Text

Environ Radioactivity Levels,Annual Rept-1982
	ML18029A462
Person / Time
Site:	Browns Ferry
Issue date:	12/31/1982
From:	Belvin E; TENNESSEE VALLEY AUTHORITY
To:	Cunningham A; NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
	NUDOCS 8504100250
	Download: ML18029A462 (188)
	v • d • e

CUNNINGIiAHiA.L ~

Region 2z Of f i ce of Director

SUBJECT:

"Environ Radi oacti vi ty Levels, Annual Rept 1982 ~" I'I/830519 lire DISTRIBUTION CODE:

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

NOTESsNHSS/FCAF 1cy.

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OL ~ 06/26/73 NMSS/FCAF icy, icy NHSS/FCAF/PM, OL;06/28/74 NHSS/FCAF icy, icy NESS/FCAF/PM

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05000296 OL:07/02/76 05000260 mrs im STE REGULATOR'f INFORMATION DISTRIBUTION SYS g$oQ

)o oooo ACCESSION NBR'.8504100250 DOC ~ DATE: 82/12/31 NOTARIZED:

NO DOCKET FACIL:50 259 Browns Ferry Nuclear Power Stations Un'it 1< Tennessee 05000259 50 260 Browns Ferry Nuclear Power Stations Unit 2~

Tennessee 05000260 50-296 Browns Ferry Nuclear Power Station~

Unit 3< Tennessee 05000296 AUTH'AME AUTiiOR A F F ILIATION BELVINgE, A ~

Tennessee Valley Authority 6 tvv-8 ~

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r TENNESSEE VALLEYAUTHORlTY MUSCLE SHOALS. ALABAMA35660 109 Multipurpose Building MAY 19 1983 P/ g~

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U.S. Nuclear Regulatory Commission c/o Regional Administrator Region II Attention:

Mr. A. L. Cunningham Suite 2900, 101 Marietta Street Atlanta, Georgia 30303

~ ~w(z

Dear Mr. Cunningham:

The enclosed report, "Environmental Radioactivity Levels Brogans Ferry Nuclear Plane - Annual Report 1982," is furnished for your information and use.

Sincerely, E. A. Belvin, Chief Radiological Health Staff Enclosure 1983-TVA 50'rH ANNlVERSARY An Equal Opportunity Employer

TENNESSEE VALLEYAUTHORITY ENVIRONMENTAL RADIOACTIVITYLEVELS BROWNS FERRY NUCLEAR PLANT ANNUAL REPORT " 1982 TVA/POWER/RHS RADIOLOGICALHEALTHSTAFF

CONTENTS List of Tables List of Figures.

Introduction

~

iv

~

111 Atmospheric Monitoring

~

Terrestrial Monitoring

~

I

~

~.

~ ~, ~

23 Reservoir Monitoring Quality Control.

~

4I 53 Data Analysis.

~

53 Conclusions.

~

53

LIST OF TABLES Table 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-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 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

'11.1

LIST OF FIGURES Figure 1

- Tennessee Valley Region Figure 2

- Atmospheric and Terrestrial Monitoring Network.

10 18 Figure 3" - Local Monitoring Stations 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 Ievels, BFN 38 Figure 8

Direct Radiation Levels, BFN (4-Quarter Moving Average) 38 Figure 9 "

Direct Radiation Levels, WBN 39 Figure 10 - Direct Radiation Levels, WBN (4-Quarter Moving Average)

Figure 11 - Reservoir Monitoring Network Figure 12 - Annual Average Gross Beta Activity in Surface Water 39 51 52

ENVIRONMENTAL RADIOACTIVITY LEVELS 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 Harch 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 beg'an 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.

Nowever, seasonal,

yearly, and random variations in the data were observed.

in order to determine the potential increases in environmental radioactiviLy-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.

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 table,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 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 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 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 NaZ(T1) gamma spectroscopy were analyzed for 14 specific gamma-emitting radionuclides

.and radionuclide combinations For these

analyses, a

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 Be, K,

212Bi~ 214Bi~

212Pb~

214Pb) 226Ra, etc.

T.LDs for'he analysis of the radio-nuclides listed below are given in table 3B.

LLDs for additional radio-nuclides identified b',,Ge(L;) an~lysis 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

<LLI)" for an isotope with no established LLD does not impl'y a value less than 0; rather it indi.cates 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 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.

r a 'The following radionuclides'and radionuclide combinations are quantified by the AIPHA-M least-squares computer code:

Ce; Cr; I; 'u;

~Cs; Cs, 5Zr-Nb Co;

~~Mn; Zn Fe Co; " K; and Ba-La.

Station Location Muscle Shoals Table 1

ENVIRONHENTAL RADIOACTIVITYSAMPLING SGHEDDLE=

Air Charcoal Rain-Heavy Particle River 'ell "Public Aquatic Life.

Filter Filter ates Failoet So I ~re statist'Ililk Water W ter Wat r d Sedieeet'oods H,

A Lawrenceburg W

W M

H A

Rogersville W

W H

H Athens W

M H

A Decatur Courtland Site I N

W W

M H

H H

A M

M Site 2

NNE W

W H

H A

Site 3

ENE W

~

W H

M A

Site NNW W

W H

H A

Site 5 (WSW Farm B Farm S

Farm P

Farm L Contro Farms Onsite Well Wheeler Dam Elk River.

Tennessee River Champion Paper Co.

Various Local Farms W

W H

H A

Q

~ Q W

Q W

W - Weekly M - Honthly (every 4 weeks)

Q - Quarterly S - Semiannually A - Annually

Table 2

Atmospheric and Terrestrial Monitoring Station Locations Browns Ferry Nuclear Plant Sam le Station Approximate Distance and Direction from Plant LM-1 BF, North IM'-2 BF, North-Northeast LM"3 BF, East-Northeast LM-4 BF, North-Northwest;"

LM"5: BF, West-Southwest PM;-1 BF., Rogersville,'AL.

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 kilometers)

NNW (4.0 kilometers)

WSW 13.8 Miles--

(22.2 kilometers)

NW PM-2 BF, Athens, AL 10.9 Miles (17.5 kilometers)

NE PM-3 BF, Decatur (Trinity), AL '.2 Miles (13.2 kilometers)

SSE PM-4 BF,, Courtland, AL RM-1 BF, Muscle Shoals,AL.'Control)

RM-2 BF, Lawrenceburg, TH=

(Control)

Farm S

Farm B

Farm L.

Farm T (Out of business'fter1/18/82) 10.5.'Miles

- (16.9 kilometers)

WSW 4.75 Miles (7.6 kilometers)

N.

7.0 Miles 5.0 Miles 7.0 Miles (11.3 kilometers)

NNW (7.0 kilometers)

NE (11.3'i:lometers)

ENE

32. 0 Miles (51. 5 kilome ters)

W 40.5 Miles (65.2 kilometers)

NNW Farm P

Farm N (Control)

Farm J (Control)

Farm C (Control)

Farm Ca (Control) 8 8 Miles 27.0 Miles 4'0.0 Miles 32.0. Miles 32.0 lliles (64.4 kilometers)

(51..5 kilometers)

(51.5 kilometers)

N (14.1 kilometers)

(43.4 kilometers)

NW

t

~

Table 3

DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS A.

S ecific Anal ses NOMINAL LOWER LIMIT OF. DETECTION LLD

Air Particulates

~ci Charcoal

~C1 Fallout Water ct/r Cccttt Vegetation and grain

~CI/

d Soil and Sedidqent

~dt/

d

. Fish, clam flesh,

plankton,

~dt/

dr Foods;

meat, Clam shells

poultry, Mi.lk pCi/C ~dr pCi/kit

~Ci/I

~ J L t

t Total a Cross a Gross 8

lill "Sr

'. 4Sr

0. 005

0. 01 0.005 0.001 0.02 0.05 0.4 2.0 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

All LLD values for isotopic separar.ions 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 sampl'e; these variations may change the LLD value for the given sample, The assumption is made tha't all samples are analyzed.uithin one veek of the collection date.

Conversion factorsl 1 pCi 3.7 x 10 Bq; 1 mCi dc 3.7 x 10

~ Bq.

d t

Table 3

DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS B.

Canna Anal ses NOMINAL LOWER LIMIT OF DETECTION (LLD Clan flesh and plankton

~CS/

d Mater and milk

~ci/I Vegetation and grain NCCI/ 'drr Soil and sedinent

~CI/

d Air particulates

~CE/o Fish

~Cl/

dr F 1*~de Li **

N I~GLI ll I

~de Li N I

~G/LI I I.~GLI N I ~GLI Foods,(tomatoes

potatoes, etc.)

Ci vet Meat and poultry NCCI//iI

'se:

Clam shells

~CI/

dr NaI

~Ce Li NaI

=

C~e Li Nai De(Lil 1 0 1 N 1 Ie ds Ce

'1 0 IrC s'Cr 1111 1 0 1 N '1 0 C R 10CR 1 li Cs C

"Zr-W sszr ssNb s0C sCMn Zn 00C Ba-La 1008 1 00La

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 O. 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 10 26 10 5

10 10 5

.15 5

10 5

15 9

10 5

150 15 25 7

O. 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 O.ll 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 0.35 0.06 0.60 0.10 0.29 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 O.ll 0.01 0.90 0.15 0,07 0:02

0. 35 0.06 0.60 0.10 0.20 0.02

.p. 45 O.ll 0.12 0.08-0.'12 0.02 0.12 '.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 9.48 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 9.02 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 33 44 8

40 26 5

10' 5

5 9

5 25 7

90 4C 200 90 50 20 1.50 90 40 50 40 15 40 20 15 55 15 40 15 70 20 30 15 400 50 50 15

+The haI(T1)

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

Mater 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 veight, then corrected to vet weight using an average moisture content of 702.

Average dry veight is 250 grams.

Air particulates are counted in a vali crystal.

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

The counting time is 4000 seconds.

All calculations are performed by the least-squares computer progran ALPHA-M.

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

++The Ce(LI) LLD values are calculated by the method developed by Pasternack and Harley as descr'ibed 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-I, Marinelli beaker as dry weight.

The average dry ueight 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 252,

14Z, 16X, or 29K Ce(Li) detector..he counting time is normally 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

All spectral anal'ysis is performed using the softvare provided with the ND-4420.

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

Conversion factor 1 1 pCi 3.7 x 10 Bq.

~ '

'gable 4

\\

Results Obtained in,lnterlaboratory Comparison Program A.

Air Filter (pCi/filter)

Gross Al ha Gross Beta Strontium-90 Cesium-137 Date EPA value TVA AVG.

~(+3a WARL EARL EPA value TVA AVG.

(+3a)

WARL EARL EPA value TVA AVG.

~(i3a WARL EARL EPA value

~(+3a TVA AVG.

WARL EARL 3/82 9/82 32+14 28 28 27+12 23 28 55+9 67+9 63 56 57 52 16+2'!6 16 15 20+2.6 17 'g14g 23+9 27+9 24 24 22 22 B.

Tritium in Urine (pCi/L) 5/82 12/82 1300+575 3830+641 Date EPA Value (+3a)

TVA AVERAGE WARL EARL 1793 1650 3510 4023

Table 4 (Continued)

Results Obtained in Interlaboratory Comparison Program C. Radiochemical Analysis of Water (pCi/L)

Gross EPA value Raa

~(3'l ha T~YAva.

WARL EARL Cross Beta EPQ value TVA

~3a

'ARL AVG EARL Strontium 89 EP* value TVA AVC.

~33 llARL EARL Strontium - 90 EPA value TVA AVC.

'~3a MARL EARL EPA value TVA

~3a WARL Iodine AVC.

EPA value EARL'3-

-131 TVA AVC WARL

EARI, 1/82 24410 2/82 3/82 19+9 4/82 5/82 27.5a12 6/82 7/82 16 9 8/82 9/82 29+13 10/82 11/82 19i9 12/82 20 19 32'9 33 28 19 20 19+9 F 19 20 26 f

19 15 40'9 38 24+9 22 23 27 38.3 2919 26 33 13 32 23 9

. 20 21 22a9 24.

22 24.5 9

30 21 21a9 20 22 12+2.6 13 12 13+2.6 11 8

14.5+2.6 13.8 14.A1 1820+592 2007 8 4eq 6h 1793 8.7 7.3 2860'624 2907 2923 62=11 18301589 1620 1810 4.4=1.2 2890i624 2903 2793 61 61 5.3 3.6 87=15 93

. 79 37 39 2560f606 2690 2510 1990+598 1943 1993 37=10 D. Ca~-Spectral Analysis of Water (pCi/L)

Chromium - 51 va ue TVA Date

(+3a)

WARL A VCR.

EARL Cobalt - 60 EPA val a T~VVr..

~3a MARL EARL Zinc - 65 EPA value

~P

~VG.

~3c WARL EARL a

Ruthenium - 106 EPA value TVA AVC.

~('3a llARL EARL Cesium 134 Cesium 137 EPA value ~~Q, EPA value 3a WARL EARL ~3V KARL EARL 2/82 0

<44 6/82 23 9

44 10/82 51+9 55

<35

<3535'0+9 21 22 29x9 32 34 "na9 18 21

)5'9 16 16 2669 29 26 24a9 25'd 25 2019 0

30+9

<40

<30

<40

<30 39d

<36 22+9 35+9 19i9 21 19 31 32 23-9 25 9

20'9 24 22 24 27 20d

Table 4 (Continued)

Results Obtained in Interlaboratory Comparison Program E. Milk (pCi/L)

Strontium 89 Strontium 90 Iodine - 131 Cesium - 137 Barium - 140 Potassium~

Cobalt - 60

'PA al 1VA AVC.

EPA vel e

TVA AVC.

EPA I e TVA AVC.

EPA al e

1VA AVG.

EPA elva TVA AVC.

EPA val e TVA AVG.

EPA v I e TVA Av Date ~3d WARL EARL ~3a IIARL ML ~(3

",. IIARI. EARL ~3a WARL EARL ~3a WARL ML ~3a WARL ML ~3a 'IARLEARL 4/82 25+9 29 28 16e2.6 16 13 '8t9 31 30

~

0 7/82 5.4+1.4

',.7 5.'1 10/82 0

<10

<10 18.6+2.6 19.5 12.8 42+10 43 42 34i9 34(

35 0

<29

<15 1500i130 1590 1413 30i6 32 29

<25

<20 1560+135 1563 1639 Strontium 89 EPA value TVA AVC.

Date

~(+3a WARL EARL 7/82 26+9 30 28 11/82 0

10

<40d F. Foods (pCi/kg, 'Wet Weight)

Strontium - 90 Iodine 131 Cesium '137 EP* v I

TvA Ava.

EPA el 3WA AVG.

EPA el e lvA

~(3a IIARL EIIRL

~(~3a WARL ML ~3a WARL 20e2.6 268'7 94e15 98 98 20i9 24 27.8-2.6 30.6 24~

25A10 20.

29 27+9 28 26 0

27 0

<25

<14

<25

<14 Barium 140 AVC.

'PA val e I~VVG EAIIL

~A3a WARL EARL Potassium EPA value

~(3e 328 WARL EARL

~

2400e208 28109 27339 2780i242 2670'903 Western Area Radiological Laboratory, Muscle Shoals, Alabama b

Eastern Area Radiological Laboratory, Vonore, Tennessee c

Ho known explanation.

Investigation underway.

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 results satisfactory.

Mn known explanation.

h NRC/EPA Low-level Iillstudy.

i Experimental detection limit is being reviewed.

Potassium values are mg/1 or mg/kg.

k Review of procedure is in progress.

kskPt is II I

'c 1

I PAOVCAHI M

0.,= 5

.(,

I

+p rACHSONi LOOISVA.Lf I

N D.

f tvANSVA.LE

'~T TENNESSEE VALLEY PEGION (TVA NUCLEAR PLANT SITES)

V A

BOWLING GREEN SLN

+HvNTGVILLE h+

VO+ENSGONO r'

K E

N T

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r/

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I NASHVILL OAIC RIOGEJ l

I r

r f

1

/ Jl rJ CHATTANOOGA~

I

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-I I

S C

A R.

J MOSCLE SHOALS M

I S S.

A L

A l~

B A'M A

G EORG I

A LEGEND

- HARTSVILLE NUCLEAR PLANT fggij -PHIPPS BEND NUCLEAR PLANT

~-CLINCH RIVER BREEDER REACTOR

-WATTS BAR NUCLEAR PLANT

-SEOUOYAH NUCLEAR PLANT.

-BELLEFONTE NUCLEAR PLANT

- BROWNS FERRY NUCLEAR PLANT

- YELLOW CREEK 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 preoperytional '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 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 flow of 3 fta/min.

In series wi'th, but downstream of, the particulate filter is a charcoal filter used to collect 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"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 di:sintegration 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'ollection.

The

. samples are co'mposited monthly for analysis of specific gamma-emitting radio-nuclides and. quarterly for Sr and Sr analysis.

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

During this reporting period, one sample wa's 'not obta'ined.because of equipment malfunction.

These data are presented in table 6.

The annual averages

'of the gross beta activity'n the air particulate filters at the indicator stations (local and perimeter monitors) and at the control stations (remot'e monitors) for'he 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.

TVA at nonoperating nuclear power plant construction sites.

Table 5 presents the maximum'permissible-concentrations.

(MPC) specified in 10 CFR 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 lost, destroyed, or damaged and analysis was not performed.

12:

Charcoal filters are collected and analyzed for radioiodine.'he 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

~

'ttl' Table '

MAXMJH PERMISS IBLE CONCENTRATIONS

'OR NONOCCUPATIONAL EXPOSURE Alpha In. Water

~Ci/I*

~ 30 In Air" gCi/m *

'Nonvolatile bet p I

Tritium',

3,000'00 3;000,000

'00,000 137C

$ <5Rg

) 44

'9 5Zr 9 5Nb 140ga 140L I

20,000 100000 10,000 60,000

'0,000 500 200 200 1',000 1,000 13)Z

.55Zn "Hq 60( o "Sr 9 OS~

I 51cr 134CS 58CO

~

I

)

300 100,000 100,000 30,000 3,000 300 2s000s000 9,000 90,000 100

".2,000 1,000 300

.300 30 80,000 400

'0000

1pCi-3,7 m

10 'q.

TABLE 6 NAHE OF FACILITY BROUNS ~FRRY LOCATION OF FACILITY ggM~~Qf R'AOIOACTIVITY IN AIR FILTER PCI/H (3) 0 ~ 037 BO/H (3)

~lAII4 DOCKET N0t ~5~~9~~0$

~9 REPORTING PERIOD 1~9/

TYPE AND TOTAL NUMBER OF ANAL'YS IS P~RFDRllm GROSS ALPHA 51 GROSS BETA 571 GAHHA (NAI) 83 CE-141m 144 K-40 FE-59 1-131 BE-7 LONER LIMI7 OF DETECTION

~D) 0'05 0'10 00030 0'00 NOT ESTAB 0 ~ 010 NOT ESTAB ALL INDICATOR LOCATIONS HEAN (F )

RANGF.

