ML18029A468

Environ Radioactivity Levels,Browns Ferry Nuclear Plant, Annual Rept - 1981. W/820505 & 0430 Ltrs

ML18029A468
Person / Time
Site:	Browns Ferry
Issue date:	12/31/1981
From:	Maxwell R TENNESSEE VALLEY AUTHORITY
To:	Cunningham A, James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
TVA-OMS-OHS-82-7, NUDOCS 8504100373
Download: ML18029A468 (188)

Text

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Region= zp Office of Director 0.'REILLYIJ ~ P, Region zi Office of Director

SUBJECT:

"Environ-Radioactivity Levels<Browns Ferry Nuclear Planti Annual. Rept 1981 '" N/820505 8

0430 ltrs, DISTRIBUTION CODE:

IE2BL COPIES RECEIVED:LTR J ENCL J SIZE:

TITLE: Periodic Environ. Monitoring Rept (50 DKT)-Annual/Semiannual/Effluent/

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BH's RASTER FILE REOULATORY INFORMATION tDSS IBUTION SYSTEM (RI

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TENNESSEE VALLEYAUTHORITY ENVIRONMENTAL RADIOACTIVITYLEVELS BROMNS FERRY NUCLEAR PLANT ANNUAL REPORT - 1981 TVA/OMS/OHS"82 7 DIVISIONOF OCCUPATIONALHEALTHANDSAFETY 8504100373'Sii231 PDR ADOCK 05000259 R

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ENVIRONMENTAL RADIOACTIVITYLEVELS BROWNS FERRY NUCLEAR PLANT ANNUAL REPORT - 1981 TVA OMS OHS-82 7

April 1982

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CONTENTS List of Tables

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o iii List of Figures.

Introduction

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iv Atmospheric Monitoring.

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Terrestrial Monitoring Reservoir Monitoring Quality Control.

Data Analysis.

Conclusions.

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LIST OF TABLES Table 1-Table 2'-

Table 3-Table 4-Table 5-Table 6-Table 7-Table 8-Table 9 "

Table 10-Table. 11-Table 12-Table 13 "

Table 14-Table 15-Table 16-Table 17-Table 18-Table 19-Table '20-Table 21-Table 22 Table 23-Table 24.-

Table 25-Table 26-Environmental Radioactivity Sampling Schedule Atmospheric and Terrestrial Monitoring Station Iocations - Browns Ferry Nuclear Plant Detection Capabilities for Environmental Sampl Analysis Results Obtained in Interlaboratory Comparison Program.

Maximum Permissible Concentrations for Nonoccupational Exposure Radioactivity in Air Filter Radioactivity in Rainwater.

Radioactivity in Heavy Particle Fallout Radioactivity in Charcoal Filters Radioactivity in Milk.

Radioactivity in Vegetation Radioactivity in Soil Radioactivity in Well Water Radioactivity in Public Water Supply.

Environmental Gamma Radiation Levels Radioactivity in Food Crops Radioactivity in Soybeans Radioactivity in Poultry Sampling Schedule - Reservoir Monitoring Radioactivity in Surface Water Radioactivity in White Crappie (Flesh Radioactivity in Smallmouth Buffalo (Flesh)

Radioactivity in Smallmouth Buffalo (Whole)

Radioactivity in Sediment Radioactivity in Clam Flesh Radioactivity in Clam Shell

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15 16 17 26 27 28 29 30 31 32 35 36 43 44 45 46 47 48 49 50

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LIST OF FIGURES Figure l

- Tennessee Ualley Region Figure 2

- Atmospheric and Terrestrial Monitoring Network.

Figure 3

- Local Monitoring Stations 3

18 19 Figure 4

Figure 5

TLD Locations, BFN Annual Average Gross Beta Activity in Air Filters, Browns Ferry Nuclear Plant 20 21 Figure.6-Annual Average Gross Beta Activity in Drinking Water, Browns Ferry Nuclear Plant 37 Figure 7-Direct Radiation Levels, BFN 38 Figure 9-Direct Radiation Ievels, WBN Figure 8 -

Direct Radiation I,evels, BFN (4-Quarter Moving Average) 38 39 Figure 10 - Direct Radiation Levels, WBN (4-Quarter Moving Average) 39

'igure ll - Reservoir Monitoring Network Figure 12 - Annual Average Gross Beta Activity in Surface Water 51 52

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ENVIRONMENTAL RADIOACTIVITYLEVELS BROWNS FERRY NUCLEAR PLANT ANNUAL REPORT 1981 Introduction The Browns Ferry Nuclear Plant (BFN), operated by the Tennessee Valley Authority, is located on a site owned by TVA containing 840 acres of land in Limestone County, Alabama, bounded on the west and south by Wheeler Reservoir (see figure 1).

The site is 10 miles southwest of Athens,

Alabama, and 10 miles northwest of Decatur, Alabama.

The plant consists of three boiling water reactors; each unit is rated at 3,293 MWt and 1,098 MWe.

Unit 1 achieved criticality on August 17, 1973, and began commercial operation on August 1, 1974.

Unit 2 began commercial operation on March 1, 1975.

However, a fire in the cable trays on March 22, 1975, forced the shutdown of both reactors.

Units 1 and 2 resumed operation and Unit 3 began testing in August 1976.

Unit 3 began commercial operation in January 1977.

The preoperational environmental monitoring program established a

baseline of data on the distribution of natural and manmade radioactivity in the environment near the plant site.

However, seasonal,

yearly, and random variations in the data were observed.

In order to determine the potential increases in environmental radioactivity levels caused by the plant, com-parisons were made between data for indicator stations (those near the plant) and control stations (those remote from the plant) in conjunction with com-parisons with preoperational data.

Staffs in the Division of Occupational Health and Safety and the Office of Natural Resources carried out the sampling program outlined in tables 1 and 19.

Sampling locations are shown in figures 2, 3, 4, and ll, and table 2 describes the locations of the atmospheric and terrestrial monitor-ing stations.

All the radiochemical and instrumental analyses were conducted in TVA's Western Area Radiological Laboratory (WARL) located at Muscle Shoals,

Alabama, and Eastern Area Radiological Laboratory (EARL) at Vonore, Tennessee.

Alpha and beta analyses were performed on Beckman Low Beta II and Beckman Wide Beta II low background proportional counters.

Nuclear Data (ND) Model 100 multichannel analyzer systems employing sodium iodide NaI(T1) detectors and ND Model 4420 systems in conjunction with Germanium Ge(Li) detection systems were used to analyze the samples for specific gamma-emitting radionuclides.

Samples of water, Vegetation, air particulates, food crops, and charcoal (specific analysis for I-131) are routinely counted with NaI(T1) detection systems.

If significant concentrations of radioisotopes are identified, or if there is a reasonable expectation of increased radioactivity levels (such as during periods of inc'reased fallout), these samples are counted on the Ge(Li) system.

Identification of gamma-emitting radionuclides in all other types of samples

is routinely performed by analysis on the Ge(Li) system.

A TVA fabricated beta-gamma coincidence counting system is utilized for the determination of I-131 concentrations in milk.

Data were entered in computer storage for processing specific to the analysis conducted.

A computer, employing an ALPHA-M least squares

code, using multimatrix techniques, was used to estimate the activities of the gamma-emitting nuclides analyzed by NaI(Tl).

The data obtained by Ge(Li) detectors were resolved by the ND4420 software.

The detection capabilities for environmental sample analyses given as the nominal lower limits of detection (LLD) are listed in table 3.

Samples processed by NaI(Tl) gamma spectroscopy were analyzed for 13 specific gamma-emitting radionuclides and radionuclide combinations For these analyses, a

radionuclide combinations such as 'u and sZr-Nb are analyzed as one radionuclide.

All photopeaks found in Ge(Li) spectra were identified and quantified.

Many of the isotopes identified by Ge(Ii) spectral analysis are naturally occurring or naturally produced radioisotopes, such as

7Be, 4oK, Bi 21~Bi

21zpb, z1~Pb, Ra, etc.

LLDs for the analysis of the radio-nuclides listed below are given in table 3B.

LLDs for additional radio-nuclides identified by Ge(Li) analysis were calculated for each analysis and nominal values are listed in the appropriate data tables.

In the instance where an LLD has not been established, an LLD value of zero was assumed.

A notation in a table of "

values

<LLD" for an isotope with no established LLD does not imply a value less than 0; rather it indicates that the isotope was not identified in that specific group of samples.

For each sample type, only the radionuclides for which values greater than the LLD were reported are listed in the data tables.

TVA's Radioanalytical Iaboratories participate in the Environmental Radioactivity Laboratory Intercomparison Studies Program conducted by EPA-Las Vegas.

This program provides periodic cross-check samples of the type and radionuclide composition normally analyzed in an environmental monitoring program.

Routine sample handling and analysis procedures were employed in the evaluation of these samples.

The EARL began processing samples in May 1980.

The results received during calendar year 1981 are shown in table 4.

The

+3a limits based on one measurement were divided by the square root of 3 to correct for triplicate determinations.

aThe following radionuclides and radionuclide combinations are quantified by the ALPHA-M least-squares computer code:

141>144Ce~ 51Cr'~

103~106Ru'4cs.

>>'.Cs,

".Zr-Nb. >>Co. ~'Mn. "Zn; "Co 4~K. and '4oBa-La.

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Table I ENVIRONMENTAL RADIOACTIVITYSAMPLING SCHEDULE Air Charcoal Rain-Heavy Particle River Well Public Aquatic Life daii t~eetatte Milk liat t Mate llatet aed dedicate Fe de Muscle Shoals W

Lawrenceburg W

Rogersville W

Athens Decatur W

M W

H W

M W

M W

H Courtland Site NW-1 Site N-2 Site NE-3 Site NW-4 W

W M

W H

W H

W H

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A Site WSW-5 W

Farm B Farm Bi/Farm P Perm H Perm T Farm L Control Farms Onsite Well Wheeler Dam Elk River Tennessee River Champion Paper Co.

Various Local Farms W - Weekly M - Hnnthly (every 4 weeks)

Quarterly S-Semiannually A-Annually

Table 2

Atmospheric and Terrestrial Monitoring Station Locations Browns Ferry Nuclear Plant Sam le'Station IM-1 BF, Northwest LM-2 BF, North LM-3 BF, Northeast LM-4 BF, Trailer Park LM"5 BF, Davis Farm PM-1 BF, Rogersville, AL PM-2 BF, Athens, AL Approximate Distance and Direction from Plant 1.0 Mile 0.9 Mile 1.0 Mile 1.7 Miles 2.5 Miles (1. 6 kilometers)

" N (1.4 kilometers)

NNE (1.4 kilometers)

ENE (2..7 kiloineters)

NNW (4.0 kilometers)

WSW 10.9 Miles (17.5 kilometers)

NE 13.8 Miles (22.2 kilometers)

NW PM-8 BF, Decatur (Trinity), AL 8.2 Miles (13.2 kilometers)

SSE PM-4 BF, Courtland, AL RM"1 BF, RM-2 BF, Farm S

Farm B

Farm H

Farm T Muscle Shoals, AL (Control)

Lawrenceburg, TN (Control)

Farm Bi (Out of business 7/20/82)

Farm P (Sampling begun 8/3/82) 4.75 Miles 7.0 Miles (7.6 kilometers)

N (11.3 kilometers)

NNW 3.75 Miles (6.0 kilometers)

N 7.0 Miles 4.5 Miles (11.3 kilometers)

ENE (7.2 kilometers)

ENE 8.8 Miles (14.1 kilometers)

E 10.5 Miles (16.9 kilometers)

WSW 32.0 Miles (51.5 kilometers)

W 40.5 Miles (65.2 kilometers)

NNW Farm N (Control)

Farm J (Control)

Farm C (Control)

Farm Ca (Control) 27.0 Miles 40.0 Miles 32.0 Miles 32.0 Miles (43.4 kilometers)

NW (64.4 kilometers)

NNW (51.5 kilometers)

N (51.5 kilometers)

W

Table 3

DETECTION CAPABILITIES FOR ENVIBONMENTAL SAMPLE ANALYSIS A.

S ecific Anal ses NOMINAL LOWER LIMIT OF DETECTION LLD +

Air Particulates

~C1 Charcoal

~cr Fallout Water mCi/km

~Ci 1 Vegetation and grain

~dr/

dr Soil and Sediment

~ci/

. dr

Fish, clam flesh,

plankton,

~cd/

dr

Foods, meat, Clam shells

poultry, Milk

~cd/

dr ccd/irk~a cdcriik Total n Cross n Cross 8

lN l llZ llS

'4Sr 0.005 0.01 0.005 0.001 0.02 0.4 2.0 0.05

2. 4 330 10 2

0.01 0.05 0.20 0.25 0.05 0.35 0.70 1.5 0.3 0.1 0.1 0.5 0.1 0.7 0.7 5.0 1.0 1.5 25 40 8

0.5 10 2

• AllLLD values for isotopic separations are calculated by the method developed by Pasternack and Harley as described in HASL-300.

Factors such as sample size, decay time, chemical yield, and counting efficiency may vary for a given sample; these variations may change the LLD value for thc given sample.

The assumption is made that all samples are analyzed uithin one veek of the collection date.

Conversion factors:

1 pCi

~ 3.7 x 10 Bq; 1 mCi ~ 3.7 x 10 Bq.

Table 3

DETECTION CAPABILITIES FOR ENVIRONHENTAL SAHPLE ANALYSIS B.

Camus Anal ses NOMINAL LOMER LIMIT OF DETECTION LLD Vegetation and grain

~Cl/

dr Mater and milk C1/1 Air particulates

~ct/

Soil and sediment

~Cl/

d Mal* ~Ce Li **

Naz

~Ce Li NaI

~Ce Li Nal

~Ce Lf Clam flesh Fish and plankton

~n/

dr '~CL/

dr N

1

~GLt N

1 ~CLt Foods, (tomatoes

potatoes, etc.)

Cf/

vet Clam shells

~Ci/

d NaI

~Ce Li Na I C~eLi Meat and poultry

~ct/ 1 e:

.'Nal Ce{LI1 1 te 1 N 1 0 de Ce C

"Cr 1311 103 ~ 10cgu 10CR 13<Ca 3 33Cs "Zr-Nb ssZT ssNb "Co s'Mn 0 sZn "Co K

3 ttOB l 008a 1 te 0 La

0. 03 0.02

0. 07

0. 03 0.01 0.01 0.04 0.03 0.01 0.02 0.01 0.01 0.01 0.01 0.01 0.02 0.01 0.02 0.01 0.02 0.01 0.01 0.01 0.10 0.02 0.02 0.01 38 0.55 33 60 44 1.10 15 8

0.35 40 0.65 40 10 26

0. 20 10 5

0 20 10 0.20 10 5

15 5

0.23 10 5

0.20 15 9

0 25 10 5

0.17 150 2'0 15 0.68 25 I

0 22 0.47

0. 09

0. 51 0.33 0.06 O.ll 0.05 0.05 0.05 0.11 0.06 0.34 0.08 0.35 0.06 0.60 0.10 0.20 0.02 0.45 0.11 0.12 0.08 0.12 0.02 0.12 0.03 0.01 0.20 0.01 0.15 0.01 0.23 0.02 0.11 0.01 0.90 0.15 0.07 0.02 0.35 0.06 0.60 0.10 0.20 0.02 0.45 0.11 0.12 0.08 0.12 0.02 0.12 0.03 0.01 0.20 0.01 0.15 0.01 0.23 0.02 0.11 0.01 0.90 0.15 0.07 0.02 0.35 0.56 0,07 0.74 0.48 0.08 0.15 0.07 0.07 0.08 0.17 0.08 0.30 0.10 0.35 0.06 0.60 0.10 0.'20 0.02 0.45 O.ll 0.12 0.08 0.12 0.02 0.12 0.03 0.01 0.20 0.01 0.15 0.01 0.23 0.02 0.11 0.01 0.90 0.15

'0.07 0.02 38 60 15 40 10 10 10 15 10 15 10 150 15 20 15 55 15 40 15 70 20 30

~

15 400 50 25 7

50 15 90 33 40 44 200 90 8

50 20 150 40 90 26 40 50 5

40 15 40 10 5

5 5

9 5

• The NaI(T1) LLD.values are calculated by the method developed by Pasternack and Barley as described in HASL-300 arid Nucl, Instr, Methods 91, 533 40 (1971).

These LLD values are expected to vary depending on the activities of the components in the samples.

These figures do not represenr the LLD'alues achievable on a given sample.

Mater is counted in a 3.5-L Harfnelli beaker.

Vegetation, fish, soil, and sediment are counted fn a 1-pint container as dry weight.

The average dry weight fs 120 grams for.vegetation and 400-500 graus for soil sediment and fish.

Meat and poultry are counted in a 1-pint container as dry vefght, then corrected to vet vefght using an average moisture content of 70Z.

Average dry vefght is 250 grams.

Air particulates are counted in a well crystal.

The counting system consists of a multichannel analyzer and either a 4" x 4" solid or 4" x 5" well Nal(T1) crystal.

The councfng time is 4000 seconds.

All calculations are peri'ormed by the least-squares computer program ALPHA-H.

The assumption fs mage that all samples are analyzed vfthin one week of the colleccion dace.

• >The Ce(bf)

LLD values are calculated by the method developed by Pasternack and Harley as described in HASL-300.

These LLD values are expected to vary depending on the activities of the components in the samples.

These figures do not represent the LLD values achievable on given samples.

Mater is counted in either a 0.5-L or 3.5-L Marinelli beaker.

Solid samples such as soil, sediment, and clam shells are counted in a 0.5-L Harinelli beaker as dry ~eight.

The average dry ~eight is 400-500 grams.

Afr filters and very small volume samples are counted fn petrfe dishes centered on the detector endcap.

The counting system consists of a ND-4420 multichannel analyzer and either a 25z, 14z, 16x, or 29z ce(Li) detector.

The counting time is normally 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

All spectral analysis is performed using the software provided with the ND-4420.

assumption fs made that all samples arc analyzed within one week of the collection date.

Conversion factorl 1 pCi 3.7 x 10 z Bq.

Table 4

Results Obtained in Interlaboratory Comparison Program A.

Air Filter (pCi/filter)

Date EPA value

(+3a)

. TVA AVC.

WARL EARL Gross Al ha Gross Beta EPA value TVA AVG.

(+30)

WARL EARL EPA value

(+3o)

TVA AVG.

WARL'EARL Strontium-90 EPA value

(+3a)

TVA AVG.

WARL EARL Cesium-137 12/80 3/81 6/81, 9/81 21+9 30+13 28+12 25+11 22 23 31 31 29 32 26 25 54+9 51+9 62 59 61 54 19+9 24 26 50+9 55 49 0

18+2.6 19+2.6 16+2.6 2

<2 18 15 19 23 16 19 19+9 14+9 16+9 19+9 20 22 15 14 17 18 21 20 B.

Tritium in Urine (pCi/L)

Date 3/81 6/81 9/81 11/81 EPA Value (+30)

.810+549 1600+585 2050+599 2700+615 TVA AVERAGE WARL EARL 713 390 1637 1830 2103 2573 2623 a.

Western Area'adiological Laboratory, Muscle Shoals, Alabama b.

Eastern Area Radiological Laboratory, Vonore,.Tennessee c.

Efficiency curves were checked and known spikes were run.

Everything found was within acceptable limits.

We are awaiting the next cross-check for further investigation.

d.

Results were mailed to EPA but not reported by them.

Table 4 (Contd)

Results Obcained in lncerlaboratory Comparison Program E.

Hi1k (pCi/L)

Scrontium - 89 EPA value TVA AVG.

3 * ~R IIARL EEIL Strontium - 90 EPA value TVA AVC.

~30 IIAAL EARL EPA value TVA AYG.

MARL EARL Iodine - 131 EPA value

~3 TVA AVC.

MARI.

EARL Cesium - 137 Barium - 140 EPA value TVA AVG.

I3a IIARL EARL Potassium EPA value

~33 TVA AVC.

'MARL EARL Cobalt - 60 EPA value TVA AVG.

~30 IIARL EAIIL 1/81 0

<10

<10 4/81 25i9 28 7/81 25+9 23 30 10/81 23i9 25 28 20 5.2 1 1i2. 6 17i2.6 18+2.6 21 20 13 14 16 17 16 26i17 26+10

.Oli 52i10 24 21 21 29

<15

<15 49 47 43+16 22i9 31+9 25+9 40 41 21 24 32 32 27 27

<25

<15

<15

<15

<15

<15 1550i232 1559i135 1600i139 1530i133 1490 1453 1513 1674 1623 1620 1620 1500 F. Foods (pCi/kg, Met Meighc) 3/81 47i9 42 44 7/81 44+9 53 51 11/81 38i9 49 54 29i2.8 31i2. 8 23i2.6 38P 31 32 25 22 119i21 82i14 hone 126 121 80 106 53+9 45i9 3319 56 55 43 54 29 35

<15

<15

<25

<25

<15

<25 2640i229 2640i229 2730+237 2857 2917 2870 3437 2820 2720 30E 9 25 32 k.

Values for potassium are reported, as mg/licer of sample.

m.

Resulcs vere marginally ouc of limits.

Efficiency curves vere checked vich no conclusive findings.

Subsequent results have been satisfactory.

n.

Only tvo results vere sent to EPA.

Results vere not included in cheir analysis.

o.

Values for potassium are reporced as mg/kg sample.

p.

Invescigacion of this problem vas initiated but no satisfactory conclusions have been reached.

Me suspect difficulties arising from sample inhomogeniety.

An incorrecc veighc vas obtained in che gamma analysis of this sample.

Further analysis destroyed che sample so chac the correct veighc could noc be determined.

r.

Invescigacion vas conducted.

No satisfactory explanation vas found.

Ocher cross-checks on this isotope in different media are satisfaccory.-

Table 4 (Contd)

Results Obtained in Interlaboratory Comparison Program C.

Radiochemical Analyses of Water (pCi/L)

Gross EPA value Dat

~RD Alpha Gross Seta Strontium 89 Strontium - 90 Tritium TVA AVG.

EPA value TVA AVG.

EPA value TVA AVG.

EPA value TVA AVG.

EPA value TVA AVG.

MARL EARL

~ (i3o)

MARL EARL (i30)

MARL EARL (i3a)

MARL EARL (i3o)

MARL EARL f

Iodine - 131 EPA value TVA AVG.

~(-3R IIAIIL EARL 1/81 9+9 2/8 1 3/81 25+ 10 4/81 5/81 21i9 6/81 7/81 22+10 8/81 9/81 33+14 10/81 11/81 2L+9 12/81 21 14 14+9 20 29 22 15+9 i

18 28i9 21 13 23i9 14 16 15 18 29 26 18 24 10 9

44i9 49 49 23

)5i 25+9 26 29 16+9 36+9 23+9 11 14 34i3. 1 388 28 40 33 22+2. 6 21 22 26 23 11+2. 6 11 10 32 28 1950i596 1990 1947 2630+613 2623 2713 2210i603 2263 2197 2700i615 2717 2807 73+13 79 73 76+13 65 56 1760+591 1917 1753 2710i615 2467 2723 30i10 D. Gamma-Spectral Analysis of Water (pCi/L)

Chromium 51 Cobalt - 60 Zinc 65 Ruthenium - 106 Cesium 134 Cesium - 137 EPA value TVA AVG.

EPA value TVA AVG.

EPA value TVA AVG.

EPA value TVA AVG.

EPA value TVA AVG.

EPA value TVA AVG.

Dat*

~ARI MARL EARL ~33)

IIARL EARL ~33 IIARL EARL

~AEI MAIIL EARL ~t3 ~

WARL EARL ~t33 MARL EARL 2/81 0

<60

<60

~

25+9 25 25 85+9 84 83 0

<40

<40 36+9 39 35 6/81 0

<60

<60 17+9 18 17 0

<15

<15 15i9

<40

<40 21i9 23 21 10/81 34+9

<60

<60 22i9 25 22 24i9 26 21 0

<40

<40 21i9 21 24 4+9 31+9 32i9 6

10 27 30 35 32 f.

Specific analysis for to test the procedures used for the analysis of milk.

g.

Investigations of the analytical procedure were conducted and new efficiency curves were determined.

Results have been satisfactory since that time.

h.

New efficiency curves were determined subsequent to this analysis.

Subsequent results were satisfactory.

i.

Excess humidity in counting room and a change in the amount of solid introduced into the sample by EPA are suspected in the difficultywith this sample type.

Steps have been taken to correct or compensate for these items.

Results are possibly due to an incorrect chemical form of the precipitate counted in this procedure.

Investigations continue.

11 Atmos heric Monitorin The atmospheric monitoring network is divided into three groups.

Four local air monitors are located on or adjacent to the plant site in the general areas of greatest wind frequency.

One additional station is located at the point of maximum predicted offsite concentration of radionuclides based on preoperational meteorological data (see figures 3 and 4).

Four per'imeter air monitors are located at distances out to 10 miles from the plant.,

and two

.remote air monitors are located at distances out to 45 miles.

These monitoring stations are shown in figure 2.

The remote monitors are used as control or baseline stations.

At each monitor, air is continuously pulled through a

Hollingsworth and Voss LB5211 glass fiber filter at a regulated flow of 3 fts/min.

In series with, but downstream of, the particulate filter is a

charcoal filter used to collect iodine.

Each monitor has a collection tray and storage.container to obtain rainwater on a continuous basis and a hori-zontal platform that is covered with gummed acetate to catch and ho3.d heavy particle fallout.

Thermoluminescent dosimeters are used to record gamma radiation levels at each remote and perimeter station.

Each of the local air monitors is fitted with a GM tube that con-tinuously scans the particulate filter.

The disintegration rate of the atmospheric radioactivity is continuously recorded at each station and radio-.

'telemetered into the plant.

Air filters are collected weekly and analyzed for gross beta activ-ity.

No analyses are performed until three days after sample collection.

The samples are composited monthly for analysis of specific gamma-emitting radio-nuclides and quarterly for Sr and oSr analysis.

The results are combined for each station to obtain an annual average.

During this reporting period, three samples were not obtained because of equipment malfunction, These data are presented in table 6.

The" annual averages of the gross beta activity in the air particulate filters at the indicator stations (local and perimeter monitors) and at the control stations (remote monitors) for the years 1968-1981 are presented in

, figure 5.

Increased levels due to fallout from atmospheric nuclear weapons testing are evident, especially in 1969,

1970, 1971,

1977, 1978, and 1981.

These patterns are consistent with data from monitoring programs conducted by TVA at nonoperating nuclear power plant construction sites.

Table 5 presents the maximum permissible concentrations (MPC) recommended by 10 CFR 20 for nonoccupational exposure.

Rainwater is collected monthly and a 3.5-liter sample'nalyzed for

, specific gamma-emitting radioisotopes and tritium.

The results are shown in table 7.

The gummed acetate that is used to collect heavy particle fallout is changed monthly.

The samples are ashed and counted for gross beta activity.

The results are given in table 8.

12 Charcoal filters are collected and analyzed for radioiodine.

The filter is counted in a single channel analyzer system.

The results are shown in table 9.

During this reporting period, two samples were not taken because of equipment malfunction.

13 Table 5

MAXIMMPERMISSIBLE CONCENTRATIONS FOR NONOCCUPATIONAL EXPOSURE Alpha Nonvolatile beta Tritium 137(

10 3 i 106Ru 144( e "Zr-"Nb

'40Ba 140La 131I sszn 64wn 60C 89Sr 90S s1C 1 34Cs 58Co In Water

~C1/1+

30 3; 000 3,000,000 20,000 10,000 10;000 60,000 20,000 300 100,000 100,000 30,000 3,000 300 2i000,000 9,000 90,000 In Air

~Ci/m +

100 200,000 500 200 200 1,000 1,000 100 2,000

"',000 300 300 30 80,000 400 2,000

• 1 pCi ~ 3.7 x 10 Bq.

TABLE 6 RADIOACTIVITY IN AIR FILTER 0 F 05(

D ~ 03-0'5(

0'5 0 ~ C6(

0 ~ 01-0 ~ 02(

0 ~ ol-0 F 09(

0%01-8/

39) 0'6 5/

39) 0'6 20/

39) 0%13 6/

39) 0 ~ G2 35/

39) 0 ~ 21 RU-103'06 ZR-95iNB-95 I-131 BE-7 0>>C40 0'10 0 010 NOT ESTAB GAHHA (GELT)

94 CE-141 0 ~ 010 0 ~ C2C NOT ESTAB D ~ 010 0 ~ 010 NOT. ESTAB 0'20 NOT ESTAB CE-144 RU-103

~ ZR-95 NB-95" K-40

.8 I-214 81-212 PB-214 PB-2)2 DE-7 TL-208 0>>020 NOT ESTAB C.osr NOT ESTAB SR 89 RR O.DOS Ceool 0 ~ 01(

0% 01-0 ~ 04(

0%02 0 ~ Gl (

0>> 00-D ~ 03(

0 ~ 01 0 ~ 05(

0%01-0 12(

0 ~ 06-0'4(

0 ~ 02-0 04(

0 ~ 04 G ~ 04(

0 ~ 02 0 ~ 01(

0 F 00 0%08(

0 ~ 05-0 ~ 01(

D>>DO 0>>G1(

0 ~ 01 0 F 00(

8/

78) 0'2 16/

78) 0%07 38/

78) 0 F 03 34/

78) 0 F 06 40/

78) 0 ~ 15 58/

78) 0 'C 44/

78) 0 ~ 09 1/

78) 0'4 28/

78) 0 ~ DR 35/

78) 0'3 41/

78) 0 47 14/

78) 0 F 01 18/

36) 0 F 01 7/

36)

NAHE OF FACILITY ~CHERRY LOCATION OF FAC'ILITY LIHCSTOQQ TYPE AND LOVER LIHIT ALL TOTAL NUHBER OF INDICATOR LOCATIONS OF ANALYSIS DETECTION +

HEAN qF)b Pf RfOR~HE

~~LQ RAN('tl" GROSS ALPHA 0 ~ 005 52 GROSS BCTA 0 010

(.08(

4S6/

465) 569 0 ~ Dl-0%38 GAHHA (NAI) 49 CE-14 1e 144 0 ~ 030 PCI/H(3) -

0 ~ 037 BG/H(3)

A A

AHA DOCKET No>>~0-25~9~?96 REPORTING PER I OD 9

CONTROL LOCATIOtiS HEAN (F)b R~Nt(f,b 0 ~ 01(

3/

52)

LH4 BF TRAILER P 1 ~ 7 HILES NNM 0'9(

50/

52) 0 F 01-0 ~ 36 C ~ 01-0 ~ 01 oe08(

103/

104) 0 0 l-0 ~ 39 LH3 BF NORTHEAST 1 ~ 0 HILE ENE LH3 BF NORTHEAST 1 ~ 0 NILE ENE ATHENS'L 10.9 HILES NE DECATUR'L 8 ~ 2 HILES SSE ATHENS'L 10 ~ 9 HILES NC ATHENS'L 10 9 HILES NE ROGERSVILLEe AL 13 ~ 8 rlLCS NM LH1 BF NOPTHMEST 1 ~ 0 HILE N ROGERSVILLCw AL 13 ~ 8 rlLES t(M DECATUR'L 8'

MILES SSE LH2 BF NORTH 0 ~ 9 NILE INC DECATUR'L 8 ~ 2 HI LES SSE DECATUR'L 8>>2 HILES SSC DECATUR'L 8

2 HILES SSE LH3 BF NORTHEAST 1 ~ 0 HILE ENE DECATUR(

AL 8 ~ 2 HILES SSE LH4 BF TRAILER P

1 ~ 7 HILES NNM LH5'F DAVIS F 2 ~ 5 HILES MSM ROGERSVlLLEe AL 0 F 06(

0 ~ 06 0'6(

0 ~ 06-0 ~ 13(

0 ~ 13-0 ~ 02(

0 ~ 02-0'2(

0 ~ 07-0'2(

0'2" 0 F 05(

0 ~ 04-0'2(

0>>01-0 F 04(

0 ~ 02-0'7(

0 ~ 03-0>>16(

0 ~ 12-0 F 05(

0 ~ 02-O.04(

0 ~ 04-0 F 05(

0>>03-0'2(

0 ~ 02-0'6(

0 ~ 05-0 F 01(

0 ~ 01-0 ~ 01(

0 ~ Ol-0 ~ 00(

ll 4)

D.O6 ll

-4)

DE 06 1/

3) 0 ~ 13 1/

5) 0 ~ 02 3/

3) 0'1 1/

10) 0 ~ 0?

2/

10) 0 F 07 4/

8) 0'3 5/

10) 0 ~ 06 8) 0 ~ 12 3/

6) 0 ~ 18 6/

8) 0 F 09 1/

8) 0'4 3/

8) 0 ~ 07 1/

9) 0 F 02 5/

8) 0'7 2/

7) 0 F 01 2/

4) 0>>Dl ll ')

0 F 04(

4/

lc) 0%03" 0%07 0%05(

2/

10) 0>>D5 0

05 0 06(

5/

10)

De02-0 ~ 13 10 VALUES <LLD 0 ~ 1D(

10/

10) 0 F 05-0'3

~

16 VALUES (LLD 0 ~ 12(

3/

16) 0'2-0 ~ 30 0 F 01(

7/

16) 0 F 01-0 F 02 0'2(

8/

16)

.0 ~ Gl-0 ~ 03 D>>05(

8/

16) 0'2 0 ~ 09 0%13(

13/

16) 0 ~ll-0 ~ 16 0>>04(

7/

16) 0 ~ 03-0 ~ 08 16 VALUES CLLD 0'3(

0 ~ 02-0 ~ 01(

0 ~ 00-0 ~ 07(

0 ~ 05-0 F 01(

0%01-0 F 01(

0 ~ 01-0 F 00(

n nn 6/

16) 0 ~ 07 7/

16) 0 ~ 02 9/

16) 0 ~ 10 3/

16) 0 F 01 4/

8) 0 ~ 01 3/

8) n nn Log!IIIQ~nv"BlkUggI al!5I!JIL "La5--

NAHE HEAN (F)b

~$ $A~C~A(~~R~T~O RAhg~+

NUHBER OF NONROUT INE REPORTED

~HAS~UR

~HN T 5

RADIOACTIVITY ltt RAI)%MATER PCI/L - 0.037 Ba/L NAHE OF F AC ILITY RR~~(FERRY LOCATION OF F AC I L I T Z L IH~STO~tt tLABAHA DOCKET NO%~5-~~96~

REPORTING PERIOD~~9 I

TYPE AMD TOTAL i(UMBER OF ANALYSIS PERFORHEO GAHHA (MA I )

97 CE 14 li144 RU-103%106 ZR-95 'tB-95 1-131 BE-7 GAHHA (GELI) 46 2R-95 t(B-95 K-40 8 I-214 PB-214 PB-212 DE-7 TRIT IUH 143 LO) EP.

L I HI T OF DETFCT I ON a (QQD) 38 000 40 F 000 10 MOOG 15 F 000 NOT ESTAB 10 F 000 5 F 000 NOT ESTAB NOT ESTAB NOT ESTAB MOT ESTAB t(OT ESTAB 330 F 000 77 VALUES <LLO 48'0(

48 20-15'2(

10%10-22%10(

22 ~ 10-51 ~ 80(

7 ~ 30-1/

77) 48'0 19/

77) 25 ~ 10 1/

77) 22 ~ 10 49/

77) 133 '0 40 VALUES <LLO 9%63(

2/

40) 8 ~ 93-10'2 81 57(

21/

40) 32'1-125 F 00 22'9(

25/

40) llew 52-48'8 17'5(

12/

40) 9'1-29'7 14%32(

8/

40) 8'9-18q09 49'5(

3/

40) 43'8-54'6 117 VALUES <LLO ANALYSIS FERFGRHED ALL INDI CATOF LOCATIONS HEAt( (F)b RANGc b DECATUR%

AL 8 ~ 2 HILES SSE LH4 BF TRAILER P 1%7 HILES NNM LH5 BF DAVIS F 2 ~ 5 NILES MSM LHS BF JA V IS F

2 ~ 5 HILES MSM LHS BF DAVIS F 2 ~ 5 HILES MSM LH3 BF ttORTHEAST I ~ 0 HILE EtiE LH3 BF NORTHEAST 1 ~ 0 NILE ENE LH3 BF NORTHEAST 1 ~ 0 HILE ENE COURTLAtiDe AL 10 ~ 5 BILES MS V LH5 BF DAVIS F 2%5 HILES MSM 48'0l 48 ~ 20-20 '0C 15 ~ 60-22%10(

22 F 10 67 F 88(

39 ~ 70-10'2(

10 ~32-125 F 00(

125%00 29'3l 16 ~ 24-28'8(

28 ~ 38-18'9(

18 ~ 09-49'5(

43 ~ 28-1/

8) 48'0 3/

8) 25'0 1/

6)-

22'0 4/

6) 115'0 1/

7)

$ 0%32 1/=

6) 125 F 00 4/

6) 48'8 1/

6) 28'8 1/

3) 18%09 3/

7) 54 F 06 CONTROL LOCATIONS MEAN (F) b R~~Gb 43 ~ 60l I/

20)c 43'0-43'0 20 VALUES <LLD 19'3(

3/

20) 10'0-35 F 10 2C VALUES <LLD 56 F 86(

14/

20) 14 F 00- 10'0 10'2(

1/

6) 10%12-10'2 13'2(

I/

6) 13'2-13 F 82 58 F 19(

2/

6) 54'9-61 78 40 ~ 21 l 3/

6) 23'9-70'1 11'6(

2/

6) 8 ~ 9S 14 16 6

VALUES <LLD 105 F 00(

1/ ')

.105 F 00-105%00 26 VALUES <LLD NUHBET OF NONROUTINE REPORTED a.

Nominal Lover Limit of Detection (LLD) as described in Table 3.

b.

Hean and range based upon detectable measurements only.

Fraction of detectable measurements of specified locations is indicated in parentheses (F).

c.

Identified as fallout.

TAFLE 8 RADIOACTIVITY IN HEAVY PARTICLE FALLOUT HEI

/KH(2) 37000060

~ 60 bQ/KH(2) hAHE OF FACILITY 8~RlltJS FJRf(Y

(.OCATIOV OF FACILITY

(.(RESTORE ALABAHA DOCKET No.~gg~298 REPORTING PERIOD~981 TYoE Ah.D TCTAL t>UMBER OF ANALYSIS P~(:F ~OH//

GPOSS BETA 143 LOVER L IHIT ALL OF

'INDICATOR LOCATIO) S DETECT IONa t(EAN (g)b 0'50 1 ~ G9( 117/

117) 0 ~ 08-3'3 LOCAI I Gt) I+/JH H~GHQQ~A~(NUQ~H~AN NA)tE HEAN (F) b LH4 BF TRAILER P

i+35(

13/

13) 1 ~ 7 HILES NNM 0 ~ 16-3'3 CONTROL LGCATIONS HEAN (F)b

~RAN b

1-04(

2e/

2e) 0+12-2'9 NUMBER OF NONROUTINE REPORTED rEASUREVE)tTS a.

Nominal Lower Limit of Detection (LLD) as described in Table 3..

b.

Mean and range based upon detectable measurements only.

Fraction of detectable measurements of specified locations is indicated in parentheses (F).

TABLE 9 RADIOACTIVITY Iti CHaRCOAL FILTERS PCI/H(3) -

0 ~ GI37 BG/H(3)

NAME OF FACILITY QfiQVCS fE'R'RY LOCATION OF FACILITY LINGSTONQ ALaoaHA DOCKET NO ~ 50-259N260+296 REPORTlhG FERIOD~)9 TYPE AND TOTAL t)UHBER OF ANALYSIS PQR~~ORH 0

IODINE IN AIR 570 LOMER LIHIT OF DETECTIONa (Lt P) 0 ~ 020 ALL INDICATOR LOCATIONS HEAR (f)b R AN(t~

0'3(

62/ 466) 0'2-0'9 NAHE HEAN (f)b QIGT~AMC

~AM GIRD'TIOID RANGf COURTLAND~

AL 0 ~ 06(

2/

50) 10 ~ 5 MILES VSb 0'2 0'9 CONTROL LOCATIONS MEAN IF/'AN 0'2(

13/

10%)

0'2-0 '%

NUHBER OF tAONROUT ItRE REPORTED

~HAS~UR tA~hTS a.

Hominal Lower Limit of Detection (LLD) as described in Table 3.

b.

Mean and range based upon detectable measurements only.

