incomplete 'effluent & waste disposal semiannual rept, … · 2018. 9. 27. · 1 v...

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. Liquid effluents: sum of individual MPC ratios g 10

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.

tI

Allowa'nce is made for a plus or minus one sigma counting error associated

with gamma isotopic analyses.'DESIGNATED ORIGIMII

R

Ce"tifie6 B

ll ~

~ E

EFFLUENT AND HASTE DISPOSAL SEMIANNUAL REPORT

SUPPLEMENTAL INFORMATION (CONTINUED)

FIRST HALF 1983II

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 ueFirst Second

a. ~tutd Quarter Quarter

( 1) Number of batches released 126 102 Each

(3) Maximum time period for a batch release 1920 960

(2) Total time period for batch releases 52952 38134 Minutes

Minutes

(4) Average time period for batch releases: 420.25 373.86 Minutes

(5) Minimum time period for batch releases 20 70 Minutes

b.

(6) Average stream flowrelease of effluent

gaseous

during period ofinto a flowing stream1

None

1To be supplied by others.

EFFLUENTS AND WASTE DISPOSAL SEMIANNUAL REPORT

FIRST HALF 1983

LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES

A. ission and ctivat on roducts

1. Total Releases (1)

First Second~ni ~ua ~te ~ua ~te

Curies 7.60E+00 2.57E+00 +1.50E+01

2. Average Diluted Conc. DuringPeriod

3. Percent of Applicable Limit0

B. ~itXum

1. Total Release

uCi/ml '.58E-083.80E+01

Curies 1 . 17E+01

1.22E-08

1 . 29E+01

6.11E+00

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

3. Percent of Applicable Limit(3E-03 uCi/ml)

C. issolved and ntrained ases

1. Total Release

2. Average Diluted Conc. Dur ingPeriod

1.32E-03 9.67E-04

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

Uci/101 .<5.22E-09 <8.06E-10

3 . Percent of Applicable Limit(6E-06 uCi/ml) <8.71E-02 <1.34E-02

D.

E.

ross A ha Radioactivit

1. Total Release

Volume of Waste Re ease

Cur ies 8. 05E-05 5. 05E-04 +1. 70E+00

F.

(before dilution) Liters 1.25E+07

2.95E+11o ume of Di ution Water for Period Liters

8.45E+06

2.11E+11

~+ . 00E+00

+1 . 00E+00

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


LIQUID RELEASES FOR FIRST HALF 1983 BATCH MODE

soto e

2 ~

Strontium-89(3)

Strontium-90(3)

3 ~ Cesium-134

Cesium-137

5 ~ Iodine-131

6 ~ Cobalt-58

7 ~ Cobal t-60

8 ~ Iron-59

9. Zinc-65

10 'anganese-54

11. Chr'omium-51

12 ~ Zirconium-Niobium-95

13 ~ Molybde nun-99

14 'echnetium-99m

15 ~

16 ~

Barium-Lanthanum-140

Cerium-141( 2)

17. Sodium-124

18 'luorine-18ota for Period

(1) Quantities listed are in cur ies.

First~ua ~te

5.31E-03

1.21E-03

<5.90E-02

<7.60E»02

<5. 14E-02

<2. 61E-03

<3.35E-02

<3.70E-03

<7.60E-02

<4.47E-03

<1.49E-02

< 4. 56E-03

< 3. 07E-03

<3.07E-03

<6.40E-03

<1.26E-02

<1.20E-02

<1.21E-03

<3.71E-01

Secondgu~ater

2.25E-03

5.27E-04

<9. 83E-02

<1.16E-01

<1.83E-02

<1.13E-03

5.80E»02

<1. 37E-03

8.35E-02

<3.03E-03

<1. 36 E-02

<4.02E-03

<1. 45E-03

<1.45E-03

<8.11E-04

<2.10E-02

<3.63E-02

<4.41E-04

<4. 61E-01

(2)calculated by multiplying Cs134 by a factor of 0.2133. (Established byratio CE141/CS134 in March 1979). A new ratio of 0.1570 wasestablished in December 1982 ~ For conservatism, use of 0.2133 factor willcontinue ~

(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)

1. Type of Waste n tFirst~ear te

SecondQueer t e

a. Spent resin, filter sludges,, m3evaporator bottoms, etc. Ci

173.051886

250.52226

b. Dry compressible wastecontaminated equip., etc.

c. Irradiated Components,control rods, etc.