N l(ITM MIG~HST ANN~~M~A NAHE HEAN (()

0 ~ 02 (

47/

52) 0 ~ 01-0 ~ 04 0 ~.05 (

2/

67) 0 F 04" 0'5 67 VALUCS <LL'0 LH2 BF NORTH 0 ~ 9 NILE NNE 0 ~ 05(

1/

7) 0 ~ 05-'

05 0 ~ 00(

0 ~ 00 G~G2(

0 ~ 01-0'7(

0 ~ 01-6/

67) 0 F 00 4/

67) 0'2 67/

67) 0 ~ 1G DECATUR'L 8 ~ 2 HILES SSE DECATUR'L 8'

MILES SSE ATHENS'L 10 ~ 9 MILES NE 0 ~ 00(

0 ~ 00 0 ~ 02 ('

~ 02-0 ~ 08(

Oi05-1/

8) 0 F 00

'1/

8)

Oa02 8/

8) 0 ~ 10 0'2( 426/ 468)

DECATUR'L 0 ~ 01-0'4 8'

HILCS SSE CONTROL LOCATION)

MEAN (F)

RAtfgJ; 0 F 01(

1/

51) 0 F 01-0 F 01 0002(

96/

103) 0 F 01-0'4 16 VALUES <LLO I

0'2(

1/

16) 0 ~ 12-0 ~ 12 16 VALUES <LLO 16 VALUES <LLD 0'7(

15/,16) 0'5-F 11 NUMBER OF NONROUTINE REPORTED MfAQU~RHfNT8 8 I-21 4 PB-214 PB-212 RA-226 BE-7 TL-208 AC-228 SR 89 SR 90 44 44 0 ~ 020 0'20 NOT ESTAB NOT ESTAB 0'50 NOT ESTAB NOT ESTAB 0 ~ 005 0 ~ 001 GAHHA (GCL I )

60 K-40

-NOT ESTAB 0'2(

32/

50) 0 F 00-0'4 0 F 05(

3/

50) 0 F 04-0 F 05 0 F 04(

3/

50) 0 ~ 03-0'4 0 F 00(

" 26/

50) 0 F 00-0 F 00 0'2(

5/

50) 0 F 00-0'4 0 F 06(

20/

50) 0 F 05-0 ~ 07 0 ~ 00l 15/

50) 0 F 00-0 ~ OG 0 F 01(

2/

50) 0 F 00-0 F 01 36 VALUES <LLD ANALYSIS PERFORHED 36 VALUES <LLO ANALYSIS PERFORHEO LH4 BF TRAILER P 1 ~ 7 MILES NNV ROGERSVILLE ~

AL 13 ~ 8 HILES NV ROGCRSVILLC ~

AL 13 ~ 8 MILES NN DECATUR'L 8'

HILCS SSC COURTLANDt AL 10 ~ 5 MILES IJSU LH5 BF DAVIS F 2~5 MILES MSM LH4 BF TRA1LER P

1~7 MILES NNV ATHENS'L 10 ~ 9 MILES NE 0'2(

0 ~ 02-D ~ 05(

0 F 05 0 F 04(

0'4 0'0(

,0 ~ 0 0-0~04(

0'4" 0 F 07(

0 ~ 07-0 ~ 00l 0 ~ 00-0<<OI(

0 ~ 01-3/

5) 0'4 1/

1) 0'5 1/

7) 0'4 2/

5) 0 F 00 1/

5) 0 F 04 1/

5)

D ~ 01 1/

5) 0 F 00 1/

5) 0 F 01 0'2(

8/

10) 0 F 00-0'3 0~03(

I/

10) 0'3-0'3 10 VALUES <LLO 0 F 00(

4/

10) 0 F 00-0'2 10 VALUES <LLD G ~ 06(

5/

10)'

'5 Oe10 G ~ 00(

5/

1G) 0+00-0 F 00 10 VALUES <LLD 8

VALUES <LLO 8

VALUES <LLD a.

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

b.

Mean and range based upon detectable measurementa only.

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

NAME OF FACILITY BROVNS FERRY LOCATION OF FACILITY~~~Q~

TABLE 7

RADIOACTIVITY IN RAINVATER PCI/L - 09037 80/L.

SOCKET NO 52 2~59 26II 292

'EPORTING PERIOD $982 TYPE ANO TOTAL NUMBER OF ANALYSIS P~Rf ORMS j)

GAHHA (NAI) 119 FE-59 BE-7 NOT ESTAB NOT ESTAB 2 ~ 76(

14/

97) 0 '10 F 50 36 64(

54/

97) 1970-71 'O GAHHA (GELI) 24 K-40, NOT ESTAB 81-214 PB-212 BE-7 AC-228 TRITIUM 143 NOT ESTAB NOT ESTAB NOT ESTAB 15 ~ 000 330 F 000 4'5(

2/

20) 1 ~38-6171 0931(

1/

20) 0'1-0931 3'8(

12/

20) 0'924-Te31 53'2(

3'/

20) 31o55-7S ~ 36 17990(

1/

20) 17'0-17'0 117 VALUES <LLD ANAL'YSIS PERFORHEO LOVER LI HIT ALL OF INDICATOR LOCATIONS DETECTION HEAN (f)

~LLD)

RANGE LM3 BF NORTHEAST 1 ~ 0 MILE ENE LH5 BF DAVIS F 2 ~ 5 MILES

'VSV 4O95(

2/

10) 4'0-5950

'5 F 71(

7/

10) 30+00-66'0 ROGERSVILLEo

.AL 13 '

HILES NV ROGERSVILLE ~

AL 13 ~ 8 MILES t(V LH2 BF NORTH 0 ~ 9 HILE NNE ROGERSVILLEO AL 13 ~ 8 HILES ttV LH3 BF NORTHEAST 1 ~ 0 MILE ENE 6 F 71(

6 ~ 71-0'1(

0 ~31-

= 7'1(

TO31-75 ~ 36(

75936-17'0(

17 ~ 90-1/

2) 6'1 1/

2) 0 ~ 31 1/

1) 7'1 1/

2) 75'6 1/

3) 17 '0 NAME HEAN (F)

ISTANCE AND DIRECT'ION RANGE b CONTROL LOCATION(

'EAN (F)

P~AGIE 5 65(

4/

22) 0'0-..

9'0 4S ~ 95(

14/

22).

15'0-.

84 ~ 60 I ~ 76(

1/

4) 1 ~ 76-1'6 4

VALUES <LLO

2'6(-

2/-

4) 2o31-2'1 VALUES <LLO 4

VALUES <LLD 26 VALUES <LLD NUMBER OF NONROUTINE REPORTED SEA~SOS IIENTS

. a.

Noninal Lover Limit of Detection Q.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 RAOIOACTIVITY IN HEAVY PARTICLE FALLOUT NAHE OF FACILITY QROVNS QfRRY LOCATION OF FACILITY~QHfSTONQ HCI/KH(2) 37000000

~ 00 BQ/KH(2)

DOCKET ALABAHA

'EPORTI NO. ~o-g~~kOo.22k NG PERIOD

) 982 TYPE ANO TOTAL NUMBER OF ANALYSIS EfJKQEBQ?

GROSS BETA 130 LOVER LIMIT OF DETECTION (LU}l 0.050 ALL INDICATOR LOCATIONS MEAN (f)

~MQE 0121(

107/

107) 0 05-0 gg~TQN~VTH HjGH~~S4I~JM Al IIE4H NAME HEAN QF~

D~E52~4ILQLRHIlM R~AE"=

COURTL ANOt AL 0 ~ 31 (

12/

12) 10 ~5'ILES

'VSV 0 ~ 14-

. 0'4 CONTROL LOCATION[

MEAN (K)

Q~Ajjf 0'0(

23/

23) 0 07 n ~ 41 NUMBER OF NONROUTINE REPORTEO Zr.aruWRm<Zs 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 parentheses (p}.

TABLE 9 r RADIOACTIVITY IN CHARCOAL FILTERS

~ PCI/H t3)'

037'BQ/Hf3)

NAIIE OF FAC ILITT ~RII S ffuff LOCATION OF FACILITY LIMESTONE A~A/AHA REPORTING PERIOD 19BP TYPE AND LOVER LIHIT.

ALL TOTAL NURSER 'F IHOICATOR LOCATIONS

~IICAT O~MH TH NBBK~uuu!IL~Au OF ANALYSIS DETECTION MEAN l()

NAHE MEAN i/3'eufuuMfu

~LRI 'INSE uesT<<cf Am ufmzee~

RAuue =

IODINE IN AIR 0 ~020; OM03(

39/.467)

ROGERSVILLE% AL OH,03(

12/

.52) 569 0.02-0.07.

13.e MILES NV 0.02-

..0.07 CONTROL

.LOCATIONS HBAN (F)b Rangy b 0 ~ 03L

'10/ 102)

OM 02 0 ~ 06

. NUMBER OF NONROUTINE REPORTED a.

Noninal Louver Lieuit of Detection (LLD) as described in Table 3

b.

Mean and range based upon detectable cTeasureuTents only.

Fraction of detectable measurefuents 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 PM-IBF WHEELER ROG"PSVILI <

OAM LEIGHTON COURTLAN0$

PM-4 F

ATHENS PM-28F BROWNS FERRY NUCLEAR PL NT OECAT R PM-38F0 HUNTSVILLE jRUSSELLVILLE IO MILES HARTSELLE T

SVIL OAM HALEYVILLE CULLMAN 45 MILES RAINWATER SOIL CI ENVIRONMENTAL MONITORING STATION NOTE: THE FOLLOWING SAMPLES ARE COLLECTED FROM EACH STATION:

AIR PARTICULATES RADIOIODINE HEAVY PARTICLE FALLOUT

PigUL e 3

.. LOCAL MONITORING STATIONS BROWNS FERRY NUCLEAR PLANT.

19 ATHENS U S HWY 72 BFN ALA. HWY 20 Legend 0

Air Monitor Autom'atic Well Sampler H

Dairy Farm DECATUR Scale 0

I

.2 S

O 5

Miles

p =(

20 r(

~<<II <<A,r rl;r 1" ~

-Figure 4

TLD Locations BFN

/7 n~r

\\(('tl

'tf ~

'I(

'i,(J./ a

(

(I

~

'l.l/)(i r (I: / t I

'I (t pt II Jg rc wl

~

.1 p

'I l l~I.

I ~ I 1

~

I 0.

~ ~

t ~,(I A

n'.

~'C'

(

~

i Il}i;

~ I III I

I

~

I

((rr}I

(

)(I I

~

".~ ~ -~tl

lN.

t

>'1 ~

.)

!t

~ I, (II

~

I

,1(

I i~

hI I ~

r I

~ rr I

'i,(II,.

~

l I

<<N N

~l IL

(/

jl N

i

(

N

.J N

N N

NN J...

It}

i I

~ I 1 ~

N

~ (

'I I,j~(~

I('+Q

~

-(

I

- ~,

~ }

I

~ 1 (N

1

Figure 5

.30

.25 Preoperational Phase I

Operational Phase Aeeu. AVERAGE 6ROSS BETA kTIVITY

>N 'A>R FtLTERS BR0WS FERRV Hua EAR PuWT.

Jt8 O0

.20

.15

.10 ClC" 0

tO H C JJ 0 E4 JJ IJ JJJ JO JJ tJ Qt 0

JJ A 0 0 tJ C

C 0 w O Ave~ra c:

Preo~erational Phase t

F< ',

K

.05 1968 1969 1970 1971 1972 1973P 19730 1974 1975 1976 19 7

1978 1979 1980 1981 1 82

23 Terrestrial Mon'itorin Milk Milk.is collected from f'our l'arms within a l0-mile radius of the plant (see figure 3),

and from at least.

one of four control 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,1982.

It was determined that there are no dairy farms nearer the plant than the nearest farm being sampled.

During this period however,'ne of the dairy farms being

'sampled (farm T,.table 2) went out of business,and all cows were s'old.

V~eetatian

'egetation is sampled quarterly at the farms from which milk is collected and analyzed for gamma-emitting radionuclides.

Approx'imately 1"2 kilograms of grass is broken or cut at ground level and returned for analysis.

Efforts are made'o sample vegetation that is representat'ive of the pasturage where cattle graze.

- Table ll gives the results obtained from the laboratory analy'ses of these samples.

Soi3, samples are collected annually near each monitoring station to pgovide 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.Water An automati,c 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 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 sampl'er 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 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.

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 site 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 calibratio'ns 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

'verage 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 construct:ed for each set.

Figure 8 presents a trend plot of thy direct radiation levels as defi'ned by the moving averages.

The data follow 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'ncluded in this report.

Therefore, for comparison

purposes, figures 9 and 10 depict the environmental gamma radiat,ion 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 Coo s

Food crops 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 radionuclid'es.

During this sampling period, samples of

corn, green beans,, potatoes, turnip greens, and tomatoes were collected and analyzed for specific 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

~O RADIOACTIVITY IN MILK PCI /L -

0 ~ 037 80/L TYPE

'ND TOTAL iNUHBEo OF ANALYSIS

~~Hfj}

GAHHA (NAI) 83 CS-137 K-40 IOOINC-131 416 GAMMA tGELI) 2G CS-137 K-40 81-2)4 PB-214 PB-212 AC-228 LOVER LI)(IT OF DETECTION LLLQl 10.000 150eDOO 0 F 500 F 000 NOT CSTAB NG I ESTAB NOT ESTAB NOT ESTAB NOT CSTAB ALL INDICATOR LOClglONS

'.HE AN (g )

RANGC 11 '0(

1/

42) 11 F 10-11 F 10 1306e32(

42/

42) 694+00-1553'0 212 VALUES'LLO ANALYSIS PERFORHED 6 ~ 31(

3/

11) 5o50-7 F 51 1269 F 10( ll/

11) 747 '1 1499'3 49'9(

2/

11) 38 ~ 29

~ 61 ~ 69 le 25(

2/

11)

PO ~ 76-61+74 1 ~ 69(

6/

11) 0.06=

4.08 11 VALUES <LLD

'SR 89 SR 90 103 103 10.000 2 ~ 000 53 VALUES <LLO ANALYSIS PERFORHEO 4(3P(

45/

53) 2p09-10 F 14 hAHC OF FACILITY QROUNS FERRY LOC( T 104 OF FACILITY J,Q~HQ/ON~

ALA/AHA PAGE FARH '

I 75 MILES E

otGr FARM 6 ~ 75 MILES E

PAGE FARH 8 ~ 75 HILES E

LOONEY FARM 5 ~ 75 'MILES ENE SMITH FARM 4 ~ 75 HILCS N

SMITH FARM 4 ~ 75 MILES N

BROOKS FARH 7 '

MILES NN)t SHI TH FAR

"(

4 ~ 75 HILES N

DOCKET NO ~ ~P~A~~9 REPORTING PERIOD 1~9 CONTROL LOCATIONS MEAN (F )

RANGE 6'2(

5 ~ 93-1354 '6(

1209 ~ 10-.

49'9(

38'9 41'5t 20 '6 2'3(

I ~ 58 2/

3) 7.51 2/

2) 1495+&3 2/

3) 69 2/

61 ~ 74 2/

3) 4 F 08 9

VALUES <LLO 1256 '7(

9/

9) 1175 '6-1362'5 c

VALUES <LLO

& ~ 02(

2/

9) 7'2-8 ~ 82 3'4(

3/

c)

I ~ 94 5'9 3'3( '/ ')

F 85-3'1 50 VALUES <LLO 5465(

12/

13) 3'6-10 F 14 3'9(

46/

50)

F 08-9'2 11 ~ 10(

1/

10) 41 VALUES <LLO 11 F 10 II~ 10 1373 '1(

10/

~ 10) 1297 F 16(

41/

hl) 1156 F 80-1455 F 50 1036 F 80-1451e60 204 VALUES <LLD NUMBER OF NONROUTINE RCPORTCD H~A1!EK~HNIS a.

No'minal 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 (P) 0

TABLE ll RADIOACTIVITY IN VEGETATION NAME OF FACILITY RROVNS FERRY LOCATION OF FAC ILI TY QQH~S~TNQ PCI/G 0 ~ 037 80/G (ORY VE IGHT)

Aj ABAHA DOCKET t)DE 50-259a260

~ 296 RI.PORTING PERIOD 1/$ 2 TYPE AND TOTAL tkUNBEP OF ANALYSIS PQtfOR 4Q)

GROSS BETA 33 GAHNA (G:LI) 33 LOVER LIMIT OF "DETECTION LLJ D 0 '00 ALL INDI'CATOR LOCATIONS HEAN ([)

RANGf 23'2(

17/

17) 3'9 69'3 NAME rEAN (F) o THRASHER FARH 69 F 43(

I/

1) 7 ~ 0 MILES ENE 69 ~ 43 69 ~ 43 CONTROL LOCATIONS MEAN t F )b RANGEb 30'3(

16/

16)

F 80-57'4 NU!(BER OF NONROUTINE REPORTED MEASURfHfNTQ CS-137 K-4 0 BI-214 81-212 PB-214 PB-212 RA 226 BE-7 TL-208 AC-228 0'60 NOT ESTAB 0 F 100 NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB 0 ~ 13(

4/

17) 0 F 07-0'8 14 '2(

17/

17) 1 ~ 87 46 ~ 29 F 10(

1/

17) 0'0-0'0 17 VALUES (LLO 0'9(

8/

17) 0 F 01 0'3 0'6(

15/

17) 0 F 00-0 ~ 16 0 ~II(

8/

17) 0 F 02-0'0 5'6(

17/

17) 0'3-

~ 15'6 0 F 02(

11/

17) 0 F 00-0 F 06 0'7( 12/'7) 0 ~ 02-1 ~ 15 SMITH FARH 4 ~ 75 'HILES A

TNR ASHER F ARM 7 ~ 0 NILES ENE SHITH FARN 4 ~ 75 MILES N

SHITH FARM 4 ~ 75 HILES N

SNITH FARN 4 ~ 75 MILES N

PAGE FARM 8'5 MILES E

BROOKS FARN 7 ~ 0 MILES NNV Tt(RASHER FARN 7(0 MILES'NE

~

THPASHER FARM 7 ~ 0 MILES ENE 0 ~ 18(

0 ~ 1 o-6 ~ 2o 46'9 0 ~ 10(

0 ~ 10-0'2(

0 09 F 07(

0 ~ 00-0'6(

0'2 7'2(

2 ~ 35-.

0 F 04(

0 ~ 04-1 ~ 15(

I ~ 15-I/

4) 0 ~ 18 1/

1) 46'9 1/

4) 0 ~ 10 3/

4) 0'3 4/

4) 0 ~ 16 2/

4) 0 ~ 50 4/

4) 15+06 I/

1) 0 F 04 1/

1)

I ~ 15 0 ~ 07(

0 ~ 07-20 F 70(

4'5 F 16(

0 ~ 16 0'1(

0 ~ 31-0'7l 0 ~ 00-0'6(

0 ~ 02-0 F 07(

0 ~ 01-4'7(

0 ~ 92-0'4(

0 ~ 01-0 ~ 14(

0'3 3/

16)

F 08 15/

16) 46 F 06 1/

16) 0 ~ 16 I/

16) 0 ~ 31 8/

16) 0 ~ 18 12/

16)

F 11 9/

16) 0'6 15/

16) 4 F 89 10/

16) 0'6 8/

16) 0'6 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 l2 NAtlE OF FACILITY ~RQ~P LOCATION OF FACILITY LIHESTONE RADIOACTIVITY IN SOIL PCI/G -

0 ~ 037 80/G (ORY.)JEIGHT)

ALABAMA DOCKET NOe~~agtt(tAg~

REPORTING PERIOD 19~8 TYPE ANO TOTAL NUMBER OF ANA(.YSIS HEQMG?

GAMMA'GELI )ll LOVER I.IHIT.

'LL OF INDICATOR LOCATIONS DETECTION

'EAN (E)

~lJJ}1 RANGE QOCA~TON itl H

H GH T

QgfJ fA~MAQ CONTROL LOCATION)

MEAN C()

RANG NGf NUMBER OF NONROUTINE REPORTED HfAS~R HfQTS CE-144 CS-137 K-40 MN-54 BI-214 BI-212 PB-214 PB-212 RA 226 RA-223 RA-224 BE-7 TL-208 AC-228 PA-234H SR 89 SR 90 Oo060 0'20 0'50 Oe010 0 ~ 050 0 F 100 0 F 050 NOT ESTAB 0 ~ 050 NOT ESTAB NOT ESTAB 0 '60 0 '20 0'60 NOT ESTAB 1 o500 ll 0 ~ 300 11 9 VALUES <LLD 0 ~ 40 (

9/

'9)

,0 F 05 lo.17

,5'2(

9/

9) 3'6-8 ~ 13 0'2(

2/

9) 0 F 01-0'2 0 91(

~ 9/.

'9) 0'5-1 ~ 18.

1 ~33l; 9/

9)

Oe68 1 ~ 78 d o02(,9/

9) 0 ~65-1 ~ 33 1 ~ 09(

9/

9) 0'2-F 45 0'1(

9/

9) 0 F 55-1 ~ 18 0'1(

6/

9) 0'4-0'7 0'9(

4/

9)

Oo53-1 ~ 42 9

VA'LUES <LLD 0 ~36(

9/

9) 0'0-

" 0'5 I ~ 12(

9/

9) 0'0-

'o51

'2 F 81(

4/

9) 2'4-

'F 15 1 ~ 82(

1/

9) lo82-lo82 9

VALUE'S <<LLO ANALYSIS PERFORMED ATHENS'L 10 ~ 9 MILES NE LM4 BF TRAILER P 1 ~ 7 MILES tJNIo LH5 BF OAVIS F

2 5

MILES VSit LH4 BF TRAILER I '

~ 7 tlILES NNII LH4 BF TRAILER P 1 ~ 7 MILES NNIJ LH2 BF MORT)I 0 ~ 9 MILE NNE LH4 BF TRAII.ER P 1 ~ 7 'ILES tJNU LH4. BF TRAILER P 1 ~ 7 tlILES NNlt LH3 BF NORTHEAST 1 ~ 0 HILE ENE LH4 BF TRAILER P 1

7 tlILES tJNiJ LH4 BF TRAILER 1 ~ 7 tlILES tJN'M LH4 BF TRAILER 1

7 MILES NNv LH5 BF DAVIS F 2 ~ 5 MILES )JSV ATHENS'L 10 ~ 9 HILES NE 1 ~ 17(

I'i17-

=

Be13(

8 ~ 13-0'2(

0 ~ 02-1 ~ 18(

lol8 1 ~ 78(

1 ~ 78-1 ~ 33(

.1 ~ 33-1 ~ 45(

1 ~ 45-1 ~ 18(

1 ~ 18-0'7(

0 ~ 37-.