Praction of detectable measurements of specified locations is indicated in parentheses'(P).

~ 18 Figure 2

.. ATMOSPHERIC AND TERRESTRIAL MONITORING NETWORK RM.2BF LAWRENCEBURG yPULASKI FAYETTEVILLE+

PM-IBF WILSON WHEELER ROBE SVIL OAM FLORENCE FFIEL MUSCLE SHOALS RM. IBF LEIGHTON TUSCUMBIA COURTLAN0$

PM-4 F pRUSSELLVILLE ATHENS PM-2BF BROWNS FERRY NUCLEAR PL NT OECAT PM 3BFO IO MILES HARTSELLE HUNTSVILLE NT SVILL OAM 25 HALEYVILLE CULLMAN 45 MILES RAINWATER SOIL Q-ENVIRONMENTAL MONITORING STATeN NOTE: THE FOLLOWING SAMPLES ARE COLLECTED FROM EACH STATION:

AIR PARTICULATES RADIOIODINE HEAVY PARTICLE FALLOUT

Figure 3

LOCAL MONITORiNG STATIONS.

BROWNS FERRY NUCLEAR PLANT 19 ATHENS U S HV/Y 72 BFN ALA. HWY 20 Legend

~

Air Monitor A

Automatic Well Sampler H

Dairy Farm N

DECATUR Scale 0

I 2

3 4

5 Miles

20 Figure 4

~I,

.t rr

~ <<

I

'I ~

4

~'i It (PJ'

~

'4

~

il

<<)

I I

H/p

'5 I it fl,.

t,l I

0

, j

.I)I rr

>> I~It

~ll~r I

'. '('

tiff I

~

~ 'I (

I pt )j>>

>>I J I>>

5 A

(I

\\

I

(

5 l,t

'I

'I I

r

'J I

I I

~ Q.I w'

l I

I

},

~If I Pr. I.;

~>I,

<<I.."

.I s (

I wtw I

Il

~I l5 ('.

~

,(.'

f(

I)

I, If('

g I ~

(

I y

I

~ pI I

I

~ A

~t I

w i

I I

~

il

.Jtt',,>>

Jl 5

~

.I<<II 4 <<".

~

.I I l I

i r 5. ~

• 'I

(

~aS

~I P'I4 tt>>I I

I i " (" t r

~h 4 >>if e

~

- f lpr>>f.

f

}r, I

~ r'

~

I

~

II

~

Wt>>>>>>I IW

~

r>>

T I

i was>>>>>>

~

t ~

~

I

~ ~

figure 5

.30

.25 Preoperational Phase Operational Phase ANNUAL AVERAGE 6ROSS BETA AC:TIVITY IN AIR FILTERS BROWS FERRY NUCmR PLANT

.20

.15 CC00 0

Cv M 4J 4J Cfl Clv 4J Cv CO 0

4Ja o 44 C

0 0 Average:

Preoperational Phase 4

.10 05 1968 I969 1970 1971 1972 19 73 1973 0 97 1975 1976 1977 1978 1979 1980 1981

,1

~

23 Terrestrial Monitorin Milk Milk is collected from at least four of five farms within a 10-mile radius of the plant (see figure 3),

and from at least one of four contxol farms.

Raw milk is, analyzed weekly for-

~ I, and monthly for gamma-emitting isotopes and for radiostrontium.

The results are shown in table 10.

Cow censuses were conducted in May and September 1981. It was determined that'here are no dairy farms nearer the plant than the nearest farm being sampled.

During this period however, one of the dairy farms being sampled (farm B, table 2) went out of business and all,cows were sold.

Another dairy farm (farm P) was added to the monitoring program on August 3, 1981.

~Ve etation Vegetation is sampled quarterly at the farms from which milk is collected and analyzed for gamma-emitting radionuclides.

Approximately 1-2 kilograms of grass is broken or cut at ground level and returned for analysis.

Efforts are made to -sample vegetation that is representative of the pasturage where'cattle graze.

Table 11 gives the results obtained from the laboratory analyses of these samples.

Soil Soil samples are collected annually near each monitoring station to provide an indication of a long-term buildup of radioactivity in the environ-ment.

An auger or "cookie cutter" type sampler is used to obtain samples of the top two inches (5

cm) of soil.

These samples are analyzed for gamma-emitting radionuclides, Sr, and Sr.

The results are given in table 12.

Ground Mater An automatic sequential-type sampling device has been installed on a well downgradient from BFN.

A composite sample from this well is analyzed for gamma-emitting radionuclides monthly and composited quarterly for determination of tritium.

A grab sample is also taken from a control well upgradient from the plant.

The results of the analysis of well water are shown in table 13.

Potable water supplies taken from the Tennessee River in the vicinity of BFN are sampled and analyzed for gross beta and gamma-emitting radionuclides, and composited quarterly for tritium, Sr, and oSr analyses.

The first potable water supply downstream from the plant is equipped with an automatic sampler with samples collected and analyzed weekly.

The sampler is located on the water intake structure and takes the sample from the river as the raw water is drawn into the water treatment facility.

Two additional supplies

24 downstream and one public water supply upstream are sampled by taking monthly grab samples of treated water at user points.

Table 14 indicates the results from the analysis of drinking water samples.

During this reporting period, six of the weekly samples were not taken because of the malfunction of automatic sampling equipment.

Figure 6 shows the trends in gross beta activity in drinking water from 1968 through 1981.

The annual average level from the raw water samples tends to run slightly hi:gher than the average for treated water samples; however the levels are consistent with the activities reported in surface water samples taken upstream from BFN (figure 12) and in samples taken from the Tennessee River in preoperational monitoring programs conducted by TVA at other sites.

Environmental Gamma Radiation Levels Bulb-type Victoreen manganese-activated calcium fluoride (Ca~F:

Mn) thermoluminescent dosimeters (TLDs) are placed at sixteen stations around the plant near the site boundary, at the perimeter and remote air monitors, and at nineteen additional stations out of approximately five miles from the site to determine the gamma exposure rates at these locations.

The dosimeters, in energy compensating shields to correct energy dependence, are placed at approxi-'ately one meter above the ground, with three TLDs at each station.

They are annealed and read with a Victoreen model 2810 TLD reader.

The values are corrected for gamma

response, self-irradiation, and fading, with individual gamma response calibrations and self-irradiation factors determined for each TLD.

The TLDs are exchanged every three months.

The quarterly gamma radiation

~

levels determined from these TLDs are given in table 15, which indicates that average levels at onsite stations are approximately 2-4 mR/quarter higher than levels at offsite stations.

This is consistent with levels reported at TVA's nonoperating nuclear power plant construction sites where the average radiation levels onsite are generally 2-6 mR/quarter higher than levels offsite.

The causes of these differences have not been completely isolated; however, it is postulated that the differences are probably attributable to combinations of influences, such as natural variations in environmental radiation levels, earth moving activities onsite, the mass of concrete employed in the con-struction of the plant, and other undetermined influences.

Figure 7 compares plots of the data from the onsite or site boundary stations with those from the offsite stations over the period from 1976 through 1981.

To reduce the variations present in the data sets, a four-quarter moving average was constructed for each set.

Figure 8 presents a trend'lot of the direct radiation levels as defined by the moving averages.

The data follow the same general trend as the raw data, but the curves are smoothed considerably.

Prior to 1976 measurements were made with less sensitive dosimeters, and consequently the levels reported in the preoperational phase of the moni-toring program are 1-2 times the levels reported herein.

Those data are not included in this report.

Therefore, for comparison purposes, figures 9 and 10 depict the environmental gamma radiation levels measured during the constructior of TVA's Watts Bar Nuclear Plant to the present.

Note that the data follow a similar pattern to the BFN data and that, as discussed

above, the levels reported at onsite stations are similarly higher than the levels"at offsite stations.

25 Poultr and Food Cro s

Food crops and poultry raised in the vicinity of BFN and at control locations are sampled as they become available during the growing season, and analyzed 'for gamma-emitting radionuclides.

During this sampling period, samples of cabbage, corn, green beans,

peaches, potatoes, turnip greens,

tomatoes, soybeans, and poultry were collected and analyzed for specific gamma-emitting radionuclides.

No sample of soybeans or cabbage was taken from a control location.

The results are given in tables 16, 17, and 18.

TABLE 10 RADIOACTIVITY IN HILK PCI/I.

0'37 BO/L NAHE OF FACILITY ~RR VNS FjRRY LOCATIOII OF FACILITY~IIIGTOIIC ALAHAHA DOCKET t(O ~ 50-25~92~60 296 RCPORTIttG PERIOD 1'9&1 TYPE ANO TOTAL NUHBER OF ANALYSIS GA)IHA (NAI) 107 LOMER LIHIT OF DETEC T IO "A

~(Q )

ALL I)COICATOR LOCATIONS HEAto (F )b R~A'Qf b LOCAT~IH IIITH Hj~GH GT Al~lt HAL IITAH NAIIE HEAN ([)

QIQJAH~AHQ Cmf,c~lo AAHTTC CONTROL LOCATION)

HCAN (g)

NUHBER OF.

NONROUTINE REPORTED

~V. Agghf.~llNTS CS-137 K-40 10 F 000 150 F 000 OH500 F 000 NOT ESTAB NOT ESTAB NOT EST/8 NOT ESTAB NOT ESTAB K-40 BI 214 PB-214 PB-212 TL 208 SR 89 SR 90 10 F 000 113 F 000 113 IODINC IN HILK 454 GAHHA (GELI) 6 CS 137 13H63 (

3/

55) 11'0-16 F 00 1246 91(

55/

55) 1049H30 1569H20 253 VALUES <LLO ANALYSIS PERFORI,CO 8'0(

3/

6) 7 54-10 1500 F 50(

6/

6) 1287 F 00- 1845 F 00 20H63(

5/

6) 7'9-30 '3 18'5(

3/

6) 14'9-20'3 14H88(

3/

6) 9'3-20'6 4'3(

2/

6)

F 18-6'8 61 VALUCS <LLD ANALYSIS PERFORATED 3'5(

61/

61)

2. 01-8.19 PAGE FARH 8 ~ 75 )(ILES E

THRASHER FARHA 7 ~ 0 HILES ENE SHITH FARH 4 ~ 75 HILES N THRASHER FARH 7HO )(ILES ENE SHITH FARH 4H75 HILES N

BROOKS FARH 7~0 HILES NNM SHITH FARH 4H75 HII ES N

PAGE FARH 8 ~ 75 BILES E

SHITH FAR)I 4H 75 HILES N

10 F 16(

10 ~ 16-1845.00(

1845 ~ 00-30'3(

30 ~ 43-20'3(

20 63-20'6(

20 ~96-6.48(

6 ~ 48-1/

1) 10'6 1/

1) 1845 F 00 1/

1) 30'3 1/

I) 20'3 1/

1) 20H96 1/

1) 6'8 4 ~ 74(

3 ~ 12-13/

13) 8'9 13H63(

3/

4) llo70-16 F 00 1308 '1(

12/

12) 1127 '0- 1569'0 10 '0(

1/

52) 10H20 10'6.

1232 '5(

52/

52) 1037'0 1391 F 80 201 VALUES <LLD 52 VALUES <LI.D 4 ~ 33(

40/

52) 2'6-7'6 a.

Nominal Lover Limit of Detection (LU)) as described in Table 3.

b.

Hean and range based upon detectable measurements only.

Fraction of detectable measurements of specified locations is indicated in parentheses (p).

NAME OF FACILITY HROMNS FERRY LOCA 10tt OF FAC ILI TY L IMESTOttE T

TABLE RAOIOACTIVITY IN VEGETATION PCI/O -

0 ~ 037 80/G (ORY MF IGtlT)

TYPE RNO TOTAL NUNBCR OF ANALYSIS PEP.FORi)ED GROSS BETA 36 GAHHA (GCLI) 38 LOVER LI HIT OF OETECTIONa

~(eO) 0 ~ 200 ALL INDICATOR LOCATIONS MEAN (

)b

~RCCC 26'3(

20/.

20) 7 70-48082 LO AT ON VT TK KIGKEST ANNUA tlEAN NAME NCAN (F)b

~gP~NC AtlQ QIQ~TIQtP

~A~b BITTING FARM 35 ~ 32(

2/

2) 4 ~ 5 NILES Et(C 31088-38075 CONTROL LOCATIONS 26052(

16/

16) 10'7-45'4 NUNBER OF NONROUT INE REPORTED Qf~k~kklI-CE-141 CE

>P.-14 4 RU-103 RU-106 CS-137 2R-95 NB-95 K-40 MN-54 Y-88 RI-214 BI-212 PB-214 PD-212 RA-226 BE-7 TL-208 AC-228 0'00 0'20 NOT ESTAB 0'00 0'10 0'60 0 ~ 110 0'50

'(OT'ESTAB 0'50 NOT ESTAB 0'00 t(OT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB NOT FSTAB NOT ESTAB NOT ESTAB a.

Nominal Lover Limit of Detectio b.

Mean and range based upon detec THRASHER FARM 7 ~ 0 MILES Ct(C LOONEY FARM 5075 )(ILES CNC LOONEY FARM 5 75 MILES ENE LOONEY FAR)1 5075 HILES ENE THRASHER FARM

.7.0 HILES ENE SITTING FARH 405 t(ILES ENE BITTING FARtl 4 ~ 5 HILES ENE BITTING FARM 4 ~ 5 MILES ENC BROOKS FARM 700 HILES ht(M THRASHER FARM 7 ~ 0 MILES ENC OITTING FARN 405

.'IILES ENE BITTING FARH 4 05 MILES CNE LHI BF r(ORTHMEST I ~ 0 HILE N BITTlt(G FARH 405 tlILES ENC LH1 BF NORTHMEST 1 ~ 0 HILE N BROOKS FARil 7 ~ 0 NILCS NNM LOONEY FARY.

5 ~ 75 NILES CNC LH1 BF NORTHliEST 100 MILE N LH1 BF NORTHMEST 1 ~ 0 MILE N able 3.

Praction of detectable 5/

21) 2092 17/

21) 5 ~ 49 3/

21) 4'1 6/

21)

F 14 2/

21) 1054 14/

21) 0'2 10/

21) 4'6 18/

21) 10 '8 21/

21) 25'8 3/

21) 0'0 1/

21) 0002 9/

21) 0 ~ 62 1/

21) 0'3 19/

21) 0 ~ 41 20/

21) 0 ~ 72 3/

21) 0 ~ 14 21/

21 )

15 ~ 63 16/

21) 0'9 18/

21) 0 F 48 n (LLD) as described in T table measurements only..

2'2(

2 ~ 92-2060(

0 41-4'1(

4 ~61-1053(

1053-1 SR(

l054-0 ~ 32(

0032 3'5(

3 ~95-4'8(

0'9 12'6(

2088-F 10(

0 ~ 1G-0002(

0'2 0049(

'0 ~ 49-0'3(

0 33-0'7(

0016 0 ~ 72(

0 ~ 72-0014(

0 ~ 14-7'7(

1012-0 ~ 29(

0 ~ 29-0'6(

0 ~ 36-ll 4) 2 ~ 92 2/

4)

R ~ 80 1/

4) 4'1 1/

4) 1053 1/

4) 1054 1/

2) 0032 1/

2) 3'5 2/

2) 8 ~ 36 4/

4) 22'6 ll 4) 0010 1/

2) 0 ~ 02 1/

2) 0'9 1/

1)

~ 0 ~ 33 2/

2) 0'8 1/

1) 0072 1/

4) 0014 4/

4) 13 F 61 1/

1) 0'9 1/

1) 0 36 1 ~ 93(

4/

17) 1 ~ 16-2'6 1069(

13/

17) 0030-5025 2 71(

1/

17)

F 71-2'1 1 ~ 39(

4/

17) 1 ~ 10-1 ~ 65 1 ~ 11(

2/

17) 0'9 1 ~ 34 0 ~ 21(

7/

17) 0'6-0 ~ 40 1 ~ 90(

8/

17) 0'0-R031 2'5(

13/

17) 0'6-9026 ll 37(

17/

17) 2023-28 95 F 10(

4/

17) 0'8-0 ~ 12 17 VALUES (LLO 0 ~ 30(

10/

17) 0011-0'064 17 VALUES (LLO 0021(

0010-F 17(

0 0'04-0007(

0 ~ 03-5'6(

2 ~ 29-0 F 05(

0001-0017(

0 ~ 02-12/

17) 0050 14/

17) 0'3 2/

17) 0011 17/

17) 14'0 9/

17) 0 ~ 16 14/

17) 0 ~ 52 measurements of specified locations is indicated in par'entlieses (P).

TABLC 12 RADIOACTIVITY IN SO IL NAME OF FACILITY PRGVHS FERRY LOCATION OF FAC ILITT~LII!STONC PCI/G -

0 ~ D37 8(F/G (ORY INC IGHT)

ALA"AHA (AOCKET

!JO ~ 50~5<a 2~60 296 REPORTING PERIOD~)

TYPE A!JD TOTAL NUHQCR OF ANALYSIS P~CR 0 R Y~C GAHHA (GCLI )ll LO'MER LIMIT OF DETECTION (LLO)

ALL INDICATOR LOCATI0!JS HE AN (E')

R AN~G 0 ~ 030 CE-14 1 CE-144 RU 103 CS-137 Zo-95 NB 95 K-4 0 81-214 BI 212 PB-214 Pj 212 RA 226 RA 223 BC 7

TL-208 AC-228 PA 234M 0%G60 NOT ESTAB 0'20 0'30 0%01D 0%250 0 ~ 050 0 F 100 0 ~ 050 NOT ESTAB CD 050 NOT ESTAB 0 ~ 160 0'20 0 ~ 060 NOT ESTAB I ~ 500 0 ~ 300 Sf 89 11 SR 90 11 nal Lover Liccit of De and range based upon a.

I(ojai b.

Mean 0 ~ 06(

1/

9) o.oe-D.ne 0 ~ 13(

4/

9) 0 F 08-0 24 0 ~ 02(

4/

9) 0%32-3 AD )3 0'5(

9/

9) 0 ~ 10-F 82 D%06(

8/

9) 0 ~ 04-0 ~ 11 0 ~ 14(

9/

9) 0 ~ 06-0'5 5%42(

9/

9) 3%90-7'3 1 ~ 01(

9/

9) 0 F 51-1 ~ 40 O.ee(

0 ~ 29-0 ~ 86 1%08(

9/

9) 0.5e-1.4e F 08(

9/

9) 0%59-1 ~ 43 1 16(

9/

9) 0'1-2'3 6 ~ 36(

4/

9) 6 ~ 29-0%46 0 ~ 24(

2/

9) 0'1 0'6 0'8(

9/

9) 0%18 0 F 48 1%12(

9/

9) 0'2-1 ~ 46 3%'50(

1/

o) 3'0-3%50 9

VALUES <LLD ANALYSIS PERFORHED 9 VALUES <LLD ANALYSIS PERFORHED taction (LLD) as described in detectable neasurenents only.

jusTANO~

ANR I~R

.FIRN

RaljR4, CONTROL LOCATION/

HEAN ([)

RANGE NUHBER OF NONROUTINE REPORTED

~HASURE~HNTS LH2 BF NORTH 0

9 HILC NNC ROGERSViLLC ~

AL 13 ~ 8 HILES N)s LH1 BF IVORTHMEST 1

0 HILE

!J ROGTERSVILLEC AL 13.8 MILES NV POGERSVILLCe AL 13 ~ 8 HILES NM ROGERSVILLEs AL 13 8 HILES NM LH4 BF TRAILER P 1

7 HILES NNM LH2 BF NORTH 0

9 HILE N!JE DECATUR'L 8 ~ 2 HILES SSE LH2 BF NORTH 0

9 NILC NNE DECATURN AL 8 '

HILES SSE ATHCNSC AL 1D 9 MILES NE L!.4 BF TRAILEP.

P 1 ~ 7 HILES NNM L".3 BF NORTHEAST 1

0 NILE CNE LH1 BF NORTHMEST 1 ~ 0 NILE

!L DECATUR'L 8 ~ 2 MILES SSC LHB BF

!JORTH 0 ~ 9 HILE !N:C 0% De(

0 ~ Ce-0 ~ 24(

0 ~ 24-0'3(

0% (F3-1%82(

1 ~ 82-0.11(

0 ~ 11-0'5(

0 ~ 35.

7%13(

7%13-1 ~ 40(

1 4O-o.Be(

0 ~ 86-1 ~ 46(

1 46-1 ~ 43(

1 ~ 43-2 III3 (

2 ~ 43-0 ~ 46(

D ~ 46-0'a(

0 ~ 26-0 ~ 48(

0 ~ 48-1 ~ 46(

1%46-3'0(

3'0 ll 1) 0 ~ 36 1/

))

0 ~ 24 1/

1) 0.03 1/

1)

I ~ 82 1/

1) 0 ~ 11 1/

I )

~ 0 35 1/

1) 7 ~ 13 ll 1) 1%40 1/

1) 0 F 86 1/

1) 1 ~ 46 1/

))

) ~ 43 1/

1) 2'3 1/

1) 0'6 1/

1) 0'6 1/

1) 0%48 1/

1) 1 '6 1/

1) 3 ~ 50 2

VALUES <LLO 2/

2) 0'2 2/

2) 0'3 2/

2) 1%28 2/

2) 0 ~ 12 2/

2) 0%19 2/

2) 4%98 2/

2) 1 ~ 02 2/

2) 0'8 2/

2) 1 ~ 04 2/

2) 1 ~ 03 2/

2)

F 02 S

<LLD D 10(

0%08-0 03(

0%02-

'696(

0 64 O.DD(

G ~ 04-0 ~ 14(

0 ~ 09-97(

4'7 0%90(

0'8 0 ~ 46(

0%34 0%92(

0 81-0'4(

0 ~ 86-0'0(

0 78-2 VALUE 0'5(

2/

2) 0 ~ 19 0 ~ 30 0 ~ 33(

2I 2) 0%31 DE 36 0'7(

2/

2) 0%90 1 ~ 05 4 09(

1/

2) 4'9 F 09 2

VALUES <LLD 2

VALUES <LLD Table 3.

praction of detectable cjeasureuents of specified locations is indicated in parentheses (p).

NAKE OF FACILITY BROI'tES~fRRY LOCATION OF FACILITY L.IH~TOQf, TD(.LE 13 RADIOACTIttITY IN LIELL MATER PC I/L -

0 ~ 031 80/L

~AApAHA DOCKET tcOG~g-cG~+A2$ ~0 REPORT IhG PERIOD~9~

TYPE AND TOTAL NUMBER OF At(ALYS IS

~PRF9RHf Q GAHHA (NAI) 19 LOltER LIHIT OF DETECT ION lhhkl ALL INDICATOR LOCATIONS HEAW (F)b 12 VALUES <LLD ANALYSIS PERFORHED

$~00TIGH UITH HIGHEGT Ihkkhh IIEhll, t<D, E HEAr (F)b CONTROL t(UHBER OF LOCATIONS NONROUTINE KEAN (g)b REPORTED 7

VALUES <(.LD GAHHA (GEL I) 7 K-40 NOT ESTAB 1

VALUES <LLO BI 214 NOT ESTAB I

VALUES <LLD P8-214 NOT ESTAB 1

VALUES <LLD PB 212 NOT ESTAB 1

VALUES <LLD TRITIUH 330 F 000 4

VALUES <LLO 8

ANALYSIS PERFORHED 99 ~ 84 (

3/

6) 86 F85-115 F 50 28.00(

28000-28'C 12'9(

2/

6) 7'2-17 76 6.48(

1/

6) 6'8-6048 VALUES <LLD a.

Nominal Lower Limit of Detection (LLD) as described in Table 3.

b.

Mean and range based upon detectable measurements only.

Praction of detectable measurements of specified locations is indicated in parentheses (P).

TAELC 14 WANE OF FACILITY PROttttS F/RAY LOCATION OF FACILITY Q~fSYONr~

RADIOACTIVITY It9 PUBLIC MATER SUPPLY PCI/L -

0 ~ C37 BO/L AQABANA DOCKET AO, rTT!-229AE~&0 296 REPORT ING PERIOO~~SB TYPC AND TOI'AL NUNBCR OF At(ALYS IS

~RS 9'I~SF GROSS BCTA 85 GAHHA (NAI) 70 L04ER LIHIT OF DCTECTIONa

~(~ )

2'00 ALL INDICATOP. LOCATIOWS FlEAtt (F)b RAN~G 3N96(

61/

72) 2'6-14'0 61 VALUES <LLO ANALYSIS PERFORNEO WANE HE'AN (F) b Q~TST NC ANO QTRECTTON RANOEO CHANP ION PAPER 4 ~ 1 1(

44/

46)

TRN 282 '

2 46-14'0 CONTROL LOCATI OQS HEAN (F)-

~RAN 3'0( ll/

13) 2<<50-4 F 08 9

VALUES <LLO NUHBER OF NONROUT I WE REPORTED

~NASSER.~NNTS BI-214 PB-214 PB 212

'L"208 SF( 89 SR 90 IR IT IUH 16 16 NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB ION000 F 000 330NOOO GAHNA (GBLI) 15 K 40 WOT ESTAB 74'l(

72 ~49-24 F 80(

12 ~ 00-15'3(

11 ~ 14 llN90 (

11'0 11 VALUES 2/

11) 75 73 8/ ll) 43 F 03 4/

11) 23N93 1/

11) ll 90

<LLD 12 VALUES <LLD ANALYSIS PERFORHED 3'5(

1/

12) 25-3 25 369N21(

1/

12) 369'1-369'1 CHANPIOti PAPCR TRH 282 '

St(EFF IELOsAL ROB TRN 254 '

CHANPION PAPCR TRH 282 '

SNEFFIELDs AL ROB TRt'. 254 3

SHEFF IELDIAL ROB TRN 254<<3 CHAHP ION PAP EP.

TRN 282' 74 F 11(

72<<49-28091(

28+91-16'3(

12N52-11 ~ 90(

IIN90<<

3'5(

3N25-369 ~ 21(

369 ~ 21-2/

8) 75 ~ 73 I/

1) 28'1 3/

8) 23'3 1/

1) 1} 90 1/.=

4 )

3025 1/

4) 369'1 101NOO(

1/

4) 101 F 00-101 F 00 17<<78(

2/

4) 13+60 21 '5 15'2(

2/

15N68-15N95 16 ~ 18(

2/

4) 13N13-19'2 5'4(

1/

4) 5'4 5'4 VALUES <LLD 4

VALUES <LLD 376~59(

1/

4) 376 '9-376'9 a.

Nominal Lower Limit of Detection (LLD) as described in Table 3.

b.

Hean and range based upon detectable meaiurements only.

Fraction of detectable measurements of specified locations is indicated in parentheses-(F).

31 Table 15 ENVIRONHENTAL GAMNA RADIATION LEVELS Average External Gamma Radiation Levels at Various Distances from Browns Ferry Nuclear Plant for Each Quarter - 1981 mR/Quarter Distance miles 0-1 1-2 2-4 4-6

>6 Avera e External Gamma Radiation Levels b 2nd uarter 3rd uarter 1st uarter 21.0 + 1.6 16.7 + 3.2 16.2 + 3.3 17.1

+ 2.2 15.9

+ 3.5 18.8 +.1.2 17.1 + 1.2 16.5 + 1.2 16.6 + 1.1 16.5 + 2.2 21.7

+ 2.0 17.3 + 2.2 15.6

+ 1.8 17.0

+ 1.6 16.8 + 2.7 4th uarter 20.0 + 1.5 20.0 + 5.0 16.5

+ 1.7 16.6 + 1.3 16.6 + 2.3

Average, 0-2 miles (Onsite) 18.4 + 1.4 20.6 + 2.8 19.9 + 2.7 20.1 + 2.1

Average,

>2 miles (Offsite) 16.5+ 1.5 16.7 + 2.0 16.6 + 2.8 16.6 + 1.7

a. Data normalized to one quarter (2190 hours0.0253 days <br />0.608 hours <br />0.00362 weeks <br />8.33295e-4 months <br />).

b. All averages reported

+1v (68 percent confidence level).

TAPLE 16 NAIIE OF FACILITY ORON44S FERQT LOCATION llF FACILITY~RSm RADIOACTIVIT'Z IN FOOD CROPS PCI/KG -

0 ~ 037 BQ/KG (VET VEIGHT)

A/A~AHA DOCKET NO ~0~9~A296 RCl GRPT ItcG PCR IOD~FQ TZPE At)0 LOVER LIHIT ALL TCTAL Nbt'BCR OF INDICATOR LOCALIONS OF ANALTSIS GETECTIONa HEAN (F)

PFRFOR)EFO (L 0)

RANGf LOCATICh VITH HIGHCST AhNUAL HCAN NAKE PEAN (F)o RADIOACTIVITT IN CABBAGE COt(T)EOL LOCATION)

MEAN (g)

RA C

NUHBCR OF NONROUTINE REPORTED NI 4 S O~RR I NIS GROSS PCTA 25 F 000 8 I-214 PB 212 NOT CSTAP NOT ESTAB 1

GAH<A.(GCLI) 1 K-4 0 NOT ESTAB 1873 F 00(

1873 ~ 00-13N40(

13 ~ 40-15 ~ 75 l 15 ~ 75-1/

1) 1873 ADO 1/

1) 13 F 40 I/

1) 15'5

')286 86(

1/

1) 4286.86-4266.86 4 HILES N R HILES N HILCS N

4 H ILES N

4286'6l 1/

1) 4286 '6-4286 '6 1873 'Cl 1/

1) 1873 F 00-1873 00 13 F 40(

1/

1) 13 F 40 13 F 40 15'5l I/

1) 15'5 15'5 GROSS BETA 25.a00 2

GAHER4 (GCLI

)

2 K-v0 NOT ESTAB 4163 ~ 82(

1/

1) 4163 82-4163 ~ 82 1964 ~ 00 l 1/

1')

Ltl2 BF NORTH 1964 ~ 00-1964 ~ 00 0 ~ 9 '9ILE tlNC 1964 F 00(

I/

1) lq32 F 00(

1/

1) 1964 F 00-1964 F 00 1932 F 00 1932 F 00 RAGIOACTIVITT IN CORN LH2 BF NORTH 4163 ~ 82(

1/

1) 3995 ~ 66(

1/

1) 0 9 I(ILE t(tJE 4163 ~ 82 416

~ 82 3995 ~ 66 3995 66 RAOIOACTIVITV Itt GREEN BEANS 25 F 000 P I-214 PB-212 t)OT ESTAB NOT ESTAB GROSS BC TA 2

GAHH4 (GCLI)

R:

K-40 NOT ESTAB ~

s.132 ~ DD (

1/

1) 2 MILES NNV 2132 'C-2132N00 I

VALUES I:LLO 6 ~ 89(

6 ~ 89-1/

1) 2 KILES NNV 6 ~ 89 4874 ~ 83(

1/

I) 2 HILES NNV 4874.83-4874.83 2132 ~ 00(

1/

1) 2132NOC-2132

~ 00 6'9(

6N89-1/

I) 6'9 4874 '3(

1/

1)

R874 F 83-4874 '3 1682 F 00(

1682 ~ 00-20 '0(

20 ~ 50-29058(

29 ~ 58-1/

1) 1682 F 00 1/

1) 20'0 I/

1) 29 F 58 3251N74(

1/

1) 3251 '4-3251 '4 a.

Nominal Lover Limit of Detection (LLD) as described in Table 3.

b.

Mean and range based upon detectable measurements only.

Fraction of detectable measurements of specified locations is indicated in parentheses (F).

NAHE OF FtCILITY BROl't(S FERRY LOC AI ION OF F AC ILIIT~M~TO)Aj, TABLE 16 (Contd)

RADIOAC'(IVITY I'I FOOD CROPS PCI/KG -

0 ~ C37 CO/KG (MEET VEIGHI

)

A~/AHA (EQCh T

)GOD 50-2~59

?60 REPORTIttG PE(AIOD $901 TYPE AND LOWE(E LIMIT ALL TOTAL NUMBER OF INDICATOR LOCATIONS OF ANALYSIS DETECTION MEAN (F)b

~CA1 GM II TH I~IGHm~AIIUAAJC~AM NAME

'EAN (F)~

~STANCE AAG GTRECTTGM RANGE CONTROL LOCATION<b tlEAN ([)

RAN6E NUMBER OF NONROUTINE REPORTED

~HEASU EHEMTS RADIOACTIVITY IN PEACHES GROSS BETA 2

6AHHA (GELI) 2 K-4 0 81-214 PB-212 25 F 000 NOT ESTAB NOT ESTAB NOT ESTAB 1697 F 00(

1697 00-22U43(

22 43-19e53(

19 ~ 53-I/

1) 1697'0 1/

1) 22+43 1/

1) 19 ~ 53 3127 13(

1/

1) 3127U13-3127 '3 SHITH FARM 4 ~ 75 MILES SMITH FARY 75 MILES SMITH FARM 4 ~ 75 MILES 1697 F 00(

1697 ~ 00-22'3(

22 ~ 43-19'3(

19 ~ 53-1/

1) 1697 'G I/

1) 22+43 1/

1) 19'3 1252 F 00(

1/

1) 125? F 00- 125? ~ OG 1

VALUES <LLO 1

VALUES <LLD SHITH FARM 3127 ~ 13(

1/

1) 2970 ~ 49(

1/

1) 4 ~ 75 HILES N 3127 ~ 13-31?7 ~ 13 2970 ~ 49-2970 ~ 49 RADIOACTIVITY IN POTATOES81-214 PB-212 NOT ESTAB NOT ESTAB GROSS BETA 25.000 2

GAMMA (GELI

)

2 K-40 NOT ESTAB 3201 'O(

3201

~ OC-15M62(

15 ~ 62-13'2(

. 13 ~ 62-1/

1) 3201 F 00 1/

1) 15 F 62

)/

1) 13'2 2 MILES NN)t 2 MILES NNI 2 HILES NNM 3201 F 00(

3?01

~ 00-15462(

15 ~ 62-13'2(

13 ~ 62-1/

1) 3201 F 00 I/

1) 15'2 1/

1) 13'2 3473 F 00(

1/

1) 3473 F 00- 3473 F 00 1

VALUES <LLD 1

VALUES <LLO 7112 ~ 16(

I/

I) 2 MILES NNN 7112 ~ 16(

1/

1) 7721U34(

1/

1) 7112 ~ 16-7112M)6 7112 '6-7112U16 7721 '4-7721 '4 a.

Nominal Lower Limit of Detection (LLD) as described in Table 3.

b.

Mean and range based upon detectable measurements only.

Fraction of detectable measurements of specified locations is indicated in parentheses (F).

NAHC GF FACILITY BRO'aNS FERRY LOCATION OF FACILITY~~HJO)sf TA<<C 16 (ContTQ RADIOACTIVITY I)

PCI/KG - 0aG37 80/KG (VCT MCIGMT)

A REPORTING PERIOD 198')

TYPE ANO LOMER LI HIT ALL TOTAL NUHBER OF INDICATOR LOCATIONS OF ANALYSIS DETECTION a MEAN (F>b

~OCATIOII II ~ttt H

H "T AkttllAT~HAN CONTROL LOCATIONS MEAN ($ )

RANGE NUHBCR OF NONROUT INC REPORTED

~NON~AN TS RADIOACTIVITY IN TOMATOES GROSS BCTA 2

GAMMA (GCLI)

K-40 PB 212 NOT ESTAB NOT ESTAB 2513 ~ GO(

1/

1)

BROOKS FAFH 2513 ~ 00(

I/

1) 2513 ~ 00 2513a00 7NG MILES NN)i 2513 ~ 00- 2513e00 11 F 15(

I/

1)=-

BROOKS FARM 11 F 15(

1/

1) lla15 llel5 7a0 MILES NNN 11'5 Iles 15 2381 F 00(

I/

1)

~

238le00-2381 '0 VALUES CLLO 25 ~ 000 5130 21(

1/

1)

BROOKS FARM 5130 ~ 2l (

I/

1) 5669 17(

I/

5130e21 5130e21

7' MILES NNN 5130 '1-5130 ~ 21 5669al7-5669e17 RADIOACTIVITY IN TURNIP GREENS GROSS OCTA 2

GAHHA (GELI )

2 K 40 81-214 PB 214 PB-212 BE-7 25a OOA)

NOT ESTAB NOT ESTAB NOT E'STAB NOT ESTAB NOT ESTAB 2262 F 00(

2262 ~ 00-22a93(

22 ~ 93-13e53(

13 ~ 53-11 ~ 42(

11 ~ 42-194 '0(

194 '0 1/

1) 2262 F 00 1/

1) 22 ~ 93 1/

1) 13'3 1/

I) 11 F 42 1/

1) 194 '0 4

MILES N MILES N 4 MILES N MILES N 4 MILES N

5500a16(

1/

1) 4 )'TILES N

5500 ~ 16" 5500 e 1 6 2262 F 00(

2262 F 00 22'3(

22 ~ 93-13'3(

13 53-llew 42(

11 ~ 42-194 '0(

194 ~ 40-1/

1) 2262 00 1/

1) 22'3 1/

1) 13'3 1/

1) 11'2 1/

1) 194 F 40 2980e00(

1/

1) 2980 F 00- 2980 00 37'4(

1/

1) 37'4-37'4 1

VALUES (LLO 26'1(

1/

I) 26'1-26a21 1

VALUES O.'LLO 5500el6(

1/

1) 5969a0$ (

1/

1) 5500el6-5500 '6 5969 F 01-5969 F 01 a.

Nominal LoToer Limit of Detection (LLD) as described in Table 3.

b-Mean and range based upon detectable measurements only.

Fraction of detectable measurements of specified locations is indicated in parentheses (p)..

TABLE 17 NAHE OF FACILITY 8ROlJNS FEAR>

LOCATION OF FAG ILI TY Q~IH SJONE RADIOACTIVITY IN SOYBEANS PCI/6 6 ~ 037 BG/G (DRY VEIGHT)

A ABAHA SOCKET NO ~50- 5) 26~0296 REPGRTING PERIOD ~9 TYPE AND TOTAL NUBBER OF ANALYSIS

~PE P~RH 5

GROSS BETA

?

GAHHA (GELI) 2 LOVER LI HIT'F DETECTION a 0 200 ALL INDICATOFL LOCATIONS HEAN (F)b

=!i RAN E

29 F 53(

2/

2) 29 F 40 29065

~O ATION N)TH HIEHEST AhNHAE NEAR NAHE HEAN (F)b j)~sT Rcf 6h~ui)~~to REEiiiih LH2 BF NORTH 29'3(

2/

2) 009 NILE NNE 29'0-29'5 CONTRGL LOCATI.ONS HEAN (F)b b

NUBBER OF NONROUTINE REPORTED

~HA Q~RHQN TS K 40 Bl 214 PB-214 BE-7 AC-228 NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB 15 ~ 74 (

14070-0003(

0003-0'5(

0 ~ 04-D020(

0'0 0011(

0 ~ 11-2/

2) 16077 1/

2) 0'3 2/

2) 0 F 06 1/

2) 0'0 I/

2) 0011 LH2 BF NORTH 009 NILE NNE LH2 BF NORTH G

9 NILE tJNE LH2 BF NORTH 0 ~ 9 NILE MNE LH?

BF NORTH 009 HILE NNE LH2 BF NORTH 009 NILE NNE 15 74(

14070 0'3(

0003-0'5(

0 ~ 04-0'0(

0020" 0 ~ 11(

0 <<11-2/

2) 16'7 1/

2) 0 F 03 2/

?)

0006 1/

?)

0'0 1/

2)

~ 0011 a.

)Jominal Lower Limit of Detection (LLD) as described in Table 3.

b.

Mean and range based upon detectable measurements only.

Fraction of detectable measurements of specified locations is indicated in parentheses (p).

NAKE OF FACILITY BROllNS FERRY LOCATION OF F AC ILIIY~~IH

~OQE TABLE 18 RADIOACTIVITY IN POULTRY PCI/KG 0 ~ 037 BQ/KG (NTET QEIGIET)

A~A/AHA REPORTING PERIOD~98 T YPE ACED TOTAL NUMBER OF ANALYSIS PERPORTED GROSS BETA 2

GAHHA (GELI) 2 LOVER LIHII OF DETECT ION a (LLO) 250000 At.L INDICATOR LOCATIONS YEAN CF)b R~A 4972066 C

1/

1) 4972 '6-4972 ~ 66.

uEEATIGN IIITK I~IIGK RT AIIN~NA II All NAHE HEAN (F)b LH5 BF DAVIS F 4972 66(

I/

1) 2' HILES MSI'972066-4972 66 CONTROL LOCATIONS.