817H drumsCi

408(3060 ft )34.1

846(6345 ft )298.1

d. Other (describe) Boxes BoxesCi

30(2890.5 ft ) 248(20434.8ft0.245 1.9

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

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

/nitFirstquarter

12.57 (237 / 1886)

29.59 (558 / 1886)

9.86 (186 / 1886)

17.13 (323 / 1886)

16.22 (306 / 1886)

0.47 ( 8.77/ 1886)

7.00 (132 / 1886)

0.50 ( 9.48/ 1886)

0.42 (7.98/ 1886)

Second~ear te

14.33 (319 / 2226)

26.59 (592 / 2226)

4.04 ( 89 / 2226)

20.26 (451 / 2226)

18.28 (407 / 2226)

0.70 ( 15 / 2226)

8.85 (197 / 2226)

0.35 (7.69/ 2226)

0.04 (0.94/ 2226)

soto e


LIQUID RELEASES FOR FIRST HALF 1983 BATCH MODE

First1~ua ~te

Second1~ua ~te

thers ot e uired for e Guide

1. Xenon-133

2. Xenon-135

3. Iodine-133

4. Cesium-136

5. Manganese-56

6. Antimony-122

7. Antimony-124

8. Copper-64

9. Arsenic-76

10. Arsenic-74

11. Iodine-135

12. Bromine-82

13. Silver-110m

14. Antimony-125

15. Samariam-153

1.52E+00

3. OOE-01

<3.69E-02

<2.74E-03

<9.44E-04

<7.85E-03

<2.27E-03

< 1 . 90E-02

<2. 16E-02

<3. 1 8E-03

<8.82E-03'3

93E-03

<1.28E-02

<6.41E-03

<3.63E-03

< 1 . 47E-01

<2.32E-02

<3.89E-03

<1.69E-03

<1.75E-04

<4. 13E-03

<1.06F 03

<2. 15E-02

<2.24F 02

<1.70E-03

<4.05E-03

<2.39E-03

<1.77E-03

< 1 . 32E-03

<2. 11E-03

1Quantities listed are in curies.


FIRST HALF 1983

SOLID WASTE AND IRRADIATED FUEL SHIPMENTS (CONTINUED)

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

a. 10. Lanthanun-140

11. Antimony-120

12. Strontium-90

13. Manganese-54

14. Silver-110M

15. Iron-59

16. Other Nuclides

b. 1. Chromium-51

2. Zinc-65

3. Iodine-131

4. Cesium-137

5. Cesium-13 4

6. Cobalt-58

7. Cobalt-60

8. Zirconium-95

9. Niobium-95

First~u t . Quarter

2.05 (38.7/ 1886)

0. 03 ( 0.635/1886)

0. 01 ( 0. 142/1886)

0.74 (13.9/ 1886)

1.20 ( 22.7/ 1886)

0.0,8 (1.52/ 1886)

2.08 (39.2/ 1886)

10.67 (3.64/ 34.1)

37.54 (12.8/ 34.1)

16.77 (5.72/ 34.1)

10.65 (3.63/ 34.1)

9.33 (3.18/ 34.1)

' 0.16 (0.0542/34.1)

5. 54 ( 1.89/34. 1)

0.75 (0.255/34.1)

0. 21 ( 0. 0708/34. 1)

Second~ua ~te

2.01 (44.7/ 2226)