1'2(

1 ~ 42" 0 ~ 45(

0 ~ 45-lo51(

F 51 F 15(

3 ~ 15-I' 82 (

lo82-1/

1) 1 ~ 17 1/

1) 8'3 1/

1) 0'2 1/

1).

1o18 1/

1) 1 ~ 78 1/

1) 1 ~ 33 1/

1) 1 ~ 45 1/

1) 1 ~ 18 1/

1) 0'7 1/

1) 1 ~ 42 1/

1) 0'5 1/

1)'

~ 51 1/

1) 3'5 1/

1) 1 ~ 82 0'2(

1/

2)

,0'2 0'2 1 ~ 17(

2/

2)

F 01-1 ~ 33 4'7(

. 2/

2) 4'7-5'T 2

VALUES <LLO 0 F 81(

2/

2) 0'3-0'9 1 ~ 03(

2/

2) 0 91-1 ~ 15 0'0(

2/

2) 0'3-0'7 0'6(

2/

2) 0 ~ BG-0'2 0 F 81(

2/

2) 0'3-0'9

~ 1 ~ 97C 2/

~2) 0'0-

~

3'4 2

VALUES <LLD 0'1(

2/

2) 0'0-0'2 0'0(

2/

2) 0 28-0'3 0 F 88(

2/

,2) 0'9-

~ 98 1 ~ 38(

1/

2) 1 ~ 38-'

~ 38 2

VALUES <LLD 2

VALUES <LLO 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 13 RADIOACTIVITY IN 'MELL MATER PCI/L -.0%037 BO/L I-131 15 ~ 000 8 VALUES <LLD NAME OF FACILITY BROMNS FERRY LOCATION. OF FACILITY~~QQf.

TYPE ANO LOMER LIMIT ALL TOTAL NUHBER OF INDICATOR LOCATIONS OF ANALYSIS DETECTION

~

HEAN Cg )

~P~~RH Q ~~ )

RANG/

GAHHA (NAI) 19 FE-59 8 VALUES <LLO NOT ESTAB DOCKET NO ~

0-259 260 296 REPORTING PERIOD )9ag CONTROL LOCATIONS IIEAN llj) 4'5(

2/

11) 2'0-.

F 80 15'0(

1/

11) 15 ~ 20-153 20

.NUHRER OF NONROUT1NE REPORTED Hf~A ~R uENTS PB-212 TL-208 TR IT IUH 8

NOT ESTAB NOT ESTAB 330 F 000 GAHHA (GELI) 7 BI-214 NOT ESTAB 14'6(

1/.

5) 14'6-14 '6=

1 ~58(

2/

5)

Io25-I+90 2'5(

2/

5)

I ~ 85 3'6 4

VALUES <LLO ANALYSIS PERFORHEO BFN MELL ¹6 0~02 MILES M

BFN MELL ¹6 0 ~ 02 MILES M

BFN MELL ¹6 0 ~ 02 HILES M

14'6(

14'6 1 ~ 58(

"1 s 25-2'5(

1 ~ 85-1/

5) 14'6 2/

5.)

I ~ 90 2/

5) 3'6 2

VALUES <LLD'

~ 99(

2/

2) 0.'78-1.20 2

VALUES <LLO VALUES <LLO 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 parentheses (P).

TABLE 14 RADIOACTIVIT'Y "IN PUBLIC I(ATER SUPPLY NAME OF FAC ILITY Q~RU EEBBX LOCATION OF FACILJT'Y LJ~ESIOK'C I/L 0

G37 BQ/L ALAPAHA DOCKET NO ~ 50 PQ9AP{iOX2~k REPORTING PERIOD~)9 g

TYPE ANO

.TOTAL NUMBER OF ANALYSIS GROSS BETA 89 GAHHA (t(AI) 70 FE-59 LONER LIHIT OF DETECTION (l lR) 2 ~ 400 NOT ESTAB PB-214 NOT ESTAB PB-212 NOT ESTAB TI.-208 NOT ESTAB SR 89 10 F 000 16 SR 90 F 000 16 TRITIUH 330 000 16 GAHHA (GELI) 19 K-40 NOT ESTAB.

ALL INDICATOR LOCATIONS MEAN (F P

~

RANG/

.3 ~ 60 (

51/

76) 2 +42-13+53 3 ~ 85(

6/ '2)

I 00" 6'0 1 ~ 04(

I/

14)

,1 o 04-1 ~ 04 8 47(

1/

1'I) 8+47 8 ~ 47 3+GB(

9/

14) 1 ~ 03-F 09 0 '2(

5/

14)

Or25=

0 F 88 12 VALUES (LLD

'ANAL'YSIS PERFORHEO 12 VALUES lLLO ANALYSIS PERFORMED 395 F 05(

2/

12) 370 F 86-419 '4 SHEFFIELO ~ AL ROB TRH 254 '

6'0(

6'C I/ ll) 6+60 CHAMPION PAPER TRM 282 '

CHAMPION PAPER TRt( 282 '

MHEELER OAHe AL TRM 274 9

WHEELER OAHt AL TRu 274 '

I ~ 04(

1 ~ G4-8 ~ 47(

8 ~ 47-3%98(

3 ~98-0 ~ 63(

0 ~ 63-I/

10) 1 ~ 04 1/

10)

Gq47 1/

2) 3'8 I/

2) 0 F 63 CHAMPION PAPER TRu 282' 419+24(

419 '4" 1/

4) 4.19 ~ 24 i

I OQA~TQ

~It TH EITHER~'BIIIIil,LfA5 (t CHAHPION PAPER 3'3(

42/

50)

TRM, 282 '

F 47-13 '3 CONTROL LOCATIONS HEAN (F $

RAh(gf 2'7(

3/

13) 2'8-3'7 8

VALUES CLLD 9'6(

1/

5) 9'6-9'6 5

VALUES <LLD 1 ~ 78(

3/

5) 1 ~32-2'7 1 ~ 29l 2/

5) 0 +70-1 ~ 88 4

VALUES (LLO VALUES (LLO VALUES (LLO NUMBER OF NONROUTINE REPORTED HfgQU~R HQNQS 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 parentheses (F).

Table, 15 ENVIRONMENTAL GAMMA RADIATION LEVELS Average External Gamma Radiation'evels at 'Various Distances from Browns Ferry Nuclear.Plant for Each Quarter - 1982

,mR/Quarter

'Distance miles Avera e External Gamma Radiation 'Levels b 0-1 1-2 4-6 18.6'+ 2.0 17.9 +.I.7

,17.4

+. 1.6 16.8 + 3.2 16.3, + 1.5 16.1 + 1.4 20;8 + 1.1-.'.. 20.3 + 1.7

" 21.3 + 1.5 18.1 + 2.1.

17;5 + 1:8 17.6 + 1.6 21.9 + 1.6 16.3 +

4.0'5.8

+ 3.8

,15.'5. + 3.6

>6 17.4 + 2.6 16.4 + 3..0 17.3

+ 3.3 15.6 + 3.2

Average, 0-2 miles (Onside)

Average,

>2 miles.

'(Offsite),

20.3 + 1.6

'17.6+ 1.9 19.4 + 2.6 16.2 + 2.0 2.0.5

+ 2.1 17.5 + 2'.2 20.5

+ 3.4 15.6 + 3.4

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

b. All averag'es reported +la (68 percent confidence level).

TABLE 16 NAHE OF FACILITY QROMNS FLURRY LOCATION OF FACILITY I,~IH STONf, RADIOACTIVITY IN CORN PCI/KG -

0'37 BO/KG CMET MEFGHT)

ALABAMA DOCKET NO ~ ~0 2599~60 22)

REPORTING PERIOD 1982 TYPE ANO TOTAL NUHBER OF =ANALYSIS P~RQ~OR H GROSS BETA 2

GAHHA IGELI) 2 K-40 PB-212 TL-208 LOMER I IHIT OF DETECTION

~JI D) 25 F 000 NOT ESTAB NOT ESTAB NOT ESTAB 1990035(

1990 ~ 35-I ~ 38(

1%38 0 ~ 03(

0 ~ 03-1/

1) 1990 '5 1/

1) 1038 1/

I )

0 ~ 03 ALL INDICATOR LOCATIONS HE A,N IF )

RANGE 3667 '2(

1'/ ')

3667 '2-.

3667 '2 7 HILES NNlJ 7 MILES NNM 7 MILES NN)J 1990 '5(

1990 '5" 1 ~ 38C I ~ 38 0'3{

0 ~ 03-1/

1) 1990 '5 1/

1) 1 <<38 1/

1) 0 ~ 03

~OA~TON MI TM HIIGMQST ANNUA~LM AN NAME HE AN l Fb)

Iuu!u!'E ~4!!1K!'Ill!

7 MILES NNM 3667 ~ 62(

1/

1) 3667 62-3667 '2 CONTROL LOCATION(

HEAN t g)

R~Af, 4983 F 14(

1/

1) 4983 F 14-4983 '4

-2040 ~ 72(

1/

1) 2040 ~ 72 2040+72 1

VALUES <LLO VALUES <LLO NUMBER OF hONROU TINE REPORTED HfAggffMfNJS 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 FLURRY LOCATION OF FACILITY QJH/STONQ TABLE 17 RAOIOACTIVI TY IN GREEN BEANS PCI/KG -

0 ~037'O/KG (MET MEIGHT)

ALABAHA OOCKET NOe~0-/~~29/

REPORTING PERIOD 1982 TYPE ANO TOTAL NUHBER OF ANALYSIS ZKEEIEQf2 GROSS BETA 2

GAHHA (GEL I) 2 LOVER LI HIT OF OETECT ION

~~l IL>

25 F 000 ALL INDICATOR LOCATIONS HEAN ([)

kMif 4257 ~ 41 l I/..

I )

4257 '1-4257 '1 CONTROL LLLiIhEKE ANQ 21EQ;ILIA RMAK.

MBfid' HILES NNM

"'. 4257 ~ 41(

I/

I) 4751 ~ 82t I/,

I) 4257 ~ 41-4257e4 1

~

. 4751 ~ 82-4751 ~ 82 NUHBER OF NONROUTINE REPORTEO QQAQQQf;~H QQS K-40 PB-212 NOT ESTAB NOT ESTAB 1900 ~ 30(

1/

I) 1900 '0-1900' 30 I ~ 68(

1/

1) 1 ~ 68-I ~ 68 7 HILES NNM 7 HILLS NNM 1900 '0(

- I/

1) 1900p30 1900 '0 I ~ 68(

1/

1) 1 ~ 68-I ~ 68 2034 '2(

1/

I) 2034 F 02 2034 '2 4'8(

I/

1)

F 08-4 F 08 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 at specified I'ocations is indicated in parentheses (F).

TABLE 18 RADIOACTIVITY IN POTATOES PCI/KG 0 ~ 037 BO/KG (MET MEIGHT)

LOCA TYPE AND TOTAL NUHBER OF ANALYSIS t.'fRERE5ftl GROSS BETA 2

GAHHA <GELI) 2 NAHE OF FACILIT'Y QROVNS FfRRY TION OF FAC'ILITY~IQfSTONf LOVER LIHII ALL OF INDICATOR LOCATIONS DETECTION HEAN Jg)

REMif 25 F 000 5373 F 00(

I/

I) 5373 F 00- 5373900 ALABAHA DOCIIET NO,~O-EDRRERRRE 9

REPORTING PERIOD 19112 CONTROL LOCATIO)JJS HEAN IFf'280

'9l 1/

I) 7280 '9-7280 F 19

~f AN~QRfCjgQN

'~A 7 HILES NNM 5373900(

1/

1) 5373 F 00- 5373 'O NUHBER OF NONROUTINE REPORTED HfAQQ~R Hfg7S K-40 NOT ESTAB 3549.88(

1/

1) 7 BILES NNM 3549 '8 3549 F 88 3549 F 88(

1/

1) 3549 '8-3549 F 88 3337 '7(

1/

1) 333'7-3337 F 57 a.

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

b.

Mean and range based upon detectable measurements only.

Fraction of detectable measurer ants at specified locations is indicated in parentheses (F).

TABLE19 RADIOACTIVITY IN TOHATOES PCI /KG -

0 ~ 037 BO/KG (MET ME IGHT)"

NAME OF FACILITY QROVNS, ffRRY LOCATION OF FACII.I.TY L~HSTONQ ALABAHA DOCKET NO ~ 50-259 '60 296

~

9' REPORTING PERIOD 1982 TYPE AND TOTAL NUHBER OF ANALYSIS Pffft)RHfQ

%ROSS BETA 2

GAHHA (GELI )

2 LOMER LIMIT OF DETECTION

~(ie) 25 F 000 ALL INDICATOR LOCA/IONS MEAN (g )

~MQf 3987 89(

1/

1).

3987 '9-3987+89 LOCATION VITH HIGHEST ANNUAL HEAN NAHE MEAN (F)o QJQTQMg~aN~QIIIQQTJ~QANge 7 MILES NNM 3987 ~ 89(

.1/

I) 3987'9-3987 '9 CONTROL NUMBER OF

'LOCATIONS NOhROUTINE MEAN ([)

REPORTED

~(~A/f

~HC.QQP E ~H 4577 '5(

I/

I) 4577 '5-4577 '5 K-4 0 PB-212 NOT ESTAB NOT ESTAB 2172+52(

1/

1) 7 MILES NNM 2172~52-2172 F 52 2 54(

1/

1) 7 HII.ES NNM 2'4-2'4 2172+52(

1/

1) 2158 '4(

1/

1) 2172 '2-2172 '2

. 2158 '4 2158 '4 2'4(

1/

1) 4~76(

1/

1) 2'4-2o'54 4a76-4 ~ 76 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 parentheses (p).

TABLE ZO NAHE OF FACILITY BROVNS FERRY LOCATION OF FACILITY Q~~Qf RADIOACTIVITY IN TURNIP GREENS PCI/KG -

0 ~ 037 80/KG (VET VEIGHT)

DOCKET NO ~

50-2~59 2~0296 REPORTING PERIOD 1982 TYPE AND TOTAL NUHBER OF ANALYSIS Pf RQQRHQQ GROSS BETA I

GAHHA (GELI ) I LOVER LIHI7 ALL

,OF, INDICATOR LOCATIONS DETECTION HEAN (F )

(I I n)

RANGE 25 ~000,7719

~ 47(

1/

'1) 7719 '7-7719 '7 7 HILES NNV 7719 47(

1/

1)

~

7719 ~ 47-7719 ~ 47 CONTROL LOCATIONS HEAN.(F)b RANGLb NUHBER OF NONROUTINE

" REPORTED CS-137 K-40 PB-212 BE-7 TL-208 5 ~ 000 NOT ESTAB NOT ESTAB NOI ESTAB NOT 'ESTAB

~

7 ~ 03 (.

"7 ~ 03-3209 '1(

3209 ~ 21-7'8(

7 ~'4 8-105s52(

105 ~52-2 ~ 15(

2 ~ 15-1/

~ I) 7'3 1/

1) 3209 '1 1/

1) 7'8

'/1) 105 52 1/

1) 2'5 7 HILES NNV

'7 HILES NNV 7 HILES NNV 7 HILES NNV 7 HILES NNV 7p03(

7 ~ 03-3209 '1(

3209 '1 32 F 48(

7 ~ 48-105 '2(,

105 '2-,

I F 15(

2 ~ 15-1/

I) 7'3 1/

1) 09q2l 1/

1) 7848 1/

1) 05 '2 1/

~ 1) 2'5 a.

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

b.

Hean and range based upon detectable measurements only.

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

t C

J P

COo O

CCo JJ o

ttt CJ CJ co ttt CJ Cp CO 0cr ctl 0 Ct

~J

'o c o

o.

Q Preoperational Phase P

P P

I P

Operational Phase 1

'NNIALAVERAGE.

'ROSS HEFA ACTIVITY IN HRI Nilt5 HATER 3JPPLIES.

BOWN FERRY Nua.EAR MhT" t

k I"

I' PC Pt

'3'9 8

19 9

19 0 1

1 19 2

19 3P 19 30 19 4

1 5

19 6 1

7

.19 8c 1

9 "19 0 1

1: '2

38 Figure 7

Oirect Radtation Levels Browns Ferry Nuclear Plant

,22 I

18 C7 CCe 16 Onstte

.P I

e" 1

~

o I

d.

'\\

1

\\

1

'gr IL'

/

1 I 'i

/

-1 LI '/

1 Jt 1

9 p,

I

/'L

~ l I '1

'5

'1 0

0

~ /

0 I<Offst te 12 1 970

~

1977 1978

.197g 1988 1981 1982 Ptsure 8

22 Oirect Radiation Levels Biowns Ferr y Nuclear Plant 8-Quarter Moving Average

s. 18 8

OILst te rO.,R

/

.o.

P:

o

,/

Offstte 1975 'g77 1978 1979 1988 1981 1982

39

,2W Fttture 9 Oirect Radtatlon Levels Mot ts Bor Nuclear Plant 22 Ce C

18 ot s

ty I

/

I I

Onstte Otfsi teo 9-o.,

I t

~I I

~ I O.

/

b I

9 o

I

'. i

\\ j tt P~

II s~o-.e.~

12 19?5 1977 1978

1979, 1988 1981 1982 Ftgure 10 Otrect Radtotlon Levels Motts Bor Nucleor Plont

'1-Quarter Moving Average 22 t.

18 a

8 Onstte

,/

0 e ~

0 o

I

~

~o o~

Of fs1 te o-.e..~

0 I

0, I

'a, 0'

97d 1977 1978 1979

't 988 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 b'ottom 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 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 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 22.

Figure 12 presents a plot of the gross 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.'ish Radiological monitoring for fish is accomplished by analysis of composite samples of adult fish taken from each of Lhree contiguous reser'-

vojrs--Wjlson, Wlleejer, and Guntersviile.

No permanenL sampling sLaLions 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'ufficient 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 p 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 Sediment 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 from each of four stations.

Locations. of these stations are shown in table 21.

Results are shown in table 26.

'Bottom Fauna The flesh and shells of Asiatic clams collected semiannually from the cross sections at four stations (table 21),are analyzed for gamma-,emitting

~radionuclides.

Levels of Sr and 9 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, two samples of clam flesh contained insufficient volume for analysis.

'Results are given in tables 27 and 28.

Table 21 SAMPLING SCHEDULE - RESERVOIR MONITORING

.Biolo ical sa les (collected semiannuall

)

River/river mile Zooplankton, chlorophyll, phytoplankton Benthic

'auna Sediment

= Water. Samples Fish (collected monthly).

.Tennessee 277.9 Tennessee 285.2 "Tennessee 288.7 Tennessee 291.7 Tennessee 293.5 X

X X

Tennessee 293.7 (discharge area) c-Tennessee 305.0

. (Control) b'ennessee 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 Guntersvil'le,

Wheeler, and Wilson Reservoirs.

.b.

Automatic sampler.

c.

Grab sample.

NAHE OF FACILITY PROVNS F/RRY LOCATION OF FACILITY~lttrSTOQf.