HEAN (F)b A

b 6458 '6(

1/

1.)

6458 '6-6458 '6 NUHBER OF NONROUTINE REPORTED K-40 8 I-214 PB-214 PB-212 NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB 2412 ~ 00C 1/

I) 2412000-2412 F 00 I VALUES <LLD 1

VALUES <LLD 1

VALUES <LLD LH5 BF DAVIS F

2 5 HILES MSN 2412 F 00(

1/

I) 2412 F 00- 2412 F 00, 2137000(

2137 F 00 19056(

19 ~56-18'8(

18'8 10'6(

10 ~ 86-1/

1) 2137 F 00 I/

I) 19056 I/

I) 18 38 1/

I) 10'6 a.

I(ominal Lover Limit of Detection (LLD) as described in Table 3.

b.

Mean and ran8e based upon detectable measurements only.

Praction of detectable measurements of specified locations is indicated in parentheses'(P).

Figure 6

IO CO Slg JJ O

oJl Ch C4I le CI}

o

~4c 0 V

le 4J

'o c0 M Q Preoperational Phase Operational Phase ANNIAL AVERAGE 6ROSS HEfA kTIVITY I N HRI N<II5 MATER SUPPLIES HROH% FERRY }%LLEAR KAhT Average:

Preoperational Phase 19 8

19 9

19 0 1

1 19 2

19 3P 19 30 19 4 1

5 19 6 1

7

.19 8 1

9 19 0

1 1

38 Figure 7

21 Olrect Rod)at)on Levels 8rowns Fer ry Nuclear P lani O

C.Q 18 C7 6

16 Onstte I

I o'

I60'sl te 0

I '1

\\

1

\\

1

\\

4, 1

I1

\\

i 1 I'

'1 I

1 6

o ~'o -o 1976 1977 1978 1979

)988 1981 Figure 8

22 OlreCI Radtat tcn LevelS Srowns Ferry Nucleor Plant

~-auar ter Hovtng Aver oge C.

Q

)8 8

0:8 16 Ons I t e

,A

.P" p"

'0

/

b

.AI

,P 0

Of fs) te

)976 1977 1978

)979

)988 198)

Figure 9

39 2t Olrect Radtot ton Levels Wot ts Bar Nuclear Plant 22 C.

s 18 Cf OC8 OesI'Ie Offst te o p-~

\\

I b

I I

I I

1976 1977 1978 1979 1988 1981 Figure 10

'2 Olrect Radtot ion Levels Mot ts Bar Nuclear Plont 0-Quar ter Moving Average Oust te 16 1976 1977 1978 1979 1988 1981

b

.I

Reservoir Monitorin Samples are collected from the Tennessee River as detailed in table 19.

Samples collected for radiological analysis include plankton from three of these cross sections and bottom fauna and sediment from four cross sections.

The locations of these cross sections are shown on the accompanying map (figure ll) and conform to sediment ranges established and surveyed by TVA.

Water Water samples are collected automatically by sequential type sampling devices at three cross sections and composite samples analyzed monthly for gamma-emitting radionuclides.

Further composites are made quarterly for strontium and tritium analyses.

In addition to these required samples, grab samples were also collected monthly from the vicinity of the plant discharge to the Tennessee

River, and at a point on the Elk River, and analyzed for gross beta, gamma-emitting radionuclides, and strontium.

Results are displayed in table 20.

Figure 12 presents a plot of the gross beta activity in surface water from 1968 through 1981.

No gross beta measurements were made in surface water samples in 1978.

The levels reported are consistent with gross beta levels measured in surface water samples taken from the Tennessee River in preoperational monitoring programs conducted by TVA at other sites.

Fish Radiological monitoring for fish is accomplished by analysis of composite samples of adult fish taken from each of three contiguous reser-voirsWilson, Wheeler, and Guntersville.

No permanent sampling stations have been established within each reservoir; this reflects the movement of fish species within reservoirs as determined by TVA data from the BFN preoperational monitoring program.

Two species, white crappie and smallmouth buffalo, are collected representing both commercial and game species.

Sufficient fish are collected in each reservoir to yield 250 to 300 grams oven-dry weight for analytical purposes.

All samples are collected semiannually and analyzed for gamma-emitting radionuclides.

The composite samples contain approximately the same quantity of flesh from each fish.

For each composite a subsample of material is drawn for counting..

Results are given in tables 21,. 22, and 23.

Plankton As indicated in table 19, net plankton (all phytoplankton and zoo-plankton caught with a 100 p mesh net) is collected for radiological analyses at each of three stations by vertical tows with a 1/2-meter'et.

At least 50 grams (wet weight) of material is necessary for analytical accuracy.

Samples are collected semiannually and submitted for gross beta analysis, and when quantities are sufficient, for gamma activity and Sr and Sr content.

During this reporting period, all samples contained insufficient volume of material for gross beta, strontium, or gamma analyses.

42 Sediment Sediment samples are collected from Ponar dredge hauls made for bottom fauna.

Gamma radioactivity and Sr and Sr content are determined 9o

'emiannually in composite samples collected from e'ach of four stations.

Locations of these stations are shown in table 19.

Results are shown in table 24.

Bottom Fauna The flesh and shells of Asiatic clams collected semiannually from the cross sections at four stations (table

19) are analyzed for gamma-emitting radionuclides.

Levels of Sr and Sr are determined on the shells, and on the flesh when sufficient amounts were available.

A 50-gram (wet weight) sample provides sufficient activity for counting.

During this reporting

period, one sample of clam flesh contained insufficient volume for analysis.

Results are given in tables 25 and 26.

Table 19 SAMPLING SCHEDULE - RESERVOIR MONITORING Biolo ical sam les (collected semiannuall

)

River/river mile Zooplankton, chlorophyll, Benthic phytoplankton fauna Sediment Pish

-=(co8ecEe5 mlnMly)

Tennessee 277.9 Tennessee 285.2 X

Tennessee 288.7 Tennessee 291.7 Tennessee 293.5 Tennessee 293.7 (discharge area)

X Tennessee 305.0 (Control)

Tennessee 307.5 (Control)

X Elk 20.5 (Control) a.

Gill net and/or electroshocker will be used for collection.

Samples of fish are collected from Guntersville,

Wheeler, and Wilson Reservoirs.

b.

Automatic sampler.

c.

Grab sample.

TABLE 20 NAME OF FACILITY BRO) NS FERRY LOCATION OF FACILITY ~JflfQJOQf.

RADIOACTIVITY Itl SURFACE rATER TOTAL PC, I/L -

0 ~ 037 BQ/L DOCKET NQ ~

50-2~59 260A296 TYPE AND TOT AL t.'JHBER OF AttALYSIS PERFORiMFD GROSS BETA 32 GAHHD (to AI )

45 LOltER L IHIT OF OETECT IONa (LLD) 2~400 ALL INDICATOR LOCATIONS MEAN (F)b RANGEb 3 53(

14/

17) 2'3-5a16 27 VALUES <LLO ANALYSIS PERFORMED LOCATION JITH HIGHEST ANNUAL HEAtt NAME MEAN ([)b OISTAttCC At'g DIRECTIOtt RANGE TRP. 293+5 3'6(

2/

2) 3'0-4'2 CONTROL LOCATIONS MEAN (F)

RAt'GEb 5~27(

12/

15) 2'9-F 58 18 VALUES <LLD NUHBER OF NONROUTINE REPORTED 81-214 PB-214 PB-212 SR 89 SR 90 TRITIUM NOT ESTAB NOT ESTAB NOT ESTAB 10 F 000 Sb 2 F 000 36 330 F 000 20 GAHHA (GELI) 20 K-40 NOT ESTAB 105'0(

~ 5/

12) 51 '2-159 'i) 15~99(

5/

12) 4'6-23 F 87 26 F 00(

I/

12) 26.00-26.00 15'5(

3/

12) 12'3-17~62 20 VALUES <LLD ANALYSIS PERFORMED F 81(

1/

20) 2'1-2~81 372ell(

2/

12) 364 F 86- '79 '5 TRH 293 '

BFlt DISCHARGE TR)'i 285 ~ 2 TRH 293 '

BFte DISCHARGE TR4 285 ~ 2 TRH 293 '

BFA'ISCHARGE TRH 293 '

139'5(

119 10-18 F 60(

IBol4-26e 00 (

26 ~ 00-17'2(

17 ~ 62-2'1(

2i8)-

379 '5(

379 ~ 35-2/

3) 159 F 80 2/

3) 19'6 1/

3) 26 00 1/

3) 17'2 1/

12)

F 81 1/

4) 379 ~ 35 96 '3(

2/

8) 74 '5-118 '0 31'4(

6/

8)

F 00-8'5 27'4(

4/

8) 10 F 44-55'9 13'3(

3/

8) 8'2-22'1 16 VALUES <LED 2'7(

I/

16) 2~07-2og7 VALUES <LLD a.

Hominal Lover Limit of Detection (LLD) as described in Table 3.

b.

Mean and range based upon detectable measurements only.

Praction of detectable measurements of specified locations is indicated in parentheses (P).

TAbLE 21 RADIOACTIVIT'I IN liHITE CRAPPIE (FLESH)

PCI/G -

0 ~ 037 BO/G (DRY MEIGIsT)

NA!IE OF FACILITY /RAN fERRY LOCATION OF FACILITY LIHESl'ONE ALABAHA DOCKET NO ~ 50-259~60 REPORTING PERIOD )9

)

TYPE AND TOTAL NUHBER OF ANALYSIS PERFORHED GROSS BETA GAHHA (GELI) 6 LOMER L I HIT OF DETECT ION a CLLJ) 0 ~ 100 ALL INDICATOR LOCATIONS HEAN (F)b RA>>G b

35018(

4/

4) 33004-37'6 NAPE HEAN CF)b MILSON RESERVOIR 35'6(

2/

2)

TRH 259-275 34 '8,-

350b4 CONTROL LOCATIONS HEAN (F)

R~N~

34 F 87(

2/

2) 33'3-36 F 72 NUHBER OF NONROUTINE REPORTED

~RII S U~R

~SR T S CS 137 K-49 BI-214 PB-214 PB-212 0 '20 NOT ESTAB 0'20 NOT ESTAB NOT ESTAB 0 ~ 12(

0 09-14 '5(

12 ~ 72-0007(

0 ~ 05 0007 (

0'6 0 ~ 02(

0 ~ 02-4/

4) 0 ~ 14 sl/

4) 15063 2/

4) 0.09 2/

4) 0'7 1/

4) 0'2 MILSON RESERVOIR TRH 259 275 MILSON RESEPVOIR TRH 259-275 MHEELER RES TRH 275-349 MILSON RESERVOIR TRH 259-275 MHEELER RES TRH 275-349 0 ~ 13(

0013-15 20(

14'7 0009(

0 ~ 09-0 07(

0 ~ 07-0'2(

0 02-2/

2) 0 ~ 13 2/

2) 15'3 1/

2) 0009 1/

2) 0007 1/

2) 0002 0'4(

2/

2) 0'9-0 ~ 18 17 '0C 2/

2) 15'9-19'1 0 ~ 06(

1/

2) 0 ~ 06-0'6 2

VALUES (LLD 0 02(

1/

2) 0 ~ 02-0'2 a.

Nominal Lower Limit of Detection (LLD) as described in Table 3.

b.

Hean and range based upon detectable measurements only.

Fraction of detectable measurements of specified locations is indicated in parentheses (F).

TAFLE 22 RADIOACTIVITY IN SHALLHOUTH BUFFALO (FLESH)

PCI/G:

037 80/G (ORY VEIGHT)

NAHE OF FACILITY BROVNS F/RRY LOCATION OF FACILITY LIHESJONE A/AGAMA DOCKET NOR~~9ggg 296 REPORT 1NR PERRON~RE TYPE ANO TOTAL:iU."OER OF'NALYSIS GRASS BETA GAMMA (GELT) 6 LOVER LIHIT OF DETECT IOM)

~Q 0'00 ALL INDICATOR LOCATIONS MEAN (F) b FT ANGEb 23N 07(

4/

4) 19P 04-27 ~ 20 iOI STANCE ANO DIRECTION RANGLb VHEELEF RES 25'7(

2/

2)

TRH 27$ -349 2'4 27'0 CONTROL LOCATIONS MEAN (F)b

~R4 N 22NRO(

2/

2) 20 F 12 24'8 NUMBER 'OF NONROUTINE REPORTED

~HAS()~RM NTS CS-137 K-40 OI-214 PB-214 PB-212 TL-208 SP 89 SR 99 0'20 NOT ESTAB 0'20 NOT ESTAB NOT ESTAB 0'20 0 ~ 500 0 F 100 "0 ~ 05(

4/

4)

OP OR-0 ~ 06 9N64 (

4/

4) 7 ~ 36-Ill56 0 ~ 06(

3/

4)

F 05-0 F 98 F 06(

2/

4) 0 F 05-0'7 0 F 04(

1/

4) 0 F 04-0 F 04 0 F 02(

1/

4)

F 02-0 F 02 1

VALUES <LLO ANALYSIS PERFORHED 1

VALUES <LLO ANALYSIS PERFORMED VHEELEP RES TRH 271 RRn MHEELER RES TRH 275-349 VILSON EEESER VAIR TRH 259-275 VHEELER RES TRH 275-349 VHEELER RES TRH 275-349 VTHEELER RES TRH 2?5-349 0 ~ 05(

0 ~ CR llew 03(

10'9 0 F 08(

0 ~ 08-0'7(

0'7 0 ~ C4(

0 ~ 04 ON02(

0 ~ 02-2/

2) 0'6 2/

2) 11 '6 1/

2) 0 ~ 08 1/

2) 0 F 07 1/

2)

OoCR 1/

2) 0 F 02 0 F 08(

2/

2) 0'7 0'8 8'2(

2/

2)

F 00-10'4 F 14(

1/

2) 0'4-0 ~ 14 ON09(

1/

2) 0+09-0'9 2

VALUES <LLD 2

VALUES <LLO 0

VALUES <LLO 0

VALUES <LLO a.

Nominal Lover Limit of Detection (LLD) as described in Table 3.

b.

Mean and ran8e based upon detectable measurements only.

Fraction of detectable measurements of specified locations is indicated in parentheses (F).

TABLE 23

~

RADIOACTIVITY IN St(ALLI-'OUTH "BUFFALO (llHOLE)

PCI/O -

0 0

7 BO/G (ORY )(EIGhT)

NaVE OF FACILITY QROVNS JERRY LOCATION OF FACILITY LJHQSJQPQ AL,a~AHA IIEPORIING PERIOO I.~R TYPE AND TOTAL t(U."BER OF ANALYSIS P~RF ~R~u GROSS BETA 6

GAHHA (GELI) 6 CS-137 K-4 0 BI-214 PB-214 PB-212 SR 89 SR 90 LOVER L IHIT OF DETECT IONa 0 100 0 ~ 020 NOT ESTAB 0'20 NOT ESTAB NOT ESTAB

'0 ~ 50 0 0 ~ 100 ALL INDICATOR LOCATiONS MEAN (F)b RANGEb 19N22(

4/

4) 18'7-19N95 0 ~ 03(

2/

4) 0 ~ 03-0 ~ 03 8N08(

4/

4)

.F 83-F 11 0'6(

4/

4) 0'4-0 F 08 ON07(

3/

4) 0 ~ 04-0 ~ 12 0 ~ 03(

2/

4) 0 03-0'3 1

VALUES CL'LD ANALYSIS PERFORMED 1

VALUES (LLO ANALYSIS PERFORMED VHEELER RES TRH 275-349 VHEELER RES TRH 275-349 MILSQW RESERVOIR TRH 259-275 (tILSOtt RESERVOIR TRH 259-275 VHEELER RES TRH 275-349 0+03(

0'3 8'0(

7 ~ 50-0 F 06(

0 04-0'2(

0 ~ 12-0'3(

0003-1/

2) 0'3 2/

2) 8'9 2/

2) 0 F 08 1/

2) 0'2 I/

2) 0 F 03 LOCATION VITH HIGH(:ST At(NUA H

AN NAME HEAN (F)

P IZIEH~N~~LECCTLJUL ~AKiK VMEELER RES 19'6(

2/

2)

TRH 275-349 IBN57-19'5 COt(TROL LOCATIONS MEAN (f)

R~Af, 20'4(

2/

2) 14'7-26'1 F 04(

1/

2) 0 F 04-0'4 7'8(

2/

2)

F 10-9'7 0 F 06(

2/

2) 0'3-ONOB 0 F 08(

1/

2) 0.08-0.08 0'3(

2/

2) 0'3-0 F 04 0

VALUES GiLLO 0

VALUES (LLD NUMBER OF NONROUT INE REPORTED a.

Nominal Lower Limit of Detection (LLD) as described in Table 3.

b.

Mean and range based upon detectable measurements only.

Fraction of detectable measurements of specified locations is indicated in parentheses (F).

I D

TABLE 24 NAKE GF FACILITY QROQNS F/RRY LOCATION OF FACILITY LIK~STO~N RADIOACTIVITY Itt SEOIKEttT PCI/G -

0 ~ 037 80/G (DRY itEIGUT)

ALAHAHA DOCKET t(04~50- $~9~60A+g t(EPORTlttG PERIOD 1981 TYPE At(D TOTAL "tUHBER OF ANALYSIS PfEEKBFD GAHHA (GELI )

8 LOitER LI HIT OF DETECT IOka

~(JJ) )

ALL INDICATOR LOCATIONS HEAN (F>b OCATION itI TH HIGH( ST AkhUAL KEAtt R

kAHE HEat

([)b gJ~TNC~ANg QiRfC/lGN R~AkG CONTROL LOCATION) t(UHBER OF

)GONROUTINE REPORTED

~A~~NT S 00010 00080 0'20 0'30 0.010 CO 60c CS-134 CS 137c ZR 95 NB-95 0 14(

5/

6>

C ~ 07-0'1 0013(

1/

~

6) 0'3-0'3 1 ~ 70(

6/

6) 0'3-2'5 6

VALUES <LLD TRH 293 F 7 BFN DISC(tARGE TRH 293' BFN DISCHARGE TRH 277'8 2

VALUES <LLO 2/

2) 0 ~ 21 1/

2) 0013 2/

2) 2'5 0 ~ 20(

0 ~ 19-0'3(

0 ~ 13 2'4(

2023 2

VALUES <LLD 2/

2) 0431 1/

2) 0 ~ 07 1/

2) 0'2 2/

2) 15'6 1/

2) 0'3 2/

2) 1 ~ 96 2/

2) 1'6 2/

2)

F 09 2/

2) 2'8 2/

2) 1096 2/

2) 0 F 87 2/

2) 0'8 2/

2) 2 ~ 68 ES

<LLO 0'7(

0'3 0'7(

0407-0012(

0412 6 VALUES <LLD TRH 288'8 TRK 29307 BFN DISCHARGE I'RH 277'8 NOT ESTAB 0'10 0'3(

0 ~ 03-1'9l 1061 1 ~ 15(

0 ~ 93-1.86(

1 ~ 64 2 F 00(

1 ~ 82 1479(

1061-0'5(

0'2 0 F 73(

0068 2'2(

1 ~ 95-2 VALU 0 ~ 020 0 '0C NOT ESTAB NOT ESTAB RA-226 RA-223 0 ~ 020 0 '60 1 ~ 5') 0 a.

b.

K-40 14 '0(

6/

6) 15e75(

2/

2)

~ 14'5l llew 42 16'2

.15007 16 ~ 42 13 ~ 64-Htt 54 0 F 05(

2/

6) 0 F 06(

1/

2) 0'4-0006 0 ~ 06-0006 t) 1-214 1035(

6/

6) 1 ~ 44(

2/

2) 1 ~ 11-1 e53 1 ~ 35-1053 Bl 212 1 06(

5/

6)

TRti 288.78 1 ~ 33(

1/

2) 0'8-1033 1033-1 ~ 33 PB-214 1 ~ 50l 6/

6)

TRH 277'8 1 ~ 68(

2/

2) 1018-1 ~ 71 1 ~ 66-1 ~ 71 PB-212 1 ~ 86(

6/

6)

TRK 288'8 2'l(

2/

2) 1 ~ 57-2 ~ Cb 1 ~ 98-F 05 NOT ESTAB 1 35(

6/

6)

TR< 277'8 1 ~ 44(

2/

2) 1 ~ll-1 ~ 53 1'5 1053 t(OI ESTAB 0 49(

2/

6>

'IRH 293 7

0050(

1/

2) 0 47-0 ~ 50 BFN DISCtiARGE 0 F 50 0 ~ 50 TL-208 3 ~ 57(

6/

6)

TRH 277 'R 0'5(

2/

2) 0044-0'7 0'2 0'7 AC-228 1.72(

6/

6>

TRK 277.98 1 ~ 89(

2/

2) 1 35-1 ~ 94 1083-1094 SR 89 6

VALUES <LLD AtiALYSIS PERFORHED SR 90 0 ~ 300 6

VALUES <LLD 0052(

1/

2) 0'2-0 ~ 52 Nominal Lovel Limit of Detection (LLD) as described in Table 3.

Mean and range based upon detectable measurements only.

Fraction of detectable measurements of specified locations is indicated in parentheses (p).

. ~-> 'tn>>or(>>nn r>>nnrrrc( herein is comparable to the distribution reported in the

TABLE 25 hAHE OF FACILITY PROUJJS FERRY LOCATION OF FACILITY LIH~STG~N RADIOACTIVITY IN CLAN FLESH PCI/O -

0 ~ 037 BC/G (ORY MEIG)sT)

ALABAHA OGCKET hOo~5 -

~59 REPORTING PERIOD

)981 TYPE AND TOTAL LUHAEW OF ANALYSIS GAHHA (GELI) 7 K-40 81-214 ch-214 PB-212 TL-208 LOUER LIHIT OF DETECT IONa (Q Q) hOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB 8 ~ 97(

6 ~ 49-4 ~ 27(

1 70-4'9(

1 10-F 12(

1 ~ 02-0 ~ 40(

0 ~ 40-4/

5) 12'5 5/

5) 7 F 05 5/

5) 9'5 3/

5) 1 ~ 17 I/

5) 0+40 ALL INDICATOR LOCATIONS HEAN (F) b TRH 288'8 TRH 277'8 TRH 277 ~ 98 TRH 288 78 TRs( 288a78 9+32(

6 ~ 49-6'0(

bo40 9'5(

9+05-1 F 17(

1+17-0 ~ 40(

Oo40-2/

2) 12 F 15 1/

1) 6'0 1/

1)

F 05 1/

2) 1'7 1/

2) 0+40 LOCATION MITH HIGHEST ANNUAL HEAN CONTROL LOCATIOJJS HEAN (F)b RANGfb 17 F 11(

1/

2) 17 ll-17 F 11 2 72(

2/

2)

F 12-3'2 4'1(

2/

2)

F 80-7'3 0'0(

1/

2) 0 ~ 50-0'0 2

VALUES (LLD hUHBER OF NOsJROUTINE REPORTED I'/~AS ~R~Hh S

s 4

a.

Hominal Lover Limit of Detection (LLD) as described in Table 3.

b.

Hean and range based. upon detectable measurements only.

Praction of detectable measurements of specified locations is indicated in parentheses (P).

TABLE 26 RAI'I OF FAOILIII RL~R FEE~R LOCAI ION OF F AC ILI TY L IHES TONE RADIOACTIVITY It'LAH SHELL PCI/G -

0 ~ 037 8( /G (DKY L'EIGHT)

AgarAHA DOCKET NO ~

REPORT I tIG PERIOD 1981 TYPE AtJO TOTAL NUHOEQ OF ANALYS IS GAu>A (GELI) 8 LOMER LIHI T ALL OF IIIOICATOR LOCATIONS DETECTIONa HEAN (F)b (LLO)

RANGL NAHE HEAth (F)b OISTANC ANO OI RECT IOtt RANG&

CONTROL NUHBER OF LOCATIO)IbS NONROUTINE HEAN (F)

REPORTED RAMOjb

~HAS~UR H

NTS K-4 0 (FI-214 51-212 PB-214 PB-212 RA-226 TL-208 4C-228 SR 89 SR 90 NOT ESTAB 0'50 0

100 0~050 NOT ESTAB 0'50 0 020 0+060 F 000 1 F 000 1 ~ 15(

6/

6) 0'9-3'2 6/

6)

F 11-1 ~ 57 0 20(

I/

6) 0'0-0'0 0'6(

6/

6) 0'9-leOS 0 ~ 39(

5/

6) 0 F 09-0 ~ 90 0'8(

6/

6) 0 ~ II-1 ~ 57 0 06(

4/

6) 0 ~ 05-0 ~ 11 0'1(

3/

6) 0'8" 0 33 6

VALUES (LLD ANALYSIS PERFORHED 1 ~ 99(

6/

6) 1 ~ 28-2 70 TRH 277'8 TRH 277'8 TRH 293' BFN DISCHARGE TRH 277 '8 TRH 277 ~ 98 TRH 277'8 TRH 293 '

BFA'(

DISCHARGE TRH 288.78 TR< 293 '

BFN OISCI<ARGE 2 ~ 4((

0'9" 0+92(

0 ~ 27-0 ~ 20(

0+20-0 ~ 63(

0 ~ 21-0 ~ 49(

0 ~ 09-0 ~ 92(

0'7 F 10(

0009-0 32(

0 ~ 32-2/

2) 3'2 2/

2) 1 ~ 57 1/

2) 0 ~ 20 2/

2) 1+05 2/

2) 0'0 2/

2) i+57 2/

2)

F 11 1/

2) 0'2 2'9(

2/

2) 2~27-2'0 2'2(

2o31-2/

2) 2'3 1 ~ 13(

2/

2) 0'6-i+41 Oe46(

2/

2) 0 '0 0

52 2

VALUES (LLD 0'6(

2/

2) 0'2 0'0 0'5(

2/

2) 0 ~ 27 0 F 44 0 F 46(

2/

2)

Oa40-0 ~ 52 0 '3(.

2/

2) 0 ~ll 0'4 R

0 53(

1/

2) 0'3" 0

53 2

VALUES (LLD a.

Nominal Lover Limit of Detection (LLD) as described in Table 3.

b.

Hean and range based upon detectable measurements only.

Fraction of detectable measurements of specified locations is indicated in parentheses (F).

Figure 11 R ESERVOIR MONITORING NETWORK 51 Elk River WHEELER DAM mile 274.90 mile 277.98 Rogersville 0

mile 282.6 mile 29l.76 Athens prni(~ 285.2 B.F. NUCLEAR PLANT A

Champion Paper Co.

0 Cour tland ile 28878 mile 293.50 mile 293.70 mile 305.0 Decatur mite 307.52

~ - Automatic Sam ler Scale of Miles

Figure 12 IOCP COC 44 P C

44 III Ir V' 44 W C P Ii I 44 CP m 0 Pt'eoperational Phase 1

Operational Phase Adieu AVERAGE 6ROSS HETA ACTIYI7/

IN SURFACE )IATER IhaeS FERRY NuCLEAR Purr Average:

T Preoperational Phase 1968 1969 1970 1971 1972 1973P 19730 1974 1975 1976 1977 1 78 1 79 1980 1 81

53 ualit Control A quality control program has been established with the Alabama Department of Public Health Environmental Health Administration Laboratory and the Eastern Environmental Radiation Facility, Environmental Protection Agency, Montgomery, Alabama.

Samples of air, water, milk, and vegetation collected around BFN are forwarded to these laboratories for analysis, and results are exchanged for comparison.

Data measured at the control stations for each medium were averaged for each sampling period.

In order to describe the distribution of control station data, a mean, standard deviation, and 3<<sigma limits were calculated.

We can expect that background concentrations would be distributed within these limits.

This prov'ides us the basis for comparing control and,.indicator data.

If the indicator data fall within the limits defined for control data, we conclude that the indicator data were not significantly affected by the nuclear plant. If the data do not fall within the limits, we will perform further analyses to determine if the difference is attributable to the nuclear plant.

Conclusions A vast majority of the indicator station data was found to be within the distribution defined by the control station data.

The data analysis software identified concentrations slightly exceeding the limits of the control station data for a small number of radionuclides in samples from indicator stations.

Many of these values may be discounted because the error reported by the analysis program was greater than the calculated concentration.

The remaining isolated elevated concentrations may be the. result of fallout, fluctuations in the existing environment, computer program artifacts, or analytical errors.

The same type of isolated high values occurred in the control station data and may be attributed to the same sources.

Increased levels of radioactivity were observed in rainwater, air particulates,- heavy particle fallout, and in vegetation in the winter and spring following the atmospheric nuclear weapons testing conducted by the Republic of China in mid-October 1980.

This'increase was seen in control stations as well as indicator stations.

The primary radioisotopes identified in the atmospheric media were Zr,

.Nb, I,

~Bi, and o Ru.

Dose estimates were made from concentrations of radioactivity found in samples of environmental media.

Media sampled include, but are not limited to, air, milk, meat, vegetation, drinking water, and fish.

Doses estimated for persons at the indicator locations were essentially identical to those determined for persons at control locations.

Greater than 99 percent of those doses were contributed by the naturally occurring radionuclide potassium-40,

54 and by strontium-90 and cesium-137 which are long-lived radioisotopes found in fallout from nuclear weapon testing.

It is concluded from the above analysis of the data and from the trend plots presented earlier that there were no measurable increases in environmental radioactivity attributable to the operation of BFN.

TENNESSEE VALLEYAUTHORITY MUSCLE SHOALS. ALABAMA35660 River Oaks Building May 5, 1982 U.S. Nuclear Regulatory Commission c/o Regional Administrator Region IT.

Attention:

A. L. Cunningham Suite 3100, 101 Marietta Street

Atlanta, GA 30303 The enclosed report No.. TVA/OMS/OHS-82/7 "Environmental Radioactivity Levels Browns Ferry Nuclear Plant - Annual Report - 1981," is furnished for your. information and use.

Very truly yours, R. B.

Max@ 11, Chief Radiological Hygiene Branch Enclosure Q~y~G~>+

An Equal Opportunity Employer

TEMMESSEE VALLEYAUTHORITY CHATTANOOGA. TENNESSEE 3740t 400 Chestnut Street Tower II April 30, 1982 U.S. Nuclear Regulatory Commission Region II ATTN:

James P. O'Reilly, Regional Administrator 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 Dear Mr.

O'Reilly.'nclosed is a copy of the following report prepared by the Tennessee Valley Authority pertaining to environmental monitoring at the Browns Ferry Nuclear Plant:

Environmental Radioactivity Levels, Browns Ferry Nuclear Plant, Annual Report 1981 This monitoring program is specifically responsive to the recommendations and requests of the United States Fish and Wildlife Service.

We understand that the Office of Nuclear Reactor Regulation will transmit five copies of the report to the Secretary of the Interior.

Very truly yours, TENNESSEE VALLEY AUTHORITY Nuclear Licensing Enclosure cc:

Director of Nuclear Reactor Regulation

(

Enclosure:

20)

Attention:

Mr. Darrell G. Eisenhut, Director Division of Licensing U.S. Nuclear Regulatory Commission Washington, DC 20555

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An Equal Opportunity Employer

TENNESSEE VALLEYAUTHORITY ENVIRONMENTAL RADIOACTIVITYLEVELS BROWNS FERRY NUCLEAR PLANT ANNUAL REPORT " 1981

, TVA/OMS/OHS-82 7 DIVISIONOF OCCUPATIONALHEALTHANDSAFETY

ENVIRONMENTAL RADIOACTIVITYLEVELS BROWNS FERRY NUCLEAR PLANT ANNUAL REPORT " 1981 TVA/OMS OHS"82 7

April 1982

CONTENTS List of Tables List of Figures.

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ill iv Introduction

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Atmospheric Monitoring Terrestrial Monitoring.

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23 Reservoir Monitoring equality Control.

Data Analysis.

Conclusions'.

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LIST OF TABLES Table Table Table 1-2-

3-Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table 6-7" 8"

910-ll-12-13-14-15-16-17-18-19-20-21-22 "

23-24.-

25-26-Table 4-Table 5-Environmental Radioactivity Sampling Schedule Atmospheric and Terrestrial Monitoring Station Locations - Browns Ferry Nuclear Plant Detection Capabilities for Environmental Sample Analysis Results Obtained in Interlaboratory Comparison Programs

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Maximum Permissible Concentrations for Nonoccupational Exposure Radioactivity in Air Filter Radioactivity in Rainwater.

Radioactivity in Heavy Particle Fallout Radioactivity in Charcoal Filters Radioactivity in Milk.

Radioactivitg in Vegetation Radioactivity in Soil Radioactivity in Well Water Radioactivity in Public Water Supply.

Environmental Gamma Radiation Ievels Radioactivity in Food Crops Radioactivity in Soybeans Radioactivity in Poultry Sampling Schedule

- Reservoir Monitoring Radioactivity in Surface Water Radioactivity in White Crappie (Flesh Radioactivity in Smallmouth Buffalo (Flesh)

Radioactivity in Smallmouth Buffalo (Whole)

Radioactivity in Sediment Radioactivity in Clam Flesh Radioactivity in Clam Shell

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13 14 15 16 17 26 27 28 29.

30 31 32 35 36 43 44 45 46 47 48 49 50

LIST OF FIGURES Figure 1

- Tennessee Valley Region 3

Figure 2

- Atmospheric and Terrestrial Monitoring Network.

Figure 3

" Local Monitoring Stations 18 19 Figure 4 Figure 5

TLD I,ocations, BFN Annual Average Gross Beta Activity in Air Filters, Browns Ferry Nuclear Plant 20 21 Figure 6 -

Annual Average Gross Beta Activity in Drinking Water, Browns Ferry Nuclear Plant 37 Figure 7-

.j Direct Radiation Levels, BFN 38 Figure 9-Direct Radiation Levels, WBN Figure 8 -

Direct Radiation Levels, BFN (4-Quarter Moving Average) 38 39 Figure 10 - Direct Radiation Levels, WBN (4-Quarter Moving Average) 39 Figure ll - Reservoir Monitoring Network 51 Figure 12 - Annual Average Gross Beta Activity in Surface Water 52

ENVIRONMENTAL RADIOACTIVITYLEVELS BROWNS FERRY NUCLEAR PLANT ANNUAI REPORT 1981 Introduction The Browns Fer'ry Nuclear Plant (BFN), operated by the Tennessee Valley Authority, is located on a site owned by TVA containing 840 acres of land in Limestone County, Alabama, bounded on the west and south by Wheeler Reservoir (see figure 1),.

The site is 10 miles southwest of Athens,

Alabama, and 10 miles northwest of Decatur, Alabama.

The plant consists of three boiling water reactors; each unit is rated at 3,293 MWt and 1,098 MWe.

Unit 1 achieved criticality on August 17,

1973, and began commercial operation on August 1, 1974.

Unit 2 began commercial operation on March 1, 1975.

However, a fire in the cable trays on March 22, 1975, for'ced the shutdown of both reactors.

Units 1 and 2 resumed operation and Unit 3 began testing in August 1976.

Unit 3 began commercial operation in January 1977.

The preoperational environmental monitoring program established a

baseline of data on the distribution of natural aqd manmade radioactivity in the environment near the plant site.

However, seasonal,

yearly, and random variations in the data were observed.

In order to determine the potential increases in environmental radioactivity levels caused by the plant, com-parisons were made between data for indicator stations (those near the plant) and control stations (those remote from the plant) in conjunction with com-parisons with preoperational data.

Staffs in the Division of Occupational Health and Safety and the Office of Natural Resources carried out the sampling program outlined in tables 1 and 19.

Sampling locations are shown in figures 2, 3, 4, a'nd ll, and table 2 describes the locations of the atmospheric and terrestrial monitor-ing stations.

All the radiochemical and instrumental analyses were conducted in TVA's Western Area Radiological Laboratory (WARL) located at Muscle. Shoals,

Alabama, and Eastern Area Radiological Iaboratory (EARL) at Vonore, Tennessee.

Alpha and beta analyses were performed on Beckman Iow Beta II and Beckman Wide Beta II low background proportional counters.

Nuclear Data (ND) Model 100 multichannel analyzer systems employing sodium iodide NaI(Tl) detectors and ND Model 4420 systems in conjunction with Germanium Ge(Li) detection systems were used to analyze the samples for specific gamma-emitting radionuclides.

Samples'f water, vegetation, air particulates, food crops, and charcoal (specific analysis for I-131) are routinely counted with NaI(Tl) detection systems.

If significant concentrations of radioisotopes are identified, or, if there is a reasonable expectation of increased radioactivity levels (such as during periods of increased fallout), these samples are counted on the Ge(Li) system.

Identification of gamma-emitting radionuclides in all other types of samples

is routinely performed by analysis on the Ge(Li) system.

A TVA fabricated beta-gamma coincidence counting system is utilized for the determination of I-131 concentrations in milk.

Data were entered in computer storage for processing specific to the analysis conducted.

A computer, employing an ALPHA-M least squares code, using multimatrix techniques, was used to estimate the activities of the gamma-emitting nuclides analyzed by NaI(Tl).

The data obtained by Ge(Li) detectors were resolved by the ND4420 software.

The detection capabilities for environmental sample analyses given as the nominal lower limits of detection (LLD) are listed in table 3.

Samples processed by NaI(T1) gamma spectroscopy were analyzed for 13 specific gamma-emitting radionuclides and radionuclide combinations For these

analyses, radionuclide combinations such as 'u and Zr-Nb are analyzed as one radionuclide.

All photopeaks found in Ge(Li) spectra were identified and quantified.

Many of the isotopes identified by Ge(Li) spectral analysis are naturally occurring or naturally produced radioisotopes, such as

7Be,

~OK, Bi y Bl )

Pb p

~ Pb p Ra y etc LLDs for the analysis of the radio-nuclides listed below are given in table 3B.

ILDs for additional radio-nuclides identified by Ge(Li) analysis were calculated for each analysis and nominal values are listed in the appropriate data tables.

In the instance where an LLD has not been established, an LLD value of zero was assumed.

A notation in a table of "

values

<LLD" for an isotope with no established LLD does not imply a value less than 0; rather it indicates that the isotope was not identified in that, specific group of samples.

For each sample type, only the radionuclides for which values greater than the LID were reported are listed in the data tables.

TVA's Radioanalytical Laboratories participate in the Environmental Radioactivity Laboratory. Intercomparison Studies Program conducted by EPA-Las Vegas.

This program provides periodic cross-check samples of the type and radionuclide composition normally analyzed in an environmental monitoring program.

Routine sample handling and analysis procedures were employed in the evaluation of these samples.

The EARL began processing samples in May 1980.

The results received during calendar year 1981 are shown in table 4.

The

+3o'imits based on one measurement were divided by the square root of 3 to correct for triplicate determinations.

a The following radionuclides and radionuclide combinations are quantified by the ALPHA"M least,-squares computer code:

+ 'Ce; s Cr; 1311.

103~166Ru; Cs;

.Cs, sZr-Nb.

Co; Mn'n; Co; OK and Ba-La 7

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-WATTS BAR NUCLEAR PLANT

-SEQUOYAH NUCLEAR PLANT

-BELLEFONTE NUCLEAR PLANT

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Table 1

ENVIRONNENTAL RADIOACTIVITYSANPLING SCHEDULE Air Charcoal Rain-Heavy Particle River Well Public.Aquatic Life st rio loaati a pilter palter Water p llo t soil

~pe et tire Milk:water litter watei aad sedi a t l'da Muscle Shoals M

Laurenceburg M

Rogersville' Athens Decatur Courtland M

Site NW-1 M

Site N-2 Site NE-3 A

Site NM-4 W

Site WSW-5 W

Farm B Farm Bi/Farm P Farm T Farm L Control Farms Cl k

t Onsite Well Wheeler Dam Elk River Tennessee River Champion Paper Co.