0.04 ( 0.88/ 2226)

0.01 (0.25/ 2226)

1.03 (22.9/ 2226)

1.50 ( 33.3/ 2226) "

0.13 (2.79/ 2226)

1.98 (44.09/2226)

11.87 (35.39/298.1)

44 95 (133 99/298-1)

3.31 (9.87/298 ~ 1)

13.31 (39.68/298.1)

10.26 (30.58/298.1)

0.74 (2.2 / 298 ~ 1)

9. 91 (29.53/298. 1)

0.40 ( 1.18/298.1)

0.61 (1.83/298.1)

~~

I If


FIRST HALF 1983


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

b. 10. Lanthanum-140

11. Antimony-124

12. Strontium-90

13. Manganese-54

14. Silver-1 10M

15. Iron-59

16. Other Nuclides

First~ui ~uarte

3.67 (1.25/34.1)

0.04 (0.0130/34 F 1)

0.003 ( 9 77E-4/34 1)

0.43 (0 '45/34 ')0.63 ( 0.215/34 ~ 1)

p 0.10 (0.0335/34.1)I

3.52 ( 1.20/34.1)

Second~uarte

0.85 (2.53/298.1)

0.06 (0.19/298.1)

0. 01 ( 0. 04/298. 1)

1.11 (3.30/298.1)

1.27 (3.78/298. 1)

0.25 (0.76/298.1)

1.11 (3.32/298.1)

c. Irradiated Components, Control Rods, etc. None

d. 1. Chromium-51

2. Zinc-65

Iodine-131

Cesium-137

5; Cesium-13 4

6. Cobal t-58

7. Cobalt-60

8. Zirconium-95

9. Niobium-95

22 ~ 12 (5.42E-2/0.245) 5.47 (0.10/ 1.9)

12.82 (3.14E«2/10.245) 12.32 (0.24/ 1.9)

11.22 (2.75E-2/0.245) 9.54 (0.18/ 1.9)

0.22 (5.39E-4/0.245) 0.56 (0.01/ 1.9)

5.76 (1.41E-2/0.245) 9.04 (0.17/ 1.9)

1.04 (2.54E-3/0.245)

0.25 (6.18E-4/0.245)

0.45 (0.01/ 1.9)

0.10 (0.02/ 1.9)

$ 9.96 (2.44E-2/0.245) '.82 (0.15/ 1.9)

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


FIRST HALF 1983


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

Firstgnat guarder

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

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

12. Strontium-90 $ 0.004 (8.72E-6/0.245)

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

Second~ua ~te

2.39 (0.05/ 1.9)

0.04 ( 0.0008/1.9)

0. 01 ( 0. 0002/1. 9)

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 nationFirst~ua ~te

422

Second~uar er

5723

Sole Use TruckSole Use Truck

Barnwell, SC

Richland, WA

B.a

r adiated uel hi ments (disposition)

um e of hi ments de of T ans o tat st at oFirst~ear te

NA

Second~ua ter

NA NA NA

( 1)Combination box/drum shipments on these dates.'( 1)Combination of irradiated components, regular boxes and drums shipped.