TABLE 22 RaOIOACTIVITY IN SURFaCE VATER TOTAL PC I/L -

0 ~ 037 80/L TYPE AND TOTAL NUHBER OF ANALYSIS GROSS BETA 65 GAHHA (NAI) 44 LOVER LIMIT OF BET EC TI ON 2 ~ 400'LL INOICtTOR LOCATIONS uCAN (F)b RANGE b 3 '9(

35/

39) 2'7-8'5 LOCATION VITH HIGHEST ANNUAL HEAN NAt!E HEAN (f)

DISTANCE At)O DIRECTION RANGE TRH 28' 4'1 l 12/

13) 2'2-8 ~ 35 CONTROL LOCATIONS HCAN (F)b RANGE 3'3(

20/

26) 2 42-6'5 NUHBER OF NONROUTINE RCPORTCD HEASUREHCNTS FE-59 1-131 NOT ESTAB 15 F 000 5 ~ 40(

3/

24)

TRH 293 '

10 F 70(

1/

7) 4'8l 5/

20)

F 70-10 F 70

~

10'0-10'0 F 00-F 50 16 ~ 70(

1/

24)

TRH 293 '

16'0(

1/

9) 2C VALUES <LLD 16 ~ 70-16(70 BFN DISCHARGE 16 ~ 70-16+70 K-40 81-214 PB-214 PB-212 SR 89 SR 90 TRIT Il)H 20 20 2 IJ GAHHA (GCLI) 21 LA-Iit0 7 ~ 000 NOT ESTAB NOT ESTAB NOT CSTAB NOT ESTAB 10 F 000 F 000 330 F 000 13'4(

1/

15) 13 ~64-

.13 o64 19'8(

2/

15) 16'0-22'6 4 '5(

1/

15) 4'5-4 '5 15 VALUES <LLO F 16(

4/

15) 1 ~ 55-2'9 12 VALUES <LLO ANAL.YSIS PERFORHCO 12 VALUES <LLO ANALYSIS PCRFORHEO 351 '8(

5/

12) 336 '3-37u ~ 86 TRH 293 '

BFN DISCHARGE TRH 285o2 TRH 293 ~ 5 TRH 293e7 BFN DISCHARGE TRH 293 ~ 7 BFN DISCHARGE 13'4(

13 ~ 64-22076(

22 ~ 76-4'5(

4 ~ 25-1/

4) 13.64 1/

5) 22 F 76 1/

6) 4+25 362'2(

353 ~ 57-2/

4) 370 F 86 2'3l I(t 4) 2'3-

' '3 6

VALUES <LLD 13'5(

1/

6) 13 F 75-13'5 2'1(

1/

6)

F 51-2 F 51 11 ~ 96 l I/

6) 11 ~ 96-11'6 2 F 51(

5/

6) 2'5 2(76 8

VALUCS <LLO 8

VALUCS <LLO 370 '3(

2/

8) 351 '6 390 F 00 a.

Nominal Lower Limit of Detection (LLO) 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).

TABLE23 RADIOACTIVIT'Y~ IN MHITE CRAPPIE (FLESH)

PCI/G -

0 ~ 037'O/G (DRY MEIGHT)

LOCA NAHE OF FAC ILITY QR~~ ffRRY TION OFFACII.ITY L IHQSTONQ ALABAHA DOCKET NO+~0-/~9 ~0 296 REPORT!NG.'PERERRATE 0

TYPE 'AND TOTAL NUHBER OF ANALYSIS GROSS BETA 6

GAHHA (GELI )

6 LOVER LIHIT OF DETECTION (l I 2) 0 ~ 100 ALL INDICATOR LOCATIONS HEAN (F)

RANGE 34 '3(

~ 4/

4) 29'2-40' KOMZlQ~UTgMIQBfkIM~NNhl. HEAD ~

NAHE.

.HEAN (F)

PEST~AN E

ANQJQR~TETTN RANEE MILSON RESERVOIR 34 ~ 93(

2/

2)

TRP 259-275 29'2-40 55 CONTROL

.LOCATIONS HEAN (F)b RA 32~76(

2/

2) 24 ~ 33-.

4 1 ~ 19 NUHBER OF NONROUT INE REPORTED CS-137 K-40 PB-212 RA-226 0'20 NOT ESTAB'OT ESTAB NOT ESTAB

0~13(

0 ~ 10-15'5(

14 ~ 58-0 F 01(

0 ~ 01-0 F 02(

0 ~ 02-4/,4 )

0 ~ 17 4/

4) 16'0 3/.

4) 0 ~ 01 2/

4) 0 ~ 02 MILSON RESBRVDIR TRH 259-275 liHEELER RES.

TRH 275-349 IIHEELER RES TRH 275-349 VHEELE,R RES TRH 275-349 0 ~14('/

2) 0 ~ 10-F 17 15'5(

2/

. 2) 15'4-16'6 0'1(

2/

2)

Oa01-0 ~ 01 0'2(

. '2/

2)

. 0 ~ 02" 0'2 0~13(

2/ ')

0 ~ 10~

0 ~ 16 14 '6(

2/

2):

13 F 45- '5sk6 0 F 01( 1/')

=

0+01 F 01 2

VALUESC'LLO A

a.

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

b.

Mean'nd range based upon detectable measuiements only.. Fraction of detectable measurements at specified'ocations is indicated in parentheses (p).: '

TABLE 24 RADIOACTIVITY IN SHALLHOUTH BUFFALO (FLESH)

PCI/G 0~037 BO/G (ORY VEIGHT)

NAHE OF FACILITY BROVNg= F/RRY LOCATION OF FACILITY QJ'H~STOgtf T YPE ANO TOTAL NUHBER OF ANALYSIS Pf,~RQRH~

GROSS BETA 6

GAHHA (GELI) 6 LOVER LIHIT OF OETECTIONa (l L.k) 0 ~ 100 ALL INDICATOR LGCATIONS HEAN ([) b RANGE 22 ~ 56(

4/

4) 18'9-29 '1 VHEELER RES 24 '8(

2/

2)

TRH 275-349 19'6 29'1 CONTROL LOCATION)

HEAN (F)

RANGE 22+51 (

PI 2) 21 '6 23 F 77 NUHBCR OF NONROUT INE REPORTED CS-137 PB-214 PB-212 BE-7 SR 89 SR 90 0'20 NOT ESTAB NOT ESTAB.

NOT,ESTAB NOT ESTAS 0 F 500 0 F 100 0'4(

3/

4) 0 F 04-GAGS 11 ~ 04 l 4/

4)

,7'6-13'0

=0 F 01(

1/

4) 0'1 0 F 01 0'1(

3/

4) 0 F 00-0'2 0 ~ 32l 1/

4) 0'2-0'2 2

VALUES <LLO ANALYSIS PERFCRHEO 2

VALUCS <LLO ANALYSIS PCRFORHED VHEELER RCS TRH 275-349 VHEELCR RES TRH 275-349 VHEELER.RCS TRH 275-349 VHECLER. RES TRH 275-349 VHEELER RES TRH 275-34'9 0 ~ 04l 0 ~ 04-11 '5l 10 ~ 60-0 F 01(

0 ~ 01-0 02(

0'2 0'2(

0 ~ 32-

. 2/

2) 0 '

2/

2) 12 '9 1/

2) 0 F 01 1/

2).

0~02 1/

2) 0'2 0'7(

2/

2) 0'6-0'9 9'7(

2/

2) 9'0-9'3 2

VALUES <LLD 2

VALUCS <LLD 2

VALUES <LLO 0

VALUES <LLD 0

VALUES <LLD a.

Nominal Lower Limit of Detec'tion (LLD) as described in Table 3.

b.

Mean and range based upon detectable measurements only.

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

TABLE 25 RADIOACTIVITY IN SHALLHOUTH BUFFALO (VHOLE)

PCI/G -

0 ~ 037 BQ(G (DRY VEIGHT)

NAME OF FACILITY BROVNS FfRRY LOCATION OF FACILITY~QH~JOgf ALAt)~HP DOCKET NO ~ 50-259~26~0296 REPORTING PERIOD )982 TYPE AND TOTAL NUHBER OF ANA(,YSIS PERFORHEO GROSS BETA 6

GAHHA (GCLI

)

6 LOVER LIHIT OF OETEC I ION

~(lQ) 0 100 ALL INDICATOR LOCAtIONS HEAN (F)

RANGEb 17 60(

4/

-4) 14 '4-20 '3 LOCATION R(ITH HIGHEST ANNUAL HEAh NAHE HEAN (F)

O~GTARC~AR OIRECTJOk RARGE VHEELER RES 20 ~ 13(

2/

'2)

TRH 275-349 19'3-20 F 43'ONTROL LOCATION(

HEAN (g)

RANGE 17 '9(

, 2/

2) 16 ~ 81-18 ~ 56

~

'NUMBER OF hOhgvUTITGE REPORTED HEASUREHENTS CS-137 O'I-214 PB-214 PB-212 RA-226 0'20 NOT ESTAB 0 ~ 020 NOT ESTAB NOT ESTAB NOT ESTAB 0'3(

0 ~ 02-6'8(

4O75-0 F 08(

0.03-0'2(

0 ~ 02-F 01(

0 ~ 01-OOOB(

0 ~ 03-3/

4) 0'4

. 7'9 2/

4)

F 12 1/

4) 0'2 4'/

4) 0 ~ 63 2/

4) 0 ~ 12 VHEELER RES TRH 275-349 VhiELER RES TRH 275-349 VHEELER RES TRH 275-349 VHEELER RES

'TRH 275-3I)9 I'HEELER RES TRH 275-349 VMEELER RES TRH 275-349 0'4(

2/

2) '

'3-0'4 6O37(

2/

2) 5'2-7'3'

'4(

1/.

2) 0 F 04-0'4 2

VALUES CLLO 0 F 03(

0 ~ 02-7'8(

7 ~ 56-0 ~ 12(

0 ~ 12

'0 ~ 02(

0 ~ 02-2/

2) 0 ~ 04 2/

2) 7'9 I/

2) 0 ~ 12 1/

2) 0002 0'2(

2/

.. 2) 0 F 01(

2/

2) 0 F 01-0'3 0 F 01-Oo01 u ~ 12(

1/

2) 0 ~ 04(

1/

2) 0 ~ 12-0'2 0 ~ 04-0 ~ 04 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 parentheses,(F).

NAHE OF'ACILITY /ROMPS ffRRY LOCATION OF FACILITY~IHfSTONQ TABLE26 RADIOACTIVITY IN SEDIMENT PCI/G -

0 ~ 037 DO/G (DRY MEIGHT)

ALAPAHA DOCKET NO ~ 50-&$9tgg~0

$ 96 REPORTING PERIOD ~9 TYPE ANO TOTAL NUMBER OF ANALYSIS PgR f,OR~M GAMMA (GELI

)

8 CE-144 c

C0-60 CS-134 c

CS-137 K-40 ZN-65 81-214 BI-212 PB-214 PB-212 RA-226 RA-223 RA-224 TL-208 AC-228 PA-234N SR 89 SR 90 0'60 0 '10 0 F 080 Qi020 NOT ESTAB 0 ~ 020 0 '20 0 F 100 NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB 0.020 0'60 NOT ESTAB I F 500 0'00 2/

6) 0'6 6/

= 6) 0 ~51

'/

6).

3'9 6/

6) 2'9 6/

6) 15+7) 1/

6)

Qa08 6/

6) 1 ~ 45 6/

6) 2'6 6/

6)

F 57 6/

6) 1 ~ 89.

6/

6) 1 ~ 45 3/

6) 0 F 89 5/

6) 2+02 6/

6)

'0 ~ 61 6/

6) 1 ~ 75 1/

6) 3'0 "1/

6) 2'3 S

<LLD Q ~ 20(

G ~ 15-G ~ 23(

0 ~ CG-A 0909(

0 ~ 09-1 ~ 35(

0 ~91-14 ~57l 12 ~ 4$ -

Oq08(

0 ~ 08-I ~ 30(

1 ~ 13-1085(

-1 ~ 61-1 ~ 36(

0 ~ 97-1 ~ 56(

lt20-1 ~ 30(

1 ~ 13-0'8(

6 ~ 56-F 83(

1+43-0 ~ 56(

0 ~ 44-li62(

1+37-3 ~ 20(

3 ~ 20-F 13(

2413-6 VALUE LOMER LIN IT ALL OF INDICATOR LOCATIONS DETECTION HEAN (()

(Len)

RANGE.'RH 293 '

BFN DISCHARGE TRH 288'8 TRH 293e7 BFN DISCHARGE TRN 277'6 TRH 277'8 TRM 293 '

BFN DISCHARGE TRM 277'8 TRH 288078 TRH 277'8 TRN 277a98 TRM 277~98 TRM 293 '

OFN DISCHARGE TRH 293 '

BFN DISCHARGE TRH 277'8 TRM 277+98 TRM 293+7 BFN DISCHARGE TRN 293 '

BFN DISCHARGE 0 ~ 20(

0 ~ 15-0 ~ 32(

0 ~ 13-6~ 09l 0 ~ 09-I ~ 94(

1 ~ lu-ll 4444(

15 ~ 16-Ci06(

0 ~ GB-I ~ 35(

1 2--

1 ~ 89l 1 ~ 78-I ~ 53(

),4e-1 ~ 78(

1 ~ 67-1 ~ 35(

I ~ 25-0'3(

0 ~ 56-1 ~ 94l 1 ~ 94-0'0(

0'9 1'0(

I ~ 65-3'0(

2 ~ 13(

2 ~ 13-2/

2) 0'6 2/

2) 0 F 51 1/

2) 0'9 2/

2) 2'9 2/

2) 15'1

, 1/

2) n 2/

2) 1 ~ 45 2/

2) 2'1 2/

2)

I ~ 57 2/

2) 1 ~ 89 2/

2) i+45 2/

2)

~

0.89 1/

2) 1 ~ 94 2/

2) 0 ~ 61 2/

2) 1 ~ 75 1/

2) 3 ~ 20 1/

2) 2'3 LK4719< HM'IIIMEX~~t>>:

L K-5~

NAME MEAN ([)

QQS T Aggf~tt Q //~RE I ~Ot 8

Atilt'tf CONTROL LOCAT lot(S HE AN (( )P R~Agf, 2

VALUES <LLD 0'3(

1/

2) 0'3-0'3 2

VALUES <LLD 1 ~ 22(

1 0"-

F 75(

I ~ 39-1 ~ 31(

I ~ 15-I ~ 47(

1 ~ 30-1 ~ 22(

1 ~ 05-0'ol 0 ~ 29-I ~ 72(

le72-0 ~ 49l 0'5 I ~ 51(

I ~ 29-4'4(

4 ~ 64-,

2 VALU 2/

2) 1 '0 2/

2) 2'1 2/

2) 1 ~ 46 2/

2) 1464 2/

2) 1 +40 1/

2) 0 ~ 29 1/

2) 1 ~ 72 2/

2) 0'3 2/

2) 1 ~ 73 1/

2) 4'4 ES

<LLD CD 34(

1/

2) 0'4-0'4 0 ~ 16(

2'/

2) 0 '4-0 ~ 18 15'1(

2/

2) 14aGT-16'5 2

VALUES <LLD NUMBER OF NONROUTINE REPORTED a.

)tcminal 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.

Thc 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 reported, are also comparable with levels reported in samples from the Tennessee River in preoperational monitoring programs conducted by TVA at other sites.

TABLE 27 RADIO'ACTIVITY IN CLAH FLESH

.PCI/G -

0 '37 DQ/G (ORY ilEIGHT)

LOCA DOCKET NOo~P~~Q~

TION OF FACILITY LIMESTONE ALABAHA

~

REPORTING PERIOD 1982 TYPE ANO TOTAL NUMBER OF ANALYSIS ZKEFQBHKD GAHNA (GELI) 6 LOVER LINIT ALL OF, INDICATOR LOCATIONS DETECTION NEAN ($ )

RANGE

~llQl CONTROL NANE NEAN CFb)

~

-HEAN (Fb) 0$8TA~f ~IIQ,QQRfQT/QN

RAmf,

~RA Gf, NUMBER OF NONROUTINE REPORTED HEASUREHENTS C0-60 CS-137 K-4 0 ZN"65 81-214 PB-214 PB-212 RA-226 TL 208 AC-228 F 080 0 F 080 NOT ESTAB 0 F 170 NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB 0'8(

0 ~24-0'7l 0 17-0 ~ 01-0'9(

0021-0%66(

0 ~ 45-0 ~ 39l 0 ~ 01-0 ~ 13(

0 ~ 10-0'1(

0021-TRH 293 '

BFN 0 ISCHARGE TRH 288'6 2/

4) 0 ~ 53 1/

4) 0'7 0'6 4/

4) 0 F 80 2/

4) 0'7 2/

4) 0'6 3/

4) 0'8 2/

4) 0'1 293o7 DISCHARGE 293 '

DISCHARGE 288 F 78 TRH 288'8 TRH 288'8 TRH 288o78 TRN 288'8 TR'l 288o78 2'7(

4/

4)

TRH 1 ~ll-4 ~ 53 BFN 1 ~ 33(

2/

4)

TRH 0 ~ 98-1 ~ 67 BFN 0'2(

3/

4)

TRH 0 ~ 53(

0 ~ 53-0 ~ 17C 0 ~ 17-2'2(

1 ~ll 1067(

1 ~ 67-0 F 76(

0076 0 F 80(

0 ~ 80-0 87(

0 ~ 87-0'6(

0 ~ 76-F 18(

0 ~ 18-0 ~ 41(

Oo41 1/

2) 0 53 1/

1) 0 ~ 17 2/

2) 4 ~ 53, 1/

2) 1 ~ 67 1/

1) 0'6 1/

1) 0 F 80 1/

1) 0 F 87 1/

1) 0'6 1/

1) 0'8

'1/

1) 0'1 2

VALUES <LLD 2

VALUES <LLO 2 ~ 34 (

2/

2) 2 ~ 24-2 ~ 45 2

VALUES <LLO 0'9(

2/

2) 0 ~ 02 0'7 0'4(

2/

2)

Ooll-0'8 0'2(

1/

2) 0 ~ 22 0 ~ 22 2

VALUES <LLO 0 ~ 16(

I/

2) 0'6-0'6 2

VALUES <LLD 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 RADIOACTIVITY IN CLAH SHELL PCI/G -

0 ~ 037 BO/G (ORY MEIGHT)

NAME OF FACILITY QROllNS jjRRY LOCATION OF FACILITY'IHfSTOAT/

Aj.ABAHA REPORTING PER TOO~9//

TYPE ANO TOTAL NUMBER OF ANALYSIS Pf RfQRHQ)

GAHHA (GELI )

8 CO-60 K-40 BI-214 PB-214 PB-212 RA-226 TL-208 AC-228 SR 89 SR 90 LOMER LIHI I'F DETECTION" lQLQ)

Oe010 NOT ESTAB 0'50 0'59 NOT ESTAB Gi050 0 ~ 020 0 ~ 060 F 000 1 F 000 0 ~ 08(

0 ~ 02-0 ~ 22l C ~ 15-0 ~ 17(

0 ~ 07-0'2(

0 ~ 07-.

0 ~lll 0 ~ 04-F 17(

G ~ 07-0'5(

G ~ 02-0 ~ 18(

0 ~ 09-5'5(

5 ~ 25-I ~ 66(

1 ~ 19-2/

6) 9 ~ 13 3/

6) 9 ~ 30 5/

6) 9 ~ 45

.5/

6) 0 ~ 68 5/

6) 0 ~ 29 5/

6),

0 ~ 45 5/

6) 9 ~ 06 5/

6) 0 ~ 30 1/

6) 5'5 6/

6) 2'0 ALL INDICATOR LOCAbTIOtiS MEAN ($ )

RANGE TRH 293 '

BFt DISCHARGE TRH 288'8 TRH 288 ~ 78 TRH 288 F 78 TRH 288'8 TRH 288o78 TRH 288 '8 TRr 288.78 TRH 277~98 TRH 288 F 78 0 ~ 13(

0 13-0 22(

0 ~ 15-0 ~ 28(

0 ~ 10-0 ~ 40(

0+13" 0'1(

0 ~ 12 0 ~ 28(

0 ~ 10-0 F 05(

0 F 05 0'7(

9 ~ 24-5'5(

5'5 1 ~ 86(

I ~ 63-I/

2) 0 ~ 13 2/

2) 0 ~ 30 2/

2) 0 ~ 45 2/

2) 0 ~ 68 2/

2)

0. 29 2/

2) 0 ~ 45 2/

2) 0 ~ 06 2/

2.

9 ~ 30 1/

2) 5'5 2/

2)

F 10 t-OC>7 ION it 1TH HIGHEST At'NUAL MEAN NAHE MEAN (IF) t'ISTANCE ANO DIRECTION RANGE CONTROL LOCATIONS MEAN (F)b RANGE 2

VALUES <LLO 1~51(

1/

2) 1 ~ 51-I ~ 51 0 ~ 87(

1/

2) 0~67-0 ~ 87 0'7(

2/

2) 0 ~ 07-0 F 87 0'2(

I/

2) 0'2-0'2

, 2 VALUES <LLO 2

VALUES <LLD 0 ~ 10(

I/

2)

CD 10-0 ~ 10 2

VALUES <LLO 1 ~ 36(

1/

2)

I ~ 36-I ~ 36 NUMBER OF NONROUTINE REPORTED HEASUREHEttTS 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).