Various Local Farms

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W - Meekly N - Monthly (every 4 ueeks) 9-quarterly S-Semiannually A-Annually

Table 2

Atmospheric and Terrestrial Monitoring Station I,ocations Browns Ferry Nuclear Plant RM-1 BF)

RM-2 BF, Muscle Shoals, AL (Control)

Iawrenceburg, TN (Control)

LM-1 BF, Northwest LM-2 BF, North LM-3 BF, Northeast LM-4 BF, Trailer Park LM"5 BF, Davis Farm PM-1 BF, Rogersville, AI PM-2 BF, Athens, AL PM-3 BF, Decatur (Trinity), AL PM"4 BF, Courtland, AL Approximate Distance and Direction from Plant 1.0 Mile 0.9 Mile 1.0 Mile 1.7 Miles 2.5 Miles (1.6 kilometers)

(1. 4 kilometers)

NNE (1.4 kilometers)

ENE (2..7 kilometers)

NNW (4.0 kilometers')

WSW 13.8 Miles (22.2 kilometers)

NW 10.9 Miles (17.5 kilometers)

NE 8.2 Miles (13.2 kilometers)

SSE 10.5 Miles (16.9 kilometers)

WSW 32.0 Miles (51.5 kilometers)

W 40.5 Miles (65.2 kilometers)

NNW Farm S

Farm B

Farm H

Farm T Farm Bi (Out of business 7/20/82) 4.75 Miles 7.0 Miles'.75 Miles 7.Q Miles 4.5 Miles (7.6 kilometers)

N (11.3 kilometers)

NNW (6.0 kilometers)

N (11.3 kilometers)

ENE (7.2 kilometers)

ENE Farm P (Sampling begun 8/3/82) 8.8 Miles (14.1 kilometers)

E Farm N (Control)

Farm J (Control)

Farm C (Control)

Farm Ca (Control) 27.0 Miles 40.Q Miles 32.0 Miles 32.0 Miles (43.4 kilometers)

NW (64.4 kilometers)

NNW (51.5 kilometers)

N (51.5 kilometers)

.W

Table 3

DETECTIOH CAPABILITIES FOR EHVIRONMENTAL SAMPLE ANALYSIS A.

S ecific Anal ses NOMINAL LOWER LIMIT OF DETECTIOH LLD

• hir Particulates

~Cf Charcoal

~cf Fallout Mater

~Cf/k CCCff1 Vegetation and grain

~CI/ ~dr Soil and Sediment

~Ctl

. d

Pish, clam flesh,

plankton,

~Cii

~dr

Foods, meat, Clam shells

poultry, Milk

~C1/

d

~fk~~ff Ccf//11 Total a Cross n Gross 9

4H 4 441 "Sr 44Sr

'0. 005

0. 01 0.005 0.001 0.02 0.4 2.0 0.05 330 10 2

0.01 0.05 0.20

0. 25 0.05 0.35 0.70 1.5 0.3 0.1 0.1 0.5 0.1 0.7 0.7 5.0 1.0 1.5 25 40 8

0.5 10 2

4hll LLD values for isotopic separations are calculared by the method developed by Pasternack and Harley as described in HASL-300.

Factors such as sample size, decay time, chemical yield, and counting efficiency may vary for a given sacaple; these variations may change the LLD value for the given sample.

The assumption is made that all samples are analyzed crithin one creek of the collection date.

Conversion factors:

1 pCi ~ 3.7 x 10 Bq; 1 mCi ~ 3.7 x 10 Bq.

Table 3

'DETECTION CAPABILITIES FOR ENVIRONMENTAL SAHPLE ANALYSIS B;

Gamma Anal ses NOMINAL LOWER LIHIT OF DETECTION'LD Vegetation and grain

~et/

d Water and milk

~ct/I Air particulates

~ct/

'al*

~Ce Li odl NaI ~Ce Li

.'laI

~Ce Li Soil and sediment

~Ctl dd

~

NaI

~Ce{Li Clam flesh Fish and plankton

~Ctl

~C1/

'd I I ~CLI C I ~ce Lt Foods, (tomatoes

potatoes, etc.)

Ci wet Clam shells

~CI/

dr NaI

~Ce Li Nal C~eLi Meat an" poultry

~CI/ k

'r:

!Iai Ge{Li1 1 I 1 ~ 1 dt ttCe S1C 1ill 1 0 1 d 1 0 cgu 106R 136G 11SC scZr-Nb SCZr SSNb

'Oco Hn 6 Szn "Co K

'"4Ba-l.a 1 4 0 Ba La 0.02 0.02

. 0.02 0.01 0.10 0.02

0. 01 0.01 0.01 0.01 0.01 0.01

0. 02

0. 01 0.03

0. 02 0.07 0.03 0.01 0.01 0.04 0.03 0.01 0.02 0.01 0.01 0.01 38 0.55 33 60 44 15 8

40 40 10 26 10 5

10 1.10 0.35 0.65 25 7

0. 20

0. 20

0. 20 10 5

15 5

0.23 10 5

0.20 15 9

0.25

-10 5

0.17 150 2.50 15

0. 68 0.35 0.22 0.47 0.60 0.09 0.20 0.45 0.51 0.33 0.12 0.06 0.12 0.12 0.11 0.05 0.05 0.20 0.05

0. 15 0.11 '.23 0.06 0.11 0 90 0.15 0.34 0.08

0. 06

0. 10 0.02 0.11 0.08 0.02 0.03 0.01 O.D1

0. 01 0.02 0.01 0.07

0. 02 0.35 0.06 0.60 0.10 0.20 0.02 0.45 0.11 0.12 0.08 0.12 0.02 0.12 0.03 0.01 0.20 0.01 0.15 0.01 0.23 0.02 0.11 0.01 0.90 0.15 0.07 0.02

0. 35

0. 56 0.07 0.74 0.48 0.08 0.15 0.07 0.07 0.08 0.17 0.08 0.30 0.10 0.35

0. 60 0.20 0.45 0.12 0.12 0.12 0.20 0.15 0.23 O.ll 0.90 0.15 38 0.06

. 0.10 60 0.02 15 40 0.11 0.08 10 0.02 10 10

0. 03

0. 01 0.01 15 0.01 10 0.02 15 0.01 10 150 15 0.07 0.02 90 33 44 200 8

50 150 40 26 40 5

40 40 10 5

5 5

9 5

4C 90 20 90 50 15 25 7

50 15 20 15 55 15 40 15 70 20 30 15 400 50

• The NaI(T1) LUl.values are calculated by the method developed by Pasternack and Barley as described in I{ASL-300 and Nucl. Instr. Methods 91, 533-40 (1971).

These LLD values are expected to vary depending on the activities of the components in the samples.

These figures do not represent the LLD values achievable on a given sample.

Water is counted in a 3.5-L Marinelli beaker.

Vegetation, fish, soil, and sediment are counted in a 1-pint container as dry weight.

The average dry weight is 120 grams for.vegetation and 400-500 grams for soil sediment and fish.

Heat and poultry are counted in a 1-pint container as dry weight, then corrected to wet weight using an average moisture content of 70Z.

Average dry weight is 250 grams.

Air particulates are counted in a well crystal.

The counting system consists of a multichannel analyzer and either a 4" x 4" solid or 4" x 5" well Nal(T1) crystal.

The counting time is 4000 seconds.

All calculations are performed by the least-squares computer program ALPHA-H.

The assumption is made that all samples are analyzed within one week of the collection date.

• • The Ce(hi)

LLD values are calculated by the method developed by Pasternack and Harley as described in HASL-300.

These LLD values are expected to vary depending on the activities of the components in the samples.

These figures do not represent the LLD values achievable on given samples.

Water is counted in either a 0.5-L or 3.5-L Harinelli beaker.

Solid samples such as soil, sediment, and clam shells are counted in a 0.5-I.

Harinelli beaker as dry weight.

The average dry ~eight is 400-500 grams.

Air filters and very small volume samples are counted in petrie dishes centered on the detector endcap.

The counting system consists of a ND-4420 multichannel analyzer and either a 25I, 14I, 16I, or 29Z Ce(l.i) detector.

The counting time is normally 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

All spectral analysis is performed using the software provided with the ND-4420.

assumption is made that all samples are Analyzed within one week of the collection date.

Conversion factor:

1 pCi << 3.7' 10 Bq.

Table 4

Results Obtained in Interlaboratory Comparison Program A.

Air Filter (pCi/filter)

Gross Al ha Gross Beta Strontium-90 Cesium-137 Date 12/80 3/81 6/81 9/81 EPA value

(+3a) 21~9 30+ 13 28+ 12 25+11

. TVA AVG.

WARL EARL 22 23 31 31 29 32 26 25 EPA value TVA AVG.

(+3a)

WARL EARL 19+9 24 26 50+9 55 49 54+9 62 59 51+9 61 54 18+2. 6 19+2.6 16+2 '

18 15 19 23 16 19 EPA value TVA AVG.

(+3a)

WARL-EARL 0

.=

~

2

<2 EPA value

(+3a) 19+9 14+ 9 16+9 19+9 TVA AVG.

WARL EARL 20 22 15 14 17.

18 21 20 B.

Tritium in Urine (pCi/L)

Date EPA Value (+30)

TVA AVERAGE 3/81 6/81 9/81 11/81

.810+549 1600+585 2050+599 2700+615 WARL EARL 713 390 1637 1830 2103 2573 2623 a.

Western Area'adiological Laboratory, Muscle Shoals, Alabama b.

Eastern Area Radiological Laboratory, Vonore, Tennessee c.

Efficiency curves were checked and known spikes were run.

Everything found was within acceptable limits'e are awaiting the next cross-check for further investigation.

d.

Results were mailed to EPA but not reported by them.

caw 1

w.~~ ln~t wn analvsgs.

There was insufficie5t time ta obtain another sample from EPA and reanalyze.

Table 4 (Contd)

Results Obtained fn Interlaboratory Comparison Program E.

Milk (pCf/L)k Strontium - 89 EPA value TVA AVC.

Date (i3s)

MARL EARL 1/81 0

<10

<10 4/81 25i9 28 7/81 25i9 23 30 10/81 23+9 25 28 EPA value

~33 3 20i5.2 11+2.6 17+2. 6 1gi2. 6 TVA AVC.

MARL EARL 21 20 13 14 16 17 16 Strontium - 90 EPA value TVA AVG.

'MARL EARL 26i17 26i10

.Oli 52ilo 24 21 21 29

<15

<15 49 47 Iodine 131 Cesium - 137 EPA value TVA AVG.

~33 IIARL EARL 43i16 40 41 22+9 21 24 31i9 32 32 25i9 27 27 EPA value

'3a TVA AVG.

MARL EARL

<25

<15

<15

<15

<15

<15 Barium - 140 Potassium EPA value TVA

~3 IIARL 1550i232 1490 1453 1559+135 1513 1674 1600i139 1623 1620 1530i133 1620 1500

.Cobalt - 60 AVC.

EPA value TVA AVC.

EARL ~3 a EARL EARL F. Foods (pCf/kg, Met Weight) 3/81 47i9 42 44 29+2.8 38 21 119i21 126 121 53i9 56 55 0

7/Bl 44+9 53 51 31+2. 8 31 32 82i14 80 106 45+9 43 54 0

11/81 3819 49 54 23i2. 6 25 22-Noae 33i9 29 35 0

<15

<15 2640i229 2857 2917 I

<25

<25 2640i229 2870 3437 q

k.

Values for potassium are reported, as mg/liter of sample.

m.

Results vere marginally out of linfts.

Efffcfeacy curves vere checked vfth no conclusive findfngs.

Subsequent results have bees satisfactory.

n.

Only tvo results vere sent to EPA.

Results vere not facluded in their analysis.

o.

Values for potassium are reported as ng/kg sample.

p.

Investigation of this problem vas faftfated but no satisfactory conclusions

'have been reached.

We suspect difficulties arising from sample inhomogeafety.

An incorrect vcfght vas obtained fn the gamma aqalysfs of this sample.

Further analysis destroyed the sample so that the correct vefght could aot be determined.

r.

Investigation vas conducted.

No satisfactory explanation vas found.

Other cross-checks on thfs isotope in different media are satisfactory.-

aa Table 4 (Contd)

Results Obtained in Interlaboratory Comparison Program C.

Radiochemical Analyses of Water (pCi/L) c)

Cross Alpha Cross Beta Strontium - 89 Strontium 90 Tritium f

Iodine - 131 Date EPA value TVA AVG.

EPA value TVA, AVG.

EPA value TVA AVC.

EPA value TVA AVG.

~33a MARL EARL (33a)

'WAIIL EARL (33a)

MARL EARL (I3a)

IIARL EllllL EPA value TVA AVG.

(i3a)

WARL EARL EPA value

~(aaa TVA AVG.

WARL EARL 1/81 2/81 3/81 4/81 5/81 6/81 7/81 8/81 9/81 10/81 11/81 12/81 9+9 25i10 21i9 22+10 33+ 14 2L+9 10 9

44i9 49 49 23 15i 25+9 26 29 21 14 14+9 14 16 16+9 11 14 34i3. 1 388 28 36+9 40 33 22i2.6 21 22 20 29 22 15+9 i

18 28i9 21 13 23+9 15 18 29 26 23i9 26 23 11i2.6 11 10 18 24 1950i596 1990 194)7 2630i613 2623 2713 73+13 2210i603 2263 2197 2700i615 2717 2807 76+13 1760+591 1917 1753 2710i615 2467 2723 30i10 32 28 79 73 6s sd Date 2/81 6/81 10/81 0

<60

<60

~

25i9 25 25 85+9 84 83 0

<40

<40 36i9 39 35 4i9 0

<60

<60 17i9 18 17 0

<15

<15 15i9

<40

<40 21i9 23, 21 31i9 34i9

<60

<60 22i9 25 22 24+9 26 21 0

<40

<4'0 21i9 21 24 32+9 6

10 27 30 35 32 D. Gamma-Spectral Analysis of Water (pCi/L)

C romium - 51 Cobalt - 60 Zine 65 Ruthenium - 106 Cesium - 134 Cesium 137 EPA value TVA AVG.

EPA value TVA AVC.

EPA value TVA AVC.

EPA value TVA AVC.

EPA value TVA AVC.

EPA value TVA AVC.

~(ARI MARL EAIIL ~I)a)

IIAIIL EARL ~aa IIARL EARL ~aa MARL EARL ~RI wARL EARL ~aa wARL EARL 3

3' E.

g.

h.i.

Specific analysis for to test the procedures used for the analysis of milk.

Investigations of the analytical procedure were conducted and new efficiency curves were determined.

Results have been satisfactory since that time.

New efficiency curves were determined subsequent to this analysis.

Subsequent results were satisfactory.

Excess humidity in counting room and a change in the amount of solid introduced into the sample by EPA are suspected in the difficultywith this sample type.

Steps have been taken to correct or compensate for these items.

Resul.ts are possibly due to an incorrect chemical Eorm of the precipitate counted in this procedure.

Investigations continue.

Atmos heric Monitorin The atmospheric ponitoring network is divided into three groups.

Four local air monitors are located on or adjacent to the plant site in the general areas of greatest wind frequency.

One additional station is located at the point of maximum predicted offsite concentration of radionuclides based on preoperational meteorological data (see figures 3 and 4).

Four peiimeter air monitors are located at distances out to 10 miles from the plant, and two

.remote air monitors are located at distances out to 45 miles.

These monitoring stations are shown in figure 2.

The remote monitors are used as control or baseline stations.

At each monitor, air is continuously pulled through a

Hollingsworth and Voss LB5211 glass fiber filter at a regulated flow of 3 fts/min, In series with, but downstream of, the particulate filter is a

charcoal filter used to collect iodine.

Each monitor has a collection tray and storage.container to obtain rainwater on a continuous basis and a hori-zontal platform that is covered with gummed acetate to catch and hold heavy particle fallout.

Thermoluminescent dosimeters are used to record gamma radiation levels at each remote and perimeter station.

Each of the local air monitors is fitted with a GM tube that con-tinuously scans the particulate filter.

The disintegration rate of the atmospheric radioactivity is continuously recorded at each station and radio-telemetered into the plant.

Air filters are collected weekly and analyzed for gross beta activ-ity.

No analyses are performed until three days after sample collection.

The samples are composited monthly for analysis of specific gamma-emitting radio-nuclides and quarterly for Sr and s Sr analysis.

The results are combined for each station to obtain an annual average.

During this reporting period, three samples were hot obtained because of equipment malfunction.

These data are presented in table 6.

The'nnual averages of the gross beta activity in the air particulate filters at the indicator stations (local and perimeter monitors) and at the control stations (remote monitors) for the years 1968-1981 are presented in figure 5.

Increased levels due to fallout from atmospheric nuclear weapons testing are evident, especially in 1969,

1970, 1971, 1977, '1978, and 1981.

These patterns are consistent with data from monitoring programs conducted by TVA at nonoperating nuclear power plant construction sites.

Table 5 presents the maximum permissible concentrations (MPC) recommended by 10 CFR 20 for nonoccupational exposure.

Rainwater is collected monthly and a 3.5-liter sample analyzed for specific gamma-emitting radioisotopes and tritium.

The results are shown, in table 7.

The gummed acetate that is used to collect heavy particle fallout is changed monthly.

The samples are ashed and counted for gross beta activity.

The results are given in table 8.

12 Charcoal filters are collected and analyzed for radioiodine.

The filter is counted in a single channel analyzer system.

The results are shown in table 9.

During this reporting period, two samples were not taken because of equipment malfunction.

13 Table 5

NAXIMMPERHISS IBLE CONCENTRATIONS FOR NONOCCUPATIONAL EXPOSURE Alpha Nonvolatile beta Tritium 1 31CS 103~ 106Ru 144Ce 96Zr-93Nb

'40Ba 140 131Z Zn

'4'0C 89Sr 90Sr "Cr 134Cs 58Co In Water

~Ci/I*

30 3, 000 3,000,000 20,000 10,000 10;000 60,000 20,000 300 100,000 100,000 30,000 3,000 300 2,000,000 9,000 90,000 In Air yCX/m'+

100 200,000 500 200 200 1,000 1,000 100 2,000 1,000 300 300 30 80,000 400 2,000

• 1 pCi ~ 3.7 x 10 Bq.

TALLE MAHE OF FACILITY ~o~t'%~ERRY LOCATION OF F AC'ILITY L~IH STD~M RAOIOACTIVITY IM AIR FILTEP PCI/H(3) - 0 037 BQ/H(3)

A A

AHA

-- DOCKET Woe~0-25~/~29/

REPORTING PERIOD TYPE ANO TOTAL NUHBER OF ANALYSIS PfRQQR~H GROSS ALPHA 52 GROSS BETA 569 GAHHA CHAI) 49 CE 141'44 RU-103'06 ZR-95eNB-95 I-131 BE-1 LOIIER L IH IT OF DETECT ION ~

~L,Ql 0 ~ 005 0 ~ 010 0 ~ 030 0'40 0 ~ 010 0 010 NOT ESTAB 6 F 08( 456/

465) 0 F 01-0 38 0 F 05(

0'3 0%05(

0 05-0~06(

0 ~ 01-0 F 02(

0 ~ Dl-0 ~ 09(

0~ 01.-

8/

39) o.e6 5/

39) 0'6 20/

39) 0'3 6/

39) 0 ~ G2 35/

39) 0021 ALL ItlCICATO% LOCATIONS tIEAM LF)b RANQL LH4 BF TRAILER P I ~ 7 MILES NNM 0 F 09(

50/

52) 0 01-0'6 I.H3 BF NORTHEAST 1 ~ 0 MILE EME LH3 BF NORTHEAST 1 ~ 0 HILE ENE ATHENS'L 10.9 HII.ES NE DECATUR'L 8~2 HILES SSE ATHEMS4 AL 10 ~ 9 HILES ME 0 F 06(

0 ~ 06-0 ~ 06(

0 ~ 06-0 ~ 13(

0 ~ 13 0 F 02(

0 F 02 0'2(

0 ~ 07-1/

4) 0'6 1/

4) 0'6 1/

3) 0 ~ 13 1/

5)

DE 02 3/

3)

D&21

~~A~T~VTH ~Hfdf AgH~~HAM WAkE

.HEAN (F)b

~gy~AC

~AN gaffrJOM RA~M+

Cot)TROL LOCATIONS HEAM (F)

~

R MG b

0 F 01(

3/

52) 0 ~ 01-0 F 01 0'8(

103/

104) 0 ~ 01-C ~ 39 Oa04(

4/

1C) 0 F 03-0+07 0~05(

2/

10) 0 F 05-0 F 05 0'6(

5/

10) 0 F 02 0'3 10 VALUES CLLO 0 ~ 10(

10/

I G) 0'5-0 ~ 23 NUHBER OF NONROUT INE REPORTED

~HAS~UR

~HMT 5 GAHHA (GELI) 94 CE 141 CE-144 RU-103 ZR-95 NB-95 K 40 SI-214 BI-212 PB-214 PB 212 BE-7 TL 208 SR 89 SR 90 44 00010 0 ~ 02C NOT ESTAB 0'10 0~010 NOT. ESTAB 0 ~ D20 NOT ESTAB 0'20 NOT ESTAB 0 ~ 05

('OT ESTAB 0 F 005 0~001 0 ~ 01(

oool-0 ~ C4(

0 02-D~GI(

0 ~ 00-0 F 03(

0 ~ 01-De05(

0 ~ 01-0 12(

0'6 0'4(

D ~ 02-0'4(

0 ~ 04-0 ~ 04(

0002-Geol(

0 ~ Go-0 F 08(

0 ~ 05-0 F 01(

o.eo-0 F 01(

0 ~ 01-0 F 00(

0 ~ 00-.

8/

78) 0 F 02 16/

78) 0 ~ 07 38/

78) 0'3 34/

78) 0'6 40/

78) 0'5 58/

78) 0 ~ 30 44/

78)

O O9 1/

78) 0 ~ 04 28/

78) 0 F 08 35/

78) 0 ~ 03 41/

78) 0 ~ 47 14/

78) 0 ~ 01 18/

36) 0 ~ 01 7/

36) 0 ~ 00 ATHENS'L 10 9 HILES NE ROGERSVILLE+

AL 13 ~ 8 HILES N)t Lkl BF NORTH(tEST I ~ 0 NILE M

ROGERSVILLEs AL 13 ~ 8 HILES MM OECATURt AL 8 ~ 2 HII.ES SSF LH2 BF NORTH De9 HILE t(ME DECATUR'L 8'

HILES SSE 6ECATURy Al.

8 2 HILES SSE DECATUR%

AL 8 ~ 2 HILES SSE LH3 BF NORTHEAST leO tllLE ENE DECATUR'L 8 ~ 2 HILES SSE LH4 BF TRAILER P 1 ~ 7 HILES NNll LH5 BF DAVIS F 2 5 tIIL'ES MSM I

0 ~ 02(

0 ~ 02-0 F 05(

0 ~ 04-0 F 02(

0 ~ 01-0 F 04(

0 ~ 02-0007(

0 ~ 03-0'6(

0 ~ 12-0 ~ 05(

0 ~ 02-0*04(

Oa04-D.O5(

0 ~ 03-0'2(

0 ~ 02-0 ~ 16(

0005 0 ~ OI (

0 ~ 01-0 ~ 01(

0 01-0 F 00(

I/

10) 0 F 02 2/

10) 0 ~ 07 4/

8) 0'3 5/

10) 0 F 06 4/

8) 0 ~ 12 3/

6) 0 ~ 18 6/

8) 0 09 I/

8) 0 ~ 04 3/

8)

D ~ 07 1/

9) 0+ 02 5/

8) 0'7 2/

7) 0 ~ 01 2/

4) 0401 1/

4) 0 ~ 03(

0 ~ 02-0 F 01(

D ~ 00 0 ~ 07(

0 ~ 05-0 F 01(

0 ~ 01-F 01(

0 ~ 01-0 F 00(

0 ~ 00-6/

16) 0 ~ 07 7/

16)

DE 02 9/

16) 0 ~ 10 3/

16) 0 ~ 01 4/

4) 0 F 01 3/

8) 0~00 16 VALUES <LLO 0'2(

3/

16) 0'2-0 ~ 30 0 F 01(

7/

16) 0 F 01-0+02 0 ~ 02(

8/

16) 0 F 01-0 ~ 03 0 ~ G5(

8/

16) 0'2-0 ~ 09 0 13(

13/

16) 0 ll-0 16 0~04(

7/

16) 0 ~ 03-0 F 08 16 VALUES (LLO

NAHE OF FACILITY QRR~NFERRY LOCATION OF FAC)LITY~IH~STO~tt RADIOACTIVITY Itt RAIhVATER PCI/L - Oo037 BO/L lLAQAHA DOCKET NO ~ 50-$ 5~9 REPORTIttG PERIOD 9

TYPE

<<ND TOTAL NUMBER OF ANAL'YSI 8 PERFORNEO GAtlt4A (NA I )

97 Cr 141 ~ 144 RU-103'06 ZR-95 '48-q5 1-131 BE-7 GAHHA (GELI) he ZR-95 WB-95 K-40 BI-214 PO-214 PB-212 Dr-7 TR ITIUH 143 LG'4EP. LIHIT OF DETFCT ION a CLLO) 38 F 000 40 000 10oOOG 15o000 NOT ESTAB 10 F 000 F 000 NOT ESTAB t(OT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB 330 F 000 77 VALUES <LLG 48'0(

48 ~20-15'2(

10 ~ 10-22 F 10(

22olO-51 ~ 80(

7 ~ 30-1/

77) 48od0 19/

77) 25 F 10 1/

77) 22'0 49/

77) 133'0 40 VALUES <LLD 9<<63(

2/

40) 8 ~ 93-10'2 81 ~ STC 21/

40) 32 F 71-125 F 00 22'9(

25/

40) 11'2-48'8 17'5(

12/

40)

F 41-29'7 lh ~ 32(

8/

40) 8'9-18'9 49'5(

3/

40) 43'8-54o06 117 VALUES <LLD ANALYSIS FERFGRHED ALL It(DICATOF LOCATIONS HEAth (F )

RANGE b DECATUR'L 8

2 tlILES SSE LH4 BF TRAILER P 1

7 HILES NNV LHS BF DAVIS F 2 ~ 5 HILES VSV LHS BF CLAVIS F

2 o5 H ILES VSV LH5 BF DAVIS F 2<<5 tlILES VSlt LH3 BF t(ORTHEAST loO HILE EteE LH3 BF NORTHEAST'

~ 0 NILE ENE LH3 BF NORTHEAST 1 ~ 0 HILE ENE COURTLAf4D~

AL 10 ~ 5 HI LES VS V LH5 BF DAVIS F 2 ~ 5 HILES. VSV 48 ~ 20(

48o20-20 ~ 20(

15 ~ 60-22olOC 22 ~ lG-67o88(

39%70 10 ~ 32(

10 ~32-125o00(

125o00 29'3(

16 ~24-28'8(

28'8 18'9(

18o09-49 ~ 35(

43 ~ 28-1/

8) 48o20 3/

8) 25010 1/

6)

=-

22 10 4/

6) 115o10 1/

7)

$ 0o32 1/

6) 125o00 4/

6) 48o38 1/

6) 28'8 1/

3) 18009 3/

7) 1 Shan 06 I

CONTROL LOCATIONS HEAN (F) b IIIrQf1 43 60(

I/

20)c 43'0-43'0 20 VALUES <LLD 19 63(

3/

20) 10'0-35'0 2C VALUES <LLD 56'6(

14/

20) 14 F 00-108o10 10'2(

1/

6) 10ol2-10ol2 13'2(

1/

6) 13'2-13o82 58'9(

2/

6) 54 '9-61o78 40 21(

3/

6) 23'9-70'1 11 ~ S6C 2/

6) 8'S-1'le 16 6

VALUES <LLO 05 F 00(

1/

6) 05 F 00-105 00 26 VALUES <LLD NUHBER OF NONROUTINE REPGRTED

~HASU~R~Hrt4TS a.

Nominal Lower Limit of Detection (LLD) as described in Table 3.

b.

Mean and range based upon detectable measuremcnts only.

Fraction of detectable measurements of specified locations is indicated in parentheses (F).

c.

Identified as fallout.

TABLE 8 RADIOACTIVITY IN HEAVY PARTICLE FALLO47 HCI/KH(2),- 370COOCO ~ GO bQ/KH(2) hAHE GF FACILITY BRQMNS FfRRY LOCATION OF FACILITY LIHESTONE ALABAMA DOCKET NO~~~

REPORT ltJG PERIOD 1901 TY~E AKD TCTAL tiUHBER OF

<<NALYSIS P~f:F ORHELP GROSS BETA 163 L OMEFE L IHI T OF DrTFCT IONa (ll,Q) 0'50 ALL INDICATOR LOCATIOhS MEAN ( ()b RANGE 1 ~ 09( 117/

117) 0'8-3<<73 NAME HEAN (F) b OJSTA4~CA~tJ i DIR~TION RAh'G~b

'LH'I BF TRAILER P 1 35(

13/

13)

I ~ 7 MILES tJNlt 0 ~ 16-3 ~ 73 CONTROL LOCATIONS MEAN (F)b

~RAN fb I ~ 04(

26/

26) 0<<12-2+79 tJUHBER OF NOtJROUTINE REPORTED PE'ASUREHC)JTS a.

Nominal Lower Limit of Detection (LLD) as described in Table 3.

b.

Ncaa and range based upon detectable measurements only.

Fraction of detectable measurements of specified locations is indicated in parentheses (F).

TABLE9 RADIOACTIVITY Iti CH>RCOAL F ALTERS PCI/tF l3) -

0 ~ 637 BO/H(3)

NAME OF F ACILITY ~Ru~t.'ERRY LOCATION OF FACILITY LIHfSTONQ ALADAHA REPORTII 9 FEII TOO~99 TYPE AND TOTAL ttUHBER OF ANALYSIS Pf,R~~ORH 0

IODINE IN AIR 570 LO)tER L IH IT OF DETECT IOka l I LR) 0 ~ 020 ALL INDICATOR LOCATIONS HEAR lf)b R ANtt~o 0

$3t 62/ 466)-

0'2-Oa09 EOCATI~OI

~TH 'EEOE

~AY EO~II A

COURTLANDe AL 0'6l 2/

50) 10 ~ 5 MILES VS) 0 ~ 02-0 ~ 09 CONTROL LOCATIONS IIEAN IF&

RAN 0 ~ 02l 13/ 104) 0'2-0 F 04 NUHBER OF NONROUTItRE REPORTED

~HAS~UR tA~hTE'.

)tominal Lover Limit of Detection (LU)) as described in Table 3.

b.

Mean and range based upon detectable measurements only.

Praction of detectable measurements of specified locations is indicated in parentheses (P).

18 Figure 2

. ATMOSPHERIC AND TERRESTRIAL MONITORING NETWORK RM.28F LAWRENCEBURG yPULASKI FAYETTEVILLE WILSON FLORENCE FFIEL MUSCLE SHOALS RM-I8F L

TUSCUMBIA EIGHTON COURTLANO$

PM-4 F pRUSSELLVILLE PM-IBF WHEELER ROBE SVILL OAM ATHENS PM-2BF BROWNS FERRY NUCLEAR PL NT OECAT PM SBF0 IO MILES HARTSELLE HUNTSVILLE GUNT SVIL HALEYVILLE CULLMAN 45 MILES RAINWATER SOIL 0- ENVIRONMENTAL MONITORING STATION NOTE: THE FOLLOWING SAMPLES ARE COLLECTED FROM EACH STATION:

AIR PARTICULATES RADIOIODINE HEAVY PARTICLE FALLOUT

Figure 3

LOCAL MONITORING STATIONS BROWNS FERRY NUCLEAR PLANT 19 ATHENS U S HWY 72 BFN ALA. HWY 20 Legend

~

Air Monitor Automatic Well Sampler H

Dairy Farm DECATUR Scale 0

I 2

3 4

5 Miles

I, 20 Figure 4

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rs/boa r/r 41

figure 5

.30

.25 Preoperational Phase Operational Phase AWUAL AVERAGE 6ROSS 8ETA kTIVITY IN AIR FILTERS BROmS FERRY NUCLEAR PLANT

.20

.15 CC o

9 IJ IJ IQ CIJ IfI 0IJ 0'4

~w IJl 0

w 4l Average:

Preooerational Phase

.10

.05 1968 7

72 1973 9730 197>>

1975 1976 1977 1978 l979 1980 198 1

1

s

• - ~j I

23 Terrestrial Monitorin Milk Milk is collected from at, least four of five farms within a 10-mile radius of the plant (see figure 3),

and from at least one of four control farms.

Raw milk is analyzed weekly for ~s~l, and monthly for gamma-emitting isotopes and for radiostrontium.

The results are shown in table 10.

Cow censuses were conducted in May and September 1981. It was determined that there are no dairy farms nearer the plant than the nearest farm being sampled.

During this period however, one of the dairy farms being sampled (farm B, table 2) went out of business and all.cows were sold.

Another dairy farm (farm P) was added to the monitoring program on August 3, 1981.

V~e etation Vegetation is sampled quarterly at the farms from which milk is collected and analyzed for gamma-emitting radionuclides.

Approximately 1-2 kilograms of grass is broken or cut at ground level and returned for analysis.

Efforts are made to sample vegetation that, is representative of the pasturage where cattle graze.

Table ll gives the results obtained from the laboratory analyses of these samples.

Soil Soil samples are collected annually near each monitoring station to provide an indication of a long"term buildup of radioactivity in the environ-ment.

An auger or "cookie cutter" type sampler is used to obtain samples of the top two. inches (5

cm) of soil.

These samples are analyzed for gamma-emitting radionuclides,

sSr, and oSr.

The results are given in table 12.

Ground Water An automatic sequential-type sampling device has been installed on a well downgradient from BFN.

A composite sample from this well is analyzed for gamma-emitting radionuclides monthly and composited quarterly for determination of tritium.

A grab sample is also taken from a control well upgradient from the plant.

The results of the analysis of well water are shown in table 13.

Potable water supplies taken from the Tennessee River in the vicinity of BFN are sampled and analyzed for gross beta and gamma-emitting radionuclides, and composited quarterly for tritium,

~Sr, and oSr analyses.

The first potable water supply downstream from the plant is equipped with an automatic sampler with samples collected and analyzed weekly.

The sampler is located on the water intake structure and takes the sample from the river as the raw water is drawn into the water treatment facility.

Two additional supplies

24 downstream and one public water supply upstream are sampled by taking monthly grab samples of treated water at user points.

Table 14 indicates the results from the analysis of drinking water samples.

During this reporting period, six of the weekly samples were not taken because of the malfunction of automatic sampling equipment.

Figure 6 shows the trends in gross beta activity in diinking water from 1968 through 1981.

The annual average level from the raw water samples tends to run slightly hi'gher than the average for treated water samples;

however, the levels are consistent with the activities reported in surface water samples taken upstream from BFN (figure 12) and in samples taken from the Tennessee River in preoperational monitoring programs conducted by TVA at other sites.

Environmental Gamma Radiation Levels Bulb-type Victoreen manganese-activated calcium fluoride (Ca~F:

Mn) thermoluminescent dosimeters (TLDs) are placed at sixteen stations around the plant near the site boundary, at the perimeter and remote air monitors, and at nineteen additional stations out of approximately five miles from the site to determine the gamma exposure rates at these locations.

The dosimeters, in energy compensating shields to correct energy dependence, are placed at approxi-mately one meter above the ground, with three TLDs at each station.

They are annealed and read with a Victoreen model 2810 TLD reader.

The values are corrected for gamma response, self-irradiation, and fading, with individual gamma response calibrations and self-irradiation factors determined for each TLD.

The TLDs are exchanged every three months.

The quarterly gamma radiation levels determined from these TLDs are given in table 15, which indicates that average levels at onsite stations are approximately 2-4 mR/quarter higher than levels at offsite stations.

This is consistent with levels reported at TVA's nonoperating nuclear power plant construction sites where the average radiation levels onsite are generally 2-6 mR/quarter higher than levels offsite.

The causes of these differences have not been completely isolated; however, it is postulated that the differences are probably attributable to combinations of influences, such as natural variations in environmental radiation levels, earth moving activities onsite, the mass of concrete employed in the con-struction of the plant, and other undetermined influences.

Figure 7 compares plots of the data from the onsite or site boundary stations with those from the offsite stations over the period from 1976'through 1981.

To reduce the variations present in the data sets, a four-quarter moving average was constructed for each set.

Figure 8 presents a trend'lot of the direct radiation levels as defined by the moving averages'he data follow the same general trend as the raw data, but the curves are smoothed considerably.

Prior to 1976 measurements were made with less sensitive dosimeters, and consequently the levels reported in the preoperational phase of the moni-toring program are 1-2 times the levels reported herein.

Those data are not included in this report.

Therefore, for comparison purposes, figures 9 and 10 depict the environmental gamma radiation levels measured during the construction of TVA's Watts Bar Nuclear Plant to the present.

Note that the data follow a similar pattern to the BFN data and that, as discussed

above, the levels reported at onsite stations are similarly higher than the levels'at offsite stations.

Poultr and Food Cro s

Food crops and poultry raised in the vicinity of BFN and at control locations are sampled as they become available during the growing season, and analyzed 'for gamma-emitting radionuclides.

During this sampling period, samples of cabbage,

corn, green beans,

peaches, potatoes, turnip greens,

tomatoes, soybeans, and poultry were collected and analyzed for specific gamma-emitting radionuclides.

No sample of soybeans or cabbage'as taken from a control location.

The results are given in tables 16, 17, and 18.

NAME. OF FAG ILITY 8~RUNS FfRRY LOC*TIOH OF FACILTTT~II OTOHE TABLE 10 RADIOACTIVITY IN MILK PC I/L 0 ~ G37 BQ/L tLABAHA COCKET IIO ~

O~C-T O

T~OO

'TO REPORTIttG PERIOD 1981 TYPE AND TOTAL ttUMBER OF ANALYSIS

~AMMA (NAI) 107 LO'NER LIMIT OF DETECT IO",

~(21 ALL INDICATOR LOCt TIONS MEAtt (F )b R~giggb QECTCN~THC~EEE~TC

IIAmf, CONTROL LOCATION)

HEAR (j)

RAN~

NUtcBER OF.

tTONROUTINE RCPORTED

~V.

AEt~f,HAUNTS CS-137 10 F 000 150 000 0 ~ 500 K-40 5 ~ 000 F(OT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB K-40 BI-214 PB-214 PB-212 TL 208 NOT ESTAB SR 89 SR 90 10 F 000 113 F 000 113 IODINE IN HILK 454 GAHHA (GELI )

6 CS-137 13'3(

3/

55) lle70-16 F 00 1246i91(

55/

55) 1049'0-1569'0 253 VALUES <LLD ANALYSIS PERFORHCD 8 90(

3/

6) 7'4-10O16 1500'0(

6/

6) 1287 F 00- 1845 F 00 20'3(

5/

6) 7'9-30'3 18 F 05(

3/

6) 14'9-20'3 14 88(

3/

6) 9'3-20'6 4'3(

2/')

F 18 6o48 61 VALUES <LLD ANALYS IS P ERFORiREO 3'5(

61/

51) 2'I 8 ~ 19 PAGE FARH 8 F 75 MiLES C

THRASHER FARt:

7' MILES ENE SHITH FARH 4 ~ 75 HILES N

THRASHER FARM 7

0 MILES ENE SHITH FARH 4'5 MILES N BROOKS FARH 7a 0 MILES NN)t SMITH FARH 4i75 tllLES N PAGE FARM 8 ~ 75 MILES C S HI TH F ARI) 4'5 t(ILES N

10'6(

10 F 16 1845 F 00(

1845 ~ 00-30'3(

30 ~ 43-20 F 63(

20 63-20+96(

20 ~ 96-6'8(

6'8 1/

1) 10%16 1/

1) 1845 F 00 1/

1) 30'3 1/

1) 20'3 1/

1) 20'6 1/

I) 6'8 4 ~ 74 (

13/

13) 3'2-8'9 52 VALUES <LLD 4 '3(

40/

SP) 2 F 06-7'6 13'3(

3/

4) 10'0(

1/

52) 11'0-16 F 00 10 '0-10'6

1308 '1(

12/

12) 1232 '5(

52/

52) 1127 '0- 1569'0...

1037'0 1391 F 80 201 VALUES <LLD a.

Nominal Lower Limit of Detection (LLD) as described in Table 3.

b.

Mean and range based upon detectable measurements only.

IFraction of detectable measurements of specified locations is indicated in parentheses (P).

NAME OF F)C ILITY BROMNS FERRY LOCa T10 tt OF F AC IL IIY~IME'S TO ttE TABLE 11 RAOIOACT I V I'IY IN VEGETATION PCI/G -

0 ~ 037 80/G CDRY VEIGHT)

OOCKCT NO ~ 50-2 9

60 TYPC 4NO TOTAL NUHBCR OF ANALYSIS GROSS BETA 36 GAIIHA (GCL I) 38 LOVER LI HIT OF DETECTION

~(LO) 0 ~ 200 ALL It(OICATOR LOCATIONS

)b

~RAl G 26'3(

20/.