FIRST HALF 1983

GASEOUS EFFLUENTS - SUMPTION OF ALL RELEASES

Summation of ll eleases

A. Fission and Activation Gases

First~nt ~na ter ~E~or

Secondua teZ $ gy~

1. Total Releases

2. Avg. release rate for period

3. Percent of technicalspeoification limit

B. ~odines

Total Iodine-131


3. Percent of technicalspecification limit

<1.46E+05 +7.60E+00

uCi/sec. <1.86E+04

<3.71E+01

1.00E-01 +1.22E+01

uCi/sec. 1 .27E-02

3.19E+00I

<9.19E+04 +7.60

<1. 17E+04

2.34E+01

5.21E-02 +1.22

6.63E-03

1.66E+00

1. Particulate with half-lives )8days


Ci <6.01E-02 +1.05E+01

uCi/sec. <7.65E-03

<3.77E-02 +1

.05'.80E-03


4. Gross alpha radioactivity

D. Tritium

Ci

1. 91E+00

<4.05E-09

1 .20E+00

<8.24E-07

1. Total release


Ci 1.22E+01 ~+.OOE+00

uCi/sec. 1.55E+00

1 . 44E+01 ~+ .00i

1.83E+00


4. Ground level releases

5. Elevated release Ci

2.86E+00

1.20E+01

1 .76E+01

1.49E+00

1 .41E+01

2.95E-01

(l) Reporting period - 181 days


FIRST HALF 1983

GASEOUS EFFLUENTS - ELEVATED RELEASE

First~ua ~te

Second(~ua ~te

Krypton-85

Krypton-85m

Krypton-87

Krypton-88

Xenon-133

Xenon-135

Xenon-135m

Xenon-138

Others (specify)

Argon-41

Unidentified

ota for Period

Ci

Ci

Ci

Ci

Ci

Ci

Ci

Ci

Ci

Ci

<1. 58E+03

<2. 35E+04

<8. 90E+03

<2. 07 E+04

<8.66E+04

<2. 06 E+02

<5. 65E+02

<3.00E+03

<8.33E+01

NA

<1.45E+05

< 1 . 21E-03

< 9. 0 9E+03

<2.72E+03

<8.20E+03

< 1. 89E+04

<3. 45E+02

<3.05E+04

<2.00E+04

<2.46E+02

NA

<9.00E+04

2. ~ofnes

Iodine-131

Iodine-133

Iodine-135

Ci

Ci

9.36E-02

3.28E-02

5-21E-02

4.81E-03

1.08-02 4.65E-03

otal for eriod Ci 1 . 37E-01 6. 16E-02


FIRST HALF 1983

GASEOUS EFFLUENTS — ELEVATED RELEASE (Continued)

3.

Strontium-89

Strontium-90

Cesium-134

Cesium-137

Barium-140

Zirconium-95

Niobium-95

CubaX+~58

Manganese-54

Zinc-65

Iron-59

Cobal t-60

nit

Ci

Ci

Ci

Ci

Ci

Ci

Ci

Ci

Ci

Ci

First~ua ter

9 ~9E-05

9.27E-06

<7.51E-05

<1.32E-04

<6. 50E-04

<2-62E-03

<7 45E-05

<1. 08E-04

<1.74E-04

<1.53E-04

'1.56E-04

6 . 82E-05

Second~ua ter

3.68E-04

4.93E-06

<4.64E-05

<5.06E-05

<1.70E-04

<3. 87E-03

<4.60E-05

<5. 18E-05

<7.28E-05

<1.01E-04

<8.93E-05

<8.19E-05

Others (specify)

Lanthanum-140 Ci

Total for Period Ci

<1. 25E-02

<1.68E-02

< 8. 57E-04

<5. 81E-03

Tritium

Predicted estimation of release(1)Ci 1.76E-01 2.95E-01

4

4


FIRST HALF 1983

GASEOUS EFFLUENTS - GROUND LEUEL RELEASES

Un tFirstquarter

Second~uar te

u—"'"Krypton-85

Krypton-85m

Krypton-87

Kr ypton-88

Xenon-133

Xenon-135

Xenon-135m

Xenon-138

Others (specify)