Figure 1.1 E

R ESERVOI R MONITORING

NETWORK 51 Elk River N

WHEELER DAM mile 274;90 mile 277.98 Rogersyille 0

mile'82.6 mile 29l.76 Athens 0

~mile 285.2 8;F.. NUCLEAR PLANT S

Champion Paper Co.

0 Courtland.

ile28878 mile 293.50 mile 293.70 0

Decatur mile 305.0

~ - Automatic Sam ter mile 307.52 Scale of Miles

Figure 12 COC O

CIIo

~I o CI IJ ca Ci CI CO o

~I r4 IC 0 Q

LI

'tS C

'o o w 0 preoperational Phase Operational Phase Aweu. AVERAGE BeSS fhW MlvtTY tH SURFACE tlATER 8RQlOS FERRY IIUClEAR P4OT Average:

T Preoperational Phase' I

44 4444 1968 1969 1970 1971 1972 1973P 19730 1974 1975 1976 1977' 78 1979 1980 1 81 19 2

a.

No gross beta eteasurestents rcade in 1978.

53 A quality,control program has been established 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 vegetation collected around BFN are forwarded to these laboratories for analysis, and results are exch'anged for comparison.

Data measured at the control stat,ions 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, 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 the exposure to members of the general public attributable to the operation of BFN.

Indications of the presence of small quantities of fission products have been seen in aquatic media (for example, Asiatic clams).

The levels me'asured were extremely law, for example near the nomimal lower limits of detection and several hundred times lower than the reporting levels outlined by,the Nuclear Regulatory Commission..

No increases of radioactivity have been

'een in water samples.

These media will be monitored closely for indications of increases.

ERRATA SHEET FOR ENVIRONMENTAL RADIOACTIVITYLEVELS BROVNS FERRY NUCLEAR PLANT, ANNUAL REPORT 1982 1.

Page 9, table 4, section E. Milk, date 10/82, TVA average under EARL for strontium-90<<-"12.8" should read "19.2 "

ca:r,," ~

J I

ENVIRONMENTAL RADIOACTIVITYLEVELS BROWNS FERRY NUCLEAR PLANT ANNUAL REPORT -

<1984'VA/NUC PR/RH Ayril 1985

TENNESSEE VALLEYAUTHORITY CHATTANOOGA. TENNESSEE 32401

~;- 400 Chestnut Street Tower II

'2 April 10, 1985 U.S. Nuclear Regulator y Commission Region II ATTN:

Dr. J. Nelson Grace, Regional Administrator 101 Harietta Street, NW, Suite 2900 Atlanta, Georgia 30303

Dear Dr. Grace:

Enclosed is a copy of the following report prepared by the Tennessee Valley Authority pertaining to the environmental monitoring at the Browns Ferry Nuclear Plant:

Environmental Radioactivity Levels, Browns Ferry Nuclear Plant, Annual Report 1984 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 repor t to the Secretary of the Interior.

Very truly yours, TENNESSEE VALLEY AUTHORITY J.

W. Hufham, Manager Licensing and Regulations Enclosure cc:

Director of Nuclear Reactor Regulation (

Enclosure:

20)

Attention:

iIr. Hugh Thompson, Director Division of Licensing U.S. Nuclear Regulator y Commission Washington, D.C.

20555 1983 TVA 50 " ANNIVERSARY An Equal Opportunity Employer

r

~

da

CONTENTS List of Tables List of Figures.

Introduction Atmospheric Monitoring Terrestrial Monitoring

~

0

~

3.1X 1v

~

0

~

1 23 Reservoir'onitoring Quality Control.

~

0

~

55 Data Analysis.

Conclusions.

55 11

4

<<~

LIST OF TABLES Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table I - I'.nvironmental 1(adioactivity Sampl.ing ScheduJe 2 - Atmospheric and Terrestrial Monitoring Station Locations - Browns Ferry Nuclear Plant 3 - Detection Capabilities for Environmental Sample Analysis 4 - Results Obtained in Interlaboratory Comparison Program 5 - Jfaximum Permissible Concentrations for Nonoccupational Exposure 6 - Radioactivity in Air Filter 7 - Radioactivity in Rainwater 8 - Radioactivity in Heavy Particle Fallout 9 - Radioactivity in Charcoal Filters 10 - Radioactivity in Milk ll - Radioactivity in Vegetation 12 - Radioactivity in Soil 13 - Radioactivity in Well Water 14 - Radioactivity in Public Water Supply 15 - Environmental Gamma Radiation Levels 16 - Radioactivity in Cabbage 17 - Radioactivity in Corn 18 - Radioactivity in Peaches 19 - Radioactivity in Peas 20 - Radioactivity in Potatoes 21 - Radioactivity in Poultry 22 - Radioactivity in Tomatoes 23 - Sampling Schedule

- Reservoir Monitoring 24 - Radioactivity in Surface Water 25 - Radioactivity in White Crappie (Flesh) 26 - Radioactivity in Smallmouth Buffalo,(Flesh) 27 - Radioactivity in Smallmouth Buffalo (Whole) 28 - Radioactivity in Sediment 29 - Radioactivity in Clam Flesh 30 - Radioactivity in Clam Shell 13 14 15 16 17 26 27 28 29 30 31 32 33 34 35 36 37 38 45 46 47 48 49 50 51 52

h

LIST OF FIGURES Figure 1

- Tennessee Valley Region

]0 Figure 2

- Atmospheric and Terrestrial Monitoring Network 18 Figure 3

- Local Monitoring Stations Figure 4

- TLD Locations, BFN 19 20 Figure 5

- Annual Average Gross Beta Activity in Air Filters, Browns Ferry Nuclear Plant 21 Figure 6

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

~

39 Figure Figure Figure Figure 7

Direct Radiation Levels, BFN 8

- Direct Radiation Levels, BFN (4-Quarter Moving Average) 9

- Direct Radiation Levels, WBN 10 - Direct Radiation Levels, WBN (4-Quarter Moving Average) 40 40 41 41 Figure ll - Reservoir Monitoring Network 53 Figure 12 - Annual Average Gross Beta Activity in Surface Water 54

V V

ENVIRONMENTAL RADIOACTIVITYLEVELS BROWNS FERRY NUCLEAR PLANT ANNUAL REPORT 1984 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 radiological 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, comparisons were made between data for indicator stations (those near the plant) and control stations (those remote from the plant) in conjunction with comparisons with preoperational data.

Radiological Health (Office of Nuclear Power) and the Office of Natural Resources and Economic Development carried out the sampling program outlined in tables 1 and 23.

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

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

Alpha and beta analyses were performed on Beckman Low Beta II, Beckman Wide Beta II low background proportional counters or a Tennelec LB-5100.

Nuclear Data (ND) Model 6700 system, in conjunction with germanium detection

systems, were used to analyze the samples for specific gamma-emitting radionuclides.

Specific analysis for iodine-131 in charcoal filters is performed using NaI(Tl) well detector systems attached to single channel analyzers.

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

II

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

The data obtained by germanium detectors were resolved by the appropriate analyzer software and the software program routine HYPERMET.'

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

All photopeaks found in germanium spectra were identified and quantified.

Many of the isotopes identified by germanium spectral analysis are naturally occurring or naturally produced radioisotopes,,-

such as Be, K,

Bi, Bi, Pb, Pb, Ra, etc.

LLDs for radionuclides identified by Ge(Li) analysis were calculated for each analysis and nominal values are listed in table 3B.

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 samplers.

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

TVA's WARL participates in the Environmental Radioactivity Laboratory Intercomparison Studies Program conducted by EPA-Las Vegas.

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

Routine sample handling and analysis pro-cedures were employed in the evaluation of these samples.

The results received during calendar year 1984 are shown in table 4.

The +30 limits based on one measurement were divided by the square root of 3 to correct for triplicate determinations.

Table 1

ENVIRONMENTAL RADIOACTIVITYSAMPLING SCHEDULE Station Locations Muscle Shoals Lawrenceburg Rogersville Athens Decatur Courtland Site 1 (N)

Site 2 (NNE)

Site 3 (ENE)

Site 4

(NNW)

Site 5 (WSW)

Farm B Farm S""

Farm P

Farm L Farar E Farm W

Control Farms Onsite Well Wheeler Dam Elk River Tennessee River Champion Paper Co.

Various Local Farms Air Filter Charcoal Filter Rain-water M

M M

Heavy Particle Fallout Soil V~oototioo A

A A

River Well Public Aquatic Life Milk Water Water Water and Sediment Foods W

W W - Weekly M - Monthly (Every 4 Weeks)

""Discontinued operation November 19B4 9 - quarterly S - Semiannually A - Annually

Table 2

ATHOSPHERIC AND TERRESTRIAL MONITORING STATION LOCATIONS BROWNS FERRY NUCLEAR PLANT Sam le Station Approximate Distance From Plant Approximate Direction From Plant LM-1 LH-2 LM-3 IA-4 I.H-5 PH-1 PH-2 PH-3 PH-4 RH-1 BF, North BF, North-Northeast BF, East-Northeast BF, North-Northwest.

BF, West,-Sout,hwest.

BF, Rogersville, AL BF, Athens, AL BF, Decatur (Trinity), AL BF, Courtland, AL BF, Muscle Shoals, AL (Control) 1.0 Mile 0.9 Mile 1.0 Hile 1.7 Hiles 2.5 Hiles 13.8 Hiles 10.9 Hiles 8.2 Hiles 10.5 Hiles 32.0 Miles

( 1.6 kilometers)

( 1.4 kilometers)

( 2.7 kilometers)

( 4.0 kilometers)

(22.2 kilomct,crs)

,(17.5 kilometers)

(13.2 kilometers)

(16.9 kilometers)

(51.5 kilometers)

N NNE ENE NNW WSW NW NE SSE WSW W

RM-2 BF, Lawrenceburg, TN (Control) 40.5 Miles (65.2 kilometers)

NNW Farm S""

Farm 8 Farm 1.

Farm P

Farm E

Farm I'a rm Farm Fa rm Farm Fa rm W

N (Control)

J (Cont,rol)

C (Control)

Ca (Control)

Cb (Control H (Control) 5.0 8.8 6.1 6.9

" 27.0 40.0

> 32.0 32.0 22.5 22.5 Hiles Hilcs Hiles Hiles Hilcs Miles Miles Miles Hilcs Miles 4.75 Miles 7.0 Hiles

( 7.6 kilometers)

(11.3 kilomet,ers)

( 7.0 kilometers)

(14rl kilometers)

('9.8 kilomct,ers)

(11.0 kilomctcrs)

(43.4 kilomctcrs)

(64.4 kilometers)

(51.5 kilometers)

(36.2 kilometers (36.2 kilometers)

N NW NE E

NE NF.

NW NNW N

W E

ENE Discont.inucd operations November 1984

Table 3

DETECTION CAPABILITIES FOR ENVIRONMENTAL SA'K1PLE ANALYSIS A.

S ecific Analyses NOMIMKL LOWER LL"1IT OF DETECTION LLD)*

Air Particulates Charcoal Fallout Water

~cr/

1

~cr/

1 ci/K 1

. Kcr/1 Vegegation and Grain I>~Ci i~Dr Soil and Sediment

~ci/

D Fish Clam Flesh,

Plankton,

~Ci/

Dr

Foods, Meat, Clam Shells

Poultry, Milk

~Ci/

Dr

~cj/K D r Kci/1 Gross a

Gross B

3H 1311 89Sr 9OSr 0.005 0.01 0.005.

0.001 0.02 2.0 0.05

. '.3 330 10 2

0.05

'.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 25 40 8

0.05 10 2

<<All LLD 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 the given sample.

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

.Conversion factors:

1 pCi 3.7 x 10 Bq; 1 mCi ~ x.7 x 10 Bq.

Table 3

DETECTION CAPABILITIES FOR ENVIRONMENTAL SA%'LE ANALYSIS B.

Gamma Anal ses NOMINAL LOWER LIMITOF DETECTION (LLD Air particulates

~CI/

NaI* ~Ge Li **

Water Vegetation Soil and and milk and grain sediment

~ct/I

~ct/ L day N~ci/

dna NaI ~Ge Li NaI

~Ge Li)

NaI

~Ge Lf Clam flesh Fish and plankton Clam shells

~Ci/ ~dr)/

~>~Ci/ ~drZ

~Ci/ ~dr)N NaI

~GG Lt Nai ~GLI I

~G* Lt Foods, (tomatoes

'Meat and potatoes, etc.)

poultry NaI Ge(Li)

NaI

~Ge Li 90 33 44 200 8

50 150 40 90 20 0.74 0.48 0.08 90 50 15 40 40 40 10 5

5 5

9 5

20 15 55 15 40 15 70 20 30 15 400 50 141>> 144Ce

0. 03 38 0.55

0. 35 0.35 0.35 38 144ce O.O2 33 0.22 0.06 0.06 0.35 0.06 Cr 0.07 0.03 60 44 1.10 0.47 0.60 0.10

, 0.60 0.10 0.56 0.60 0.10 60 3 I 0.01 0.01 15 8

0.35 0.09 0.20 0.02 0.20 0.02 0.07 0.20 0.02 15 103N106Ru Oa04 40 0.65 0.45 0.45 0.45 40 106Ru 0.03 40 0.51 0.11 0;11 0.11 40 4Cs 0.01 0.02 10 26 0.20 0.33

'0:12 0.08 0.12 0.08 0.12 0.08 10 26 Cs 0.01 0.01 10 5

0.20 0.06 0.12 0.02 0.12 0.02 0.12 0.02 10 5

96Zr-Nbo. 01 10 0.20 0.12 0.12 0.12 10 9szr O.O1 10 0.11 0.03~,,

0.03 0.15 0.03 0.01 5

0.05 0.01 0.01 0.07 0.01 66Co 0.02 0.01 15 5

0.23 0.05 0.20 0.01 0,20 0.01 0.07 0.20 0.01 15 6"Mn 0.02 0.01 10 5

0.20 0.05 0.15 0.01 0.15 0.01 0.08 0.15 0.01 10 Zn OG02 Oaol 15 9

0 25 Oa 11 Q 23 P 02 0 23 OG02 Oa 17 OG23 Oa02 15 60co 0,01 0.01 10 5

0.17 0.06

.0.11 0.01 0'll 0.01 0.08 0.11 0.01 10 46K 0.10 150

2. 50

0. 90 0;90 0.90 150 1<<Ba-La O.OZ 15 0.68 0.15 055 0.15 15 14oB 0.02 25 0.34 0.07 j

0.07 0.30 0.07 25 50 140La 0.01 7

0. 08 0.02 0.02 0.10 0.02 7

15

~The NaI(T1) LLD values are calculated by the method developed by Pasterna 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 act vities of the components fn the samples.

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

Water fs counted in a 3.5-1 Marinelli beaker.

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

The average dry weight fs 120 grams for vegetatfon 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 702.

Average dry weight is 250 grams.

Air particulates are counted in a I/ell crystal.

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

The counting 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'ne week of the collection date.

1

~e Ge(Li) LLD values are calculated by the method developed by Pasternack and Harley as described in HASL-300 These LLD va1 ese va ues are expected to vary depending on the activities of the components fn the as~plea.

These figures do not represent the LLD values achiev bl Water is counted in either a 0.5-L or 3.5-L Marinelli beaker.

Solid samples, such as soil, sediment, and clam sheila're counted in a 0 5 L a ues ac eva e on given samples.

Marinelli beaker as dry weight.

The average dry weight is 400-500 grams.

Air filters and very small volume samples are co centered on-the detector endcap.

The counting system consists of a ND-6620 multichannel analyzer and germanium detector havi ffff 20 Percent.

The counting time is normally 4-15 hours.

All sPectral analysis is Performed using the software Program HYPER.

Th p f etector av ng an efficiency of is made that all.samples are analyzed wit'hin one week of the collection date.

~ am

~

The assumption Conversion factor:

1 pCi Na x.7 x 10 2 Bq.

TABLE 4 RESULTS OBTAINED IN INTERLABORATORY COMPARISON PROGRAM A.

Air Filter (pCi/Filter)

Date EPA value

(+3o)

TVA

~AV

~

Gross Al ha Gross Beta EPA value TVA

(+3a)

~Av.

Strontium-90 EPA value TVA

(+3a)

~Av.

Cesium-137 EPA value TVA

(+3a)

~Av.

11/83 3/84 8/84 19+9 15+9 17+9-a

<1 18 17 50+9 51+-9 51+9 40 60 60 15+3 16 21+A 20 18+&

N/A 21+9 11+9 15+9 20 10 15 B.

Tritum in Urine (pCi/1)

Date 2/84 11/84 EPA value (+30) 2383+608 2012+598

~TVA Av 2466 2047 a.

Sample fouled in preparation.

Procedure modified to prevent recurrence.

b. Lost in analysis.

TABLE 4 (Continued)

RESULTS OBTAINED IN INTERLABORATORY COMPARISON PROGRAM C.

Radiochemical Analysis of Water (pCi/1)

Date Gross Al ha EPA value TVA (i3o)

~Av.

EPA value

(+3a)

TVA

~Av Gross Beta Strontium-89 EPA value TVA

(+3a)

~Av.

Strontium-90 EPA value TVA

~3a)

~A Tritium EPA value TVA

~3a

~Av.

Iodine 131 EPA value

~(AAa 1/84 3/84 4/84 5/84 6/84 7/84 8/84 9/84 10/84 10/84 11/84 12/84 10+9 5+9 3+9 6i9 519 1419 7+9 10 6

6 5

ll 8

1219 20+9 6k9 13f9 16i9 64+9 20+9 15 20 6

16 12 60 22 25i9 32 34k9 41 ll+9 12 36+9 39 24i3 5i3 19i3 12i3

'23 18 13 3508+630 3580 3081+622 2770 2817+617 2607 2810+617 2517 31821624 3400 6+0.8 6

34+10 36 36+10 33 D.

Gamma-Spectral Analysis of Water (pCi/1)

Date Chromium-51 EPA value TVA (i3a)

~Av Cobalt-60

. EPA value TVA

(+Ma)

~Av.

Zinc-65 EPA value TVA

~(~3a

~A Ruthenium-106 EPA value TVA

(+3a)

~Av.

Cesium-134 EPA value TVA

~(~3 a

~A Cesium-137 EPA value TVA

(+3o)

~Av.

2/84 6/84 10/84 10/84

~ 4019

<44 66+9 72 4019 43 10+9 3+9 20+9 14+9 11 32 22 17 50+9 50 63%9 66 14749 151 61+9 53 29i9

<40 47i9 48 3119 29 47+9 44 31+9 29 2+9

<5 16i9 15 37+9 37 24+9 26 14+9 16

c. Laboratory performance evaluation study

TABLE 4 (Continued)

RESULTS OBTAINED IN INTERLABORATORY COMPARISON PROGRAM E.

Foods (pCi/kg, Wet Weight)

Strontium-89 Strontium-90 Iodine-131 Cesium-137 Potassium-40 d Date EPA value TVA

(+3a)

~Av.

EPA value

(+3a)

TVA

~Av.

EPA value (i3a)

TVA

~Av.

EPA value TVA (i3a)

~Av.

EPA value TVA

(+3a)

~Av.

1/84 7/84 34+9 40 25+9 N/A 2013 20+3 19 N/A 20+10 39+10 20 40 20+9 25+9 21 26 2730+236 2670 2605+226 2624 F.

Milk (pCi/1)

Date S troat ium-89 EPA value TVA

(+3a)

~Av.

Strontium-90 EPA value TVA

(+3a) 'Av.

Iodine-131 EPA value TVA

~(33a

~Av.

Cesium-137 EPA value TVA

~(3a

~A Potassium-40 f EPA value TVA

~(33a

~A 3/84 6/84 10/84 25-9 22+9 24 26 17+A 18 16+3 15 6+0 9 6

43 bio 39 4)+10 40 35'-9 32+9 34 30 1496+-130 1483 1517+132 1563

d. Values reported as mg K/kg.

e. Lost in sample preparation.

f. Values reported as mg K/1.

NENRNIS II

\\

I M

I SS.

I I

c 1

(

~r P4OVC4 v/

}j.

-i,.

t/

- VRCNSONg

(

IN 0.

