03 1 ~ PE-03 I ~ 3C-C3 C ~ TE!lNESSEE RIVER POPULATIO!l (Hhtl-REH) 1 9~-(2 3.6E-03 2 2 c I 2E-02 2 'E-02 I ~ 2C-02 II ~ FISH I'lGESTION FROH WHEELER LAKE BELD" BFN A~

8 HA XIHUY I'lDI VIDUAL CHILD HA X IHVH 16(OI VIDUAL ADULT (YREH)

(HREH)

V.

5 I6-6 St-02 6

7

.. 6-"L6

'E-03 6 ~

7 66-6 3E-0?

~ 6 7

66,-92

'E-C2 6 ~ EE.-O~

9.9C-02

.66=62 7 2E-02

&.1560'.7E-QI

~

C TENNESSEE R IVER POPULATION (HA.'t-REH) . 5 BE GQ 5 7E 0( '9 &~~+GO So 7E~~

III'ECREATION At

)tHECLER LAKE BLLOM HFN 4~ SHORELItlE INDIVIDUAL (YREY) I.ec-02 I.ec-02 1.4C:92 I 6E-02 4C-02 I ~ 9C-02 POPULATION (HAN-REH) 9 4C-(62 8 'E-02 7.4E-02 8.4E-G2 7. IE-02 16 QE~Q 8 ~ I V-)TATER I 'lDI VIDUAL (HRCt()

POPULATIOt.'riAN-RCH) 66-66 I.SC-04 6 6C-64 I ~ 2E-04 P,6~6$

1 ~ IE-04

,6 66 I ~ 3C-04 I 6 IE-04

.62E=B 1 ~ 6C 04 C ~ ABOVE-RATER I!(DIVIDUAL (HREH) 3. Pc- 066 ~ 6C-04 2.4E-G4 266C-04 2 62E-04 3~ IC 04 POPULATION (l'.AN-REH) 4 ~ QP 066 2E-04 2.9E-04 3.4C-G4 2.9E 04 4 'C-04 IV ~ TOTAL A ~ 6(AXIHUH INDIVIDUAL CHILD (HREH) 9 'E-02 I ~ BE-C2 3 'E-02 3 ~ 3E-02 1 ~ IC-QI 366'-02 8 l AXIHUY I)lot VIDUAL ADULT (t(RLH) 7 'C-:-2 2 'E-02 961E-02 9 'C 02 1 ~ IE-01 9 'E-02 C~ TENNESSEE RIVER POPULATIOtl (HA!<-REH) 6.2E-QO 6+St-01 5-9L+00 ST 8C+00 9 ' ~ + 0 3.1E-03 = 3.1 x 10

Table 15 Browns Ferr Nuclear Plant - Five-Year Summar of uarterl Doses Air Submersion Li uid Effluents Air-T Air-P Skin Total Body Maximum Organ Total Body Maximum Organ Year Quarter (mrad) (mrad) (mrem) (mrem) (mrem) (mrem) (mrem) 1978 3 1.41 13.20 4.60 .89 .17 Thyr. .04 .08 GI Tract 4 .43 4.16 1.42 .26 .08 Thyr. .08 .27 GI Tract 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 l. 19 .26 Thyr. .04 .04 Thyr.

4 2.25 16.00 5.65 1.27 .14 Thyr. .06 .06 Thyr.

a .21 .11 Thyr. .05 .03 Thyr.

1980 ] .35 ~ 44 .31 2 .39 .48 .33 .22 1.19 Bone .03 .Ol Thyr.

3b .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 .>6 .09 .07 .13 Bone .11 .13 Liver 2 .33 .52 .23 .17 .11 Bone .06 .07 Liver 3 .27 .35 .37 .2/ .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 Liver Plant procedures were revised in early 1980 for determining more realisticially 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.

'P T

NNESSEE VALLEY AUTHOR i Y Browns Ferry Nuclear Plant P.'. Box 2000 Decatur, Alabama 35602 FEB 02 1983 Director, Office of Inspection and Enforcement Nuclear Regulatory Commission 101 Marietta Street Suite 3100 Atlanta, Georgia 30303

Dear Sir:

As required by Regulatory Guide 1.21, Revision 1, we are submitting the enclosed, report of radioactive discharges released from Browns Ferry during the period of July l, 1982 thru.December 31, 1982.

The corresponding report on the "Radiological Impact on Man" will be forwarded separately by TVA's Radiological Hygiene Branch. (

Very truly yours, t TENNESSEE VALLEY AUTHORITY.

G. T. Jones Power Plant Superintendent Enclosure cc:, Milliam J. Taylor Chief, AL/MS Compliance Group Mater Enforcement Branch Enforcement Division 305 Courtland Street Atlanta, Georgia 30308 gg James M. Marr p(~-

Alabama Mater Improvement Commission State Office Building Montgomery, Alabama 36130 An Equal Oppo'rtunity Employer

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