Argon-41

Unidentified

Ci

Ci

Ci

Ci

Ci

Ci

<1.01E+00

2.16E+01

<5. 42E+01

<5.59E+01

<1.55E+02

<1.04E+02

<9.18E+01

<3.50E+02

<2. 29E+02

<3. 03E+02

<4.10E+01

<1. 12E+02

<6.94E+01

<2.56E+02

<5.57E+01

<2.20E+02

<7.78E+02

<6.02E+Ol

NA

Total for Period Ci <8.56 E+02 < 1 . 90E+03

2. ~ediuea

Iodine-131

Iodine-133

Iodine-135

Ci

Ci

Total for Period Ci

6 .59E-03

<2. 08E-03

<8. 53E-03

<1.72E-02

2.43E-06

<3.81E-03

< 1 . 59E-02

<1.97E-02

EFFLUENTS AND 11ASTE DISPOSAL SEHIANNUAL REPORT

FIRST HALF 19834

GASEOUS EFFLUENTS - GROUND LEVEL RELEASES (Continued)

uarter ua ter

3 |!"Strontium-89

Strontium-90

Cesium-134

Cesium-137

Barium-140

Zirconium-95

Niobium-95

Cobalt-58

Hanganese-54

Zinc-65

Iron-59

Cobalt-60

Others (specify).

Lanthanum-140

Ci

Ci

Ci

Ci

Ci

Ci

Ci

Ci

Ci

Ci

2. 82E-04

1 . 17E-04

<2.43E-03

<2.51E-03

5.86E-03

<4.23E-03

<1.86E-03

<1.82E-03

<1.83E-03

< 5. 56 E-03

<5.04E-03

4.59E»03

<7.18E-03

2.00E-04

5. 08E-05

<8.56E-04

<9.34E-04

6 .26 E-04

<1.68E-03

< 1 . 77E-02

<5.25E-04

<5.70E-04

<2.75E-03

<1.14E-03

2.59E-03

<2.29E-03

Total for Pe iod <4.33E-02 '3.19E-02

4. Tritium(1) Predicted estimation of releases.

Ci 1.20E+Ol 1. 41E-01

~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

>ALS

N<>I>l<~ I~ .">s<": 7 A<1'l<>s( ~

I3 A 1

I'Ios('ot.a

I hody2

Ski n2

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

30

f>O

15

II~ . I:.

I.'.)x.

Vxp.'()

si d en c(

Residences

0.4 j mr.><l

O. 45 Ii» ')(I

0. 16 mrem

0.24 mrem

a <> 4

')374h7

'>3>)

755>> 6 >>

,> H'>

743>') 5>

>6

>(>(>

>7>>

<75

Ban�('cri

Lira 1 organ)

II) <;>k<l<>wn «I lodin(/I':)rt i culat( I'.xposures (mrem)

>It( getabl( lng( sL ian

IIPPIIngesL)an'nE)al

)Lian

Grour)<l Cont.aminaLion

Re;) 1

Pa t.hway"

Ch)ld

2.2.'3 x 10

2.78 x 10 ')

1.52 x 10

2.60 x 10 2

0.25 mr('m

Adult

8.6:3 x IO

1.98 x 10

'>.53

x 10 "

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 - InrlivirluaI Doses From Gaseorrs I'.fflrrenLs

Srrconrl err;rrtcr l983

I,"ffluerrL ~Pa Lhwa

Noble gases T Air. dose

P Air. dose

Total bodyS

Skins

I orli rros/I';r r t, I err I a Les

Gui de 1 ine"

30

60

45

Point.

Hax. Exp.r

llax. Exp.2

Residence"

Residence"

Dose

0.48 mrarl

0.42 mrarl

0.19 mrem

0.32 mrem

Tlryroid(critical organ)

RealPathway"

0.31 mrem

llrr ak<lowrr ol'orlirre/I'arL I err laLe I'.xposrrres (mrem)

Vegetable Irrgestion

Heel'ngestiorr2

I nba 1 a t. ion

Clri ld

2.20 x 10

'<lu lt

1.04 x 10

2.25 x l.0 2.11 x 10

1.78 x 10 2 8.89 x 10 s

Ground Contamination

Tota I

7.44 x 10 2

3.14 x 10

7.44 x 10 2

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

SVBHER S ION

GROV> 0

I'iH«L

AT�)ON

CO«H I LK

BE F INGEST ION

YEG INGEStIGN

INF ANTLIY

CHILi" t ~ CN TOtALS

a1,44c.-01 9 ~ QOC-Cl 5 ~ 73C-01 2 ~ 65E~ 00 4 ~ 27i+00

5 24c.-03 3 ~ 27E-0? 2 ~ OBC-02 9 ~ 64C-0? ) ~ 55i-0)