20)

Ta70-48a82 SITTING FARM

~ 35a32(

2/

2) 4 ~ 5 MILES ENC 31 88-38 75 CONTROL LOCATIONS 26~52(

16/

16) 10 F 07-45~74 NUMBER OF NONROUT INE REPORTED

~ASQQf~MNTS CC-141 144

>P-144 RU-103 RU-106 CS-137 ZR-95 NB-95 K-40 MN-54 Y 88 AI-214 8 I-212

>8-214 oO"212 RA-226 BE-7 I'L-208 AC-228 al Lowe and ran a.

Homin b.

Mean 0'00 0~220 NOT ESTAB 0~200 0~510 0.060 0 ~ 110 0 '5G NOT ESTAB 0'50 NOT ESTAB 0'00 NOT ESTAB ttoT EST~8 NOT ESTAB NOT CSTAB NOT CSTAB NOT ESTAB NOT ESTAB 1 ~ 93(

1 ~ 21-1 56(

0 ~ 23-3'0(

I ~ 43 I ~ 25(

0 ~ 22-1'8(

1+01-0 ~ 16(

0 ~ 07-1'6(

0 ~ 17-2'4(

0 06-

)0+40(

2 ~ 00-0'8(

0 ~ 06-

~ 0'2(

0002 0 ~ 35l 0 ~ 14-0'3(

0 ~ 33-0 ~ 20(

0 ~ 31-0 ~ 18(

0 ~ 03-0'9(

0 ~ 06-5 ~ 65(

lo12-0 ~ 08(

0 ~ 00-0'3(

0 ~ 07-ction (LLD) as de etectable measur r Limit Se base of Bete d upon d THRASHER FARM 7.0 MILES CNC LOONEY FARM 5.75 MILES Et;E LOONEY FARH 5 75 t(ILES CNE LOONEY FARM 5+75 t(ILES ENE THRASHER FARM

~ 7 ~ 0 HILES CNE BITTING FARM ha5 MILES ENE BITTING FARtt 4 ~ 5 HILCS CNE BITTING. FARM 4 ~ 5 MILES ENE BROOKS FAR(

7~0 MILES ht(M THRASHER FARM 7

0 MILES ENE OITTING FARH 4 ~ 5 MILES CNE BITTING FARH 4a5 HILES CNC LHl BF t(ORTHMEST I ~ 0 MILE N BITTl(IG FARH 4

S HILCS ENC LH1 BF NOR TIIMEST 1

0 HILE N BROOKS FARIL 7 ~ 0 MILES NNM LOONEY FARt".

Se75 MILES EWE LH1 BF NORTHliCST leO NILE N L.'ll BF NORTHMEST I ~ 0 HILE N

able 3.

Fraction of detectable 5/

21) 2+92 17/

21)

So49 3/

21) 4'1 6/

21)

.2+14 2/

21) lo54 14/

21) 0'2 10/

21) 4 ~ 46 18/

21 )

10 ~ 28 21/

21) 25 98 3/

21)

F 10 1/

21) 0'2

'9/

21 )

0'2 1/

21) 0'3 19/

21) 0 ~ 41 20/

21) 0 ~ 72 3/

21) 0'4 21/

21 )

15'3 16/

21) 0'9 18/

21) 0'8 scribed in T emeute only..

2'2(

2+92-2060(

0 41-4061(

4o61-1~53(

1 53-1 ~ 54(

1 ~ 54-,

0'2(

0+32-3 ~ 95(

3 ~ 95-4'8(

0 ~ 39-12'6(

2088-0 10(

0 ~ 10-0~02(

0 ~ 02-0 49(

"0+49-0 ~ 33(

0 ~ 33-0 ~ 27(

0 ~ 16-0 ~ 72(

0 72-0 ~ 14(

0 ~ 14-7'7(

1 12-0'9(

0 ~ 29-0'6(

0 ~ 36-1/

4) 2'2 2/

4) 80 1/

4) 4~61 1/

4) 1+53 1/

4) 1~54 1/

2) 0~32 1/

2) 3'5 2/

2) 8~36 4/

4) 22'6 1/

4) 0 ~ 10 1/

2) 0 F 02 1/

2) 0+49 1/

1) 0033 2/

2)

Ga38 1/

1) 0~72 1/

4) 0 ~ 14 4/

4) 13'1 1/

1) 0 ~ 29 1/

1) 0 36 1 ~ 93l i+16-1'9(

0 ~30-F 71(

2 ~71-lo39(

1 ~ 10 1 ~ 11(

0'9 0 '1C 0 ~ 06-I ~ 90(

0 ~ 30-2'5l 0 ~ 06-Ila37(

2~23-0 ~ 10(

0 ~ 08-17 VALU 4/

17) 2'6 13/

17) 5'5 1/

17) 2'1 4/

17) 1 ~ 65 2/

17) 1 ~ 34 7/

17) 0'0 8/

17) 4'1 13/

17) 9'6 17/ '7) 28'5 4/

17) 0 ~ 12 ES

<LLO 0 ~ 30( 10/'7)

Oo1 1-0'+64 17 VALUES <LLO.

0+21(

0 ~ 10-F 17(

0 ~'04 0 F 07(

0 ~ 03-5 96(

2 ~ 29-0 ~ 05(

0 ~ 01-0 ~ 17(

0 ~ 02-12/

17) 0050 14/

17).

0'3 2/

17) 0 ~ 11 17/

17) 14'0 9/

17) 0 16 14/

17) 0 ~ 52 measurements of specified locations is indicated in parentlieses (F).

TAbLC 12 RADIOACTIVITY IN SOIL t'AHE OF FACILITY QRCVNS FgoRY LOCATION OF FAEILTTT~LIR STORE oCI/G -

0 ~ 037 84/G (DRY vCIGHT)

ALAr>HA (AOCKET t 0 ~ 50-259A2~60 296 RCPORT ING PERIOD~1

~

~

T TPC At(D TOTAI. NUHBC4 OF ANALYSIS FERFORIIEO OAFIIA TOELII 11 LOVER L 1t! I T CF DETCCT ION ALL INDICATOrs LOCATIONS HCAN (E)

R~ATAtG CC-141 CE-144 RU-103 CS-137 2 EA-95 G ~ 030 0'60 tiOT ESTAB 0'20 0 ~ 030 0 ~ 010 0 ~ 250 0 ~ 050 0 F 100 0 ~ 050 NOT ESTAP ti'8-95 K-4 0 GI-214 81-212 PB-214 PB-212 RA-226 RA-223 OC-7 TL-208 AC-228 PA-234il C

-".50 NOT ESTAB 0 F 160 0 ~ 020 0

060 NOT ESTAB 1 ~ 500 Sr 89 11 SR 90 11 a.

Nominal Lover Limit of De b.

)tean and range based upon 0 ~ 06(

1/

9) o.oe-0.06 0'3(

4/

9) 0 F 08-0o24 0 F 02(

4/

9) 0 32-0

>3

~

0'5(

)/

9) oolo-F 82 0 06(

8/

9>

0 ~ 04-0 ~ 11 0 ~ 14(

9/

9) 0 ~ 06-0 ~ 35 5o42(

9/

9)'o90-To13 lool(

9/

9) 0'1-1 ~ 40 0'6(

9/

9) 0 ~29-0 ~ 86 lo08(

9/

9) 0'P-1 ~ 46 I ~ 08(

9/

9)

Oe59-1 ~ 43 I ~ 16(

9/

9>

0 ~ 51-2(43 6 ~ 36(

4/

9)

G ~ 29-0 ~ 46 0'4(

2/

9) 0'1-0 ~ 26 0'8(

9/

9) 0 ~ 18-0 ~ 48 1 ~ 12(

9/

9) oe52-1 ~ 46 3'0(

1/

o)

F 50-3 50 9

VALUES <LLD ANALYSIS PERFORHED 0 ~ 300 9 VALUES <LLD ANALYSIS PERFORHED taction (LLD) as described in detectable measurements only.

CONTROL LOCATI GNRI HEAN ($ )

RANGE NUHBER OF NONROUTINE REPORTED

~HASUR~~HTS LHZ BF NORTH Coo HILC NNC ROGCRSVILLCo AL 13 ~ 8 HILCS Nli LHl BF NORTHVEST 1 ~ 0 NILE N

ROGCRSVILLCs AL 13 8 HILCS tJV POGCRSVILLE ~

AL 13 8 HILES NV ROGERSVILLCt AL 13e8 tlILCS NV LH4 BF TRAILER P I ~ 7 HILES NNV LH2 BF NORTH oe9 HILE Nt(E DECATU4t AL 8 ~ 2 HILES SSC LH2 BF NOPTH 0e9 HILE NtJE DECATURE AL 8'

HIILES SSE ATHENS'L 10 9 HILCS NE LV4 BF TRAILER P

I ~ 7 HILCS ttNV L"3 BF NORTHEAST loo NILE CNE LH1 BF NORTHVCST 1 ~ 0 HILE ti UECATURE AL 8 ~ 2 HILES SSE LHZ GF NORTH 0 ~ 9 HI LE tttt E o.oe(

0 ~ C&-

0 ~ 24(

0 ~ 24-Oo03(

0 ~ 63-1 ~ 82(

1 ~ 82-0 ~ll(

oell-0 ~ 35(

0 o 35-.

7ol3(

7 ~ 13-1 ~ 40(

1 ~ 40-O.86(

0 ~ 86-1 ~ 46(

1 ~ 46-1 ~ 43(

1 ~ 43-2e43(

2 ~ 43-0 ~ 46(

oo46-0 ~ Za(

0 ~ 26-0 ~ 48(

0 ~ 48-I ~ 46(

1 ~ 46-3 50(

3 ~ 50-I/

1) 0 F 06 1/

I) 0o24 1/

1) 0 F 03 1/

1)

I ~ 82 1/

I>

F 11 1/

I) oe35 1/

1) 7 ~ 13 1/

1) 1 40 1/

1>

0 ~ 86 1/

1) 1 ~ 46 1/

I )

I ~ 43 I/

1) 2'3 1/

I) 0 ~ 46 1/

1) 0 ~ 26 I/

1) 0'8 1/

1) 1 ~ 46 1/

1>

3'0 2

VALUCS <(.LO 0 ~ 10(

0 ~ 08-0 ~ 03(

0 ~ 02-0 ~ 96(

0o64-0 F 08(

0 ~ 04-0'4(

0 ~ 09-4 o97(

4 ~97-Oe90(

0 ~ 78-0 ~ 46(

0 ~ 34-0 92(

oe81-0 ~ 94(

0 ~ 86-0 ~ 90(

0 ~ 78-2 VALU 2/

oolZ 2/

2) oo03 2/')

le28 2/

2) 0 12 2/

2) 0 19 2/

2) 4o98 2/

2)

F 02 2/

2) 0 ~ 58 2/

2) 1 ~ 04 2/ ')

1 ~ 03 2/

2) 1 ~ 02 ES

<LLD 0'5(

2/

2) 0 ~ 19-0 ~ 30 0 ~ 33(

. 2/

2) 0 ~31-0 ~ 36 0'7(

2/

2) 0'0-1 05, 4'9(

1/

2) 4'9- ~

4'9 2

VALUES <LLD 2

VALUES <LLD Table 3.

Fraction of detectable measurements of specified locations is indicated in parentheses (F).

TD( LE 13 tiARE OF FACILITY CAROL'tsS~JRRY LOCATION OF FACILITY Q~R~STOQf, RADIOACTIVITY IN llELL NATER PC I /L -

0 ~ 037 80/L

~aa jjAh*

DOCKET NOU~~4$~0~

REPORT IhG PERIOD~'~9 TYPE AND TOTAL NUBBER OF At(ALYSI S GANNA (NAI) 19 LOiiER LINIT OF OETECTIOI4 ALL IliDICATOR LOCATIONS MEAti (F)b RANG b

12 VALUES <LLD ANALYSIS PERFORNED CONTROL LOCATIONS BEAN (g)b A~Ah 7

VALUES <LLD NURSER OF tiONROUTINE REPORTED Pj A S Ufjf~RS S GAMBA (GELI) 7 K-40 NOT ESTAB 1

VALUES <LLD BI-214 NOT ESTAB 1

VALUES <LLD P8-214 NOT ESTAB 1

VALUES <LLO PB-212 NOT ESTAB 1

VALUES <LLD TR I T I Ut(

330 F 000 VALUES <LLO 8

ANALYSIS PERFORNEO 99 F 84(

3/

6) 86 85-115'0 28 F 00(

1/

6) 28~00-28'G 12%59(

2/

6) 7'2-17'6 6~48(

1/

6)

F 48 6U48 VALUES <LLO a.

Nominal Lower Limit of Detection (LLD) as described in Table 3.

Nean and range based upon detectable measurements only.

Fraction of detectable measurements of specified locations is indicated in parentheses (P).

TAELC I4 RADIOACTIVITY ItA PUBLIC )tATCR SUPPLY

.'4 4 HE OF F AC I LI T Y P R OL4>l~~

F /R R Y LOCATION Of FACILITY

~IHLSYOQ~

PCI/L -

0 ~ 037 BO/L TYPE AND TOTAL NUMBER OF At4ALYS IS

~RRFDR~R GROSS BETA 85 GAHHA (NAI) 70 LO)IER LIMIT Of DE TEC T I 0)t

~(L~)

F 400 ALL

'NDICATOR LOCATIONS HEA(4 (F)b RAN~Gb 3%96 (

61/

72) 2G46-14 ~ 70 61 VALUES <LLO ANALYSIS PERFORMED t(AHE MEAN (F) b Q~ISTAMC AttD QIRQCTIDII RARGGG CHAMPION FAPER 4 ~Il(

44/

46)

TRH 282 '

2 46-14'0 CONTROL LOCATIONS MEAN (F)

RAN 3'0(

11/

13) 2~50-4 F 08 9

VALUES <LLO NUt(BER OF NONROUTIttC REPORTED ct 1-214 PB-214 PB-212 TL-208 SR 89 16 SR 90 16 TRITIUM 16 NOT ESTAB NOT ESTAB NOT ESTAB NOT CSTAB 10 F 000 F 000 330G000 GAMMA (GEL I )

15 K-40 tlOT ESTAB 74 F 11(

2/

11) 72'9-75'3 24G80(

8/ ll) 12 F 00-43 F 03 15'3(

4/

11) 11 ~ 14-23'3 Ii+90(

1/

11) 11 90 11 90 11 VALUES <I.LD 12 VALUES <LLD ANALYSIS PERFORHEO 3 25(

1/

12) 3'5-3'5 369G21(

1/

12) 369'1-369'1 CHAMPIOti PAPER TRH 282 ~ 6 SHEFF IELD~ AL ROB TRM 254 3

CHAMPIOt4 PAPCR TRH 282' SHEFFIELD>AL ROB TRt'54~3 St(EFF ICLOrAL ROB TRt4 254 '

CHAMPION PAPER T(AK 282G6 74 F 11(

72e49-28 ~ 91(

2&+91-16 ~ 33(

12 ~ 52-II~ 90(

II~ 90>>

3'5(

3 ~ 25-369'1(

369G21-2/

8) 75'3 I/

I) 28'1 3/

8) 23'3 1/

1) 11 90 1/

4) 3e25

'I/

4) 369'1 101 F 00(

1/

4) 101 F 00-101 F 00 17'8(

2/

4) 13G60-21 '5 15'2(

2/

4) 15G68-15'5 16 18(

2/

4) 13'3-19'2 5G84(

I/

4) 5 84-5'4 R

VALUES <LLO R

VALUES <LLD 376'9(

1/

4) 376'9-376 '9 a.

Nominal Lover Limit of Detection (LLD) as described in Table 3.

b.

Mean and range based upon detectable measurements only.

Fraction of detectable measurements of specified locations is indicated in parentheses (F).

31 Table 15 ENVIRONMENTAL GAMMA RADIATION LEVELS Average External Gamma Radiation Levels at Various Distances from Browns Ferry Nuclear Plant for Each Quarter - 1981 mR/Quarter Distance miles Avera e External Gamma R

2nd uarter adxatxon Levels 0-1 1"2 2-4 4-6

>6 18.8 + 1.2 17.1 + 1.2 16.5

+ 1'2 16.6 + 1.1 16..5 + 2.2 21.7 + 2.0 17.3 + 2.2 15.6 + 1.8 17.0 + 1.6 16.8 + 2.7 21.0 + 1.6 16.7

+ 3.2 16.2 + 3.3 I

17.1 + 2.2 159+35 20.0

+ 1.5 20.0 + 5.0 16.5

+ 1.7 16.6 + 1.3 16,6 + 2.3

Average, 0-2 miles (Onsite)

Average,

>2 miles (Offsite) 18.4 + 1.4 16.5+ 1.5 20.6 + 2.8 16.7

+ 2.0 19.9 + 2.7 16.6 + 2.8 20.1 + 2.1 16.6 + 1.7

a. Data normalized to one quarter (2190 hours0.0253 days <br />0.608 hours <br />0.00362 weeks <br />8.33295e-4 months <br />).

b. All averages reported +lo (68 percent confidence level),

TAPLE 16 RADIOACTIVITY IN FOOD'ROPS PCI/KG -

0 ~ D37 89/KG

((JET MEIGHT)

LOC < T ION OF FAC ILITY~~IN

~TNr DOCKET NOe~~5<

-6."A296 TYPE At,'D LO)JER LIMIT ALL TCTAL t(UPBER OF INDICATOR LOCATIONS OF ANALYSIS DETECT IONa

."EAN (F)

L ATIOh MITH HIGHES ANNUAL MEAN NAME rEAN (F)o CONTROL LOCATION)

MEAN (()

RAN NUMBER OF NONROUTINE RFPORTED

~HAS

~R~HE TS RADIOACTIVITY IN CABBAGE ol-"14 PB-212

'JOT EST AP NOT ESTAB GROSS PETA 25 F 500 1

GA)t"4 (GELI )

1 K-40 NOT ESTAB 1873~00(

1873 00-13'0(

13 ~ 4C-15 ~ 75(

15 ~ 75-1/

1) 1873'0 I/

1) 13+40 I/

I) 15'5 4286e86(

1/

I) 4286'6-4266 '6 t(ILES N

4 MILES N MILES N

4 t(ILES tl 4286 '6(

I/

1) 4286 '6-428'6 1873 'G(

1/

1) 1873+00-1873+00 13'0(

I/

I) 13'0 13'0 15~75(

I/

I) 15e75-15'5 RADIOACTIVIT'I IN CORN GROSS BETA 25 ~ DOO 2

GA)t"4 (GELI) 2 K-4 0 NOT ESTAB 4163+82(

I/

I)

LN2 BF NORTH 4163 ~ 82-4163 ~ 82 0

9 NILE t'NE 4163e82(

1/

I) 4163'2-416'2 3995 '6(

I/

I) 3995+66-3995+66 1964.00(

I/

1)

Lt(2 BF ~ORTH 1964.CO(

I/

I) 1432.00(

I/

, I) 1964 DO-1964 F 00 0'

'NILE tJNE 1964 00-1964 F 00 1932 00- 1932 '0 RADIOACTIVITY IN GREEN BEANS GROSS BETA 2

GAMI44 (GELI

)

C

'K hn 9 I-214 PB-212 25 F 000 NOT ESTAB NOT ESTAB NOT ESTAB 2132 ~ OD(

1/

1) 2132 'C-2132 ~ 00 I VALUES (LLD 2 MILFS NNO 6+89(

I/

I) 6 ~89-6 ~ 89 2 )(ILES NNU 4874 ~ 83(

I/

I )

2 NILFS NN(J 4874~83-4874+83 2132 F 00(

I/

1) 2132 'C-2132 F 00 6 ~ 89(

5 ~ 89-1/

I )

6.89 1682 F 00(

I/

I) 1682 F 00-1682 'C 20 '0(

I/

1) 20'0-20'0 29'8( '/

I) 29 58-29 58 4874 '3(

1/

I) 3251~74(

I/

I) 4874 83-4874 83 3251 '4-3251 74 a.

Nominal Lover Limit of Detection (LLD) as described in Table 3.

b.

Mean and range based upon detectable measurements only.

Fraction of detectable measurements of specified locations is indicated in parentheses (F).

NAHC OF F AC ILITY BROI'NS FCRRY LOCAIION OF FAC ILI TY~H~~T>hL TABLC 16 (Contd)

RADIOACTIVITY I"A FOOD CROPS PCI/KG -

OHC37 EO/KG

('~CT VCIG)Sl)

AI A/AHA REPORT))SG PERIOD-1481 TYPE hNO LOQEIG LIHIT ALL ~

TOTAL NUHBER OF INDICATOR LOCATIONS OF AHACTSIS OETECTIOH MESH I[IS

~C41 OH II TH HIGHm~TA I UA JIEAH NAHE HEAD (F~l CONTROL LOCATIoi($

HEAN (5)

RANGE NUHBER OF NONROUT INC REPORTED

~FASU FEMTS RADIOACTIVITY IN PEACHES GROSS BETA 2

GAHHA (GCLI) 2 K~40 BI-214 PB-212 25eooo NOT ESTAB NOT ESTAB NOT ESTAB 1697 00 t 1697 ~ 00-22'3(

22 ~ 43-19e53(

19'3 I/

I) 1697 AGO I/

1) 22e43 1/

1) 19 ~ 53 SHITH FARH 4 ~ 75 H ILES SHITH FARr 4 ~ 75 HILES Ss(ITH FARH 4 ~ 75 HILCS 1697 F 00(

1/

1) 1697 F 00- 1597 ~ 0G 22 F 43(

I/

1) 22'3-22e43 19e53(

1/

1) 19'3-19'3 1252 F 00(

I/

1) 1257 F 00 125'G 1

VALUES <LLD 1

VALUES <LLO 3127e13(

1/

ll SHITH FARH 3127e13(

1/

ll 2970e49(

1/

ll 3127 ~ 13-3127 ~ 13 4 ~ 75 HILES K

3127 ~ 13-31?7 ~ 13 2970 49-2970 49 RADIOACTIVITY IN POTATOES Bl-214 PB-212 NOT ESTAB NOT ESTAB GROSS BETA 25 F 000 2

GAHHA (GELI )

2 K-40 NOT ESTAB 3201 ~ CO(

3201 ~ 00-15'2(

15 ~ 62-13'2(

13 ~ 62-1/

I )

3201 F 00 1/

1) 15'2 I/

1) 13'2 7112 ~ 16 (

I/

I )

7112 ~ 16-7112 F 16 2 MILES NY)s' HILES NNM 2 HILCS NN)T 2 HILCS NNM 3201 ~ PO(

3?01

~ 00-15'2(

15 ~ 62-13'2(

13e62-1/

I) 3473 F 00(

I/

1) 32Ol.OO 3473.00-3473.00 1/

1),

1 VALUES <LLO 15'2 1/

1) 1 VALUES <LLO 13'2 7112 F 16(

I/

1) 7721 '4(

I/.

1) 7112 F 16-7112e16 7721 '4-7721 '4 a.

- Nominal Lower Limit of Detection (LLD) as described in Table 3.

b.

Mean and range based upon detectable measurements only.

Fraction of detectable measurements of specified locations is indicated in parentheses (F).

EAS

TABLE 16 (Contd)

RADIOACTIVITY IN POOD CROPS PCI/KG - 0.037 8(t/KG (MET MEIGHT)

NAME CF FACILITY BRoitJS FERRY LOCATION OF F ACILITY~~HJON(

TYPE AND LOMER LIMIT ALL TOTAL NUHBER OF INDICATOR LOCATIONS OF ANALYSIS DETECTION a HEAN (F)

,02;II~MR 22 RAN~

AOCATIOII HI~TH H GH "I AHIIUAQ~HA CONTROL LOCAI IONG HEAN (f )

~RANG OGCK I NO ~50-250 2600206 Q~AA A

REPORTING PERIOD 198)

NUMBER OF NONROUTINE REPORTED

~MR~UN II T 0 RADIOACTIVITY IN TOMATOES 25 000 GROSS BETA 2

Git(KA (GEL I

)

2 K-4 0 NOT ESTAB NOT ESTAB PB-212 2513 'O(

1/

1) 2513 F 00- 2513 F 00 11')5(

I/

1) llH15-11'5 BROOKS FARM 7 ~ 0 MILES NNL BROOKS FiRN 7~0 MILES hNli 5130H21(

1/

1)

BROOKS FARM 5130 H21-5130 H21

~

Ti0 MILES NN)t 5130 '1(

I/

1) 5669'7l 1/

1) 5130 '1-513P ~ 21 5669'7-5669 '7 2513 F 00(

1/

1) 2381+00(

I/

1) 2513 00- 2513 F 00 2381 00- 2381 00 11 ~ 15(

1/

1) 1 VALUES CLLD 11 ~ 15-11 ~ 15 RADIOACTIVITY IN TURNIP GREENS GROSS BETA

?

GAMMA (GEL I )

2 K-4 0 BI-214 PB-214 PB-212 BE-7 25+000)

NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB 2262 F 00(

2262 ~ 00-22'3(

22 ~ 93-13 53(

13 ~ 53-llew 42(

ll~ 42-194 '0(

.194 ~ 40-1/

1) 2262 F 00 1/

1) 22'3 1/

1) 13'3 1/

1) 11'2 1/

1) 194 '0 5500M 16(

1/

1) 5500 '6-5500HI6 4 tlILES N

HILFS N

MILES tt MILES tt 4 MILES N HILES N

2262 F 00(

2262 ~ 00-22'3(

22 ~ 93-13 53(

13 ~ 53-11'2l 11 ~ 42-194 '0l 194 ~ 40-1/

1) 2262 00 1/

1) 22 ~ 93 1/

1) 13'3 1/

1) 11 '2 1/

I) 194'0 2980 F 00(

1/

1) 2980i00-2980H00 37'4(

1/

I) 37'4-37'4 1

VALUES (LLD 26'1(

1/

1) 26'1 26021 1

VALUES 0.'LLO 5500 ~ 16 l 1/

I )

~

5969~ 01 (

1/

1) 5500 '6-5500 '6 5969 F 01-5969 F 01 a.

Nominal Lover Limit of Detection (LLD) as described in Table 3.

b.

Hean and range based upon detectable measurements only.

Fraction of detectable measurements of specified locations is indicated in parentheses (P)..

RADIOACTIVITY IN SOYBEANS PCI/G -

6 ~ 037 80/G (CRY VEIGHT)

NArC OF FACILITY BROUNS FEAR)

COCIIIION OF FACILIIT

/~IN STOAT/

A~ARANA REPORTING PERIOD~)9 TYPE AND TOT>L NUi(BER OF ANALYSIS

~PE QFI~RO GROSS BETA LOVER LIMIT GF DETECTION a

~IOl 0 ~ 200 Bl-214 PB-214 BE-7 AC-228 NOT ESTAB iNOT ESTAB NOT ESTAB NOT ESTAB 2

GANNA CGEL I )

2 K-40 NOT ESTAB 15474 C

14470 0 ~ 03(

0403-0 ~ 05(

0 ~ 04-0 ~ 20(

0.20-0 ~ 11C 0411 2/

2) 16 ~ 77 1/

2) 0'3 2/

2) 0006 1I 2) 0 ~ 20 1/

2) 0 ~ 11 ALL INDICATOR LOCATIONS NEAN (F)b 29453(

2/

2) 29 F 40 29'5 LN2 BF hORTH 0

9 NILE NNE LN2 BF hORTH 0.9 NILE NNE Li(2 BF NORTH 0 9 NILE NNE LN2 BF NORTH 0.9 NI1.E Nt E LN2 BF NORTH 0

9 NILE NNE 15474C 14 ~ 70-0'3(

0 ~ 03-0 '5C 0404-0420(

'0'0" 0 ~ 11(

F 11 2/

2) 16'7 1/

2T 0'3 2/

?)

0406 1/

2) 0'0 1I 2)

-0411 LN2 BF NORTH 29'3(

2/

2) 0 ~ 9 NILE NNE 29440 29'5 CONTROL LOCATIONS NEAN (F)b b

NUNBER OF NONROUT LNE REPORTED a.

Nominal Lower Limit of Detection (LLD) as described in Table 3.

b.

Mean and range based upon detectable measurements only.

Fraction of detectable measurements of specified locations is indicated in parentheses (F).

NAHE OF FACILITY BROUNS FERRY LOCATION OF FACILITY~~INC TO~E TABLE 18 RADIOACTIVITY Itl POULTRY PCI/KG OP037 BO/KG ()lET MEIGHT)

A A'AHA COCKET hOH~O-259 0 ~

REPOITINO PERIOO~99 TYPE ANO TOTAL tNURCOER OF ANALYSIS PERFORt'EO GROSS BETA 2

GAHHA (GELT) 2 LOMER LIt'.IT OF DETECTION a CLI Q) 25 000 ALL INDICATOR LOCATIONS BEAN (F)b R~A 4972%66(

1/

1) 4972 '6-4972 '6.

LOCATION VITH RICHEST ANNI~I~HAH NAHE HEAtt (F)b REFERRER REEL RE~Nu~oRMRE'H5 RIF DAVIS F 4972466(

I/

I) 2 5 HILES )tgl'972'6-4972 ~ 66 CONTROL LOCATIONS.

t(EAN (F )b.

b 6458 '6(

1/

I) 6458 '6-6458 36 ICUHBER OF NONROUTINE REPORTED H

TS K-4 0 8 I-214 PB-214 PB-212 NOT ESTAB NOT ESTAB NO'I ESTAB NOT ESTAB 2412 ~ OOC 1/

I) 2412~00-2412 F 00 VALUES <LLO 1

VALUES <LLO 1

VALUES <LLO LH5 BF DAVIS F 2~5 MILES )tS)i 2412 F 00(

1/

I) 2137 F 00(

2412 F 00 2412 F 00 2137 F 00 19H56(

19 ~ 56-IBH38(

18'8 10 '6(

10 ~ 86-1/

1) 2137 F 00 1/

1) 19 ~ 56 1/

1) 18'8 1/

1) 10 F 86 a.

Hominal Lover Limit of Detection (LLD) as described in Table 3.

b.

Mean and range based upon detectable measurements only.

IPraction of detectable measurements of specified locations is indicated in parentheses",{P).

Figure 6

COCo clC ll Q laJl 4J CA 4J 4

Ch o

4J 0

Ci Jl "0

C C 0 H Q Preoperational Phase Operational Phase ANNuu AVERAGE 6ROSS HEfA ECTIVITY INRl H<I% RATER SUPPLIES 1hOWM FERRY Noae MhT Average:

Preoperational Phase I

19 8

19 9

19 0 1

1 19 2

19 3P 19 30 19 4

1 5

19 6 1

7

.19 8 1

9 19 0 1

1

38 Figuxe 7

Otrect Radtat ton Levels Browns Ferry Nuclear Planl C.

O 0 18 8

8 Ons1 te I

O" I I

'i i

o I

'%i o'

I

~ Of fsllte 0/I

\\

\\

\\

I I

I 1 I

I

/j g

\\

I I

12 1976 1977 1978 1979 1988 1981 Figure 8

22 Otrect Radlatlon Levels Browns Ferrv Nuclear Plant I-Ouar ter Movtng Aver age Onstte 16 12 1976 1977 1978 1979 1988 1981

Figure 9

39 Oirect Radiot ion Levels Wot ts Bar Nuclear Plant 22 C.

C s 18 Ct s

Onsiie Offsi tee I

I b

f' I

I b-4 12 1976 1977 1978 1979 1988 1981 Figure 10 22 0 iree t Radiation Levels Wo t t s Bar Nuc lear P ion 1 4-Quarter Moving Average C.0 C.0 18 8

s 16 Onsite

/

ts b.~.~

/

.a.w Of fsi le o.~.~

tt

'e I

1976 1977 1978 1979 1988 1981

P'

Table 19 SAMPLING SCHEDULE - RESERVOIR MONITORING Biolo ical sam les (collected semiannuall

)

River/river mile Zooplankton, chlorophyll, phytoplankton Benthic fauna Sediment Fish (co8ecfe5 mlnMly)

Tennessee 277.9 Tennessee 285.2 Tennessee 288.7 Tennessee 291.7 Tennessee 293.5 X

X X

X Tennessee 293.7 (discharge area)

Tennessee 305.0 (Control)

Tennessee 307.5 (Control)

Elk 20.5 (Control)

X a.

Gill net and/or electroshocker will be used for collection.

Samples of fish are collected from Guntersville,

Wheeler, and Wilson =Reservoirs.

b.

Automatic sampler.

c.

Grab sample.

TABLE 20 RADIOACTIVITY ltl SURFACE rATErt TOTAL PC I/L -

0 ~ 037 80/L RANE OF FACILITY BRO'FANS FERRY LOCATION OF FACILITY-MI~HQ~OJtg TYPE AND TOTAL t)JHBE(

OF ANALYSIS PERFORMED GROSS BETA 32 GAMMA (NAI )

45 LOMER LIHIT OF OETECTIONa (LLD) 2'00 ALL INDICATOR LOCATIOt:S HE AN (F )b RANGE b 3 53(

14/

17) 2'3-F 16 27 VALUES <LLD ANALYSIS PERFORMED LGCATIOL4 A)TH HIGHEST ANNUAL HEA(J NAME MEAN ($ )b O~S Tat(CC At'P PIRECTIOrt RANGE TRH 233 ~ 5 3'6(

2/

2) 3+30-4'2 CONTROL LOCATIONS HE'AN (F P sar.~s>

5 27(

121 15) 2'9-9'8 18 VALUFS <LLO NUHBER OF NONROUTINE REPORTED

~H~ASUR MEhT~c 81-214 PB-214 PB-212 SR 89 SR 90 TRIT IUH 20 NOT ESTAB NOT ESTAB NOT ESTAB 10 F 000 F 000 330 F 000 GAHHA (GELI) 20 K-40 NOT ESTAB 105 ~ 50(

=

5/

12) 51 52-159 F 60 15~99(

5/

12) 4'6-23~87 26 F 00(

1/

12) 26.00-26.00 15'5(

3/

12) 12 03-17 62 20 VALUES <LLD ANALYSIS PE,RFORHEO 2 81(

1/

20) 2 F 81-F 81 372 F 11(

~ 2/

12) 364 F 86-37'5 TRH 293 '

BFN DISCHARGE TRH 285 '

TRH 293 ~ 7 OFT DISCHARGE TRM 285 '

TRM 233~7

~

BFt DISCHARGE TRH 293 '

13'5(

II9 ~ )0-1'060(

18 ~ 14-26i00(

26.00-17'2(

17 ~ 62-2 ~ 81(

2 ~ 81-379 35(

379 35-2/

3) 159 F 80 2/

3) 19'6 1/

3) 26 00 1/

3) 17'2 1/

12)

F 81 1/

4) 379'5 96'3(

2/

8) 74 '5-118 '0 31 F 14(

6/

8) 5a00-83'5 27'4(

4/

8) 10'4-55'9 13'3(

3/

8) 8 F 42-22'1 16 VALUES <LLO 2'7(

I/

16) 2+07-2i07 8

VALUES <LLD a

Nominal Lover Limit of Detection (LLD) as described in Table 3 ~

b.

Hean and range based upon detectable measurements only.

Fraction of detectable measurements of specified locations is indicated, in parentheses (F).

NAHE OF FACILITY //~0M ~fEPRY LOCATION OF FACILITY LIHESTONE TabLE 21 RADIOACTIVITY INI ) HITE CRAPPIE (FLESH)

PCI/G -

0 ~ 037 BQ/G (DRY )TEIG)GT)

BAAL)AHA DOCKET NO 50-259A~~O REPGRTTIIG PERTUSSIS I

TYPE AND TOTAL NUHUER OF ANALYSIS PERFORHED GROSS BETA ES GAHHA (GEL I )

6 CS-137 K-49 BI-214 PB-214 PB-212 LOMER LIHIT OF DETECT ION a (LLR))

0 ~ 100 0'20 NOT ESTAB 0 ~ 020 NOT ESTAB NOT ESTAB 0 ~ 12(

0%09 14'5(

12 ~ 72-0+07(

0005 0+07(

0 ~ 06-0'2(

0 ~ 02-4/

4) 0 ~ 14 4/

4) 15'3 2/

4)

OP09 2/

4) 0 F 07 1/

4) 0 F 02 ALL INDICATOR LOCATIONS BEAN (F)b RANGE b 35 F 18(

4/

4) 33s04-37'6 MILSON RESfRVOIR TRH 259-275 NILSON RESEPVOIR TRH 259-275 MHEELER RES TRH 275-349 MILSON RESERVOIR TRHi 259-275 VHEELER RES TRH 275-349 0'3(

0 13-15P20(

14 ~ 77-0 F 09(

0 ~ 09-0'7(

0 ~ 07-0'2(

0 02-2/

2)

OP13 2/

2) 15'3 1/

2) 0009 I/

2) 0+07 1/

2) 0 02 NAPE HEAN (F)b WILSON RESERVOIR 35 ~ 26(

2/

2)

TRH 259-275 34's98-35 ~ 54 CONTROL LOCATIONS HEAN (F)

~RUG U

34 '7(

2/

2) 33'3-36'2 0 ~ 14(

2/

2) 0'9-0 ~ 18 17 F 50(

2/

2) 15'9-19'1 0 F 06(

1/

2) 0 F 06-Os06 2

VALUES (LLD 0 ~ 02(

1/

2) 0 ~ 02-0'2 NUHBER OF NONROUTINE REPORTED GERS~US

~ll IITS a.

Nominal Lover Limit of Detection (Lu)) as described in Table 3.

b.

Hean and range based upon detectable measurements only.

Fraction of detectable measurements of specified locations is indicated in parentheses Q').

TahLE 22 RADIOACTIVITY Itl SHALLHOUTH BUFFALO (FLESH)

PCI/G -.'9037 BO/G (DRY ME.IGHT) 9 lAl'E OF FACILITY BPOMNS FfRRY LOCALION OF FACILITY L INES TOtlE AQAOAHA DGCKET NOO~~9QA296 REPORTIHG PER I00~901 TYPE lNO TOTAL:lU."DER OF AtlALYSIS G'ROSS BETA 6

GbuHA (GELI )

6 LOMER LIHIT ALL OF INDICATOR LOCATIONS DETECT IONa MEAN (F) b

~(LIl 8 ANGEb 0 ~ 100 23007(

4/

4) 19 F 04-27'0 RGGATJOA~UTH ~!GHOST A

UUAR HEAR RlauE MEAN (F)b D I STANCE Al'0 DIR CTIOtl RANGLb MHEELEP RES 25'7(

2/

2)

TRH 275-34a 24'4-27a20 CONTROL LOCATIONS HEAtG (F)b 22 40(

2/

2) 20'2-24'8 tlUHBER OF NONRDUTINE REPORTED H /~ASHNT S CS 137 K-40 DI 214 PB-214 PB-212 TL-ZnH SR 93 0'20 NOT ESTAB 0 ~ 020 NOT ESTAB NOT ESTAB 0~020 0'00 0 ~ 100 0.05(

0004-0'6 9 ~ 64(

4/

. 4) 7'6-11056 0.06(

3/

0 F 05-0 F 08 0'6(

2/

4) 0 ~ 05-0'7 G ~ 04(

1/

4) 0 F 04-0 F 04 0 F 02(

1/

4) 0.02-0.32 1

VALUES <LLD ANALYSIS PERFORHED 1

VALUES <LLD ANALYSIS PERFORHED VHEELEP RES TRH 27'-'49 MMEELER RES TRH 275-3GI9

'MILSON EAESERVOIR TRH 25+ 275 MHEELER RES TRH 275-349 MMEELER RES TRH 275 349 VHEELER RES TRH 275-349 0 ~ 05(

0 ~ 04-11'3(

10 ~ 49-0 OBC 0 ~ 08-0007(

Oe07-0 ~ 04C 0 ~ 04-0 ~ 02(

0002-2/

2) 0'6 2/

2) 11 ~ 56 1/

2) 0 F 08 1/

2)

DE 07 1/

2) 0004 1/

2) 0002 0 ~ 08(

2/

2) 0 '7-0 F 08 8 F 82(

2/

2)

F 00-10'4 0 ~ 14(

1/

2) 0'4-0014 0 F 09(

1/

2) 0 ~ 09-0 F 09 2

VALUES <LLD 2

VALUES <LLD 0

VALUES <LLD 0

VALUES <LLD a.