LOVISVLLE TENNESSEE VALLEY REGION

(

V A

BOWLING GREEN S

S C

A R

SNORLS

/

/J A L.A B

A M

A LEGEND

~ -WATTS BAR NUCLEAR PLANT X8 -SEOUOYAN NUCLEAR PLANT

- BELLEFOHTE NUCLEAR PLANT

-. 8ROWNS FERRY NUCLEAR PLANT G EORG I

A (TVA NUCLEAR PLANT SITES)

VOWENSBORO K

E N

T U

C K

Y

(

V

~ M

/

I

~ M

'I

//

I

~/ V~~4r 4SNVILL ORII RIGGED N iN E

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1

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SON

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I CH4TTANOOG4m e

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1 BLN gNVNTSVILLE NVSCLE tq /

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 off-site 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 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 particulate filter at a flow rate 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 horizontal 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 continuously scans the particulate filter.

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

Air Filters Air filters are collected weekly and analyzed for gross beta activity.

No analyses are performed until three days after sample collection.

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

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

These data are presented in table 6.

During this reporting period, three samples were not obtained because of equipment malfunction.

One sample was damaged beyond use.

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 1968-1984 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) specified in 10 CFR 20 for nonoccupa-'ional exposure.

'N

Rainwater 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.

During this reporting period, one sample from each station (ll) was not available due to extended drought conditions.

Fallout 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.

During this reporting period, one sample was inadvertently destroyed and could not be analyzed.

Charcoal Filters 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, two samples were destroyed during filter change, and two samples were lost during analysis.

13 Table 5

MAXIMUMPERMISSIBLE CONCENTRATIONS FOR NONOCCUPATIONAL EXPOSURE Alpha Nonvolatile beta Tritium 1 37Cs 103>106R 44Ce Zr-Nb 140Ba 140L 131I 6sZn

'4Mn 6 0(o "Sr 90Sr "Cr 134C 0Co In Mater

~Ci/1*

30 3, 000 3,000,000 20,000 10,000'0,000 60,000 20,000 300 100,000 100,000 30,000 3,000 300 2,000,000 9,000 90,000

'n Air

~Ci/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

1 pCi

= 3.7 x 10 Bq.

TABLE 6

LOCA NAME GF FACILITY EBQBJQEEBBJ TION Of FACILITY tIIUEBIQHE-RADIOACTIVITY IN AIR FILTER PC I/M(3) - 0 ~ 037 8 0/V. (3)

DOCKET NO ~ 29=222c209c22E TYPE AND TOTAL NUMBER OF ANALYSIS EEBE985EQ GROSS ALPHA 5C GROSS BETA 568 GAHHA (GELI)

,1 43 LONER LZHZT CF DETECTION ILL92 0 ~ 005 0 ~ 010 ALL INDICATOR LOCATIONS HEAN (F)b 8889Eb C 02( 437/ 466)

C ~01-OeC4 ATMENSr AL 1C 9 HILES NE 0 02(

50/

52)

O.C1-G.O4 LQt hIIQb MIIU bISJESI hbUQSL HE'S~

NAMc MEAN ([)

QI~~IBUQE 889-QIBEQII95-----BASGE-----

CONTROL LCCAT IOTAS MEAN (F) 8689E 0 01(

1/

50) 0 ~ 01-G 01 0 02(

96/ 102) 0 ~01-0'4 NUMBER OF NONROUTINE REPORTED EPKQBELEHIE K-40 BI-214 BI-212 PB-214 PB-212 BE-7 TL-208.

AC-228 PA-234M SR 89 SR 90 NGT ESTAB O.GZO NOT ESTAB

" O.C20'-

NDT ESTAB 0'50 NGT ESTAB NOT ESTAB NOT ESTAB 0 F 005 0'01 Ceoz(

58/ 117)

G GO-0 C4 CD 02(

1/ 117)

C.OZ-O.oz 0'1(

1/ 117)

C.01:-

0 01 CD 02(

2/ 117)

CD 02-0 ~ 02 0+00(

21/ 117)

C.oo-0 ~ GG C ~ 06(

85/ 117)

CD 05-0'1<<

C.OO(

19/ 117)

C ~00-0 F 00 G 00(

8/ 117)

AGO-0 ~ Co CD 18(

2/ 117)

C ~ 17-0 19 36 VALUES <LLO ANALYSIS PERFORHEO 3e VALUES <LLD ANALYSIS PERFORHED LM2 BF NORTH 0 ~ 9 MILE NNE LH1 BF NORTHilEST 1 ~ C MILE N

RCGERSVILLEr AL 13 ~ 8 HILES NN LV1 BF NORTHMEST 1 ~ C MILE N

LV5 BF DAVIS F

2 ~ 5 MILES bSN ATHENSr AL 10 9 MILES NE COURTLANDr AL 1G ~ 5 HILES NSQ LV3 BF NDRTHEAsT 1 AC HZLE ENE ROGERSVILLEr AL 13 ~ 8 HILES NM 0 C2(

0 ~ C1-0 C2(

0 ~ C2-0 01(

0 G1--

0 ~ C2(

0 ~ C2-0 ~ CO(

0 ~ CO" O.C7(

0 ~ C5-0 ~ Co(

=0 ~ Co-0 ~ CO(

Oo 00-0 ~ 19(

0 ~ 1 9-.

5/

13) 0 04 1/

13) 0 02.

1/

13) 0 01 1/

13) 0 ~ 02 2/

13) 0 00 10/

13) 0 ~ 10 1/

13) 0 00 1/

13) 0 ~ 19 0 ~ 01(

12/

26) 0 ~ 01-C ~ 02 0 ~ 02(

1/

26) 0 ~ 02-G ~ 02 26 VALUES <LLD 0'2(

1/

26) 0>>02-G ~ 02 0 00(

. 6/

26) 0 ~ Oo-0 00 0 F 07(

18/

26) 0 F 05-0'2; 0 F 00(

6/

26) 0 F 00-0 00 0'1(

2/

26) 0 ~ 00- -

0 ~ 01 26 VALUES <LLO 8

VALUES <LLC 8

VALUES <LLC a.

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

b Mean and range based'upon detectable measurements only.

Fraction o'.; detectable measurements, at specified locationT, is indicated, in,parentheses (F),.

TABLE 7

NAHE OF FACILITY BEQll8S EEEEI LOCATION OF FACILITY LIUrSIQllE RACIOACTIVITY IN RAINMATcR PCI/L - 0 ~ 037 80/L DOCK T

NO ~ SQ=2S2c24Qc220 REPORTING PERIOD 12SB TYPE AND TOTAL NUHBcR OF ANALYSIS EEEEQEHEQ GAHHA (GELI) 132 K-4C BI"214 PB-214 PB-212 BE-7 TRITIUM 132 NOT ESTAB NOT ESTAB NOT ESTAB NCT ESTAB NOT ESTAB 330 F 000 22 ~ 33(

9/ 108) 6'7" 45'8 5 93(

52/ 108) 0'3-28'8 4'8(

29/ 108)

C ~ 07-20'1 1 '0(

35/ 108)

CD 18" 4 o2 49 37(

28/ 108) 29'6-99'0 108 VALUES <LLD ANALYSIS PERFORHED LOME R LIMIT ALL CF INDICATOR LCC4TIONS DETECTION HEAN (F)

LLLQ?

EBtlQC LH1 BF NORTHMEST 1 ~ 0 MILE h CCURTLANDr AL 10+5 MILES MSM COURTLANDr AL 1C ~ 5 HILES MSM ATHENSr AL 10 ~ 9 HILES NE RCGERSVILLEr AL 13mB MILES NM 38 ~ 51 (

38 ~ 51-7 6(

0 ~ 77-6 20(

1 ~ 46-2 46(

1 e20 58 F 88(

42 ~ 48-1/

12) 38 ~ 51 11/

12) 28 ~ 18 8/

12) 20 ~ 11 5/

12) 4'2 4/

12) 99'0 27'2(

2/

24) 21 '5 33 F 00 6'5(

14/

24) 0'0" 28'8 9'9(

5/

24) 3'2-24'3 F 80(

5/

24) 0'9 3'4 45'9(

8/

24) 38'5-71 '9 24 VALUES <LLD CONTROL NUHSER OF I QQBIIQll llLIU bIQllESI BhllQBl llCBU NOhRCUTINc NAME HEAN (FT MEAN (F)

REPORTED QISIBllQ= BllQ QIEEGIIQU BBQQE h EBllQEb 5EBSQECLE5IS 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 8"'AME OF FACILITY EBQHHE EEBBI LOCATION OF.FACILITY t,IgEEIQHE RADIOACTIVITY Ih HEAVY PARTICLE FALLOUT MCI/KH(2) -

570COOOO ~ 00 EQ/KV(2)

DOCKET NO

>Q=2%2c28Qc228 8L6E886 REPORTING PERIOD

$ QE$

TYPE AND TOTAL NUMBER OF ANALYSIS BEBEQBHEQ GROSS BETA 142 LONER LIMIT OF DETECTION Lt LQX 0'50 ALL INDICATOR LOCATIONS MEAN (F)

-b B859R 0'2( 114/

11 6)

C.06-1.25 LQE6IIQB HIIU EIQtfEEI 8h5Q6L UE88~

NAPE MEAN (()

QI I85QE 85Q QIBEQIIQB B889E LM4 SF TRAILER P

0%46(

12/

12) 1 ~ 7 MILES NNM 0'1" 1 '5 CONTROL LOCATIO)lS HEAN ([)P B8UQE 0 ~ 16(

25/

26) 0'6-0'6 NUMBER OF NOhROUTINE REPORTED BE8El!BELEUZE a.

Nominal Lo~er 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).

r r' TABLE 9 TYPE AND TOTAL NUMBER OF ANALYSIS RfBEQSBf Q I ODIN E-1 31 565 LONER LIMIT OF DETECTION a 1LLQ?

0 020 ALL INDICATOR LOCATIONS MEAN (F) b B689f b CD 02(

27/ 463) 0 02-0'4 NAME OF FACILITY gggggg ffggg LOCATION OF FACILITY gggfgIQHf LQG'BIiQb 8!IU UIGUf5I dhUllhL HfBH E NAME MEAN (F)

QISISHQf BUQ QIBEGIIQU BhUGf LY2 BF NORTH 0 ~ C3(

2/

52) 0 ~ 5 MILE NNE 0 ~ 02-0 03 CONTROL LOCATIONS MEAN (F) gb BBHG~

0'2(

10/

1C2) 0'2-0'3 RADIOACTIVITY IN CHARCOAL FILTERS PCI/M(3) " 0 ~ 037 BQ/M(3)

DOC<ET NO ~ ZQ=222c2ftQc22fj I Pfogg RcPORTINu PERIOD NUMBER OF NONRCUTINE REPORTED 5fhfQBfffHID a.

Noninal Lower Linit of Detection (LLD) as described in Table 3.

b.

Mean and ranpe based upon detectable neasurenents only.

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

18 Figure 2

ATMOSPHERIC AND TERRESTRIAL MONITORING NETWORK RM.28F LAWRENCEBURG yPULASKI FAYETTEVILLE

'ILSON FLORENCE OAM PM-IBF WHEELER ROBE SVIL OAM ATHENS PM-2BF FFIEL MUSCLE SHOALS RM-IBF LEIGHTON TUSCUMBIA COURTLANO PM-4 F

pRUSSELLVILLE BROWNS FERRY NUCLEAR PL NT OECAT R

PM-DBFO IO MILES HARTSELLE HUNTSVILLE GUNT SVIL OAM 25 HALEYVILLE CULLMAN 45 MILES RAINWATER SOIL Q-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 ATHENS U.. HWY 0

0 ALA. HWY 20 Legend 4

Air Monitor A

AUtomatic Well Sampler H

Dairy Farm Other Forms Scale 0

I 2

Miles DECATUR

20 Figure 4

>>I<<

TLD Locations BFN

<<L~wak.

s)

I

')

~

p>>gg I

I,

)

~

I Nl N

I

,>>II I

r...

'I

~

I)/

D

~ ~(,<<p, L

11

'1>>

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Figure 5

.30

.25 Preoperational Phase I

Operational Phase heauu AVERAGE 6ROSS SETA ACTIVITY IN AIR FILTERS Hearn FERRY NUCmu< PLANT

'. 20

.15 CO Cl Co C H 4l C cO CC A Ch olJ A C

O O Ll Q

C C o I

Ave~ra e:

Preo~erational Phase

.10

.05 I

.1 C 1968 1969 1970 1971 19 30 1974 1975 1976 19 7

1978 1979 1980 1981 1 82 1983 1984 72 1973P 197

23 Terrestrial Monitorin Terrestrial monitoring is accomplished by collecting environ-mental media within the general area of the plant for indicator locations, and at remote locations for controls.

These media sampled include milk, vegetation, soil, ground water-, drinking water, and food crops.

In addition, environmental gamma radiation levels are determined by strategic placement of thermoluminescent dosimeters.

Twice each year a land use survey is conducted to determine milk producing animal census and location.

Land Use Surve The land use surveys were conducted in June and September of 1984.

Milk animal census and locations were unchanged from the previous survey.

Projected doses to individuals in the area were not significantly different from those calculated for 1983. It was determined that the current environmental monitoring program is adequate.

Milk Milk is collected from four farms within a 10-mile radius of the plant (see figure 3),

and from at least one of six control farms.

During this reporting period, one indicator dairy farm disposed of all milk animals and ceased operations (November 1984).

Information provided by the latest land use survey indicated that there are no replacement dairies in the vicinity of the plant.

In compliance with plant technical specifications, a Special Report was submitted to the Nuclear Regulatory Commission on December 13, 1984.

Raw milk samples are collected from indicator and control

farms, and are analyzed weekly for iodine-131 and monthly for gamma-emitting isotopes and radiostrontium.

Analytical results are summarized in table 10.

During the 1984 reporting period, 13 samples were not available for collection.

Four samples spoiled and could not be analyzed.-

1 V~e etation Vegetation is sampled monthly at six.indicator farms (four dairies and two farms with one milk-producing animal),

and at each air monitoring station.

(}uarterly vegetation samples are collected at four control farms.

The monthly samples are analyzed for iodine-131 and gamma-emitting isotopes with analysis for radiostrontium performed on the, last, monthly sample of each quarter.

Samples collected quarterly are analyzed for gamma-emitting isotopes.

Table 11 summarizes analytical results.

During this reporting period, one monthly sample was not collected because of severe weather conditions, one sample spoiled, before a

gamma scan could be performed, and one set of samples for March were "lost" prior to strontium analysis because of analytical difficulties.

Laboratory procedures were revised to prevent reoccurrence.

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

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, strontium-89, and strontium-90.

The results are given in table 12.

Ground Water I

An automatic sequential-type sampling device collects groundwater from 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 monthly from a control well upgradient from the plant.

The results o'

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 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 into the water treatment facility.

Two additional supplies 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, gross beta of one of the weekly samples was not determined because of insufficient sample size caused by the malfunction of automatic sampling equipment.

Figure 6 shows the trends in gross beta activity in drinking water from 1968 through 1984.

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 (CazF:

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 approx-imately five miles from the 'site to determine the gamma exposure rates at these locations.

The dosimeters, located inside energy compensating shields to correct for energy dependence, are placed at approximately one meter above the ground, with three TLDs at each station.

They are

25 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'ttributable to combinations of influences, such as natural variations in environmental radiation levels, earth moving activities onsite, the mass of concrete employed in the construction of the plant, and other undetermined influences.

Figure 7 compares plots of the'ata from the onsite or site boundary stations with those from the offsite stations over the period from 1976 through 1984.

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 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 monitoring program are up to 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.

Food Products Food products raised in the vicinity of BFN and at control locations are sampled as they become available during the growing

season, and analyzed for gross beta activity and for gamma-emitting radionuclides.

During this sampling period, samples of cabbage,

'corn,

peaches, peas,

potatoes, poultry, and tomatoes were collected and'nalyzed for specific gamma-emitting radionuclides.

The results are given in tables 16 through 22.

f

TABLE 10 NAME OF FACILITY BBQUUS fEBBI LOCATION OF FACILITY LIUESIQUE RADIOACTIVITY IN HILK PCI/L - 0 ~ 037 BQ/L DOCKET NO ~

5Q=2S2c25Qc22(!

SI.BEBUNG iREPORTING PcRICO

//BED TYPE AND TOTAL NUHBER OF ANALYSIS EEBEQBUEQ IODINE-131 497 GAMMA (GELI) 124 LONER LIMIT CF DETECTION a SLl.kl 0'00 ALL INDICATOR LOCATIONS MEAN (F)b b

BBUQE 195 VALUES <LLD ANALYSIS PERFORMED l.QEIIIQU UJIU UIQUESI hhUllhl BEAU~

NAPE MEAN ($ )

QESISUQE 6UQ QTBEQITQU BOUSE CONTROL LOCATIONS HEAN ([)b

.BBUQE

.302 VALUES <LLC NUMBER OF NONROUT INE RcPORTcO UESSQBE" EUIS CS-1 37 K-40 BI-214 5 ~ 000 NOT ESTAB NOT ESTAB TL"208 AC-228 SR 89 SR 90.

NOT ESTAB NOT ESTAB 10 000 122 2

COO 122 PB 214

NCT ESTAB PB-212 NOT ESTAB 7 ~55(, 7/

48) 5'5-11 '1 1271.95(

48/, 48) 881 '9" 17o7 ~ 99 11 '5(

27/

48) 0.47-126 o7 19 F 05(

13/

48)

C ~00-140'0

2 21(

10/

48) 0 F 80-3 80 0'1(

11/

48) 0'2" 3'1 8 ~ 21(

5/

48) 2'3-13'6 46 VALUES <LLO ANALYSIS PFRFORHED 4 26(

41/

46) 2 23-7 29 PAGE FARM 8 75 MILES E

SMITH FARH 4 75 HILES N

PAGE FARH 8 ~ 75 HILES E

PAGE FARM Bi?5 HILES E

SMITH FARH 4 ~ 75 MILES N LCCNEY FARF 5%75 MILES ENE SHITH FARH 4 ~ 75 HILES N

~ 8 20(

4/

12) 5 15-11 ~ 01 1337 93(

10/

10) 1 1155 58-1787 ~ 99 19 15(

10/

12) 1 ~ 11-1?6 67 39 ~ E6(

4/

12)

,0'0-140'0 2'3(-

2/

12) 231" 274 1 22(

5/

10) 037-331 13+36(

1/

13) 13m 36-13 ~ 36 5 ~10(

10/

10) 3 ~ 49 7 ~ 29 5 ~ 67(

1/

76) 5 67-5'7 270 F 05(

76/

76) 789'9-1839 '6 7 F 43(

55/

76) 0 36-19'7 6'6(

38/

76) 0'2" 25'4 1 '9(

22/

76) 0'2-

4'1 1 33(

20/

76) 0'3-2'9 5'9(

7/

'?6)

Oe?2-25'2 76 VALUES <LLD F 88(

71/

76) 2e'07-8'9 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 at specified locations is indicated in-parentheses (F).