5 ~ 72C-03 6 ~ 32i-G2 2 ~ 63E-02 8 ~ BOC-02 I o84 -Ol

1 ~ 985-03 6 '4C-C3 I o9E-03 6."6c.-03 I ~ 73"-02

0 ~ OOE 00 2 '3C-03 1 13E-03 6 '2E-03 4 ~ 6:C-03

0 ~ OOE~ 00 I ~ 42E-03 7 '6i-04 3. 85E-03 6 OGC-03

I'sF ANT:"Or.C

Cr)L= TICN

I ~ 44. -Gl 9 ~ COC-Gl 5 ~ 73C-01

«DVLI

2 6SE "C

TO'IAL4

4 '7E~CO

44r Gl 3 '7E-02 2 '6E-02 9 '4E-02

I ~ 94E 0 I 2 ~ 05C 03 F ~ 22E 04 2 ~ +OE 0 6 ~ 371 C3

I ~ 55E-C3 6 56E-03 I 56E-03 5 '7C-03 ) ~ 54F-02

O.QCr QG ).AFE-03 6.76E-04 3.73i-03 6.27F-C3

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)." :.".ULt TOTALS I NF AN T

tOTAL BOOTerr l1.o 'Tier,'DULT TGTALS

SUBHCRS ION

GoQUND

I NIALAt ION

C54 H ILcc

BCEF I'JGCS I ION

YCG I rrGEST IOrr

-7.37E-03 4.5. E-9? 2 ~ 92C-02 I. '5r-Cl

2 ~ 39i-03 2 ~ 44i" 02 9m44E-03 3 ~ 61C-"2

2. ) ir-7 ~ 745- 2

I 13E-Ql 2 9)E-Cl 7 ~ 72C-02 2 ~,?E-Ql 7 ~ 7 i-01

G ~ OQE+QQ 3 22E«03 I ~ 38C-Oc 8 ~ 431.-93

0 ~ OQE+ QO 3 ~ I BC-02 I ~ 36C-02 7 ~ 86C- 42

I ~ 3i". -02

I ~ 24C nl

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

7 ~ 37r-03 4 ~ 59C-02 2 ~ 92E-02 I ~ 35C- 1 2 ~ 16C-91

I ~ 9ir-C3 2 '3E-02 7 '4E-03 2 '4C-92 5 '3C-02C3E- 94 I 74E-03 7.09E'-04 3 '8r -03 6.448-93

O.OQC 09 2 '6E-04 I ~ 99C-04 I ~ 745-93 2.2)E-03

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

Table 13

Li uid Effluent DosesBrowns Kerr Nuclear Plant Routine Releases

I o I ATER IMGCST IOlt ATU ~ S ~ PL YVCOO CH'P I Gt, P»PER

Pptt f GI T=::. Thv&GIO TOTtL ROOT LIVEP SK I 'I

A ~ " ' I "UH I'eO I VIDUAL CHIT.O I YRC'4)9 ~ MAXIMUM IhOI V)DU L ADULT IMRC ') Ic. TEt.ttcssEc R IvER popULATIGU IYAtt-REH) 2.

a5C-036L'-034E-02

I ~ 4 -02I ~

v TE-92 Ie

42C-03 ).6C-C3 I ~ 2E-G3

11 ~ F ISH Ii)GEST I 0)t FROM'WHEELER LAKE BELO" SF"