Nominal Lover Limit of Detection (LLD) as described in Table 3.

b.

Mean and range based upon detectable measuremcnts only.

Fraction of detectable measurements of specified locations is indicated in parentheses (F).

TABLE 23 RADIOACTIVIT'Y IN SNALLI-'OUTH BUFFALO (VHOLE)

PCI/O - GN037 BC/G (DRY VEIGhT)

NAI'E OF FACILITY QROMNS FLURRY LOCATION OF FACILITY L~MQSJOPQ ALA~AHA DOCKET NO 55~259 6

29'EPORTING PER IOD~4~8 TYPE AND TOTAL ttUPBER OF ANALYSIS

~PRFttR~u GROSS BETA 6

GAMMA (GELI) 6 CS-137 K-40 BI-214 PB-214 PB-212 SR 89 SR 90 LO'VCR LIMIT OF DETECT IONa

~(

0 ~ 100 0 ~ 020 NOT ESTAB 0 ~ 020 NOT EST~8 NOT ESTAB 0 F 500 0 '00 ALL INDICATOR LOCATIONS MEAN (F)b RAHGEb 19'2(

'l/

4) 18 F 57-19'5 0'3(

2/

4) 0503-0 ~ 03 8'8(

4/

4)

~ 6'3-F 11 0'6(

4/

4) 0'4-0+08 0'7(

3/

4) 0'4-F 12 0'3(

2/

4) 0 ~ 03-0 ~ 03 1

VALUES

%.'L'LD ANALYSIS PERFORMED 1

VALUES (LLO ANALYSIS PERFORNED

@HEELER RES TRH 275-349 VHCCLER RES

'(RN 275-349 VILSOt( RCSERVOIR TRN 259-275 VILSOtt RESERVOIR TRN 259-275 VHEELER RES TRM 275-349 0%03(

0 ~ 03 8 ~ 20(

7 ~ 50-0 F 06(

0+04-F 12(

0012 0'3(

ON03-1/

2) 0'3 2/

2) 8'9 2/

2) 0 F 08 1/

2) 0 ~ 12 1/

2) 0'3 LOCATION VITH HIGHEST AHHUA H

AH NAME NEAN (F)

Ql&EH~AB~~RTIRB

~5M VHEELER RES 19'6(

2/

2)

I'RM 275-349 18'7-19'5

.CONTROL LOCATION/

IIEAN ((I 2ONNE 29 99(

2(

2(

14 97-26 ~ 91 0'4(

1/

2) 0 F 04-0504 7'8(

2/

2) 5510-9'7 0'6(

2/

2)

ON03-ONOS 0 F 08(

1/

2) 0508-0508 0'3(

2/

2) 0'3-0 F 04 G

VALUES ((LLO 0

VALUES (LLD N(UNBCR OF NOtJROUT INC REPOITTED MgAS ~Un

~MNT~

a.

Nominal Lover Limit of Detection (LLD) as described in Table 3.

b.

Mean and range based upon detectable measurements only.

Fraction of detectable measurements of specified locations is indicated in parentbeses (F).

TABLE 24 NAKE OF FACILITY QROuNS FLURRY LOCATION OF FACILITY LIH~STO~N RAOIOACTIVITT IN SEOIHCNT PCI/G -

0 '37 80/G (DRY MCIGHT)

ALABAMA DOCKET NOo~0- $~$ 60AQQ REPORTING PCRIOO 1981 LOiIER LIMIT OF OE TEC T ION'(

LD)

(YoC AND TOTAL NUHBCR OF ANALYSIS

=PQKRB KEG GAMHA (GEL I )

8 CO-60 c NUMBCR OF hONROUT INC REPORTED

~HA QPf,~HQ T S CONTROL LOCATION)

ALL lluult

~onM~CQNQ plllfggIIIM

~II@MS VALUES (LLO VALUES <LLO TRH 293 '

BFN DISCHARGE TRHi 293o7 BFN DISCHARGF.

T8 Hi Z 77 ~ 98 2/

2) 0'1 1/

2)

Do13 2/

2) 2'5 0 ~ 010 0 ~ 080 0'20 0'30 0'0(

0 ~ 19-0 ~ 13(

0 ~ 13-2'4(

2o23-0 ~ 14(

5/

6) 0'7-0'1 0'3(

1/

6) 0 ~ 13-D ~ 13 I ~ 70(

6/

6)

Do83-2'5 6

VALUES (LLD CS-134 CS 137c ZR-95 NB-95 2/

2) 0'1 1/

2) 0'7 1/

2) 0'2 2/

2) 15'6 I/

2) 0 ~ 03 2/

2) 1096 2/

2) 1'6 2/

2) 2 ~ 09 2/

2) 2'8 2/

2) 1 ~ 96 2/

2) 0 F 87 2/

2) 0 F 78 2/

2) 2 68 UES

<LLD 0'7(

0'3 0 F 07(

Do07-0 F 12(

0 ~ 12-0 F 010 6 VALUES (LLO 15'5(

15 ~ 07-0'6(

0 F 06 1 ~ 44l 1 ~ 35-1 ~ 33(

1 ~ 33-Io68(

1 ~ 66-2 F 01(

lo98-1 ~ 44(

1'5 0'0(

0 ~ 50-0'5(

0 62-I ~ 89(

lo83-CSTAB 13 ~ 64-0'3l 0 ~ 03-lo79(

1 ~ 61-F 15(

0 ~ 93-1 ~ 86(

1 ~ 64-2 F 00(

1082-1'9(

1061 Do75(

0 ~ 62-Oo73(

0'8 2'2(

I 95" 2

VAL 0 ~ 010 TRH 293 '

BFN DISCHARGC TRH 277'8 Do020 BI-212 PB-214 NOT NOT NOT RA-226 RA-223 TL-208 AC-228 1 ~ 530 K 40 NDT 14 'D(

6/

6)

TRH 288'8 2/

2)

~ 14'5(

11'2-16'2 16o42 HN-54 0 ~ 05l 2/

6) 1/

2) 0'4-0'6 Do06 BI-214 I ~ 35(

6/

6) 2/

2) 1 ~ 11-1 ~ 53 lo53 0'00 1 ~ 06(

5/

6)

TRH 288 F 78 1/

2) 0'8-1%33 1 ~ 33 CSTAB 1'0(

6/i 6)

TRH 277'8 2/

2)

I ~ 18-1 ~ 71 1 ~ 71 PB-212 ESTAB 1 ~ 86(

6/

6)

TRK 288'8 2/

2) 1 ~ 57-2'b 2'5 ESTAB 1 35(

6/

6)

TRK 277 '8 2/

2) 1 ~ 11-1 ~ 53 I ~ 53 NOT ESTAB 0'9(

2/

6)

TRH 293 '

1/

Do47-0 F 50 OFN DISCHARGE 0 ~ 50 0'20

) ~ 57l 6/

6)

TRM 277'8 2/

2) 0'4 0'7 0'7 0 '60 1 ~ 72(

6/

6)

TRH 277 '8 Z/

2)

I 35-1 ~ 94 I 94 SR P9 6

VALUES (LLD ANALYSIS PERFORHEO SR 90 0'00 6

VALUES (LLD 0 ~ 52(

1/

2) 0'2-0'2 a.

Nominal Lowef Limit of Detection (LLO) as described in Table 3.

b.

Mean and range based upon detectable measurements only.

Fraction of detectable measurements of specified locations is indicated in parentheses (F).

c., The distribution of Co and Cs between indicator and contrail locations reported herein is comparable to the distribution reported in the

~ oo<=or~ a)so comoarable with levels reported in samples from the

~

TAoLC 25 NARC OF FACILITY PROVt(S FERRY LOC AT ION OF F ACILII Y L~HSTO~tt RAOIOACTIVITY IN CLAP FLESH PCI/O -

0'37 UC/G.(ORY UEIGKT)

ALABAHA OGCKET NUo~5 REPORTING PER IOO )981 TYPE AND TOTAL LUHBER OF ANALYSIS GAHHA (GELI) 7 LOMCR LIHIT OF OETECT IONa

~(Q)

ALL INOICATOR LOCATIGNS HEAN (F) b LOCAT10l4 Ml TH HIGH/ST ANhUAL HEAN NAHE HEAN (F)

CONTROL LOCATIOtts HEAN (F)b R AhGLb hurBER OF t:ONROUTINE REPORTEO P Q~A~R~HN S

K-40 8 I-214 F H "214 PB-212 TL-208 NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB 8 ~97(

6 ~ ')9-4 ~ 27(

1~70-4'9(

1 ~ 10-F 12(

1 ~ 02 0040(

Oo40-4/

5) 12'5 5/

5)

F 05 5/

5)

F 05 3/

5) i+17 5)

Oa40 TRH 288'8 TRH 277'8 TRH 277 '8 TR)'88'8 TRH 288 76 9'2(

6+49-6 ~ 40(

6 ~ 40-9 ~ 05(

9 ~ 05-lel7(

1 17-Oa40(

0040 2/

2) 12'5 1/

1) 6'0 1/

1) 9'5 1/

2)

I ~ 17 1/

2) 0 ~ 40 17'I(

1/

2) 17 ll-17'l 2'2(

2/

2) 2'2-3'2 4 71(

2/

2)

F 80-7'3 0 ~ 50(

I/

2)

G ~ 50-0+50 2

VALUES (LLD

~

a.

Nominal Lover Limit of Detection (LLD) as described in Table 3.

b.

Hean and range based upon detectable measurements only.

Fraction of detectable measurements of specified locations is indicated in parentheses (p).

TABLE 26 NAME OF FACILITY BRQVQS FLP~

LOCATION OF FACILITY L IHESTGNE RADIOACTIVITY IN CLAH SHELL PCI/G - 0.037 Bl /G lORY VEIGHT)

ALABAMA COCKET NO+ ~g$~9~4?~

REPORTING PERIOD 1981 TYPE ANO TOTAL NUMBER OF ANALYSIS GAR>A (GELI) 8 K-40 GI-214 91-212 PB-214 PB-212 RA-226 TL-208 AC-228 SR 89 SR 90 LOVER LIMIT OF DETECT I ON a (LLO)

NOT ESTAB 0 ~ 050 0 ~ 100 Oa050 NOT ESTAB 0'50 0 ~ 020 0+060 F 000 1 F 000 ALL ItlDICATOR LOCATIONS MEAN (F)b 8 ANGLb 1 ~ 15(

6/

6) 0 ~ 19-3'2 3 ~ 46(

6/

6)

Os)i-I ~ 57 0'0(

I/

6) 0'0-0'0 0'6(

6/

6) 0 ~ 09-1+05 0.39(

5/

G ~ 09-0 ~ 90 0'8(

6/

6)

Oel)-

i+57 0 F 06(

4/

6) 0'5 F 11 0'1(

3/

6) 0'8 0

6 VALUES <LLO ANALYSIS PERFORHEO 1 ~ 99(

6/

6) 28-2 70 TRH 277'8 TRH 277 '8 TRH 293+7 BFN DISCHARGE TRH 277 '8 TRH 277 98 TRH 277 ~ 98 TRH 293 '

BFN DISCHARGE TRH 288'8 TRH 293 '

BFN DISCHARGE 2'6(

0 ~ 99-0'2(

0+27-0 ~ 20(

0+20 0'3(

Oo21-0 ~ 49(

0009-0 ~ 92(

0 ~27-F 10(

0 09-0'2(

0 32-2'9(

2 ~ 27-2/

2) 3'2 2/

2) 1 57 1/

2) 0420 2/

2) 1~05 2/

2) 0'0 2/

2)

I ~ 57 2/

2)

F 11 1/

2) 0 ~ 32 2/

2) 2'0 CONTROL LOCATIONS MEAN (F)

RAPGEb 0'6(

0 ~ 22-0'5(

0 ~ 27" 0'6(

Oa40-0 ~ 13(

0 ~ ll-0 ~ 53(

0 ~ 53-2 VALUES 2/

2) 0'0 2/

2)

Oo44 2/

2) 0 F 52 2/

2)

F 14 a

1/

2) 53

<LLO 2 42(

2'1" 2/

2) 2'3 1 13(

2/

2) 0 86-1 ~ 41 0'6(

2/

2) 0'0-0 ~ 52 2

VALUES <LLO NUHBER OF NONROUTINE REPORTED

~HASU~RH NTS a.

Nominal Lower Limit of Detection (LLD) as described in Table 3.

b.

Mean and range based upon detectable measurements only.

Fraction of detectable measurements of specified locations is indicated in parentheses (F).

Figure 11 R ESERVOIR MONITORING NETWORK 51 Elk River N

'ttI/HEELER DAM mile 274.90 mile 277.98 Rogersville 0

mile 282.6 rnite 29l.76 Athens

~mile 2852 B.F. NUCLEAR PLANT 8

Champion Paper Co, 0

Cour tland ife Z88.78 mite 293.50 mite 295.70 mile 306.0 Decatur

~ - Automatic Sam ler rnite 307.52 Scale of Miles

Figure 12 no cln il o lJ Jl N -~

l M o

JJ W e 0 V I n 0

~ 0 Preoperational Phase Operational Phase keeu AvaeGE 6ROSS SETA ACTIVITY IN SURFACE tlATER IhOWS FaeV NOCI.EAR Purr hverage:

Preoperational Phase 1968 1969 1970 1971 1972 1973P 19730 1974 1975 1976 1977 1 78 1 79 1980 1 81

53 ualit Control A quality control program has been established with the Alabama Department of Public Health Environmental Health Administration Laboratory and the Eastern Environmental Radiation Facility, Environmental Protection Agency, Montgomery, Alabama.

Samples of air, water, milk, and vegetation collected around BFN are forwarded to these laboratories for analysis, and results are exchanged for comparison.

Data measured at the control stations for each medium were averaged for each sampling period~

In order to describe the distribution of control station data, a mean, standard deviation, and 3-sigma liiits were calculated.

We can expect that background concentrations would be distributed within these limits.

This prov'ides us the basis for comparing control and.indicator data.

If the indicator data fall within the limits defined for control data, we conclude that the indicator data were not significantly affected by the nuclear plant. If the data do not fall within the limits, we will perform further analyses to determine if the difference is attributable to the nuclear plant.

Conclusions A vast majority of the indicator station data was found to be within the distribution defined by the control station data.

The data analysis software identified concentrations slightly exceeding the limits of the control station data for a small number of radionuclides in samples from indicator stations.

Many of these values may be discounted because the error reported by the analysis program was greater than the calculated concentration.

The remaining isolated elevated concentrations may be the result of fallout, fluctuations in the existing environment, computer program artifacts, or analytical errors.

The same type of isolated high values occurred in the control station data and may be attributed to the same sources.

Increased levels of radioactivity were observed in rainwater, air particulates, heavy particle fallout, and in vegetation in the winter and spring following the atmospheric nuclear weapons testing conducted by the Republic of China in mid-October 1980.

This increase was seen in control stations as well as indicator stations.

The primary radioisotopes identified in the atmospheric media were S Zr,

.Nb S I,

~Bi, and O Ru.

Dose estimates were made from concentrations of radioactivity found in samples of environmental media.

Media sampled include, but are not limited to, air, milk, meat, vegetation, drinking water, and fish.

Doses estimated for persons at the indicator locations were essentially identical to those determined for persons at control locations.

Greater than 99 percent of those doses were contributed by the naturally occurring radionuclid'e potassium-40,

54 and by strontium-90 and cesium-137 which are long-lived radioisotopes found in fallout from nuclear weapon testing.

It is concluded from the above analysis of the data and from the trend plots presented earlier that there were no measurable increases in environmental radioactivity attributable to the operation of BFN.

ENVIRONMENTAL RADIOACTIVITYLEVELS BROWNS FERRY NUCLEAR PLANT ANNUAL REPORT - 1982 TVA/POWER/RHS April 1983

CONTENTS List of,Tables

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

111 List of Figures.

~

~

~

~

~

~

~

~

~

~

~

~

~

~

~

iv Introduction Atmospheric Monitoring Terrestrial Monitoring Reservoir Monitoring Quality Control.

~

~

~

~

~

~

~

~

0

~

~

~

~

~

~

~

~

~

~

0

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23 41 53 Data Analysis.

~

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53 Conclusions.

~

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53

l'

LIST OF TABLES Tab'le 1

Table 2

Table 3

Table 4

Table 5

Table 6

Table 7

Table 8

Table 9

Table 10 Table.ll Table 12 Table 13 Table 14 Table 15 Table 16 Table 17 Table 18 Table 19 Table 20 Table 21 Table 22 Table 23 Table 24 Table 25 Table 26 Table 27

'Table 28 le Environmental Radioactivity Sampling Schedule Atmospheric and Terrestrial Monitoring Station Locations - Browns Ferry Nuclear Plant Detection Capabilities for Environmental Samp Analysis Results Obtained in Interlaboratory Comparison Program.

Maximum Permissible Concentrations for Nonoccupational Exposure Radioactivity in Air Filter Radioactivity in Rainwater.

Radioactivity in Heavy Particle Fallout Radioactivity in Charcoal Filters Radioactivity in Milk Radioactivity in Vegetation Radioactivity in Soil Radioactivity in Well Water Radioactivity in Public Water Supply.

Environmental Gamma Radiation Levels Radioactivity in Corn Radioactivity in Green Beans.

Radioactivity in Potatoes Radioactivity in Tomatoes Radioactivity in Turnip Greens Sampling Schedule - Reservoir Monitoring Radioactivity in Surface Water.

Radioactivity in White Crappie (Flesh).

Radioactivity in Smallmouth Buffalo (Flesh)

Radioactivity in Smallmouth Buffalo (Whole)

Radioactivity in Sediment Radioactivity in Clam Flesh Radioactivity in Clam Shell

~

~

~

~

~

~ ~

~

~

3 4

.5 13 14 15 16 17 26 27 28 29 30 31 32 33

~

34 35 36 43 44 45 46 47 48 49 50

N R

A C

h E

LIST OF FIGURES Figure l

- Tennessee Valley Region Figure 2

- Atmospheric and Terrestrial Monitoring Network.

Figure 3'

Local Monitoring Stations 10 18 19 Figure 4

Figure 5

TLD Locations, BFN Annual Average Gross Beta Activity in Air Filters, Browns Ferry Nuclear Plant 20 21 Figure 6-Annual Average Gross Beta Activity in Drinking Water, Browns Ferry Nuclear Plant 37 Figure 7-Dire'ct Radiation Levels, BFN Figure 8 -

Direct Radiation Levels, BFN (4-Quarter Moving Average) 38 38 Figure 9-Direct Radiation Levels, WBN 39 Figure 10 - Direct Radiation Levels, WBN (4-Quarter Moving Average) 39 Figure 11 - Reservoir Monitoring Network 51 Figure 12 - Annual Average Gross Beta Activity in Surface Water 52

ENVIRONMENTAL RADIOACTIVITYLEVELS BROWNS FERRY NUCLEAR PLANT ANNUAL.REPORT 1982 1ntroduction The Browns Ferry Nuclear Plant (BFN), operated by the Tennessee Valley'uthority, is located on a site owned by TVA containing 840 acres of land in Limestone

County, Alabama, bounded on the west and south by Wheeler Reservoir (see figure 1).

The site is 10 miles southwest of Athens,

Alabama, and 10 miles northwest of Decatur, Alabama.

Th'e plant consists of three boiling water reactors; each unit is rated at 3,293.MWt and 1,098 MWe..

Unit 1 achieved criticality on August 17,

1973, and began commercial operation on

.August 1, 1974.,

Unit '2 began commercial operation on March 1, 1975.

However, a fire in the. cable trays on March 22, 1975, "forced the shutdown of, both reactors.

Units 1'nd 2 resumed operation and Unit 3 began testing in August 1976.

Unit 3 began commercial operation in January 1977.

I The preoperational environmental monitoring program established a

baseline of data on. the distribution of natural and manmade radioactivity in the environment near the plant site.

However, seasonal,

yearly, and random variations in the data were'observed.

fn order to determine the potential increases in environmental radio ictivit.y levels caused by the plant, com-parisons were made between data for indicator stations (those near the plant) and control stations (those remote 'from the plant) in conjun'ction w'ith com-parisons with preoperational data.

.The Radiological Health Staff (Office of Power) and the Office of

~ Natural Resources carried out, the sampling program outlined in tables 1 and 21.

Sampling locations are, shown in figures 2, 3, 4, and 11, and'able.2 describes the locations of the atmospheric and terrestrial monitoring stations.

All the radiochemical and instrumental analyses were conducted in TVA's Western Area

, Radiological Laboratory (WARL) located at'uscle

Shoals, Alabama, and Eastern Area Radiological. Laboratory (EARL) 'at Vonore, Tennessee.

Alpha and beta analyses were performed on Beckman Low Beta II and Beckman Wide Beta II low background proportional counters.

Nuclear Data (ND) Model 100 multichannel analyzer systems employing sodium iodide NaI(Tl) detectors and ND Model 4420 systems in conjunction with Germanium Ge(Li) detection systems were used to an'alyze the samples for specific gamma-emitting radionuclides.

Samples of water, vegetation, air particulates, food crops, and charcoal (specific analysis for I-131) are routinely counted with NaI(Tl) detection systems.

If significant concentrations of radioisotopes are identified, or if there is a

reasonable expectation of increased radioactivity levels (such as during periods of increased fallout), these samples are counted on the Ge(Li) system.

Identification of gamma-emitting radionuclides in all other types of samples

is routinely performed by analysis on the Ge(Li) system.

A TVA fabricated betq-gamma coincidence counting system is utilized for the determination of I-131 concentrations in milk.

Data were entered in computer storage for processing specific to'he analyst.s conducted.

A computer, employing an ALPHA-M least squares-

code, using multimatrix techniques, was used to estimate the activities of the gamma-emitting nuclides analyzed by NaI(T1).

The data obtained by Ge(Li) detectors were resolved by the appropriate analyzer software and the metric minimization routine HYPERMET.

The detection capabilities for environmental sample analyses, given as the nominal lower limits of detection (LLD) are listed in table 3.

Samples processed by NaI(Tl) gamma spectroscopy were analyzed for 14 specific gamma-emitting radionuclides.and radionuclide combinations For these

analyses, a

radionuclide combinations such as 'u and sZr-Nb are analyzed as one radionuclide.

All photopeaks found in Ge(Li) spectra. were identified and quantified.

Many of the isotopes identified by Ge(Li) spectral analysis are naturally occurring or naturally produced radioisotopes, such as

.Be,

, K,

.Bi, Bi, Pb, Pb, Ra, etc.

TLDs for the analysis of the radio-nuclides listed below are given in table 3B.

LLDs for additional radio-nuclides identified b'y Ge(L;),.an~>ysis were calculated for each analysis and nominal values are listed in the appropriate data tables.

In the instance where an LLD has not been established, an LLD value of zero was assumed.

A notation in a table of ".

values

<LJ,I)" for an isotope with no established LLD does not imply a value less than 0; rather it indicates that the isotope was not identified in that specific group of samples.

For each sample -type, only the radionuclides f'or which values greater than the LLD were reported are.

listed in the data tables.

TVA's Radioanalytical Laboratories participate in the Environmental Radioactivity Laboratory Intercomparison Studies-Program conducted by EPA-Las Vegas.

This program provides periodic cross-check samples of the type and radionuclide composition normally analyzed in an environmental monitoring program.

Routine sample handling and analysis, procedures were employed in the evaluation of these samples.

The results received during calendar year. 1982 are shown in table 4.

The +3v limits based on one measurement were divided by the square root of 3 to correct for triplicate determinations.

a The following radionuclides and radionuclide combinations are quantified by the, ALPHA-M least-squares computer code:

'e; Cr; I; 'u; Cs a Cs, 5Zr-Nb~

ssCo; 54Mn; 65Zn; 59Fe; 60Co; 40K; and i40Ba-La.

Station Location Muscle Shoals Table 1

EhVIROhHENTAL RADIOACTIVITYSAMPLING SGHEDULE Air Charcoal Rain-Heavy Particle River 'ell 'Public Aquatic Life F'tter Filter

<< ter Fallout do i V~eetati a.'Hilk Water litter '<< ter aad dediueat'ooda A

Lawrenceburg W

W M

H

~

A Rogersville Athens Decatur Courtland Site 1

N Site 2 NNE Site 3

(EhE W

W H

M A

H H

A W

W H

M A

W W

M H

A W

W H

H A

W H

H A

W M

H A

Site NNW W

H H

A Site 5

(WSW)

Farm B

Farm S

Farm P

Farm L Control Farms Onsite Well Wheeler Dam Elk River-Tennessee River Champion Paper'Co.

Various Local Farms W

W H

H A

Q

~

W Q

W

.Q W

W - Weekly H - Honthly (every 4 weeks)

Q - Quarterly S - Semiannually A -'nnually

4 Table,2 t

Atmospheric and Terrestrial Monitoring. Station Locations.

Browns,.Ferry Nuclear Plant Approximate Distance and Direction from Plant LM-.l BF, North LM-..2 'BF, North-Northeast LM-3 <<BF, East-Northeast LM-.4"BF, North-,Northwest LH-.S IBF,, West-Southwest PM-1~>BF, 'Rogersville, AL 1.0 Mile (1.6 kilometers)

N 0.9 Mile 1.0 Mile

~ 1.7 Miles 2.5 Miles (1.4 kilometers)

NNE (1.4'kilometers),

ENE (2.7 kilometers)

NNW (4.0 kilometers)

WSW 13.8 Miles (22.2.kilometers)

'NWi PM-2 <BF, Athens, AL, PM-3 ~BF, Decatur (Trinit'y),

PM-4 BF, Courtl'and, AL RM-1,BF, Muscle Shoals,,:AL (Control)

RM-2 'BF, Lawrenceburg, TN-

-'Control) 10.9 Miles AL '.2 Miles 10.5 Miles

'32.0 Miles 40.5 Miles (17.5 kilometers)

NE (13.2 kilometers)

SSE (16.9 ki'lometers)

WSW (51.5 kilome'ter's)

W 4

(65.2 kilometers)

NNW Farm S

4.75 Miles (7.6 kilometers)

'N Farm'B 7.0 Miles",

(11.3 kilometers)

NNW Farm 'L Farm T (Out of business,

, after, 1/18/82)

"'a rm'.'P Farm N (Control)

Farm J.(Control)

Farm C (Con'trol)

Farm Ca (Cont.rol)

, 5.0 Miles 7.0 Miles 8.'8"Miles 27: 0* Hiles

',40.0 Miles

.32.0 Hil'es 32.0 >tiles (7:0 'ilometers)

NE (11.3'flometers)

ENE

,i (14.'1 kilometers)

E (43.4 kilometers)

NW (64.4 kil'ometers)

NNW (51..5 kilometers)

N (51..5 kilometers)

W

Table 3

DETECTION CAPABILITIES FOR ENVIRONMENl'AL SAMPLE ANALYSIS A.

S ecific Anal ses NOMINAL LONER LIMIT OF DETECTION LLD

• Air Particulates Charcoal

~ct/

~ct/

Fallout Mater Ct/k

~ct t Vegetation and grain

~dt/

dr Soil and Sediment

~dt/

. dr

Pish, clam flesh,

plankton, Clam shells

~Ct/

d

~ct/

d

Foods, meat,

poultry, Milk PCi/k~gt

~Ci/I Total a Gross a Cross B

H 1311 0SS sOSr

0. 005

0. 01 0.005 0.001 0.02 0.05 0.4 2.0 2 '

330 10 2

0.01 0.05 0.20 0.25 0.05 0.35 0.70 1.5 0.3 0.1 0.1 0.5 0.1 0.7 0.7 5.0 1.0 1.5 25 40 8

0.5 10 2

• AllLLD values for isotopic separations are calculated by the method developed by Pasternack and Harley as described in HASL-300.

Factors such as sample size, decay time, chemical yield, and counting efficiency nay vary for a given sample; these variations may change the LLD value for rhe given sample, The assumption is made tha't all samples ale analyzed within one week of the collection date.

Conversion factors:

1 pCi 3.7 x 10 Bq; 1 mCi ~ 3.7 x 10. Bq.

Table 3

DETECTION CAPABILITIES FOR E.'>VIRONMENTAL SAMPLE ANALYSIS B.

Ca~ Anal ses NOMINAL LOVER LIMIT OF DETECTION {LLD Soil and sediment

~CI/

dr Clam flesh Fish and plankton

~CS/

dr

~nl dr Vater and milk

~C1/1 Air particulates

~ct/e Vegetation and grain

~Ct/ 'r Clam shells

~ct/

dr Fat* ~ce Ll. **

Lai ~CLI) ital

~ce Lt N I Ce(LI)

P*i.CALI)

Fel

~ce Lt N I C~LI Foods, (tomatoes

potatoes, etc.)

Ci/

wet Na I C~eLi Meat"'n

,) ~"

poultry,

~ct/ I Nai Ge{lil 161> 166Ce 1

4{

"Cr 1311 103 ~ 306R 106R 136CS 1 33CS ssZr-bb 332?

ssgb "Co Mn 6 sZn "Co K

Ba-La 3 >cog 160La

0. 03 0.02

'.07

0. 03 0.01 0.01 0.04

0. 03-0.01 0.02 0.01 0.01 0.01 0.01 0.01 0.02 0.01

'0.02 0.01 0.02 0.01 0.01 0.01

- 0.10

0. 02

0. 02

0. 01 38 33

, 60 44 15 8

40 40 26 5

10 10 10 10 5

15 5

10 5

15 9

10 5

150 15 25 7

0.55 0.22 1.10 0.47 0.35. 0.09 0.65 0.51 0.20 0.33 0.20. 0.06 0.20 0.11 0.05 0.23 0.05 0.20 0.05 0.25 0.11

0. 17

0. 06 2.50 0.68 0.34 0.08

• e 0.35 '.06 0.60r 0.10 0;20 0.02 0.45 0.11 0.12 0.08 0.12

. 0.02-0.12 0.03 0.01 0.20 0.01 0.15 0.01 0.23 0,02 0.11 0.01 0.90 0.15 0,07 0;02 0.35 0.60 0.20 0.45 0.12 0:12 0.12

0. 20 0.15 0.23

0. 11 0.90 0.15 0.06 0.10 0.02 0.11 0.08

~

0.02

0. 03 0.01 0.01 0.01 0.02

0. 01 0.07 0.02 0.35, 0:56 0.07 0. 7I4 0. 4 8 0. 08 0.15 0.07 0.07 0.08 0.17 0.08 0.30 0.10 0.35

, 0.60 0.20

0. 45 0.12 0.12 0.12 0.20 0.15 0.23 0.11 0.90 0.15

0. 06.

0. 10

0. 02 0.11 0.08 0.02

0. 03

0. 01

0. 01 0.01 0.02 0.01 0.07 0.02 38 60 15 40 10 10 10 15 10 15 10 150 15 40 26 40 5

40 40 10 20 5

15 15 15 20 15 90 50 15 5

55 5

40 9

70 5

30 400 50 25 7

50 15 90 33, 40 44'00 90 8

50 20 150

• The NaI(TI) LLD values are calculated by the method developed by Pasternack and Harley as described in HASL-300 and Nucl. Instr. Methods 91, 533-40 (1971).

These LLD values are expected to vary depending on the activities of the components in the samples.

These figures do not represent the LLD values achievable on a given sample.

Vater is counted in a 3.5-L Marinelli beaker.

Vegetation, fish, soil, and sediment are counted in a 1-pint container as dry weight.

The average dry weight is 120 grams for vegetation and 400-500 grams for soil sediment and fish. Meat and poultry are counted in a 1-pint container as dry weight, then corrected to wet weight using an average moisture content of 70X.

'Average dry weight is 250 grams.

Air particulates are counted in a well crystal.

The counting system consists of a multichannel analyzer and either a 4" x 4" sol.id or 4" x 5" well NaI(T1) crystal.

The co~nting time is'4000 seconds.

All calculations are performed by the least-squares computer program ALPHA-M.

The assumption is made that all samples are analyzed within one week o! the collection date.

0+The Ge(Li) LI.D values are calculated by the method developed by Pasternack and Harley as described in HASL-300.

These LLD values are expected to vary depending on the activities of the components in the samples.

These figures do not represent the LLD values" achievable on given samples.

Vates is counted in eithel' 0;5-L or 3.5-L Marinelli beaker.

Solid samples such as soil, sediment, and clam shells are counted in a 0.5-L Marinelli beaker -as dry weight.

The average dry weight is 400-500 grams.

Air filters and very small volume samples are counted in petrie dishes centered on"'the 'detectoi endcap.

The. counting system consists, of a hT3<<4420 multichannel analyzer and either a 25X, 14X, 16X, or 29X Ge(Li) detector.;he counting time is normally 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

All sPectral anal'ysis is Performed using the software Provided with the ND-4420.

The assumption is made that all samples are analyzed within one week of the collection date.

Conversion factors 1 pCi 3.7 x 10 Bq.

Table 4 Results Obtained in.Interlabora'tory Comparison Program A.

Air Filter (pCi/filter)

Gross Al ha Gross Beta Strontium-90 Cesium-137 Date EPA value TVA AVG.

(a3u)

WARL EARL EPA value TVA AVG.

(+3o)

WARL EARL EPA value TVA AVG.

(+3o)

WARL EARL EPA value

(+3o)

TVA AVG.

WARL EARL 3/82 9/82 27+12 32+14 23 28 28 28 55+9 67+9 63 56 57 52 16+2.6 16 15 20+2. 6 17 'g14 g 23+9 27+9 24 24 22 22 Date B.

Tritium in Urine (pCi/L)

EPA Value (~3a)

TVA AVERAGE 5/82 12/82 1300+575 3830+641 WARL EARL 1793 1650 3510 4023

l Table 4 (Continued).

Results Obtained in Interlaboratory Comparison Program C. Radiochemical Analysis of Water (pCi/L)

Gross

=

.- EPA.value G ee

~3a'1/82 24i10 2/82 3/82 1949 4/82 5/82 27.5~12 6/82 7/82

=

16A9 8/82 9/82.

29i13 10/82 11/82 19'9 12/82 Al ha T~VAVG.

WARL EARL Gross Beta EPA value TVA'VG;

~('3a WARL EARL Strontiumt-89'"-"

Strontium - 90 EPA value TVA AVG. 'PA value TVA AVG.

~3e)

I:ARL EARL ~3a MARL EARL 20 19 19 20 27 '38.3 32'9 1969 29'9 F 19 20 26 33 2259 24.

22 13i2.6 11 8

32'6 f

23 9 40 9

ZO 21 38 f

24.5 9

30 21 14.5i2.6 13.8 14.8 19 15 24i9 '2 23 33 28 21 9

20 22 12a2.6 13 12

. Trltiun). ~

Iodine -131 EPA.value TVA

~3a MARL 1820M592 2007 2860+624 2907 1830i589 1620 AVG 1793 EPA value

~3=

6h 2923 62-11 2h 1810 TVA AVG.

'WARL EARL 8.7 7.3 61 61 5.3 3.6 87=15 93 79 2560-'606 2690 2510 1990G598 1943 1993 37=10 37 2890i624 2903 2793 D. Ga( w-Spectral Analysis of Water (pCi/L)

Chromium - 51'obalt 60 Zinc. - 65..

Ruthenium - 106 Cesium 134 Cesium - 137 Date ve1 e

Yl,'A Ava.

Ep'A vel e

lvA Avr..

( 3tl)

'ARL EARL '~3a WARL EARL EPA value ~P~VG.

~3II VARL EARL EPA vel e

~VVA va.

~(~3a WARL EARL EPA value ~~~V EPA value

-3 a WAIIL EIIRL ~3a 4'ARL EARL

.2/82 6/82 10/82 0

23+9 51i9

<44

<".5 2069 21 22 4d

<35 29'9

. 32

'4 55

<35

."n 9 18 21 15i9

~

. 16 16 2649 29 26 24~9 25d 2

20i9 0

30G9

<40

<30

<40

<30 39d

<36 22a9 35'9 19~9 21 19 31 32 19d 17 23 9

25 9

20-'9 24

. 22 24 27 20d 22

Table 4. (Continued)

Results Obtained in Interlaboratory Comparison Program E. Milk (pci/L)

Strontium - 89.

'Strontium '- 90 Iodine - 131

. Cesium

-. 137

'arium 140 Potassium~

Cobalt - 60 EPA value TVA AVG.

EPA el e TVA AVG.

EPA al e TVA AVG.

EPA al e TVA AVG.

EPA alue TVA AVC.

EPA val e TVA AVG.

EPA I e

~TVA VC.

Date ~3a WARL EARL ~(~3e MARL 'EARL ~(3a

~.

MARL EARL

( 3e)

WARL EARL ~3a)

WARL EARL '~3 WARL EARL ~3a)

WARL EARL 4/82 2549 29 28 16~2.6 7/82 10/82 0

<10

<10 18.6~2.6 16 13 5.4t1.4h '.7

.5.1 19.5 12.8 42i10

.43 '2 28f9 31 30 3469 '

. 34)

'IS 0

<29

<15 1500i130 1590 1413 30A6 32 29'

<25. <20

- 15603135 1563 1639 St'rontium - 89 EPA value TVA AVG.

Date ~3a WARL EARL Strontium - 90 F. Foods (pCi/kg, Wet Weight)

Iodine 131 Cesium "137 EPA value TVA AVG.

(=3o)

'ARL EARL EPA value TVA AVG.

EPA value TVA

(-3v)

WAIIL. EARL ~3a WARL Barium AVG.

'EPA value EARL (i3a)

- 140 TVA AVC MARL EARL Potassium EPA value (a3o)

WARL EARL 7/82 2649 30 28 20 11/82 0

<10

<40 27.8=2.6 30.6 24~k 94615 98 25310 20 98 2069 24 29 27+9 28 26 0

27

~

0

<25

<14

<25

<14 2400~208 2810 9 2733 9 2780f242 2670.-

2903' Western Area Radiological Laboratory, Muscle Shoals, Alabama b

Eastern Area Radiological Laboratory, Vonore, Tennessee c

No known explanation.

Investigation underway.

d Analysis completed after report date e

Equipment malfunction, analysis completed after report date f

Poor analysis.

Equipment taken out of service for recalibration.

Further results satisfactory.

Previous and Subsequent resi)lts satisfactory.

Nn known explanation.

e h

NRC/EPA Low-level I study.

i Experimental detection limit is being reviewed.

Potassium values are mg/1 or mg/kg.

k Revie~ of procedure is in progress.

'g (

PADIPCANI' O

S

(

t

+N~

CKSONe

(

/I NEVPMS l

CN LOVISVLLE I

N D.

EVANSVLI.E'ENNESSEE VALLEY-REGION 4.

(TVA NUCLEAR PLANT SITES)

V A

S 8I.N jItUNTSVILLE

,1 w

fOWENSSOIIO K.

E N

T U-C K

Y,

.r I

(

SOWLING GRE EN V ~

)/

..J

/

~/

g gIENi

/

PSN

/

)

/M~~

g NASlHVILL OAK R(DOER L,r I

N N

E I/I

~wH

'L/

(

7

(

SWN J

A I.

CHATTANOOGA~

e'~ J I

S CAR.

MVSCL8

/

M.

I S S.

SHOALS

/

~

I A

L A

J 8

A. M. A G EORG I:A LEGEND

- HARTSVILLE NUCLEAR PLANT

'gg -PHIPPS BEND NUCLEAR PLANT YK!RP CLINCII RIYER BREEDER REACTOR

'.-WATTS BAR NUCLEAR PLAIYT Xg *-SEQUOYAH NUCLEAR PLANT, jKg' BELLEFONTE NUCLEAR PLANT 9E5[ - BROWNS FERRY NUCLEAR PLANT.

'~-- YELLOWCREEK NUCLEAR PLANT

11 Atmos heric Monitorin The atmospheric monitoring network is divided into three groups.

Four local air monitors are located on or adjacent, to the plant site in the general areas of greatest wind frequency.

One additional station is located at the point of maximum predicted offsite concentration of radionuclides based on preoperational meteorological data (see figures 3 and 4).

Four perimeter air monitors are located at distances out to 10 miles from the plant, and two remote ai.r monitors are located at distances out to 45 miles.

These monitoring stations are shown in figure 2:

The remote monitors are used as control or baseline stations.. At each monitor, air is continuously pulled through a

Hollingsworth and,Voss LB5211 glass fiber filter at a flow of 3 fts/min.'n series wi:th, but downstream of, the particulate'ilter is a charcoal filter used 'to co'llect iodine.