TABLE 11 RADIOACTIVITY IN PCI/G '- 0 037 BC/G VEGETATION (DRY hEIGHT)

NAME GF FACILITY EBQ}{t{S EEBBI LOCATION OF FACILITY LIHESI{}5E DOCKET NO ~

SQ=2SRA28Q4228 8L8{}8t{8 REPORTING PERIOD TYPc AND TOTAL NUMBER OF ANALYSIS BEBEQB}{EQ GROSS ALPHA 1

GROSS BETA 1

IODINE-131 220 GAHHA (GELZ) 235 LOWER LIHIT OF DETECTION a Il LQ2 0 ~ 050 0 ~ 200 NOT ESTAB ALL INDICATOR LOCA)IONS HEAN (F)

B8HQE 0 05(

1/

1)

Ce05-Oeo5 7 ~ 94(

1/

1) 7 94-7 94 0 00( 161/ 194) 0 F 00-0 01 LQC8IIQ1 }{IIU}{IQUESI 85t{ll8L }{E8t{ 8 NAMc MEAN (F)

QISI85CE 85Q QIBECIIQ}{

-B8}{QEb SHITH FARH 0 ~ C5(

1/

1) 4 ~ ?5 HILES N

0 ~ G5-0 05 SMITH FARM 7 ~ 94(

1/

1) 4 75 'MILES N

7 ~ 94-7 ~ 94 LM1 BF NORTHWEST 0 ~ Co(

13/

13) 1 ~ C HZLE N

0 Co-0'1 CONTROL LOCATIONS HEAN (F)b B8}{QEb 0 00(

19/

26) 0 ~ 00-0 01 NUMBER OF NCNROUTINE REPORTED UE8SMBELE}{IS C0-60 CS-137 K-40 BZ-214 BI-212 PB-214 PS-212 RA-223 SE-7 TL-208 AC-228 PA-234H SR 89 52 SR 90 52 0 ~ 060 0 ~ 060 NOT ESTAB 0 ~ 100 NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB 0'50 0 ~ 050 0 ~ 14(

0 ~ 14 0 ~ 08(

0 ~ 06-10'5(

e.46-0 ~17(

0 ~10-0'7(

e.o6-0 08(

0 ~ 00-0 F 04(

0 ~ 00-CD 12(

0 1 2-5 F 88(

0 ~ 21-0 ~02(

e.oo-0 ~ 11(

C ~ 00-3 64(

2 ~78-CD 48(

0 ~ 29 0 ~ 26(

0 05-1/ 193) 0 14 11/ 193) 0 ~ 15 193/ 193) 40 ~ 10 57/ 193) 0+43 10/ 193) 0 ~ 38 167/ 193) 0 40 136/ 193) 0 27 1/ 193) 0 ~ 12 192/ 193) 25 72 114/ 193) 0 ~ 10 111/ 193) 1 ~ 15 4/ 193) 4 96 5/

46) 0 ~ 80 45/

46) 1 G5 LH1 BF NORTHWEST 1 ~ C HILE N

SMITH FARM 4e?5 HILES N

LH2 SF NORTH 0

9 HZLE NNE ATHENSr AL 1C ~ 9 HILES NE WISER FARH 6 ~ 9 HILES NE EVANS FARM 6%1 HILES NE LH4 SF TRAILER. P 1a?

HILES NNW LH5 BF DAVIS F

2 ~ 5 MILES leSW ROGERSVILLEr AL 13 ~ 8 HILES NW LH3 BF NORTHEAST 1

C HILE ENE ATHENSr AL 10 ~ 9 HILES NE LH1 SF NORTHWEST C HILE N

LP4 BF TRAILER P

1 ~ 7 HILES NNW ROGERSVZLLEr AL 13 ~ 8 HILES NW 0 ~ 14(

0 ~ 14-0 ~ 15(

0 ~ 15-14 35(

1 ~ 25-0 25(

0 ~ 25-0 ~ 37(

0 ~ 37-0'1(

0 ~ 01-0 CB(

0 ~ C2-0 ~ 12(

0 ~ 12-9 ~ 71(

1 ~ 23-0 ~ C4(

0 Co-0 31(

0 Ce-4 ~ 96(

4 ~ 96-0 ~ Ee(

0 ~ 80-0 75(

0 ~ 63-1/

13) 0 ~ 14 1/

13) 0 ~ 15 1 3/

13) 34'3

.1/

13) 0 ~ 25 1/

13) 0 37 13/

13) 0'0 12/

13) 0 ~ 16 1/

13) 0 12 12/

12) 25 ~ 72 6/

13) 0 ~ 10 4/

13) 1 15 1/

13) 4 96 1/

3) 0 80 3/

3) 0 ~ 86 42 VALUES <LLO 0'2(

5/

42) 0 ~ 07-0 ~ 25 13'2( - 42/

42) 0 ~ 82-39'4 0'9(

14/

42) 0'1-0'8 0'?(

3/

42) 0+25 0 ~ 48 0'0(

35/

42) 0 F 00 0 ~ 42 0'6(

25/

42) 0 F 00-0+27 42 VALUES <LLO 6 53(

42/

42) 0 88-1?e23 0 02(

21/

42) o.oo-e.1o 0~11(

18/

42)

Oeeo-0 ~ 33 2'3(

1/

42) 2 03-2'3 6 VALUES <LLC 0 46(

6/

6) 0 26-CD 91 a.

Nominal Lover Liait of Detection (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).

TABLE 12 RANE CF FACILITY ffQjjgg L'OCATION OF FACILITY $$5fgZQDf RADIOACTIVITY IN SCIL PCI/O C ~ 037 BC/G (CRY MEIGl;T)

DOCKET NO ~

$ Q=f$2cfyQcggy BLkf858:

REPORTING PERIOD

$2fg TYPE ANO TOTAL NUNBER OF ANALYSIS EfEEQBBf Q GAHHA (GELI) 11 LOWER LIMIT CF, DETECTION SLLQ}

ALL INDICATOR LOCATIONS MEAN (F) b 885Qf I QQP IIQh HIXU UIQUfBI k hUllBt 5fhB ~

NAME HEAN (F)

QISIhUQf 65Q QIBfQIIQH BBHQf CONTROL LCCATION)

HEAN (F)

BhHQf NUMBER OF NONROUTINE REPORTED 5fhkQBfLfUI5 CS-134 CS-137 BI-214 BI-212 PB-214~

PB-212 RA-226 RA-223 RA"224 BE-?.

TL-208 AC-228 PA-234H SR 89 11 SR 90 11 0.080 0'20 0.250 0 ~ C50 0'00 0.050 NOT ESTAB 0 050 NOT ESTAB NOT ESTAB 0 160 0'20 0 060 NCT ESTAB 1

500 0'00 CD 16(

0 16" C 39(

C ~ 06-5.28(

3 ~ 32-F 00(

G ~61-1.24(

C 75-1 ~ 10(

CD 68 1.08(

0'7 1.00(

0 ~ 61 G 35(

G 28-1 '9(

0 ~ 67-9 VAL 1/

9) 0 ~ 16 9/

9) 1 ~ 03 9/

9) 7 ~ 29 9/

9) 1 ~ 30 9/

9)

.1 ~ 89 9/

9) 1 47 9/

9) 1 60 9/

9) 1 ~ 30 4/

9) 0 ~ 43 6/

9) 1 47 UES

<LLO 0 38(

9/

9) 0 20-0'3 1 13(

9/

9)

G.60-"

1 '8 2'4(

5/

9) 1 '0-3'4 9

VALUES <LLO ANALYSIS PERFORHEO 9

VALUES <LLO LN1 BF NORTHMEST 1 ~ C MILE N LM5 BF DAVIS F 2

5 HILES LSW LM4 BF TRAILER P

1 7 HILES NNM LH1 BF NORTHWEST 1 ~ C MILE N

LN1 BF NORTHMEST 1 ~ C HILE N

LN1 BF NORTHWEST 10HILEN LN1 BF NORTHMEST 1 ~ C NILE N

LH1 BF NORTHWEST

.1 ~ C HILE N

ATHENSr AL 10 ~ 9 HILES NE OECATURr AL 8 ~ 2 MILES SSE LH1 BF NORTHWEST 1 ~ C HILE N

LN1 BF NORTHWEST 1 ~ C MILE N

LH1 BF NORTHWEST 1

C MILE N 0 ~ 16(

0 ~ 16-1 '3(

1 ~ C3-7 ~ 29(

7 ~ 29-1 ~ 30(

1 ~0-1 89(

1 ~ 89-1 ~ 47(

1% 47-1 ~ 60(

1 ~ 60-1 0(

1 ~ 30-0 43(

0 ~43-1 ~ 47(

1 ~ 47 0 53(

0'3" 1 ~ 68(

1 ~ 68-3 64(

3 ~ 64-1/

1) 0 16 1/

1) 1 ~ 03 1/

1) 7 29 1/

1) 1~0 1/

1) 1%89 1/

1) 1 ~ 47 1/

1) 1 60 1/

1) 1 30 1/

1) 0 43 1/

1) 1%47 1/

1) 0 53 1/

1) 1 ~ 68 1/

1) 3'4 2

VALUES <LLC 0 51(

2/

2) 0'6-0'6 4 63(

2/

2) 4 ~ 15-5 ~ 11 1 06(

2/

2) 0'0-1 '1 1 30(

2/

2) 1 '5-1 '5 1 ~ 13(

2/

2) 0 ~ 98-1 28 1 16(

2/

2) 1 ~ 15-1 ~ 17 1'6(

2/

2) 0'0-1 '1 0'9(

1/

2) 0'9-0 29 2 VALUcS <LLO 0'9(

1/

2) 0 ~ 19 0 ~ 19 0'2(

2/

2) 0 F 42" 0 F 42 1 '8(

2/

2) 1 ~ 15-1 ~ 22 2 ~ 19(

1/

2) 2 ~ 19-2 ~ 19 2 VALUES <LLO 0'4(

1/

2) 0'4-0'4 oa.

'Noninal'Lover -Linit of Detection -(LLD) as d'escribed in:Table 3.

b.

Mean and range based upon detectable aeasurenents only.

Fraction oi detectable neasurenents at specified locations is.indicated in parentheses (F).

TABLE 13 NAME CF FACILITY EBQgbg fEBBI LOCATION OF FACILITY LIgEEZQBE RADIOACTIVITY IN NELL HATER PCI/L - 0 ~ C37 BC/L DOCKET NO ~ EQ=222A25QA225 BLflEh58 RF PORTING Pc RICO TYPE ANO TOTAL NUMBER OF ANAL'YSIS BEBEQBBEQ GAMHA (GELI) 26 LO'MER LIMIT CF DETECTION a SLLQ2 ALL INDICATOR LOCA)IONS HEAN (F)b B65QE LQQBIIQh BJIU UIQUEKI 85UQhL BE85 ~

NAPE MEAN-(F)

QIGIhUQE 65t'IBEQIIQ5 B65QE CONTROL LOCATION)

MEAN (F) b BBBQE NUMBER OF NDNROUTINE REPORTED 5EBR!lBELEtlIX K 40 BI-214 PB-214 PB-212 TL-208 AC-228 TRITIUH NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB 330 F 000 21 ~ 78(

1/

13) 21 ~78-21 ~ 78 7'3(

11/

13)

CD 12-14'0 7 50(

7/

13) 2'4-13 26 1 '7(

3/

13) 0 F 07 2'2 1 03(

2/

13) 0'9-1 '8 13 VALUES <LLD 4

VALUES <LLO ANALYSIS PERFORHED BFN NELL 06 0 ~ C2 MILES N

BFN NELL A6 0 ~ 02 HILES N

BFN NELL A6 O'2 HILES N

BFN NELL N6 0

C2 HILES N

BFN WELL N6 0 ~ CZ HILES 21 ~ 78(

21 ~ 7 8-7 23(

0 ~ 12-7'0(

2 ~ 74-1.C7(

0 ~ C7-1 ~ 03(

0 ~ ~9-1/

13) 21 78 11/

13) 14 30 7/

13) 13 26 3/

13) 2 ~ 3Z 2/

13) 1~68 15 ~ 98(

2/

13) 12 F 05-19'1 187'4(

13/

13) 14'7" '44 '2 186'2(

13/

13) 28 92-367 80 3 89(

3/

13) 3'0-5'1 0 64(

3/

13) 0'1-0'6 4'9(

2/

13) 2'7-6'0 4 VALUES <LLC 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 (P).

TABLE 14 RADIOACTIVITY Ih PUBLIC WATER SLPPLT PCI/L -

0 037 BC/L NAHE OF FACILITY EBQ)f5'EBBI DOCKET NO fg"222425gc225 LOCATION OF FACILITY l,IQEEIQBE hl,9E858 REPORTING PERIOD TYPE AND TOTAL NUHBER OF ANALYSIS REBEQB5jg GROSS BETA 90 GAHHA (GELI) 91 K-40 BI-214 PB-214 PB-212 LOWER LIHIT OF DETECTION a LLIgl 2 400 NOT ESTAB NOT ESTAB NOT ESTAB NOT cSTAB AC-228 SR 89 SR 90 TRITIUH 16 NOT ESTAB 10 F 000 F 000 330 F 000 TL-208 NOT ESTAB ALL INDICATOR LOCATIONS rEAN (F)b b

Bhtlgj 00(

46/

77) 241-510 17 ~ 88(

6/

78) 9'0-33'6 5'4(

46/

78)

CD 14-24 79 4'8(

26/

78)

CD 35-19%47 1 '9(

23/

78) 0'5-4'0 1 18(

11/

~ 78) 0'8-3'8 6'9(

7/

78)

F 08-17%19 12 VALUES <LLD ANALYSIS PERFORHED 12 VALUES <LLO ANALYSIS PERFORHFD 12 VALUES <LLD ANALYSIS PERFORHED CHAHPION PAPER TRH 282 '

WHEELER DAHr AL TRH 274 '

CHAHPICN PAPER TRr 282 '

SHEFFIELDrAL ROB TRH 254 '

WHEELER OAH~

AL TRH 274 '

CHAHPION PAPER TRr. 282.6 18%62(

9 70-6'6(

2.85-5'7(

0%41-2 ~ 38(

0%58 1 '7(

1%22 7'3(

1 ~ 08-5/

52) 33'6 9/

13) 12 ~ 98 14/

52) 19'7 4/

13) 4'0 2/

13)

~ 1 '2 4/

52) 17 ~ 19 LQGBIIQh HIIU UIQUEEI Bhtlght, BEIB ~

NAHE HEAN (F)

QIEIhHQE 659 QZBEQIIQU BSUQE b CHAHPICN PAPER 3'2(

40/

52)

TRH 282 '

2'6-5 10 CONTROL LOCATIONS HEAN (F) b b

BBUQE F 06(

5/

13) 2'5-3'1 28 73(

1/

13) 28'3-28 73 6 23(

9/

13) 3'9-8'7 5'0(

6/

13) 1%84-11 '6 1'5(

6/

13) 0 37-4 44

~ 1 '5(

5/

13) 0%23 2'2 0 96(

1/

13) 0'6-0'6 4 VALUES <LLO

.4 VALUES <LLD 4 VALUES <LLD NUrBER OF NONROUTINE REPORTED BEPKQBEEESIE 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 at specified locations is indicated in parentheses (P).

31 Table 15 ENVIRONMENTAL GAMMA RADIATION LEVELS Average External Gamma Radiation Levels at Various Distances from Browns Ferry Nuclear Plant for Each Quarter 1984 mR/Quarter Distance Miles 0-1 1-2 2-4 4-6

>6 1st uarter 19.4+1.7 18.5+2.,0 17.5+1.5 16.9+1.3 16.7+1.3 2nd uarter 19.9+1.4 17.5+1.7 17.8+1.9 17.5+1.7 16.4+1.1 3rd uarter 21.9+3.0 19.2+3.7 17.7+3.5 17.2+2.7 15.9+2.6 Avera e External Gamma Radiation Levels-b 4th uarter 20.5+1.5 19.4+2.2 17.8+2.1 17.9+1.4 17.1+1.5

Average, 0-2 miles (Onsite) 19.5+1.8 19.3+1.7 21,2+3.2 I ~

20.2+1.7

Average,

>2 miles (Offsite) 16.9+1.3 17.2+1.6 16.9+2.8 17.6+1.6 aDate normalized to one quarter (2190 hours0.0253 days 0.608 hours 0.00362 weeks 8.33295e-4 months ) bAll averages reported +le (68/ confidence level)

TA8L E 16 RADIOACTIVITY IN CABBAGE PCI/KG - 0 ~ 037 BO/KG ()iET 1iEIGHT)

NAHE OF FACILITY BBQll8$ ffBBI DOCKET NO 5Q=2 2A2fiQc225 LOCATION OF FACILITY l-.I5fhIQbf=

= -Sl,flBBdh

,REPOR o 12B TYPE ANO TOTAL NUMBER OF ANALYSIS EfBEQB5f Q GROSS BETA 2

GAHHA (GELI) 2 K-40 BI-214 PB-214 PB-212 LoiiER LIMIT OF DETECTION a Sl LQ?

25 F 000 NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB ALL INDICATOR LOCATIONS HEAN (F) b BellQf b 3903 ~ 25 (

1/

1) 3903 '5-3903 '5 1557 ~ 05(

1/

1) 1557%05-1557%05 1

VALUES <LLO 1

VALUES <LLO 2 ~24(

1/

1) 2'4-2'4 7 PILES NNR 155? ~ C5(

1/

1) 1557 F 05-1557 05 7 FILES NNli 2 ~ 24(

1/

1) 2'4-2~24 I QQBIIQ5 BJIU LIQllffIhh5llhL llfhH ~

HAKE HEAN (F)

QIRIhUQf 85Q QIBfQIIQB.

BBUQf 7 HILES NNR 3903 ~ 25(

1/

1) 3903 25-3903~25 2257'9(

225?a49-4 ~ 96(

4 ~ 96-5'3(

5e13-0 ~ 91(

0 ~ 91-1/

1) 2257'9 1/

1) 4 ~ 96 1/

1) 5 ~ 13 1/

1) 0'1 CONTROL LOCATIONS HEAN (F) b b

B85Qf 368? ~ 1 8 (

1/

1) 3687 ~ 1 8-3687 ~ 1 8 NUHBER OF NCNROUTINE REPORTED 5fBKQBftfUIX a.

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

b.

Mean and range based upon detectable measurement's only.

iraction of detectable measurementd at specified locations is, indicated gn parentheses..(E).

NAHE OF FACILITY BBQHHl EEBBX LOCATION OF FACILITY lIHESIQHE TABLE 17 RADIOACTIVITY IN CORN PCI/KG - 0 ~ 037 BG/KG (MET MEIGHT)

DOCKET NO 59=222c25Qc225 gLgggHg REPORTING PERICo 1256 TYPE ANO TOTAL NUHBER OF ANALYSIS BEBEQBHEQ GROSS SETA 2

GAHHA (GELI) 2 K-40 BI-214 PB-214 PB-212 LONER LIMIT OF DETECTION SLLQ?

25 000 NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB ALL INDICATOR LOCATIONS MEAN ($ )

BSHQE 3551%07(

1/

1) 3551 F07-3551 07 2254 39(

1/

1) 2254 '9-2254 39 1

VALUES <LLO 1-VALUES <LLO 1 ~ 44(

1/

1) 1 '4-1 '4 7 HILES NNM 2254 ~ 39(

1/

1) 2254 '9-2254 '9 7

P ILES NNM.

1 ~ 44(

1/

1) 1 ~ 44-1 ~ 44 LQCBIIQH HIIH HIQHESI SHHUBL HE6H NAME MEAN (F9'IGIhHCf 5HC QIBECIIQH BBHQE 7 MILES NNM 3551 ~ 07(

1/

1) 3551e07-3551 07 CONTROL LOCATIONS HE AN (F $

'aHQd'172%74(1/

1) 2172 74-2172.74.

2094 54(

1/

1) 2094 '4-2094 54 3 86(

1/

1)

F 86-3'6 0'8(.

1/

1) 0'8-0'8 1

VALUES <LLO NUHBER OF NONROUTINE REPORTED HEBRUBCLCHI5 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 NAME OF FACILITY EBQ852 Pf BBI LOCATION OF FACILITY LIUEEIQbE RADIOACTIVITY IN PEACHES PCI/KG - 0 ~ 037 80/KG (hET %EIGHT)

DOCKET. NO ~ GQ=222A2{iQc228 TYPE AND TOTAL NUMBER OF ANAL'YSIS PEBEQBBEQ GROSS BETA 2

GAMMA"(GELI) 2 K-40 BI-214 PB-214 PB-212 LOWER LIMIT OF DETECTION a ELLQ?

25 F 000 NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB ALL INDICATOR LOCATIONS MEAN (F) b B88QE 2273 65(

1/

1) 2273 65-2273 '5 1955 30(

1/

1) 1955 '0- 1955 '0 C.79(

1/

1)

'0 79-0'9 9'7(

1/

1) 9'7-9'7 0'8(

1/

1) 0'8 0'8 4 MILES N

4 HILES N

4 MILES N

4 HILES N

1955 ~ 30(

1955 ~ 30-0'9(

0 ~ 79-9'7(

9 ~ 47-0'8(

0 ~ 98-1/

1) 1955 '0 1/

1) 0'9 1/

- 1)

= 9+47 1/

1) 0'8 LQQ8IZQb HIIU UIQUEZI 8hUQ8L 5E88 8

NAME MEAN (F)

QIEI85QE 85Q QIBEQIIQ5.

B85QE 4 MILES N

2273 ~ 65(

. 1/

1) 2273 '5-2273'5 1595 F 08(

1595 ~08-5'9(

5 79-2'6(

2 ~ 46-1 ~ 68(

1 68-1/

1) 1595 F 08 1/

1) 5'9 1/

1) 2 46 1/

1) 1'8 CONTROL LOCATIONS MEAN (F)

B85QE 2772'5(

1/

1) 2772 '5-2772 '5 NUMBER OF NONROUTINE REPORTED 5E85QBEBEBIS--

a.

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

b.,

Mean. and range based upon detectable aeasureaents-only.~

Fraction of detectable neasurements at specified, locations is indicated in, parentheses (F).