MAX IHUH I:TOI VIOL'AL Ctll LO IHPCH)6. YAXI..UY It:OIvIDUAL AOULT lrRCY)C ~ TEA'SSEE R lvr" +OPULATIOU IHt tt-RrH)

r>.5r-024 ~ 3j, 024 ~ 9E+CG 6 ~ 4

6.6C-C2 I ~ 2C-0?E-4'P 5:5E=~ 6r= .5: E

r'--'oiE~C

C C+00 7.6E+00

111 ~ »CRCATIOA'HEELER

LA<E 84LOV iFV

A ~ SHCRf L ICE It)OI v ~ OU-'L I YRC Y)POPO' I I Oh; (HAlt~ -Rr

I ~ 6C-0??+5C-62 2 ~ 2 2 2e O'02 2 2E- 0'2 I ~ 9E-02

I ~ 7r-022.7E-02

8 ~ I" CATER I "DIVIDUAL lHRrr)T'OPU' IGX I H A'-RE,

C ~ A80V ~ -I'ATER I'i IVIOUAL IAPCH)PCi JL T IC'I IHAt'CY)

Pi 045.4C-~5

I ~ 4C 04

c ~ I':

~ ~

2 ~ "f-04 2 'C-04 2 ~ 4r-15 ~:z=v~ ~ E - 5

".1E-6< 2:6E~C r..- ~;a.-lc. ~ 7L-05 ITIC-04 9 'E-05 1..4E-04

IV ~ TOTAL

".AX I "U". IiOIV: ~ 'L CHILO l "FE"). ~ MAXI>UH IVOIVI »-L AotJLT IYPC .)

C ~ TE i ~ ESSEE RIV'CPULAT Ctt l ~ A't RC ')

2.FE-02 2 'E-02" (..I - f"~'.--' ~ 6 -G2 I lC=~'C - 2 1'4U-'0

4 ~ 9E~ 0; 4.2C~GQ 4.5Ei(0 7 ~ 6E i'3 4 5E~GO

3.5E-03 = 3.5 x 10 S

a3 >E-03 - 3.5 x 10 B

Table 14

Li uid Effluent DosesBrowns Ferry iVuclear Plant Routine Releases

Second uarter 1983

80"E Gl T66 ACt THYROID TOtAL BOOT LIVER SKIN

I ~ (:ATFR I VGEST'10tl ATU ~ S ~ PLY'6(OOD-Cl AHP ION I'APCR

6(AXIHUH INDIVIDUAL CHILD (HREH)B. YAxlrUr. INDlvIOVAL ADVLt (..RCH)C ~ TE!lNESSEE RIVER POPULATIO!l (Hhtl-REH)

a3 ~ IC-G3l. 3r 031 9~-(2

3 'E-G45 'E-043.6E-03

4 'C-C33.1C-G32 2 c

7.5C-04 3 'E-03 USE-04I ~ 3L-03 1 ~ PE-03 I ~ 3C-C3I 2E-02 2 'E-02 I ~ 2C-02

II ~ FISH I'lGESTION FROHWHEELER LAKE BELD" BFN

A ~ HA XIHUY I'lDI VIDUAL CHILD (YREH)8 ~ HA X IHVH 16(OI VIDUAL ADULT (HREH)C TENNESSEE R IVER POPULATION (HA.'t-REH)

V. I6-6 6 .. 6-"L6 6 ~ 66-6 ~ 6 66,-92 6 ~ EE.-O~ .66=625 St-02 7 'E-03 7 3E-0? 7 'E-C2 9.9C-02 7 2E-02&.1560'.7E-QI . 5 BE GQ 5 7E 0( '9 &~~+GO So 7E~~

III'ECREATION At)tHECLER LAKE BLLOM HFN

4 ~ SHORELItlE INDIVIDUAL (YREY)POPULATION (HAN-REH)

I.ec-02 I.ec-02 1.4C:929 4C-(62 8 'E-02 7.4E-02

I 6E-028.4E-G2

4C-027. IE-02

I ~ 9C-0216 QE~Q

8 ~ I V-)TATER I 'lDIVIDUAL (HRCt()POPULATIOt.'riAN-RCH)