Each monitor has a collection tray and sto'rage container to obtain rainwater on a continuous basis and a horizontal platform that.is covered with gummed acetate to catch'nd hold heavy particle fallout.

Thermoluminescent dosimeters are used to record gamma radiation levels at each remote and perimeter station.

Each 'of the local air monitors is fitted with a GM tube that con-tinuously. scans the particulate filter.

The disintegration rate of the atmospheric radioactivity is continuously recorded at each station and radio-telemetered into the plant.

Air filters are collected weekly and a'nalyzed for gross beta activ-ity;

. No analyses are performed until three days after sample collection.

The

. samples are'omposited monthly for analysis of specific gamma-emitting radio-nuclides and, quarterly for Sr and Sr analysis.

The results are combined for each station to obtain an annual average.

During this reporting period, one sample,was not obta'ined,because of equipment malfunction.

These data are presented in table 6.

The annual averages of the gross beta activity in the air particulate filters at the indicator stations (local and perimeter monitors) and at the control stati,ons (remot'e monitors) for the years 1968-1982 are prese'nted in figure 5..

Increased levels due to fallout from atmospheric nuclear weapons

'testing are evident, especially in 1969,

1970, 1971,

1977, 1978, and 1981.

These patterns are consistent with data from monitoring programs conducted by.

TUA at nonoperating nuclear power plant construction sites.

Table 5 presents the maximum'permissible concentrations (MPC) specified in 10 QFR 20 for non-occupational exposure.

Rainwater is collected monthly and a 3.5-liter sample analyzed for specific gamma-emitting radioisotopes and'ritium.

The results are shown in table 7.

'The gummed acetate that is used to collect heavy particle fallout is changed monthly.

The samples are ashed and counted for gross beta activity.

The results are given in table 8, Thirteen samples were los't, destroyed, or damaged and analysis was not performed..

12 Charcoal filters are collected and analyzed for radioiodine.

The filter is counted in a single channel analyzer system.

The results are.shown in table 9.

During this,reporting period, three samples were not taken because of equipment malfunction or filter damage.

~

~

I Table 5

MAXIMUMPERMISSIBLE CONCENTRATIONS FOR NONOCCUPATIONAL EXPOSURE Alpha I

Nopvolatile bq)a Tritium

'"cs

) 03'06R

]44C

",Zr-"Nb 140/a 140La k 3) I 65ZQ

'"Mn

",Co

""Sr "Sr.

"Cr

]34(s SSG In Water

~Ci/1*

30 3,000 3,000,000 20,000 10,000 10,000 60,000 20,000 300 100,000 100,000 30,000 3,000 300 2,000,000 9,000 90,000 In Air

~Ci/m +

100 200,000 500 200 200 1,000 1,000 100

.2,000 1,000 300 300 30 80,000 400

',000

>1 pCi ~ 3,7 q 10 Q~.

TABLE 6 TYPE ANO TOTAL NUMBER

. OF ANALYSIS PfR F 0 R II E D GROSS ALPHA 51 GROSS BETA 571 GAHHA (NAI) 83

-CE-1 41 y 144 K-40'E-59 I-131 BE-7 LOVER LIMIT OF DETECTION CLLD) 0 '05 0 '10 0+ 030 0 ~ 100 NOT ESTAB 0 ~ 010 NOT ESTAB ALL INDICATOR LOCATIONS MEAN (F)

RANGE 0'2( 426/ 468) 0 01-0'4 0'5(

2/

67) 0'4-0'5

~

67 VALUES-<LLD 0 F 00(

6/

67) 0 00-ONOG 0'2(

4/

67) 0 F 01-'

'2 0 F 07(

67/

67) 0 F 01-0'0 NAHE OF FACILITY BROVNS ~FRRY LOCATION OF FACILITY

$$H~S~TNf, R'AOIOACTIVITY IN AIR FILTER PCI!H(3) -

0'37 BO/H(3)

~AA Akll T

N HATH HIGH~AT. AHH~UL II ANN NAHE

- 'EAN (f.)

0'2(

47/

'52) 0 F 01-.

0 F 04 DECATUR'L 8'

MILES SSE LH2 BF NORTH 0 ~ 9 MILE Nt(E DECATUBU AL 8;2 HIiES SSE DECATUR'L 8'

MILES SSE ATHENSU AL 10 ~ 9 I ILES NE 0'5(

1/

7) 0'5-'

F 05 0 F 00(

0 ~ GO-D 0202(

0 ~ 02-0 ~ 08(

0 ~05-'/

8) 0 F 00 1'/ ~ '

)

OR 02 8/'c 8) 0'0 16 VALUES <LLD 0'2(

1/

16)

GN12-0'2 16 VALUES <LLO 16 VALUES <LLO 0'7(

15/.16) 0 '5-Gall DOCKET.NOe~2~59

~660'96 REPORTING PERIOD 198g - -.

~ A CONTROL NUMBER OF LOCATION)

R

- JIONROUTINE HEAN (F)

REPORTED RANGE HEASUREHf NTS 0 ~ 01 (-

1/

"'51 )

0 ~ 01-0 ~ 01 0 F 02(

96/ 103) 0 F 01=

0'4

\\

Ic A ~

8 I-214 PB 214 P.B-212 RA-226 BE-7 TL-208 AC-228 SR 89 SR 90 44 44 GAHHA (GELI) 60 K-40 NOT ESTAB 0 ~ 020

~

0 ~ 020 NOT ESTAB NOT ESTAB 0 ~ 050 NOT ESTAB NOT ESTAB 0 '05 0@001 0'2(

32/

50) 0 F 00" 0 F 04 F 05(

3/

50) 0 04 0 F 05 0 F 04(

3/

50) 0'3-ON04 0 F 00( - 26/

50) 0.00-0.00 ON02(

5/

50) 0 F 00-

0 F 04 0 F 06(

20/

50) 0 ~ 05-0 ~ 07 0 F 00(

15/'0) 0 F 00-0 ~ GG 0 F 01(

2/

50) 0 F 00-0 F 01 36 VALUES <LLD ANALYSIS PERFORHED

, 36 VAI.UES <LLD ANALYSIS PERFORHED LH4 BF TRAILER P

1.7 MILES t)NV ROGERSVILLE ~

AL 13 ~ 8 HILES NV ROGERSVILLE ~

AL 13 8

r. ILES'il DECATUR'L 8 ~ 2 MILES SSE COURTLANDy AL 10 ~ 5 H ILES VSV LH5 BF DAVIS F 2 ~ 5 MILES VSV LH4 BF TRAILER P

1 ~ 7 MILES NIVV ATHENSU AL 10 ~ 9 'l'ILES NE 0 F 02(

0 ~ 02-0'5(

0 ~ 05-0 04(

" 0'4 0 F 00(

.0 ~ 00-ON04(

0 ~ 04-0'7(

0 ~ 07-0 F 00(

0 ~ 00-

~ 0'1(

0 F 01 3/

5) 0 ~ 04 1/

7) 0 05

1/

~

g) 0'4 2/

5) 0 F 00 1/

5) 0'4 1/

5) 0 F 07 1/

5),

0 F 00 1/.

5) 0 F 01 0'2(

8/

10) 0.00-0.03 0 '3C 1/

1G) 0 03-0'3 10 VALUES <LLO 0 F 00(

4/

10) 0 F 00-0'2 10 VALUES <LLO G ~ 06(

S/

10) 0'5 0'0 G ~ 00(

5/

10) 0 F 00-0 F 00 10 VALUES <LLO 8

VALUES <LLD

'I

8. VALUES <LLD a.

Nominal Lover Limit of Detection (LLD) as described in Table 3.

b.

Mean and range based upon detectable measurements only.

Fraction of detectable measurements at specified locations is indicated, in pazentheses (F).

TABLE 7

RADIOACTIVITY IN RAINVATER NAHE OF FACILITY BROVNS. FERRY LOCATION OF FACILITY~Q~~Q~'C I/L -

Oo 037 BQ/L.

~AAMg COCKET 00 00-2~59 260 290 REPORTING PERIOD~98~

TYPE ANO TOTAL NUMBER OF ANALYSIS

~PRFORIIEO GAHNA (NAI )

119 FE-59 BE-7 LOVER LI NIT OF DETECTION

~(f,D)

NOT ESTAB NOT ESTAB ALL INDICATOR LOCA/TONS HEAN (f)

RANGE 2 ~ 76(

14/

97) 0'0-

.5'0 36 ~ 64 (

54/

97) lo70-71 'O LH3 BF NORTHEAST loO,MILE ENE LH5 BF DAVIS F

2 ~ 5 MILES VSV 4'5(

. 4 ~ 40-45'1(

30o00-2/

10)

F 50 7/

10) 66'0 CO~CAT 0 IIITH HIGHEST AHIIOAE~II Ag NANE HEAN (F)

DISTANCE AtlD DIRECT'ION RANGE CONTROL L'OCATION)

MEAN (F)

RANGE 5'5(

4/

22) 0'0-50 45'5(

14/. 22) 15990-.

84'0 NUMBER OF NONROUTINE REPORTED HEASURENENTS GAHNA (GELI )

24 K-40 8 I-214 PB-212 BE-7 AC-228 TRITIUH 143 NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB 15 F 000 330 ~ OGO F 05(

2/

20) 1'8-6'1 0'1(

1/

20) 0'1-Oo31 3'8(

12/

20) 0' 24 7'1 53o42(

3/

20) 31 55-75'6 17%90(

1/

20) 17'0-17'0 117 VALUES <LLO ANALYSIS PERFORHED ROGERSVILLEO AL 13' NILES NV ROGERSVILLE ~

AL 13 ~ 8 MILES t(V LH2 BF NORTH 0'

MILE Nt)E ROGERSVILLEe AL 13 ~ 8 N ILES t(V LH3 BF NORTHEAST 1 ~ C HILE ENE 6'1(

6 ~ 71-0'1(

0 31-7'1(

7 ~ 31-75'6(

75936-17990(

17'0 1/

2) 6'1 1/

2) 0'1 1/

1) 7'1 1/

2) 75 36 1/

3) 17'0 1 ~ 76(

1/

4) 1 '6-1'6 4

VALUES <LLD

'2 ~ 36 (

2/

4) 2'1-2'1 VALUES <LLO 4

VALUES <LLO 26 VALUES <LLD a.

Nominal Lover Limit of Detection O.LD} as described in TAble 3.

b.

Mean and range based upon 'detectable measurements

only, Fraction of detectable measurements at specified locations is indicated in parentheses.

(F}.

-TABLE 8 RADIOACTIVITY IN HEAVY PARTICLE FALLOUT NAHE OF F'AGILITY BROVNS FLURRY LOCATION OF F ACILITY~~H~STONf, HCI/KH(2) - 37000000

~ 00 80/KH(2)

ALABAHA DOCKET NO ~ 50-~2A 2~0 REPORTING PERIOD 1902 TYPE AND TOTAL NUHBER OF ANALYSIS EQKQE5Q?

GROSS BETA 130 0 ~ 050 0'1( 107/

10T) 0'5-0'4, LONER LIHIT-'LL OF INDICATOR LOCA'LIONS DETECTION HEAN (F)

~R

~~AT QN VITH H~IGH ST 4~1ttl ll~llE4$

NAME MEAN (F~

COURTLANDo AL 0'1(

12/

12) 10 ~ 5 MILES MSV 0 ~14-, 0 ~ 44 CONTROL LOCATIONS HEAN (()

EANQK 0'0(

23/

23) 0 F 07 0'1 NUMBER OF NONROUTINE REPORTED Hf,~AQ~R~H/S a.

Noainal Lover Liqit of Detection (LLD} as described in Table 3.

b.

Mean and range based upon=detectable ncasurements only.

Fraction of detectable neasurenents at specified locations is indicated in parentheses (p).

NAME OF FACILITY /ROVERS FLURRY LOCATION OF FACILITY -LIMESTONE TABLE 9

. RADIOACTIVITY IN CHARCOAL.FILTERS PC I/H.(3) -

0 ~ 037 'Q/H (3) ll~lI8 AIIA DOCKET REPORT

>0 ~252x2fdlx2~~

ING. PERIOD 19RP TYPE AND TOTAL NUHBER.

OF ANALYSIS

~PR QRMQQ IODINE IN AIR 569 LOMER LIMIT OF DETECTION 0'20 ALL INDICATOR LOCATIONS HEAN (()

RANGE 0'3(

39/.467) 0 02-0'7.

LOCATION UI TH H~GM QT A~NN

/~MAN ROGERSVILLEi AL 0+03(

12/

52) 13 8 HILES NM

=

0 ~ 02-

.,0 ~ 07 CONTROL LOCATIONS HBAN (Fb)b RANGE 0 03(

10/ 102) 0 F 02-0'6 NUHBER OF NON ROUTINE REPORTED a.

Noninal Lower Linit of Detection (LLD) as described in Table 3

b.

Mean and range based upon detectable cteasurenents only.

Fraction of detectable measurements at specified locations is indicated in parentheses (F).

18 Figure 2

ATMOSPHERIC AND TERRESTRIAL MONITORING NETWORK

'RM.28F LAWRENCEBURG yPULASKI FAYETTEVILLE' WILSON FLORENCE FFIEL MUSCLE SHOALS RM-IBF

'TUSCUMBIA g pRUSSELLVILLE PM-IBF WHEELER ROGEPSVILI g OAM C

LEIGHTON

.COURTLANO PM-4 F

ATHENS PM-2BF BROWNS FERRY NUCLEAR PL NT OECAT R

PM 38FD IO MILES HARTSELLE HUNTSVILLE GUNT SVIL OAM HALEYVILLE

~CULLMAN 45 MILES RAINWATER SOIL Q-ENVIRONMENTAL MONITORING STATION NOTE

I THE FOLLOWING SAMPLES ARE COLLECTED 0 FROM EACH STATION:

I AIR PARTICULATES 5 RADIOIODINE

,"HEAVY PARTICLE FALLOUT

Figure 3

'.. LOCAL MONITORING STATIONS BROWNS FERRY NUCLEAR PLANT 19 ATHENS U S HWY 72 ALA. HWY 20 Legend

~

Air Monitor Aufoin'otic Well Sampler H

Dairy Farm DECATUR Scale 0

l,.2 B

0 6

Miles

20 Pigure 4

'(j r+

4 f

'ta

'P

~ 'j"~~ ~'.$ y TLD Locations

~ I I'

j

'if)

/a iV)f f'

)

1 r ro fr

.)Ia~If') j".~'~

>>i tI'II Q)

I

]j f )l ltl

/+(.)

f f

~

l f)I tip' 1

1 I

I I(

I

~ (

I I V n.

)IC I(

gf ')I(4

't~

<<I

, ~

a

~l

~

1

Figure 5

.30

.25 Preoperational Phase I

Operational Phase Amuu AERAGE 6ROSS BETA kTIVITY IN AIR FILTERS HROWS FERRV Noae PueT-

.20

.15 CC0 C

IJ 0 C~

IJ IJ M 0IJ IJ M 0IJ C 0 IJ C

C 0 w CJ Ave~ra e:

Preo~erational Phase

.10

.05 1968 1969 1970 1972 1973P 19730 '974 1975 1976 1977 1978 1979 1980 1981 1 82 1971

23 Terrestrial Monitorin Milk Milk is collected from four larms within a 10-mile radius of the plant (see figure 3),

and from at least one of four control farms.

Raw milk i'nalyzed weekly'or I,

and monthly.for gamma-emitting isotopes and for radiostrontium.

The results are shown in table,10.

Cow censuses were conducted in May and September.1982.

It was determined that there are no dairy farms nearer the plant than the nearest

'arm being-sampled.

During this period however,'ne of the'airy farms being

'sampled (farm T,.table 2) went out of business and all cows were s'old.

~Ve etation

'egetation is sampled quarterly at the farms from which milk is collected and analyzed for gamma-emitting radionuclides.

Approximately 1-2 kilograms of grass is broken or cut at ground level and returned for analysis'.

Efforts are made'o sample vegetati,on that is representative of the-pasturage where cattle graze.

Table-ll gives the results obtained from the laboratory analyses of these samples.

Soil Soil. samples are collected annually near each monitoring station to provide an indicati,on of a long-term buildup of radioactivity in the environ-

ment, An auger or. "cookie cutter" type sampler is used to= obtain samples of the,top, two inches (5 cm) of soil.

These samples are analyzed'or gamma-emitting radionuclides, Sr, and Sr.

The results are given in table 12.

Ground~.Water An automatic sequential-type sampling, device has been installed on a well downgradient from BFN.

A composite sample from this well is analyzed for

.gamma-emitting 'radionuclides monthly and composited quarterly for determination of tritium-.

A grab sample is also taken from a control well upgradient from the plant.

The. results of the analysis of well water are shown in table 13.

Drinkin Water Potable water suppli.es taken from the Tennessee River in the vicinity of BFN are sampled,and analyzed for gross beta and gamma-emitting radionuclides, and composited quarterly for tritium, Sr, and Sr analyses.

The first potable water supply downstream from the plant is equipped with an automatic sampler with samples collected and analyzed weekly.

The sampler is located on the water intake structure and takes the sample from the river as the raw water is drawn j.nto the water treatment facility.

Two addi.tional supplies

24 downstream and one public water supply upstream are sampled by taking monthly grab'samples of treate'd water at user points.

Table 14 indicates the results from the analysis of drinking water samples.

During this reporting period, one of the weekly samples was not taken because of the malfunction of automatic sampling equipment.

Another sample was missed due to inaccessability caused by bad weather.

I e

Figure 6 shows the trends in gross beta activity in drinking water from 1968 through 1982.

The annual average level from the raw water samples tends to run slightly higher than the average for treated water samples;

however, the levels are consistent with the activities reported in surface water samples taken upstream from BFN (figure 12) and in samples taken from the Tennessee River in preoperational monitoring programs conducted by TVA at other sites.

Environmental Gamma Radiation Levels Bulb-type Victoreen manganese-activated

'calcium fluoride (Ca~F:

Mn) thermoluminescent dosimeters (TLDs) are placed at sixteen stations around the plant near the site boundary, at the perimeter and remote air monitors,and at nineteen additional stations out to approximately five miles from the'ite to determine the gamma exposure rates at these locations.

The dosimeters, in energy compensating shields "o correct energy dependence, are placed at approxi-mately one meter above the ground, with three TLDs at each station.

They are annealed and read with a Victoreen model 2810 TLD reader.

The values are corrected for gamma

response, self-irradiation, and fading, with. individual gamma response calibrations and self-irradiation factors determined for each TLD.

The TLDs are exchanged every three months.

The quarterly gamma radiation levels determined from these TLDs are given in table 15, which indicates that average levels at onsite stations are approximately 3-5 mR/quarter higher than levels at offsite stations.

This is consistent with levels reported at TVA's nonoperating nuclear power plant construction sites where the average radiation levels onsite are generally 2-6=mR/quarter higher than levels offsite.

The causes of these differences have not been completely isolated; however, it is postulated that the differences, are probably attributable to combinations of influences, such as -natural variations in environmental radiation levels, earth moving activities onsite, the mass of concrete employed in the con-struction of the plant, and other undetermined influences.

Figure 7 compares plots of the data from the onsite or site boundary stations with those from the offsite stations over the period from 1976 through 1982.

To reduce the variations present in the data sets, a four-quarter moving average was constructed for each set.

Figure 8 presents a trend "plot of the direct radiation levels as defined by the moving averages.

The data

'ollow the same general trend as'he raw data, but the curves are smoothed considerably.

Prior to 1976 measurements were made with less sensitive dosimeters, and consequently the levels reported in the preoperational phase of the moni-toring program are 1-2 times the 'levels reported herein.

Those data are not included in this report.

Therefore, for comparison

purposes, figures 9 and 10 depict the environmental ganuna. radiation levels measured during the construction of TVA's Watts Bar Nuclear Plant to the present.

Note that the data follow a similar pattern to the BFN data and that, as discussed

above, the levels reported at onsite stations are similarly higher than the levels at offsite stations.

25 F~ood Cro o

Food crops raised in the. vicinity of BFN and at control locations are sampled-as they. become available during the growing season, and anal'yzed for gamma-emitting radionuclides.

During this sampling period,. samples of

corn, green beans,. potatoes, turnip greens, and tomatoes were collected and analyzed for speci.'fic gamma-emitting radionuclides.

No sample of turnip greens was taken from a control location.

The results are. given in tables 16, 17, 18, 19, and 20.

TABLE 10 NAHE Of FACILITY RROMNS FERRY LOCATION OF FACILITY LIHEQQONg RADIOACTIVITY IN HiILK PCI/L -

0'3) BQ/L ALABAHA DOCKET NO ~ ~g+9k~xk99i REPORTING PERIOD'982 TYPE

<<ND TOTAL iVUHBEo OF ANALYSIS

~E~F "EQ GAHHA (NA I )

83 CS-137 K-40 I OO IiVE-1 31 916 GAHHA (GELI

)

'- 26 LOVER LIHIT QF.

DETECT ION'I l.Ql 10 F 000 150 F 000 0 ~ 500 ALI INDICATOR LOCATIONS

'.HE AN (g )

RANG/

11 '0(

1/

42) 11'0-llew 10 1306 '2(

42/

42) 684 F 00- 1553o60 212 VALUES <LLO.

ANALYSIS PERFORHED o

PAGE FARH 8 ~ 75 I(ILES E

PAGE FARH 6 ~ 75 HILES E

11 F 10(

ll~ 10-1373 '1(

1156 ~ 80-1/

10) 11'0 10/. 10) 1455'0 DISTANCf~AN ~gRffTION PANGE CONTROL.

NUHBER OF LOCATIONS NONROUT INE HEAN (F ) b REPORTED R ANGP H~AQRQ~HN$$

41 VALUES <LLD 1297 ~ 16(

41/

41) 1036o60-1451o60 204 VALUES <LLO CS-137 K-,I)0 BIo214 PB 214, PB-212 AC-228 SR 89 SR 90 103 103 o

1'0 F 000 2

000 F 000 NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB 6'1(

3/

11)

F 50-7'1 1269 F 10(

11/

11) 747 '1 1499'3 49'9(

2/

11) 38'9-

~ 61'9 41 '5(

2/

11)

?0 '6-61'4 1 ~ 69(

6/ ll)

'."06-4.08 11 VALUES <LLO VALUES <LLO ANALYSIS PERFORHEO

) ~ 3&,(.

49/

53) 2o09-.

10 F 14 PAGE FARH 8

75

.",ILES E

LOONEY FARH 5 ~ 75 ')iILES ENE SHI TH fARH 4 ~ 75'iILES N

SWITCH FARM

'} ~ 75 MILES BROOKS FARP 7

0 QILES NNM SHI TH FAP'5

~

4 ~ 75 HILES N'

'2(

5 ~ 9 3-'354 F 46(

1209 ~ 10-

,49 '9(

38 ~ 2'9-41 '5(

20 ~ 76-2'3/

1 ~ 58 2/

7. ~ 51 2/

2) 1499 F 83 2/

3) 61 '9 2/

3) 61'4 2/

3?

4'8 5'5!

12/

13) 3'6-10'4 9

VALUES <LLD 1256 '7(

9/

9) 1175 '6-1362 '5 9

VALUES <LLD

& ~ 02(

2/

9) 7 "22-8 82 3 ~ 44(

3/

9) li94 5'o 3o03( '/"')

2'5-3'1 50 VALUES.<LLO 3'9(

46/

50) 08-,

9 72 a.

No'nin'al Lower-Liriit of Detection (LLD) as described in Table 3.

b.

Mean and range based upon detectable neasurenents only.'raction of detectable measurements at specified'ocations is indicated in parentheses (F).

i

TABLE RADIOACTIVITY IN VEGETATION i(AHE OF FAC ILITY BRO)JNS FERRY LOCATIO)J OF FACILITY LIMESTONE PCI/G -

0 ~ 037 BQ/G (OR Y )JEIGHT)

ALABAMA DOCKE'T tJOo~50-59A260AQ96 REPORTING PERIOD 19~2 TYPE AND TOTAL NUMBEP OF ANALYSIS

~PR FOR."~

~

~

GROSS BETA 3%

GAH.JA (G=LI) 33 LO)JER L!MI T OF

'E TEC T-I 0 lJ

~a~

0 ~ 200 ALL INDI'CATOR LOCATIONS HEAN (F) b RANGFb 23 82(

17/

17) 3'9-69 '3 Q~OA~TC)N CJI TH ~HGHgST A;JNUAQ MfAN tJAHE

'EAN (F)+

THRASHER FARH 59 ~ 43 (

I/

1) 7 ~ 0 BILES ENE 69'3-6'3'ONTROL LOCATIONS MEAN (F 0 RANGEb 30 '3(

16/

16)

F 80-57'4 NUMBER OF NONROUTINE REPORTED CS-137 K-4 0 8 I-214 BI-212 0 '60 NOT ESTAB 0 F 100 NOT ESTAB 0 ~ 13(

4/

17) 0 F 07-0 ~ 18 14 F 92(

17/

17) 1 ~ 87

't6 ~ 29 0 10(

1/

17) 0 ~ 10-0'0 17 VALUES <LLO

-SMITH FARM 4

75 MILES THRASHER FARM 7 ~ 0 MILES Et(E SMITH FARH 4 ~ 75 MILES N

0 ~ 18(

0 ~ 18-46 46 ~ 29-0+10(

0 ~ 10-I/

4) 0 ~ 18 1/

1) 46+29 1/

4) 0 ~ 10 PB-214 3/

4) 0'3 4/

4) 0 ~ 16 2/

4) 0'0 4/

4) 15'6 I/

1) 0 F 04 1/

1) 1 ~ 15 PB-212 RA 226 BE-7 TL-208 AC 228

'JOT ESTAB 0 ~ 09(

8/

17)

SHITH FAR.'I 0 ~ 12(

0 ~ 01-0 ~ 13 4 ~ 75 MILES N

0 ~ 09-0 ~ 06(

15/

17).

SMITH FARM 0'7(

0 ~ 00-0 ~ 16 4 ~ 75 MILES i'J 0 ~ 00-0 ~ 11(

8/

1?)

PAGE FARH 0 ~ 26(

0 ~ 02-0 ~ 50 8 ~ 75 MILES E

0 ~ 02-tJOT. ESTAB 5 ~ 86(

17/

17)

BROOKS FARM 7'2(

0 ~ 33-

~ 15 ~ 36

?o 0 HILES NN)J 2 ~ 35-.

IJOT ESTAB 0 ~ 02(

11/

17)

TtlRASHER FARM 0 ~ 04(

0 ~ 00-0 ~06,

7) 0. MILES'NE ~

0 ~ 04-0 ~ 17 (

12/

17 )

THP ASHER FARM 1 al5(

0 ~ 02-1 ~ 15

?o0 HILES ENE.

I ~ 15-a.

-Nominal Lower Limit of Detection (LLD) as described in Table 3.

b.

Mean and range based upon detectable measurements only.

Praction of detectable measurements 0 ~ 07(

0 ~ 07-20 AD ?0(

4'5 F 16(

0 ~ 16-0'1(

0 ~31-0 ~ 07(

0 F 00" 0 '6C 0 ~ 02-0 F 07(

0 ~ 01-4'7(

0 ~ 92-0'4(

0 ~ 01-0 '4C 0 ~ 03-3/

16) 0 F 06 15/

16) 46 F 06 1/

16) 0'6 1/

16) 0 ~ 31 8/

15) 0 ~ 18 12/

16) 0 ~ 11.

9/

16) 0'6 15/

16) 8 ~ 8 10/

16) 0'6 8/

16) 0'6 at specified locations is indicated in parentheses (P).

TABLE 12 RADIOACTIVITY IN SOIL NAME OF FACILiTY l)~RQ~QR LOCATION OF FACILITY LIMESTONE PCI/G -

0 ~ 037 80/G Al.ABAMA (DRY MEIGHT)

DDCKET MO ~EEREDEAEEO REPORTIMG PER IOD~19G TYPE AND TOTAL NUHBER OF ANALYSIS EKEEQEEKR GAHMA (GELI)ll LOMER LIMIT ALL OF INDICATOR LOCATIONS DETECT IOtla HEAN (g) o

~LLQ2 RANGE J,OCATION MITH H GH T

ANN NAME D~GTAM ~AM

~RECTIOM RAN//,

CONTROL LOCATION)

HEAN (g)

RANGE NUHBER OF NONROUTINE REPORTED CE-144 CS-137 K-40 HN-54 81-214 8 I-212 PB-214 PB-212 RA-226 RA 223 RA-224 BE"7 TL-208 AC-228

. "PA 234M SR 89, SR 90 0'60 0 ~ 020'

'50 0 F 010 0 F 050 0 F 100 0 ~ 050 NOT ESTAB 0 ~ 050 NOT ESTAB

'OT ESTAB 0 ~ 160 0 ~ 020 0 ~ 060 NOT ESTAB 10500 0'00 9

VALUES <LLD 0'0(

9/

9)

-0 ~ 050 1017 95'2(

9/

9) 3'6- '

'3 0 F 02(

2/

9) 0001-0 ~ 02 0091(

. 9/.

9) 0'055-1 ~ 18, 1 ~ 33('

9/

9)

Oe68-1078 4 ~ 02 (

.9/

9) 0'5 1 ~ 33

~

1 ~ 09(

9/

9) 0 ~ 62-1 ~ 45 0 ~ 91(

9/

9) 0'5-1 ~ 18 0'1(

6/

9) 0 24-

'0, ~ 37 0 ~ 99(

4/

9) 0 ~ 53-

-F 42 9

VA'l.UES <LLO 0 ~36(

9/

9) 0 ~ 20r 0 ~ 45 I F 12(

9/"

9) 0 ~ 60-

~ 51

- '2 F 81(

4/

9) 2 ~44-,

'3 ~ 15 1082'(

1/

9) 1 ~82" 1 ~ 82 9 VALUES <LLD ANALYSIS PERFORMED ATHENS'L 1,0 ~ 9 HILES NE LM4 BF TRAILER P

1 ~ 7 MILES NNM LH5 BF

~ DAVIS F

2 ~ 5 MILES MSM LH4 BF TRAILER I '

~ 7 NILES NNV LN4 BF TRAILER P 1 ~ 7 NILES NNM LH2 BF NORTH 0 ~ 9 HILE hhE LH4 BF TRAILER P 1 ~ 7 MILES tRNM LN4. BF TRAILcR P 1 ~ 'I MILES NNM LH3 BF NORTHEAST 1 ~ 0 HILE ENE LH4 BF TRAILER P 1 ~ 7 tlILES WN'TR LN4 BF TRAILER P 1 ~ 7 MILES t(NM LM4 BF TRAILER P 1 ~ 7 MILES NNV LN5 BF DAVIS F 2 ~5'ILES MSM ATHENSD AL 10 ~ 9 MILES NE 1 ~ 17(

1'017-8'3(

8 ~ 13-0 ~ 02(

0 ~ 02 1 ~ 18(

1'0 18-1 ~ 78(

1 ~ 78-1 ~ 33(

.1 ~ 33-1 ~ 45(

1 ~ 45-1.18 (

1 ~ 18-0 ~ 37(

0 ~ 37 1042(

1 ~ 42-0 ~ 45(

0 ~ 45-F 51(

1 ~ 51-3'5(

3 ~ 15-1 ~ 82(

1 ~82-1/

1) 1 ~ 17 1/

1) 8 ~ 13 1/

1) 0 ~ 02 1/

1)

~

1 g18 1/

1) 1 ~ 78 1/

1) 1 ~ 33 1/

1 I 1 ~ 45 1/

1) 1 ~ 18 1/

1) 0'7 1/

1) 1042 1/

1) 0'5 1/

1) 1 ~ 51-1/

.1)

F 15 1/

1)

, 1 ~ 82 0 ~ 12(

I/

2)

.0 12-0 ~ 12 1 ~ 17(

2/

2) le01-.

1'3 4,57(

"2/

2) 4'7-5'7 2

VALUES <LLD 0 ~ 81(

2/

2) 0 ~ 73-0 ~ 89 1 ~ 03(

2/

2) 0091 1 ~ 15 0'0(

2/

2) 0'3 0'7 0 F 86(

2/

2) 0 F 80 0'2 0'1(

2/

2) 0 ~ 73 0 ~ 89

~ 1 ~ 97(

2/

2) 0'0-3'4 2

VALUES <LLD 0 '1(

2/

2) 0020"..

0'2 6'0(

2/

2) 0'8-0'3 0088(

2/

.2) 0'9

-0'8 1 38(

1/

2) 1038-'

~ 38 2

VALUES <LLO 2

VALUES <LLD a.

)tominal Lover Limit of Detection (LLD) as described in Table 3.

b.

Mean and range based upon detectable measu'rements

only, Fraction of detectable measurements at specified locations is indicated in parentheses (F),

TABLE I3 RADIOACTIVITY IN, MELL MATER PCI /L -

~ 0 ~ 037 80/L NAHE OF FACILITY DROWNS FERRY LOCATION. OF FACILITY~~~TQj

~/~ASH DDOKET NO 59-259 268 296 REPORTING PERIOD"1982 TYPE AND TOTAL NUHBER OF ANALYSIS

~PR

~RH GAHHA (NAI) 19 FE-59 I-131 NOT ESTAB 15 F 000 8

VALUES <LLD 8

VALUES <LLD LOVER LIHIT, ALL OF INDICATOR LOCATIONS DETECTION

HEAN (f)

~(~ )

4 ~ 35(

22990-15+20(

'15 ~ 20-2/

11) 5'0 1/

11) 15'0 CONTROL LOCATIONS HEAN (()

RANGE

.NUMBER CF NONROUTJNE REPORTED HKASQKU~NTS PB-212 TL-208 TRITIUH 8

NOT ESTAB NOT ESTAB 330 F 000 GAHHA (GELI) 7 BI-214

-. 'OT ESTAB 14 ~36(

1/,

5) 14'6-14'6.

1 ~ 58('/

5) 1925-1990 2'5(

2/

5) 1'5-3'6 4

VALUES <LLD ANALYSIS PERFORHED BFN WELL s6 Oa02 HILES V

BFN WELL 06 0

C2 MILES BFN WELL s6 0 ~ 02 HILES V

14'6(

14 ~ 36-1 ~ 58(

1 ~ 25-2'5(

1 ~ 85-1/

5) 14'6 2/

S.)

1 ~ 90 2/

5) 3'6 2

VALUES

<LLD'0

'9(

2/

2) 0978-1 20 2

VALUES <LLD VALUES <LLD a.

Nominal LoEEer Limit of Detection (LLD) as described in Table 3.

b.

Mean and range based upon detectable measurements only.

Fraction of detectable measurements at specified locations is indicated in parentheses (p).

TABLE 14 RADIOACTIVIT'Y IN PUBLIC VATER SUPPLY PCI/L -

0 ~ 037 BQ/L NAIIE OF FACILITY N~ll lt EENTSY DOCKET NO ~

50-259NPQ~O 296 LOCIITION OF FACILITY L~l> STONE ALAPAHA REPORTING PERIOD

~19 2

TYPE ANO

.TOTAL NUHBER OF ANALYSIS PQRFO~RH GROSS BETA 89 GAHHA (NAI )

70 FE-59 LOMER LIHIT OF DETECTION (LLO) 2 ~ 400 NOT ESTAB ALL INDICATOR LOCATIONS HEAN (j)P RANGE

~3'0(

51/

76) 2 42-13'3 3 ~ 85(

6/

62)

I ~ 00-6'0 SHEFFIELONAL ROB TRiH 254 ~ 3 6'0(

6 ~ 6C-1/

11) 6N60 LOCA~I~NO TN NENNEO~TLILINAL ~FAN CHAHPION PAPER 3'3(

42/

-50)

TRH 282' 2'7-13'3 CONTROL LOCATION)

HEAN (F)

RANGE 2'7(

3/

13) 2 F 58-F 17 8

VALUES <LLO NUHBER OF NONROUTINE REPORTED HQQSU~R HAUNTS PB-214 PB-212 TL-208 SR 89 SR 90 16 NOT ESTAB NOT ESTAB NOT ESTAB 10 F 000 2 '60 TRITiUM 16 330 F 000 16 GAHHA.(GELI) 19 K-40 NOT EST AB.

1 ~ 04(

1/

14)

I ~ 04-

~

1 ~ G4 8 ~ 47(

1/

14) 8 ~ 47-8'7 3'8(

, 9/

14)

IN03-4'9 0 ~ 52(

5/

14) 6 ~ 25-.

Oa88 12 VALUES <LLD ANALYSIS PERFORHEO 12 VALUES <LLO ANALYSIS PERFORi".ED 395 05(

2/

12) 37'6-419 '4 CHAHPION PAPER TRH 282 '

CHAHPION PAPER TRH 282 '

MHEELER DAHN AL TRH 274 '

MHEELER DAHN AL TRu 274 '

CHAHPION PAPER TR>> 282 '

1'4(

1 ~ 64 8'7(

8'7 3N98(

3 ~ 98-0'3(

0'3 419 '4(

419 ~ 24-1/

10) 1 ~ 04 1/

10) 8 ~ 47 1/

2) 3'8 1/

2) 0'3 1/

4) 419'4 9'6(

1/

5) 9'6-9'6 5

VALUES <LLO 1 ~ 78(

3/

5) 1 ~32-2'7 1 '9(

2/

5)

ON70-1 ~ 88 4

VALUES <LLD VALUES <LLO 4

VALUES <LLO a.

Nominal Lower Limit of Detection'(LLD) as described in Table 3.

b.

Mean and range based upon detectable me'asurements only.

Fraction of detectable measurements at specified locations is indicated in parentheses (F).

31 Table 15 ENVIRONMENTAL GAMMA RADIATION LEVELS Average External Gamma Radiation Levels at 'Various Distances from Browns Ferry Nuclear Plant for Each Quarter - 1982 mR/quarter Distance miles Avera e External Gamma Radiation Levels b 2nd uarter 1st uarter 4th uarter 0-1.

1-2 2-4 4-6 20,.8

+. 1.1.

N s

18.6 + 2.0 17.9 + 1.7 17.4 + 1.6 17.4 + 2.6 20.3 + 1.7 16.8 + 3.2 16.3 + 1.5 16.1 + 1.4 16.4 + 3.0 21.3 + 1.5 18.1

+ 2.1 17.5 + 1.8 17.6

+ 1.6 17.3

+ 3.3 21.9

+ 1.6 16s3

+

4.0'5.8

+ 3.8 15.5 + 3.6 15.6 + 3.2

Average, 0-2 miles (Onside) 20.3 + 1.6 19.4

+ 2.6 20.5 + 2.1 20.5 + 3.4

Average,

>2 miles (Offsite),

17.6+ 1.9 16.2 + 2.0 '7.5

+ 2.2 15.6 + 3.4 a,'ata normalized to one. quarter (2190 hours0.0253 days <br />0.608 hours <br />0.00362 weeks <br />8.33295e-4 months <br />),

b. All averages reported +la (68 percent confidence level).

TABLE16 NAME OF FACILITY-L)ROMNS-FERRY LOCATION OF FACILITY L IH~STONQ RADIOACTIVITY IN CORN PCI/KG - 00037 BQ/KG (MET )'EIGHT)

ALABAHA OOCIIET NO 52-25~252 295 REPORTING PERIOD 1'982 TYPE ANO TOTAL NUMBER OF 'ANALYSIS P~Rf ~RM GROSS BETA 2

GAMMA (GELI )

2 LOVER LI HIT

,ALL OF

"'NDICATOR LOCATIONS DETECTION MEAN (F )

~IEQ I R~Afjj 25 F 000 3667 '2(

1'/

1) 3667 '2-.

3667 '2 LOCA~7 ON MITM HIGHEST ANNUAL MEAN NAHE MEAN (Fb)

TEIIEENNf ANTI OIRECTIQN

~RlN j 7 HILES NNM 3667 ~ 62(

1/

1) 3667 F 62-3667 '2 CONTROL LOCATION(

MEAN (F )~

~RA N 4983 F 14(

1/

1) 4983 14-4983 14 NUMBER OF NONROUTINE REPORTED HQ~AQ~R~HNJ S K-40 PB-212 TL-208 NOT'ESTAB NOT ESTAB NOT ESTAB 1990 '5(

1990 ~ 35-

.,1- ~ 38 (

1 38-0'3(

0 ~ 03-1/

1) 1990'5 1,/

1 )

1 ~ 38 1/

l) 0'3 7 HILES NNM 7 HILES NN)(

7 MILES NNM 1990 '5(

1990 '5 1038(

1 ~ 38-0'3(

0'3" 1/

1) 2040 '2(

1/

1) 1990 '5 2040 '2-2040 '2 1/

1)

VALUES <LLO 1038 1/

1) 1 VALUES <LLO 0'3 a.

Koninal Lover Linit of Detection (LLD) as described in Table 3.

b.

Mean and range based upon detectable neasurenents only.

Fraction of detectable neasurenents at specified locations is indicated in parentheses (F).

NAME OF FACILITY BROVNS FfRRY LOCATION OF FAGILIT'Y Q~MfSTONf TABLE 17 RADIOACTIVITY IN GREEN BEANS PCI/KG -

0 ~ 037'O/KG (BET WEIGHT)

ALABAHA DOCKET NO ~ ~0-$ ~59 ~20 296 REPORTING PERIOD 1982 TYPE ANO TOTAL NUHBER OF ANALYSIS ZKEQEHfII GROSS BETA 2

GAHHA (GEL I) 2 K-40 PB-212 LO'llER LI HIT OF DETECTION 25.000 NOT ESTAB NOT ESTAB ALL INDICATOR LOCATIONS HEAN ($ )

RPQSf 4257 '1(

1/,

I) 4257 F 41-4257 '1 1900 '0(

1/

I) 1900 '0- 1900'0 I ~ 68(

1/

I>

le68-lo68 7 HILES NNV 7 MILKS NNM 1900 '0(

. 1/

1) 1900i30-1900 '0 1 ~ 68(

1/

1)

I ~ 68-1 ~ 68

$ 034 ~ 02(

1/

1) 2034 ~ 02-2034 ~ 02 4 ~ 08(

1/

1) 4 ~ 08-4 ~ 08 CONTROL J,ORAT~ON VITM HI'GHEST ANNUAL MEAN LOCATIONS NAME

MEAN (g

'EAN (,F) 7 HILES NNN)I

'. 4257 ~ 41(

1/

I) 4751 ~ 82(

1/.

I)'257

~ 41-4257 ~ 41

~

.-. 4751 ~ 82-4751 ~ 82 NUMBER OF NONROUTINE

REPORTED, QfAQQQf~MNgS

'a.

Nominal Lower Limit of Detection (LLD) as described in Table 3.

b.

Mean and range based upon detectable measurements only.

Fraction of detectable measurements at specified locations is indicated'in parentheses (F).

TABLE 18 RADIOACTIVITY IN POTATOES PCI/KG 0 ~ 037 BO/KG

('MET MEIGHT)

NAHE OF FACILITY BROMNS FERRY LOCATION OF FAC'ILITY~~IH STON~

ALABAHA OGONET NO,

$ 2-2$ ERERRR2 IR REPORTING PERIOD 19II2 TYPE AND TOTAL NUHBER OF ANALYSIS P~R~f+H~

GROSS BETA 2

GAHHA (GELI) 2 K-40 LOMER LIHIT OF DETECTION

~(~ )

25 F 000 NOT ESTAB.

ALL INDICATOR LOCATIONS HEAN (()

REMK 5373 ~ 00 (

I/

1) 5373 F 00- 5373 00 3549 ~ 88(

1/

1) 7 HILES NNM 3549 F 88-3549 F 88 3549 F 88(

1/

1) 3549 F 88-3549 F 88 LOCATION MITH HIGHEST ANNUAL HEAN

~ITANC~AN~IRQCTION RAN~

7 HILES NNM 5373 ~ 00(

1/

1) 5373 F 00- 5373 F 00 CONTROL LOCATIONS HEAN (F f'7280

'9(

1/

1) 7280 F 19" 7280 F 19 3337 '7(

1/

-1) 3337 '7-3337 '7 NUMBER OF NONROUTINE REPORTED HQAQQ~R HfggS a.

Nominal Lover Limit of Detection '(LLD) as described in Table 3.

b.

Mean and range based upon detectable measurements only.

Fraction of detectable measurer ants at specified locations is indicated in parentheses,(F).

NAHE OF FACILITY RROMNS, F jRRY LOCATION OF FACILITY=

LI~HSTONQ TABLE19 RADIOACTIVITY IN TOHATOES PCI/KG -

0 ~ 037 BQ/KG (MET )'EIGHT)

'LABAHA DOCKET NO ~ 50-259 '60 296-

~

REPORTING PERIOD 1982 TYPE AND TOTAL NUMBER OF ANALYSIS Pf~RR HQ)

GROSS BETA 2

GAHHA (GELI )

2 LOMER LI HI T OF 0 ET E.CIION

~(42) 25 F 000 ALL INDICATOR LOCA)IONS HEAN (j )

HAHSE 3989 89I Il II 3987 89-3987 '9

~IICIITIOM VITH HIGHEST IIH:ICAL IIEAH NAHE HEAN,(F)

I IIILES HHV 3989 89I ll I>

~ 3987889-3987 '9 CONTROL NUMBER OF

'LOCATIONS NONROUTINE MEAN ($ )b REPORTED 4577 '5(

1/

1) 9577 ~ 95 4577 '5 K-40 PB"212 NOT ESTAB NOT ESTAB 2172 '2(

1/

I) 2172 '2-2172 '2 2'4(

1/

1) 2'4-2854 7 NILE S NNM 7 HILES NN)(

2172 '2(

1/'

)

2158 '4('/

1) 2172 52-2172 '2

. 2158 '4-2158 '4 2'4(

1/

1) 4~76(

1/

1,)-

2'4-2'4 4 ~ 76 4 ~ 76 a.

Nominal Lower Limit of Detection (LLD) as described in Table 3.

b.

Mean and range based upon detectable measurements only.

Fraction of detectable measurements at specified locations is indicated in parentheses (F).

NAHE OF FACILITY BROVNS FERRY LOCATION OF FACILITY~~~Nf TABLE 20 RADIOACTIVITY IN TURNIP GREENS PCI/i(G -

0 ~ 037 BOPKG (VET 'VEIGHT)

DOCKET AQ~AAPQ REPORT NO ~ 50-259 260 296 ING PERIOD

) 982 TYPE AND TOTAL NUHBER OF ANALYSIS GROSS BETA 1

GAMMA (GELI) 1 CS-137 K-40 PB-212 BE-7 TL-208 LOVER LIHIT OF DETECTION Q) 25~000 ALL INDICATOR LOCATIONS

~ HEAN '(F)-

RANGE b

,7719 '7(

1/

1) 7719 '7-7719 '7

'/

I)

F 03 1/

1) 3209 '1 1/

1) 7 ~ 48

'/1)

'105+52 1/ ')

F 15

/

F 000

'7 '

(.

"7 ~ 03-NDT ESTAB '

3209 ~ 21(

3209 ~21-NOT ESTAB 7'8(

7 ~'48-NOT ESTAB..

105 ~ 52(,

105o52-NOT ESTAB 2 ~ 15(

2 ~ 15-7 HILES NNV 7 HILES NNV 7 MILES NNV 7 HILES NNV 7 MILES NNV 1/,

1),

7'3 1/

1) 09421 1/

1) 7448 1/

1) 05(52 1/

1) 2'5 7'3(

.7 ~ 03-3209421(

3209 '1-32 7'8(

7e.48-105 ~ 52(,

105 '2-,'

F 15('

~ 15-LOCATION V)TH HIGHEST ANNUAL HEAN "NAHE

~

MEAN (F P 0 ISTANCf AN5 51RECTI ON

~

R'ANGEb 7 HILES NNV'719 47(.

1/

I) 7719 F 47 7719 '7

/

CONTROL LOCATIONS HEAN.(F)b RANGLb NUMBER OF NONROUTINE REPORTED a.

Nominal Lover Limit of Detection (LLD) as described 'in Table 3.

b.

Mean and rarige based upon detectable measurements only.

Friction of detectable measurements at specified locations is indicated in parentheses (F).

Figure 6.

COCo C

JJ o

CS W JJ JJ (0

CIJ CIJ o

JJc o Cl

'o co.

Preoperational Phase I

I Operational Phase ANNIALAyERAGE =

'ROSS HETA kTIVITY I N HRI tKIIG MATER.SUPPLIES

~

1haum FERRY Nun.EAR Purr

'L 1

8 19 9

19 0 1

1 19 2

19 3P 19 30 19 4 1

5 19 6 - 1 7

.19 8' 9

'19 0 1

1.- '2

38 Piguro 7

Oirect Rodtotion Levels Browns Ferry Nuclear Plont

.22 C.I I

)8 C7 It:s 16 Onst te j

i

'1,d I

1/'

5 I

I<Offst te

'1

\\

1 1

gr

/1 6

1 I

'1

./ '1 i'1 I

\\

/

~

'5 l/

10

'2

'1 976 1977 1978 1979 1988 1981 1982 Ptguru 8

22 Oirect Radiation Levels Brawns Ferry Nuclear Plant 8-Quarter Having Average

.18 CT 16 Onstte

~+c rO,,R yW

)y

.r r'.

It" 0

.s, P.'~.4t

~'r EI Off st te 12 1976 '977 1978 1979 1988 1981

~

1982

39 Fteurc 9

Oif ect Radiation Levels Watts Bor Nuclear Plont 22 C

t 18 Cf rLS 16 Onstte Offsiteo I

9

\\

I j'i II 12 1976 1977 1978 1979 1988 1981 1982 Fteurc 10 2t

'22 Dtrect Radiation Levels Watts Bor Nuclear Plant

'I-Quarter Moving Average o

t g 18 CS Ks 16 Onstte ft"9

.//

0.o-~

p o

/

~ ~o o+

OffsI te o-.o..~

tf

/

e.

//

tr 12 1976 1977 1978 1979 1986

"'1981 1982

I

41 Reservoir Monitorin Samples are collected from the Tennessee River as detailed in

.table 21.

Samples collected for radiological analysis include plankton from three of these cross sections and bottom fauna and sediment from four cross sections.

The locations of these cross sections are shown on the accompanying map (figure ll) and conform to sediment ranges establi:shed and surveyed by TVA.

Water Water samples are col'lected automatically by sequential type sampling devices at three cross sections and composite samples analyzed monthly for gross beta and gamma-emitting radionuclides.

Further composites a'e made quarterly for strontium and tritium analyses.

In addition to these r'equired

samples, grab samples were also collected monthly from the vicinity of the plant discharge to the Tennessee

River, and at a point on the Elk River, and analyzed for gross

beta, gamma-emitting radionuclides, and strontium.

Results are displayed in table 22.

Figure 12 presents a plot of the gros's beta activity in surface water from 1968 'through 1982.

No gross beta measurements were made'n surface water samples in 1978.

The levels reported are consistent with gross beta levels measured in surface water samples taken from the Tennessee River in preoper-ational monitoring programs conducted by TVA at other sites.

Fish Radiological monitoring for fish is accomplished by analysis of composite samples of ad>>lt fish taken from each of three contig>>ons reser'-

voirs--Wilso>>, Wheeler,

<<>>d Guntersviile.

No perma>>ent sampling statlo>>s have been established within each reservoir; this reflects the movemeht of fish species within reservoirs as determined by TVA data from the BFN preoperational monitoring program.

Two species, white crappie and'mallmouth buffalo, are collected representing both commercial and game species.

Sufficient fish are collected in each reservoir to yield 250 to 300 grams oven-dry weight for analytical purposes.

All samples are collected semiannually.

and, analyzed for gamma-emitting radionuclides.

The composite samples contain approximately the same quantity of flesh from each fish.

For each composite a subsample of material is drawn for counting.

Results are given in tables 23, 24, and 25.

Plankton As indicated in table 21, net plankton (all phytoplankton and zoo-plankton caught with a 100 ij mesh net) is collected for radiol'ogical analyses at each of three stations by vertical tows with a 1/2-meter net..

At least 50 grams (wet weight) of material is necessary for analytical accuracy.

Samples are collected semiannually and submitted for gross beta analysis, and when quantities are sufficient, for gamma activity and Sr and oSr content.

During this reporting period, all samples contained insufficient volume of material for gross beta, strontium, or gamma analyses.

42'ediment Sediment samples are collected from. Ponar dredge hauls made for bottom fauna.

Gamma radioactivity and Sr and Sr content are determined semiannually in composite 'samples collected fromm each of four stations.

Locations, of thesestations are shown in table 21.

Results are shown in tabl'e 26.

Bottom, Fauna.

The flesh, and shells of Asiatic clams collected, semiannuallyc from the cross sections at four stations (table 21) are analyzed for gamma-emitting, radionuclides.

Levels of Sr and o Sr are-determined on the shells, and on

, the flesh when, sufficient amounts were avail,able..

A 50-gram (wet weight) sample provides sufficient activity for counting.

During this reporting

period, two samples of clam flesh contained insufficient volume. for analysis.

Results are given in t'ables 27 and 28.

Table 21.

SAMPLING SCHEDULE RESERVOIR MONITORING Biolo ical sa les (collected semiannuall

)

River/river mile Zooplankton, chloro'phyll, phytoplankton Benthic fauna Sediment Pish Water Samples (collected monthly)

,Tennessee 277.9 Tennessee 285.2 Tennessee 288.7 Tennessee 291.7 Tennessee.

293.5 X

X b

Tennessee 293.7 (discharge area)

Tennessee 305.0

. (Control)

Tennessee 307.5 (Control)

X Elk 20.5 (Control) c a.

Gill net and/or electroshocker will be used for collection. 'amples of fish are collected from Guntersvil'le, Wheeler, and Wilson Reservoirs.

.b.

Automatic sampler.

c.

Grab sample.

TABLE 22 RADIOACTIVITY IN SURFACE VATER TOTAL PC I/L -

0 037. eO/i TYPE AND TOTAL NUYBER OF ANALYSIS GROSS BETA 65 GAHHA (NAI)

FE-59 I-131 LOMER LIHIT OF DETEC TION 2 ~ 400 NOT ESTAB 15 F 000 ALL INOICtTOR LOCATIONS vEAN (F)b RANGEb.

3 ~ 69( 35/

39) 2 ~ 4'7-.

8 ~ 35 5 ~ AOl 3/

24)

F 70-10'0 16 '0(

1/

24) 16 'G-16(70

.NAME OF FACILITY ~ROMPS FLURRY LOCATION OF FACILITY~I+<STONQ'OCKET NO ~ 50 2$ 9AQQ@296 REPORTING PERIOD ~9/

CONTROL LOCATIONS HEAN (F)b RANGE 3'3(

20/

26) 2'2-6'5 A~ABAHA TRYi 293+5 TRYi 293' BFN OISCHAPGE 10 ~ 70(

1/

7) 10 F 70-10 F 70 16+70(

1/

9) 16'0-16 F 70 4'8(

5/

20)

F 00-7 F 50 2C VALUES <LLD 0

0 ATION MITH HIGHEST ANNUAL HEAN

. NAHE MEAN ($ )

QISTANCE ANO DIRECTION RAt4GC TRH 285+2 4'1(

12/

13) 2'2-8+35 NUYBER OF NONROUT INE REPORTED HEAS~UR

~Y NTS K-40 81-214 PB-214 PB-212 7 ~ 000 NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB SR 89 SR 90 TR I T I\\JH 10 F 000 20 2 ~ 000 20 330 F 000 2G GAYHA (GELI) 21 LA-140 13 ~ 64 (

1/

15) 13 +64-,1 3 64 19 ~ 68(

2/

15) 16'0-22'6 4 ~ 2Sl 1/

15) 4 ~25-4 ~ 25 15 VALVES <LLO 2 ~ 16(

4/

15)

'I ~ 55-2'9 12 VALUES <LLD ANALYSIS PERFORMED 12 VALUES <LLD ANALYSIS PERFORMED 351 +8(

S/

12) 336 '93-370 ~ 86

'TRH 293' BFN DISCHARGE TRH 285 '

TRH 293 ~ 5 TRH 29347 BFN DISCHARGE TRH 293 '

BFN DISCHARGE 13o64(

13'4 22'6l 22 ~ 76-4 ~ 25l 4 ~ 25-1/

4) 13 i64 1/

S) 22 F 76 1/

6) 4'5 362~22(

353 ~ 57-2/

4) 370-86 2'3(

1/

4) 2'3-2'3 6

VALUES <LLD 13 ~ 75(

1/

6) 13'5-13'5 2 51(

1/

6) 2 51-2'1

),I ~ 961 1/

6)

Iles 96-11 '6 2'1(

5/

6) 2+35-2'6 8

VALUES <LLD 8

VALVES <LLO 370 '3l 2/

8) 351 86-390 F 00 4

a..

Nominal Lover Limit of Detebtion (LLD) as described in Table 3.

b.

Mean and range based upon detectable measurements only.

Fraction of detectable aeasureaents at specified locations is indicated in parentheses (F).

TABLE23 RADIOACTIVIT'Y IN MHITE CRAPPIE'FLESH)

PCI/G -

0 ~ 037'O/G (DRY MEIGHT)

NAHE OF FACILITY PR~M~ Ff RRY LOCATION OF FACILITY L IHESTONE ALABAMA DOCKET NO ~ 50-2~92~02'~9 REPORTING PERIOD~1 TYPE 'AND TOTAL NUHBER OF ANALYSIS GROSS BETA 6

GAHHA (GELI) 6 LOMER LIMIT OF DETECTION (l LQ) 0 ~100'LL INDICATOR LOCA/IONS HEAN (F)

RANGE 34 '3(

- 4/

4) 29'2-40'5 L~OA~Tg~NM TH~~gQT A ~NN A L Hg AN MILSON PESERVOIR 34 ~ 93(

2/

2)

TPP 259-275 29'2 40 F 55 CONTROL

-LOCATIONS MEAN (F)b RANG+

32~76(

2/

2) 2 l~3x 4i,la NUHBER OF NON ROUTINE REPORTED CS-137 K 40 PB-212 R A-22'6 0'20 NOT ESTAB NOT ESTAB NOT ESTAB 0+13(

C ~ 15-15'5(

14 ~58-0 F 01(

0 ~ 01-0 ~ 02(

0 ~ 02-4/

.4) 5 ~ 17 4/

4) 16'0 3/

4)

Qo01 2/

4)

F 02 MILSON RESERVOI'R TRH 259-275 MHEFLER RES.

TRH 275-349 VHEELER RES TRH 275-349 MHEELER RES TRH.275-349 0'4(

0.10-15'5(

15 ~ 04-0 ~ 01C 0 ~ 01-0 ~ 02(

0 ~ 02-2/

2)

F 17 2/

2) 16 F 86 2/

2)

Qo01 2/

2) 0 F 02 0 ~ 13(

2/ ')

Oi10 5 ~ 16 14 ~ 36(

2/

2);

13'5-15e26 0 01( 1/')

0~01-0 F 01 2

VALUES CLLD a.

Nominal Lower Limit.of Detection (LLD) as described in Table 3.

b.

Mean and range based upon detectable measurements only.

Fraction of detectable measurements at specified" locations is indicated in parenthese's (P).

T'ABLE 24 RADIOACTIVITY IN SHALLHOUTH BUFFALO (FLESH)

'CI/G -

0 ~ 037 BO/G (DRY MEIGHT)

NAME OF FACILITY BROVNS Ff RRY'OC/TION OF FACILITY L~TN STOT!f A~ABAHA DOCKET NO ~ 50-P59M260 ~ 296 REPORTING PER IOD~~98 TYPE ANO TOTAL NUMBER OF ANALYSIS Pg~RF R~H GROSS BETA 6

GAHHA (GELI) 6 CS-137 f(-4 0 PB-214 PB-212 BE-7

.SR 89, SR 90 LOVER LIMIT OF'ETECT IONa (I LQ) 0 ~ 100 0 ~ 020 NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB 0 ~ 500 0 ~ 100 ALL INDICATGR LOCATIONS HEAN

(

) b RAA ~G 22 '6(

4/

4) 18'9-29'1 0 04(

3/

4) 0 F 04-QM,05 11 04("

4/

4) 7'6-13'0 01(

1/

4) 0 F 01-0'1 0 F 01(

3/

4) 0 F 00-0'2

.0'2(

1/

4) 0'2-0'2 2

VALUES <LLO ANALYSIS PERFORMED 2 VALUES <LLO ANALYSIS PERFORHEO VHEELER RES TRH 275-349 VHEELER RES TRH 275-349 MHEELER.RES TRH 275-349 MHEEEER. RES TRH 275 349 MHEELER RES TRH 275-3fs9 0 ~ 04(

0 ~ 04-11 '5(

10 ~ 60-0 F 01(

0 F 01 0'2(

0 ~ 02 0 ~ 32(

0 32-

'/

2) 0 F 05 2/

2)

IZ ~ 69 1/

2) 0 ~ 01 1/

2).

0 02 1/

2)

GM32 EEISTANC~4M OIRECTIOM I!Al Of MHEELER RES 24'8(

2/

2)

TRH 275-349 19M76-29 '1 CONTROL LOCATION(

HE AN (F)

RANGE ZPM5](

P/

2) 21 '6-23'7 0 F 07(

2/

2) 0'6-0'9 9 57(

2/

2) 9'0 9'3 2

VALUES <L(.O 2

VALUES <LLO 2

VALUES <LLO 0

VALUES <LLD 0

VALUES <LLD NUMBER OF NONROUTINE REPORTED llfAS~UR tl NTS a.

MocIinal Lover Linit of Detection (LLD) as dcscribcd in Table 9.

b.

Mean and range based upon detectable neasurements only.

Fraction of detectable cfeasuretEents at specified locations is indicated in parentheses (F).

TABLE 25 RADIOACTIVITY IN SHALLHOUTH BUFFALO (MHOLE)

PC I/G -

C ~ 037 80/G (ORY 'MEIGHT)

LOCA NAME OF FAG I

/ION OF FACILI LITY'ROMNS FERRY TY~IH&TOHf DOCKET AI A/AH/

REPORT NO ~

50-2~59 260A296 ING PERIOD 19AP TYPE AND TOTAL NUHBER OF ANALYSIS GROSS BETA 6

GAHHA (GELI

)

6 CS-137 K-4 0 8 I-214 PB-21.4 PB-212 RA-226 LONER LIHIT OF DETECTION

,~(I 0) 0 ~ 100 0'20 NOT ESTAB 0 ~ 020 NOT ESTAB NOT ESTAB NOT ESTAB 0 ~ 03(

0 02-6'8(

4 ~ 75-0 F 08(

0 ~ 03-v~02(

0 ~ 02-C ~ 01(

0+01-0 F 08(

0+03 3/

4) 0'4 4/

4)

, 7'9 2/

4)

0. ~ 12 1/

4) 0 ~ 02 4/

4) 0 ~ (13 2/

4) 0'2 ALL INDICATOR LOCATIONS HEAN (F) b

'ANGEb 17 ~ 60(

4/

4,)

14 ~ 94 20 ~ 43 MHEELER RES TR)i 275-349 MHEELER RES TRH 275-349 MHEELER RES TRH 275-349 MHEELER RES

-'TRH 275-349 MHEELER RES TRH 275-349 MHEELER RES TRH 275-349 F 03(

0 ~ 02-7'8(

I ~ 56-0 ~ 12(

,0 ~ 12

'0 02(.

0 ~ 02-0 F 02(

Oo 01-.

v ~ 12(

0 12-2/

2) 0 F 04 2/

2) 7'9 1/

2) 0'2 1/

2) 0+02 2/

2) 0'3 1/

2)

F 12 QOCATIOh MITH HIGHEST ANNUAL njAh NAHE MEAN (F)

STANCE ANO DIRECTION RANGE MHEELER RES 20 13(

2/

'2)

TRH 275-349 19'3-20 CONTROL LvCA TIDE HE AN (()

RANGE 17 '9(

2/

P) 16 F 81-

.'18 '6.

0'4(

2/

.2)'

'3-0'4 6'7(

2/

2) 5'2-7'3'

'4(

1/,

2) 0 F 04-0'4 2

VALUES (LLD 0 F 01(

2/

2) 0 F 01-0 F 01 0 '44 1/

2)

F 04-0 F 04 P

'NUHBER OF hONRvUTINE REPOR'TEO MEASUREMENTS a.

Nominal, Lower Limit of Detection (LLD) as described in Table 3.

b.

Mean and range based upon detectable measurements only.

Fraction of detectable measurements at specified locations is indicated in parentheses

.(F).

c'v

TABLE26 RADIOACTIVITY IN SEOIIIENT NAME OF'ACILITY QROk~ Ff RRY LOCATION OF FACILITY, LIMESTONE PCI/G -

0 '37. BO/G (PRY )(EIGHT)

ALABAMA DOCKET. NO ~ 5'0"259',26~0

$ 96 REPORTING PERIOD~19 K-40 ZN-65 LONER LIHIT OF BET EC T I.ON (I I 9) 0 ~ 060'

'10 0'80 GiC20 NOT ESTAB 0 '20 81-214 BI-212 PB-214 PB-212 RA-226 RA-223 RA-224 TL-208 AC-228 P A-234 H SR 89 SR 90 0 ~ 020.

0 100 NOT ESTAB NOT ESTAB NOT ESTAB NCT ESTAB NOT ESTAB 0'20 0 ~ 060.

NOT ESTAB 1 F 500 8

0 ~ 300 8-TYPE ANO TOTAL NUPiBER OF ANALYSIS P f,~RF 0 1 L GAMMA (GELI

)

8 CE-144 c

CO 60 CS-134

=

c CS-137 ALL INDICATOR LOCATIONS MEAN (()

RAIJGE 0'0(

2/

6)

G 15-0'6 G ~ 23(

6/

6) 0.08-0.51 0 ~09('/

6).

0 '9-0 ~ 09 1 ~ 35(

6/

6) 0 '1-2'9-

~

~ 14 '7(

6/

6) 12'1- '5'1 0 ~ 08(

1/

6) 0 F 08-0 F 08 1 ~ 30(

6/

6) 1 ~ 13-1 '5 lo85(

6/

6)

~ 1 ~ 61-2ou6 1 ~ 36(

6/

6) 0'7-lo57 1 ~ 56(

6/

6) 1 ~ 20- '

~ 89.

1 ~ 30(

6/

6) i13-1 o45 0 '8(

3/

6)

G ~ 56-0'9 F 83(

5/

6)'

~ 43-F 02 0 '6(.

6/

6) 0'4-0'1 F 62(

6/

6) 1 ~ 37-1 ~ 75 3'0(

1/

~ 6)'

'0'= ~

3'0 2il3(

'1/

6) 2o13-2'3 6

VALUES <LLD TRH 293 ~ 7 BFN DISCHARGE TRH 288'8 TRM 293o7 BFN DISCHARGE TRM 277'8 TRM 277'8 TRM 293 ~ 7 BFN DISCHARGE TRY, 277 ~ 98 TRM 288 ~ 78 7RH 277o98 TRH 277'8 TRM 277'8 TRH 293 '

BFN DISCHARGE TRM 293o7 BFIJ DISCHARGE TRH 277 ~ 98 TRM 277o98 TRH 293 ~ 7 BFN 0 ISCHARGE TRM 293i7 BFN DISCHARGE 0 ~ 20(

0 ~ 15-0'2(

G ~ 13-G ~ 09(

0 ~ 09-1 ~ 94(

1 ~ lu-ll 4444(

15'6 C ~ 08(

0 ~ u8 i'5(

1 25-1 ~ 89(

1 ~ 78-1,53(

1 ~ 46" 1 ~ 78(

1 ~ 67 1 ~ 35(

1 25-0'3(

56-loC4(

1 ~ 94-ei60(

C ~ 59-1 ~ 70(

1 ~ 65-3'0(

3 '07 2'3(

2i13-2/

2)',

0'6

- 2/

2)

Ci51 1/

2) 0'9 2/

2) 2.79 15'1

.if n

08 2/

2) 1 ~ 45 2/

2) 2 ~ 01 2/

2) 1 ~ 57 2/

2) 1 ~ 89 2/

2) 1 ~ 45 2/

2)

O)89 1/

2) 1 ~ 94 2/

2) 0'1 2/

2) 1 ~ 75 1/

2) 3'0 1/

2) 2i13 j O~A~TI N

~)I TH Hajj)(/~<AT'JNIJII XfAQ CONTROL LOCATIONS ME AN tg )P RAIJGE.

2 VALUES <LLO 0'3(

1/

2) 0'3-0 F 03 2

VALUES <LLD 1 ~ 22(

li75(

1 ~ 39-lo31(

1 ~ 15-1.47(

~1 ~ 30-1 o22(

. 1.05-0'ot 0 ~ 29-I ~ 72(

1 72-0'9(

0 ~ 45-1 51(

29-4i64(

64-2 VAL

('

34 (

Co34-2/

2) 1 ~ 40 2/

2) 2 il 2/

2) 1 ~ 46 2/

2) 1 ~ 64 2/

2)

'I ~ 40 1/

2) 0'9 1/

2) 1 ~ 72 2/

2) 0 ~ 53

" 2/

2) 1 ~ 73 1/

2) 4 i64 UES

<LLO 1/

2) 0 ~ 34 Co16(

2'/

2) 0 '4-Ci18 15 '1(

2/

2) 14'7-16'5 2

VALUES <LLO NUHBER OF NONROUTINE REPGRTED a.

hominal Lower Limit of Detection (LLD) as described in Table" 3.

b.

Mean and range based upon detectable measurements only.

Fraction of detectable measurements at specified locations is indicated in parentheses (F).

c.

The distribution of Co and Cs between indicator and control locations reported herein is comparable to the distribution reported in the preoperational monitoring program from 1968 to mid-1973.

The levels repoited,are.also comparable with levels reported in samples from the Tennessee River in 'preoperational monitoring programs conducted by TVA ai other sites.

n

NAIIE OF FACILITR B~RIINS FERVOR LOCATION OF FACILITY LIHESTONE TABLE 27 RADIO'ACTIVITY IN CLAM FLESH PCI/G -

0 ~ C37 BQ/G (DRY

'AJEI GHT)

ALABAHA DOCKET NON~P~~Q~9 REPORTING PERIOD 1982 2/

4) 0'3 I/

4) 0'7 4/

4) 4 ~ 53 2/

4) lN67 3/

4) 0 ~ 76 4/

4) 0 ~ 80 2/

4) 0 F 87 2/

4)

ON76 3/

4)

F 18 2/

4) 0'1 0'8(

0 ~ 24-0 ~ 17(

0 17-2'7(

1 ~ 11 1 ~33(

ON98-0 ~42(

0 ~ 01-0'9(

CN21-0 ~ 66(

0 4R 0 ~ 39(

0 ~ 01-0 ~ 13(

0 ~ 10 0 ~ 31(

ON21-0 F 080 0 ~ 080 NOT EST AB 0 ~ 170 NOT ESTAB CS-137 K-40 ZN-65 BI-214 PB-214 PB-212 RA-226 TL-208 NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB AC-228 NOT ESTAB TYPE AND LOlJER LIMIT ALL TOTAL NUMBER OF INDICATOR LOCATIONS OF ANALYSIS DETECTION MEAN ([)

EKEEQEHKR

~2)

RANGE GAHHA (GELI) 6 C0-60 TRH 293NT BFN DISCHARGE TRH 288'8 TRQ 293N7 BFN DISCHARGE TRH 293 '

BFN DISCHARGE TRH 288'S TRH 288'8 TRH 288 F 78 TRH 288'8 TRH 288'8 TR'( 288N78 0N53(

0 ~ 53-0 ~ 17(

0 ~ 17-2N82(

1 ~ll-1 ~ 67(

1 ~ 67-0 F 76(

0~76 0.80(

0 ~ 80-0 F 87(

0 ~ 87-0.76(

0 ~ 76-0 ~ 18(

0 ~ 18-0'1(

ON41 1/

2) 0'3 I/

1) 0'7 2/

2) 4'3 1/

2) 1 ~ 67 1/

1) 0'6 1/

1) 0 ~ 80 1/

1) 0'7 1/

I) 0076 1/

1)

~

0'8 1/

1) 0'1 2

VALUES <LLD 2

VALUES <LLD 2 ~ 34(

2/.

2) 2'4-2'5 2

VALUES <LLD 0'9(

2/

2) 0'2-QN37 3'4(

2/

2) 0 ~II-0'8 0'2(

I/

2) 0 ~ 22-0 ~ 22 2

VALUES <LLD 0 ~ 16(

1/

2)

F 16-

'- 0 ~ 16 2

VALVES <LLO CONTROL.

LOCATION lJITH HIGHEST ANNUAL HEAN LOCATIONS NUMBER OF NONROVTINE REPORTED a.

Nominal Lower Limit of Detection (LLD) as described in Table 3.

b.

Mean and"range based upon detectable measurements only.

Fraction of detectable measurements at specified locations is indicated in parentheses (F).

TABLE 28 TYPE AND TOTAL NUMBER OF ANALYSIS GAHHA (GELI )

8 C0-60 K-40 81-214 PB-214 PB-212 RA-226 TL-208 AC-228 SR 89 SR 90 LOWER LIHIT OF DETECTION (Q~L) 0+010 NOT ESTAB 0 '50 0 '50 NOT ESTAB 0 F 050 0 '20 0'60 5 F 000 1 F 000 ALL INDICATOR LOCAbTIOtiS t'EAN ([)

RANGE 0'8(

0 ~ 02-0.22(

C ~ 15-0'7(

0 ~ 07-0'2(

0 ~ 07-0 ~ 11(

0 ~ 04-0'7(

G ~ 07-0'5(

0 ~ C2-0.18(

0 ~ 09-5'5(

5 ~ 25-I ~ 66(

I ~ 19-2/ ')

<<J ~ 13 3/

6) 0 ~

0 5/

6)

"~45 5/

6) 0 ~ 68 5/

6) 0'9 5/

6) 0'5 5/

6) 0 ~ 06 5/

6) 0 ~ 30 I/

6) 5'5 6/

6) 2'0 NAME OF FACILITY BROWNS F jttRY LOCATION OF FACILITY~IV~STONf RADIOACTIVITY IN CLAH SHELL PCI/G -

0 ~ 037 BO/G (ORY WEIGHT)

LOCA T I Ot( WITH HIGHEST ANNUAL HEAN NAHE HEAN (IF)

DISTANCE AttO DIRECTION RAt(GE TRV 293 '

BFN DISCHARGE TRH 288 F 78 TRr..288.78 TPH 288'8 TRH 288 '8 TRH 288o78 TRH 288'8 TRV, 288'8 TRH 277.98 TRH 288'6 0'3(

0>>13-0'2(

0 ~ 15-0'8(

0 ~ 10-0'0(

0 ~ 13-0'1(

0 ~ 12-0'8(

0 ~ 10-0 F 05(

0 ~ 05-0'7(

0 ~ 24-5'5(

5 ~ 25-1 ~ 86(

I ~ 63-1/

2)

Oil3 2/

2) 0 ~ 30 2/

2) 0'5 2/

2) 0 F 68 2/

2) 0 ~ 29 2/

2) 0'5 2/

2) 0'6 2/

2.

0'0 1/

2) 5'5 2/

2)

F 10 2

VALUES <LLD 1 ~ 51(

1/

2) 1~51-I ~ 51 0'7(

1/

2) 0 67-0 F 87 0'7(

2/

2) 0'7-0'7 0'2.(

1/

2)

'0'2-0'2 2

VALUES <LLO 2

VALUES <LLD 0 ~ 10(

1/

2)

CD 10-0 ~ 10 2

VALUES <LLD 1 ~ 36(

1/

2)

I ~ 36-I ~ 36 DOCKET NO ~ 50-259 260 796 A~ABAHA REPORTING PERIOD~9//

CONTROL LOCATIONS EAtt (F) b RANGE NurBER OF NONROUTINE REFORTED rEAsUREHEt(Ts a.

Honinal Lower Lini.t of Detection (I.LD) as described in Table 3.

b.

Mean and range based upon detectable neasurenents only.

Fraction of detectable neasurenents at specified locations is indicated in parentheses (F).

Pigure 1l R ESERVOI R MONITORING 'ETWORK Elk River WHEELER DAM mile 274.90 mile 277.98 Rogersville 0

rnite. 282.6

~mi(e 285.2 mile 29l,76 Athens 0

B;F,. NUCLEAR PLANT 8

Champion Paper Co.

0 Cour tland ile 288.7B mite 293.50 fnile 295.70 mile 305.0 Decatur rnite 307.52

~ - Automatic Sam ler Scale of Miles 0

Eigure 12 O

COC0 C

C V) oVc o o vV C

'C O

Preoperational Phase Qperational Phase ANNNL AVERAGE ASS SETA ACjlVITY IN SURFACE 1'IATER EemS FERRV i"IUCLEAR I'ueT Average:

Preoperational Phase 7$

1968 1969 C

7 1970

,1971 1972 1973P 19730 1974 1975 1976 1977'978 1979 1980 1 81 19 2

a.

No gross beta measurements made in 1978.

, ~ ~

53 F

A quality.control program has been establi.shed with the Alabama Department of Public Health Environmental. Health Admini'stration Laboratory and the Eastern Environmental Radiation Facility, Environmental Protection Agency, Montgomery, Alabama.

Samples, of air, water, m'ilk, and ve'getation collected around BFN are 'forwarded to these laboratories for analysis,

-and results are exchanged foi comp'arison.

Data measured at the control stations for each medium were averaged for each sampling period.

In order to describe the distribution of control station data, a mean, standard deviation, and 3-sigma limits were calculated.

We cari expect that background concentrations would be distributed within these

~ limits'.

This provides us the basis for comparing control and indicator data.

If the indicator data fall within the limits defined for control data, we conclude that the indicator data were not significantly affected by the nuclear plant. If the data do not fall within the limits, we will perform further analyses to determine if the difference is attributable to the nuclear plant.

Conclusions A vast majority of the indicator station data was found to be within the distribution defined by the control station data.

The data analysis software identified concentrations slightly exceeding the limits of the control station data for a small number of radionuclides in samples from indicator stations.

Many of these values may be discounted because the error 'reported by the analysis program was greater than the calculated concentration.

The remaining isolated elevated concentrations may be the result of fallout, fluctuations in the existing environment, computer program artifacts, or.

analytical errors.

The same type of isolated high values occurred in the control station data and may be attributed to the same sources'.

Dose estimates were made from concentrations of radioactivity found in samples of environmental media.

Media sampled include, but are not limited to,'ir, milk, meat, vegetation, drinking water, and fish.

Doses estimated for persons at the indicator locations were essentially identical to those determined for persons at control -locations.

Greater than 99 percent of those doses were contributed by the naturally occurring radionuclide potassium-40,

54 and.'y, stronti.um-90'nd'esium-137 which are long-, lived radioisotopes f'ound in fallout from nuclear'eapon testing.

Zt is concluded from; the above analysis. of the d'ata and; from, the trend; plots'resented'.

earlier that there were no measurable increases in the'xposure to, members oE the general public attributable. to the operation'..

of BFN.

Indications. of the presence of smal'1 quantities of fission products:

have been seen. in'quatic media (for example, A'siatic cl'ams)'.

The levels'easured, were extremely low for. example near the nomimal lower limits. of detection and: several hundred'imes lower than the reporting levels outlined'y the Nuclear Regulatory; Commission.

No~ increases of radioactivity. have been.

seen: in water samples.

These media wi:ll. be monitored: closely for indications of, increases,.

TENNESSEE VALLEYAU HORI CHATTANOOGA, TENNESSEE 37AO 400 Chestnut Street Tower II May 3, 1983 U.S. Nuclear Regulatory Commission Region II ATTN:

James P. O'Reilly, Regional Administrator 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30303

Dear Mr. O'Reilly:

Enclosed is a copy of the following report prepared by the Tennessee Valley Authority pertaining the environmental monitoring at the Browns Ferry Nuclear Plant:

Environmental Radioactivity Levels, Browns Ferry Nuclear Plant, Annual Report 1982 This monitoring program is specifically responsive to the recommendations and requests of the United States Fish and Wildlife Service.

We understand that the Office of Nuclear Reactor Regulation will transmit five copies of the report to the Secretary of the Interior.

Very truly yours, TENNESSEE VALLEY AUTHORITY L. M. Mills, M nager Nuclear Licensing Enclosure cc:

Director of Nuclear Reactor Regulation (20)

Attention:

Mr. Darrell G. Eisenhut, Director Division of Licensing U.S. Nuclear Regulatory Commission Washingtoh, D.C.

20555 p>>;,

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+il ppp[QQjL C An Equal Opportu ity Employer

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