66-66 6 6C-64 P,6~6$ ,6 66I.SC-04 I ~ 2E-04 1 ~ IE-04 I ~ 3C-04 I 6 IE-04

.62E=B1 ~ 6C 04

C ~ ABOVE-RATER I!(DIVIDUAL (HREH)POPULATION (l'.AN-REH)

3. Pc- 066

4 ~ QP 066

~ 6C-04 2.4E-G42E-04 2.9E-04

266C-043.4C-G4

2 62E-042.9E 04

3 ~ IC 044 'C-04

IV~ TOTAL

A ~ 6(AXIHUH INDIVIDUAL CHILD (HREH)8 l AXIHUY I)lot VIDUAL ADULT (t(RLH)C ~ TENNESSEE RIVER POPULATIOtl (HA!<-REH)

9 'E-027 'C-:-26.2E-QO

I ~ BE-C2 3 'E-022 'E-02 961E-026+St-01 5-9L+00

3 ~ 3E-02 1 ~ IC-QI9 'C 02 1 ~ IE-01ST 8C+00 9 '

366'-029 'E-02

~ + 0

3.1E-03 = 3.1 x 10

Table 15

Browns Ferr Nuclear Plant - Five-Year Summarof uarterl Doses

Air Submersion Li uid Effluents

Year QuarterAir-T(mrad)

Air-P(mrad)

Skin Total Body(mrem) (mrem)

Maximum Organ Total Body(mrem) (mrem)

Maximum Organ(mrem)

1978

1979

1980

1981

1982

1983

341

234]

a

23b

41

2341

2341

2

1.41.43

1.44.79

1.942.25

.35

.39

.40

.931.97

.28

.15

.09

.11

.33

.27

.19

.47

.48

13.204.165.017.00

12.9016.00

~ 44.48.52

1.092.11

.35

.19

.12

.>6

.52

.35

.23

.45

.42

4.601.422.242.494.365.65

.31

.33

. 31.

.641.40

.23

.11

.09

.09

.23

.37

.20

.24

.32

.89

.26

.89

.51l. 191.27

.21

.22

.21

.45

.96

.15

.07

.06

.07

.17

.2/

.13

.16

.19

.17 Thyr.

.08 Thyr.

.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.

.04

.08

.02

.02

.04

.06

.05

.03

.09

.15

.07

.21

.23

.05

.11

.06

.10

.07

.07

.09

.08 GI Tract

.27 GI Tract

.13 GI Tract

.07 GI Tract

.04 Thyr.

.06 Thyr.

.03 Thyr.

.Ol Thyr.

.11 Liver

.19 Liver

.10 Liver

.25 Liver

.28 Liver

.06 Liver

.13 Liver

.07 Liver

.12 Liver

.08 Liver

.09 Liver

.11 Liver

Plant procedures were revised in early 1980 for determining more realisticially Kr-85 releases via the plant

bgaseous 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.

NNESSEE VALLEY AUTHOR i YBrowns Ferry Nuclear PlantP.'. Box 2000Decatur, Alabama 35602

FEB 02 1983

Director, Office of Inspectionand Enforcement

Nuclear Regulatory Commission101 Marietta StreetSuite 3100Atlanta, Georgia 30303

Dear Sir:

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

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

Very truly yours,t

TENNESSEE VALLEY AUTHORITY.

G. T. JonesPower Plant Superintendent

Enclosurecc:, Milliam J. Taylor

Chief, AL/MS Compliance GroupMater Enforcement BranchEnforcement Division305 Courtland StreetAtlanta, Georgia 30308

James M. MarrAlabama Mater Improvement CommissionState Office BuildingMontgomery, Alabama 36130

ggp(~-

An Equal Oppo'rtunity Employer

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