TABLE 19 NAME CF FACILITY QEQE55 EEBBZ LOCATION OF FACILITY Lj5ESIQHE RADIOACTIVITY IN PEAS PCI/KG -

C 037 SC/KG (HET HEIGHT)

DOCKET NO~ 2Q=222c24QcZ25 hL62555 REPORTING PERICD TYPE AND TOTAL NUMBER OF ANAI.YSIS EfBEQE5EQ GROSS SETA 2

GAHHA (GE LI) 2 LONER LIMIT OF DETECTION SLLQ?

25 F 000 ALL INDICATOR LCCATICNS MEAN (F)

-b B68QS 6965 '6(

1/

1) 6965 66-6965 66 LQQhIZQb HJIU tfIQUEKI hhHUhL 5EhB~

NAFE HEAN ([)

QZSISHQf hUQ QlERQIIQU EBUQE 4 FILES N

6965 66(

1/

1) 6965 '6-6965 '6 CONTROL LOG ATI0QS HEAN (g) 855QE 5614 87(

1/

1) 561 4 ~ 87 561 4 ~ S7 NUHSER OF NCNRCUTINE REPORTED 5ESRQEELFUI5 K-4C BI-214 PB-214 NCT ESTAB NOT ESTAB NOT ESTAB 3461 '9(

3461

~ 39-6 03(

6 03-5'3(

5'3 5 ~ 03-1/

1) 3461 +39 1/

1) 6 03 1/

1) 5 03 5 03 4 FILES N

4 FILES N

3461 ~ 39.(

3461 39-6 C3(

6 ~ C3-5 ~ C3(

5 ~ C3-5+C3-1/

1)

~

3651 65(

1/

1) 3461 39 3651 65-3651 '5 1/

1) 1 VALUES <LLD 6 03 1/

1) 1 VALUES <LLD 5'3 5'3 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 at specified locations is indicated in parentheses (F).

NAME OF FACILITY ag{}55$ EcEEI LOCATION OF FACILITY Lj5EEIQ5E TABLE 20 RADIOACTIVITY IN POTATOES PCI/KC - 0 ~ 037 BC/KG (NET HEIGHT)

DOCKET NO.

NQ-222A25QA225 BLBEB5B RcPORTING PERIOD JgpB TYPE ANO TOTAL NUHBER OF ANALYSIS EEEEQ85EQ GROSS BETA 2

GAHHA (GcLI) 2 LO'NER LIMIT OF DETECTIONa Il LQ 1 25 OOOO ALL INDICATOR LOCATIONS MEAN (g) b BB5QE 7312.07(

1/

1) 7312 F 07 7312 F 07 LQQAIIQ5 HII5 5IQUESI 455QBL 5EB5~

TAHE MEAN (j)

QIEIB5QE A5Q QIEEQIIQ5 BB5QE 7 rILEs NNv 7312.c7(

1/

1) 7312 ~07" 7312 07 CONTROL LOCATIONS HEAN (g)

EB5QE 6571 '0(

1/

1) 6571 ~ 60-6571

~ 60 NUMBER OF NONROUTINE REPORTED 5EBkllEELE5IE K-40 BI-214 PB-214 PS-212 NOT ESTAB NOT ESTAB NOT ESTAB NCT ESTAB 3287o97(

3287o97" 2'3(

2.73-CD 78(

0.78-CD 83(

Ce83-1/

1) 3287.97 1/

1) 2m 73 1/

1) 0+78 1/

1) 0.83 7 rILEs NNM-7 NILE5 NNN 7 rILES NNN 7 rILES NNM 3287 ~ 97(

1/

1) 3287o97-3287

~ 97 2 ~ 73(

1/

1) 2'3-2'3 Oo78(

1/

1) 0'8" 0 F 78 0'3(

1/

1) 0'3-0 ~ 83-3924 ~ 85(

1/

1) 3924.85-3924 F 85 3.29(

1/

1) 3'9" 3'9 12 44('/

1) 12 44-12 ~ 44 1

VALUES <LLD a.

Noninal Louer Linit of Detection (LLD) as described in Table 3.

b..

Mean'and range based. upon detectable measurements only. 'Fraction of detectable neasurenents at specified locations is indicated in parentheses (F).

TABLE 2l NAME OF FACILITY EBQBUX EEBBZ LOCATION OF FACILITY LIVE/IDEE RADIOACTIVITY IN POULTRY PCI/KG - 0 ~ 037 BQ/KG (lrET NEIGI T)

DOCKET NO ~

XQ=222c28QA225 T'YPE ANO TOTAL NUMBER OF ANALYSIS BfBEDEWED GROSS BETA 2

GAHHA (GELI) 2 LONER LIHIT OF DETECTION SOLD?

25 F 000 ALL INDICATOR LOCATIONS MEAN ($ )

B8BQE 5016.47(

1/

1) 5016 '7 5016 '7 LQG8IIQh 'dLIU UZQUESI 8hUD8I. UE88 NAME HEAN (FT DIEI85QE 85K D!BEQIIQH B88QE PAGE FARH 5016 ~ 47(

1/

1) 8 ~ 75 HILES E

5016 ~ 47-5016 ~ 47 CONTROL LOCATIO!jS HEAN gF)'8SQ.

4902 '4(

1/

1) 4902'4-4902 '4 NUHBER OF NON ROUTINE REPORTED 5E 85l!BEBEUIB K-40 BI-214 PB-214 NOT ESTAB NOT ESTAB NOT ESTAB 2511 67(

2511 ~ 67-12 62(

12 ~62-8 61(

8 ~ 61-1/

1) 2511 '7 1/

1) 12'2 1/

1) 8 ~ 61 PAGE FARH 8 75 HILES E

PAGE FARH 8 75 MILES E

PAGc FARH 8%75 HILES E

2511 ~ 67(

2511 67-12'2(

12 ~ 62-8'1(

8%61 1/

1) 2511 ~ 67 1/

1) 12 ~ 62 1/

1) 8'1 2317% 20(

1/

1) 231? 20-2317 ~ 20 8 ~ 41(

1/

1) 8 "41=

8 ~ 41 8 ~ 90(

1/

1) 8% 90-8 ~ 90 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 parentheses (F).

NAME CF FACILITY BQUUg EEBBI LOCATION OF FACILITY LIUEBIQUE TA8LE 22 RACIOACTIVITY IN TOMATCES PCI/KG - 0 ~ 037 SQ/KG (MET MEIGl'T)

OOCKET. NO fQ 222AZCQc2R4 Sl SESUS RcPORJING PERICO

$ gE$

TYPE ANO TOTAL NUMBER OF ANALYSIS BEBEQBUEQ GROSS SETA 2

GAMMA (GELI) 2 LONER LIMIT CF OET ECTION ILLQ?

25 000 ALL INGICATOR LCCATIONS MEAN (F) b BSUQE 1617 91(

1/

1) 161? 91" 1617 ~ 91 CONTROL LQCSIIQU HIIU UIQUESI ShUUSL UESU~

NAME MEAN (F)

MEAN (F)

QIEXSUCcE SUB DIBEQIIQU BSUQE BSUQE 7 FILES NNM 1617 91(

1/

1) 3007 ~ 66(

1/

1) 1617 91-1617 91 3007 66-300'7 ~ 66 iVUMBER OF NONROUT INE REPORTED UESEllBEUEUIE K-40 NOT ESTA8 2161.25(

1/

1) 7 rILES NNM 2161.25-2161 ~ 25 2161 25(

1/

1) 2552 '2(

1/

1) 2161 '5-2161 '5 2652 92-2652%92 a.

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

b.

Mean and.range based upon detectable tteasurenents only.

Fraction of detectable neasurenents at gpecified locations. is indicated in,parentheses (F).

Pi8ure 6

cc ~

Cl 0

4J Cl cl 4Jcl Cl '0 Q

JJ JJ O

CC CJ no ccCo cl JJ 4J cll cl 44 cll o

4J cl 0 V

JJ

'D C0 CJ Preoperational Phase Operational Phase ANNuu AVERAGE 6ROSS BETA ACTIVITY I N HRI M>e 1976 1977 1978 1979 1988 1981 1982 1983 1981

41 Olrect Radlatlon Levels Ilalts BN Nuclear Plant 22 e

~'

le 0

o.'

16 One i te Ottstteo o-+

!I I

I I I

'e I

'e w IiIl I

1 I

l,a I

I i!

I I

i jlj e

o~

I 1

~

I I' I

tt ~

I I'2 1976 1977

".'978

'1979 1988 1981 1982 1983 1984

\\

I'tenre 10 Olrect Rodlot ton Levels liat ts Bor Nuclear Plant I-Ouarter Having Average 22 28 L

e 0 18 0

e 16 ensile O.g I

'e-o

.0"e i

~..e-o y'"~

Oftstto o o~

e o

e~%

I 1976 1977 1978 1979 1988 1981 1982 1983 1981

U Bf

Reservoir Monitorin Samples are collected from various Tennessee River cross sections as detailed in table 23.

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 accompaiiying map (figure 11) 'and conform to sediment ranges established aiid surveyed by TVA.

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

Further composites are made quarterly for strontium and tritium analyses.

In addition to these'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. 'esults are displayed in table 24.
Figure 12 presents a plot of the gross beta activity in surface water from 1968 through 1984.
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 reservoirs--
Wilson, Wheeler, and Guntersvi.lie.
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 25, 26, and 27.
Plankton Net plankton (all phytoplankton and zooplankton 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 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 Sr content.
During this reporting period, samples collected during the first half of the year contained insufficient volume for any analysis.
During the second half of the year, plankton could riot be located in sufficient quantities to be collected.
44 Sediment Sediment samples are collected semianhually from Ponar dredge,'hauls made for bottom fauna.
Gamma radioactivity and Sr.and Sr content are.
determined in composite samples collected from, each of four stations.
Locations of these stations are shown in table 23.
Results are shown in table 28.
Bottom Fauna The flesh and shells of Asiatic clams collected semiannually from the cross sections at four stations (table 23) 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.
Results are given in tables 29 and 30.
Clams from one location were not available; and from two locations, insufficient quantities were collected to permit analysis of clam flesh.
Table 23
\\
SAMPLING SCHEDULE - RESERVOIR MONITORING Biolo ical sam les (collected semiannuall
)
Zooplankton, chlorophyll, Benthic River/river mile phytoplankton fauna Sediment Fish Water Samples (collected monthly)
Tennessee 277.9 K
Tennessee 285.2 Tennessee 288..7 Tennessee 291.7 Tennessee 293.5 X
X Tennessee 293.7 (discharge area)
X Tennessee 305.0 (Control)
Tennessee 307:5 (Control)
X X
Elk 20.5 (Control) a.
Gill net and/or electroshocker will be used for collection.
from Guntersville,
Wheeler, and Wilson Reservoirs.
b.
Automatic sampler.
c.
Grab-sample.
h.
Samples of fish are collected
TABLE.24 hAHE CF FACILI Y inQnb~
LOCAT

CN OF FACILITY L3ME)IQbE RACIOACTIVITY IN SURFACE LATER TOTAL PCI/L - 0 ~ 037 EQ/L Q "RRAikQA2o>
REFORTI.iu FERICO 19~4 TYPE ANO TOTAL NUHBER OF ANALYSIS 2EEEQEQEQ GROSS ALPHA 1
GROSS BETA 65 GAHHA (GELI) 6c LOwER LIHIT CF OETECTIOh a ILi..?
2.C00 2 '00 ALL INCICATOR LCCATIOtiS YcAN (F) b 4
JQs E
VALUES <LLC ANALYSIS PERFORr.EO 3 '2(
27/
39)
Zo54-5e18 TRY 3 31(
Ze54-8/
13) 4o25 LQSAIIQh tt3IU LIQiifkI >h'dQAi "f85 S
NAYE rEAN (F)s QISIoNQf ~bi QIB=QI3Qb "ASQE CONT RCL LOCATIONS YcAN ([)b E659E 1
VALLES <LLC 3'2(
d0/
26) 2~43-12a06
.'iUro R
CF tiCtiROUT I NE REPORTED
"-821!"ft'-hIS K
4C BI-214 PB-214 PB-212 SR d9 SR 9E TRIT IUH NCT
=STAB
~
lc
,'tCT c ST,AB
~ 000 10 ZC 2
2C 330 2C CGO
. COO NCT cSTAB NCT ESTA3 21.09(
5/
39)
ED 59-,
38.69 5.56(
14/
39)
CD 61-1S 71 3.06(
7/
39)
C.01-
-~ 14 1'1 (
20/
3.9)
C ~ 10-4 ~ 52 12 VALUES <LLO ANALYSIS PERFORt'EO 12 VALUcS <LLC ANALYSIS PERFORHEO 387 92(
2/
12).
359 53" 416 31 TRY 285 '
TRY 293 '
BFh CISCHARGc TRY Z93 F 7 BFN DISCHARGE TRY-285 2
TRY 293 '
23'5(
23.C5-8 ~ 39(
2.18-3'5(
0 ~ 72-F 64(
0.99-1/
13) 23.05 5/
13) 18 71 4/
13) 7'4 5/.
1 3)
4. 52 416 ~ 31(
1/
4) 416 ~ 31-416 31 23 43(
2/
26) 19'4-27.12 o ~ 57(
15/
26) 0'Z-26'7 6 71(
14/
26) 0 ~ 59-18 ~ 1C 2.64(
r 7/
26) 0'd-5'5 8
VALUES <LLG 8
VALUES <LLC 8
VALUES <LLD a.
Noninal Lover Linit of Detection (LLD) as described in Table 3.
b.
Hean and range based upon detectable neasurenents only.
Fraction of detectable neasurenents at specified locations is 'indicated in parentheses (F)..
TABLE 25 RADIOACTIVITY Ih NHITE GRAF F I E (FLESn)
PCI/O C ~ 037 BC/0 (CRY 4 EIGI T) hANE CF FACILITY ggQ)lbA" fj3$I LOCATICN OF FACILITY LgQ
$ $ Q>f BLAfn58 NO ~
cQ 2+2A RQCRXa--------
REPORTING FERICC TYPE ANO TOTAL NVABER OF ANALYSIS PEBfQ3"=EQ GROSS BETA 6
GAHHA (GELI)
LONER LINIT CF OETECTIOh a SI I QR 0.100 ALL IN"ICATOR LCCATIONS Y.EAN (F)b oANnc b Si QO Zge19(
4/
4) 21 'C-33 ~ 50 LQCRXTQh l(kent t?QLl=cI khhQAL-L=
NAYc YEAN QckIhdQcc bhQ Q13ccQIIQh 8ABQ wNEELER RES 29'(
2/
TRY 275-349 25 ~ 1>>-
(F) cb 4
))
~ 9o CONTROL LOCATIONS NEAN (F)
EBhQE ZZ.B9(
2/
2) 20'6-37'3
)LI'5ER GF Y~iROUT Ihf REPCATE" r~faccQB'YfbT$
CS-1 3?
K-4C BI-214 PB-214 PB-212 SR 89-SR 9C 0.020 NCT ESTAB 0 ~ CZO NCT "STAB NCT ESTAB 0'00 0 ~ 100 C C9(
C.CE-15 3C(
12.8C-C.C4(
C.04-CD 17(
CD 05" C 01(
C ~01-2 VAL ANALYSIS 2
VAL ANALYSIS 3/
4) 0 11 4/
4) 1?
51 1/
4) 0.04 2/
4) 0.28 1/
4) 0 01 UES
<LLD P ERFORYEO UES
<LLO PERFORHEO NILSON RESERVCIR TRY 259-27c
'NNEELER RES TRIP 275-649 NFEELER Rcg TRY Z?c-ILSON REScMVCIR TRY 259"275, NYEcLcR RES TRY 275-349 0 ~ 11(
~ 11 16m 14(
14.77-C+C4(
0 c4 C.
8(
C 28-G.C1 (
0 ~ C1 1/
2)
C 11 2/
2) 1?s51 1/
2)
" ~ 04 1/
2)
C ~ 28 1/
2) 0'1 2/
2)
C ~ 11 2/
2) 16.85 1/
2)
C ~ 02 1/
2) 0 03 1/
2) 0 ~ OC
<LLC C ~ 09(
0.07" 14'9(
11o72-0 02(
C.02-
.0.03(
0.03-O.OC(
0.00-1 VALVES 1
VALUES <LLC a.
Nominal Lover Limit of Detection (LLD) as described in Table 3.
b.
)lean and range based upon detectable measurements only.
Fraction of detectable measurements at specified locations is indicated in parentheses (F).
c
TABLE 26 RAOIOACTIV!TY I't St'ALLttOUTt =LFFALC (F LES) )
PCI/G -
C ~ 037 BC/6 (CRY S=IG>T) hAHE CF F'CILITY g3gttVjg j=R3$
LOCATICh OF FACILIT'Y f,qLr~c$Jg~u OGCKET HO. ~G=ii2ci(tGAi24 REFORTI!tG FcRI u ]$ ~s~
TYPE ANO TOTAL KU,'tBER OF ANALYSIS REBFQRCKQ GROSS BcTA GANESA (GcLI)
CS-157 K-40 BI-Z14 PB-214 P3 212 SR 89 4
SR 9C 4
LO~ER LIP IT CF CETECT Ch LI l 0 1 0
OoC23 DICT ESTAB 0.020 NOT FSTAB ttCT ESTAB 0.5GG 0.100 ALL IACICATCR LCCATICttS PEAtt (c) 8hhct-2c.56(
4/
4) 12'2-39'8 C ~ 05(
3/
4)
CD G4-G.C7 12 96(
4/
4) 2.8 6" 1b.33 C ~ C4(
2/
4)
C.04.-
G.G5 CD G4(
3/
4)
C.GZ-0.7o C'o 01 (
1/
C.G1-G.G1 3.VALUES <LLC A'tALYSIS PERFORREO VALUcS <LLO AttALYSIS P ERFORHEO trHccL R
RCS TRY. 275-349
'WHEELER RE<
TRY 275-349 4'ILSOtt REScRVCIR TRR 259"275 ttILSOtt RESERVOIR TRF.'59-275 HHEELER RES TRr 275-349 Q. 6(
C C4-15 44(
12 ~ 55-0 ~ C5(
0 ~ C5-GsC5(
0 ~ C6" 0 C1(
2/
2) 0 07 2/
2) 15.33 1/
2) 0.05 1/
2) 0.0o 1/
2) 0.01 LQ{;AITQh H1t) hatt'dt;5I AhtiUBL "RhU~
fiT516bki Bbk Q ~ Bf;CIIQb RAbki WHEELER RE<
32 'B(
2/
2)
TRODI 275-345 25'r-39'd COhTRCL LCCATICttS VcAh (g) 20>>42(
2/
2) 19 F 86-2G ~ 98 0.05(
1/
2) 0.05-C.06
12. 11(
2/
2) 9'4" 14 BE 2
VALUES <LLC F 02(
2/
2) 0.01-G ~ 03 0 '01(
2/
2) 0 F 00-0.01 1
VALLES.<LLC 1
VALUES <LLC NLt'BER OF hChRCI.'T IhE PGRTcG u=tt'MS'""gIS a.
)tominal Lover Limit of Detection (LLD) as described in Table 3.
nt
.at s ecified locations is;-indicated in parentheses (F).
b..'tean and:ange based upon detectable "easurements only. 'Fraction'of'detectable measuremen s.at spec e
oca ons s;-
TABL=
27 R'DIGACTIVITY IN SYALLYOUT. Bl.FFALC ('iJMGLE)
PCI/O - C.C37 BC/G ('RY ~EIGYT) tiAME CF FACILITY c3lig"'$
LOCATION OF F'CILITY gIg"$Iggc "CARn5A OCChET NO ~ >Q-agog,7ggg,P>>"
REFORTItiG PERICD TYPc AND TOTAL NUMBER OF ANALYSIS oitti9B"'9 GROSS ScETA 6
GAMMA (GELI)
LOii R
L Y IT CF CETECTICNa CLt ~2 0 ~ 109 ALL INCICATCR LCCATICiVS McAN (F)
.b 865(th ZC ~ 52(
4/
I )
13.60-33.71 LQCRIIGh 'JJIId tiatt~caI chUUkL Llchtt~
tJAYc MEAN (F)
O':IBDCJ; hh'C QIB=CI'JJ5 Shfik=
NILSON RESERVCIR 23 ~ co(
2/
2)
TRt'59-275 13.c9-33 ~ 71 CONTRCL LOCATIONS YEAiV (F)
A,, b hCE 15+90(
2/
2) 15 ASS-16+25 Nl ""=R C.
NCNRCL1 INE RcPC" TEG EAKllc=p=hIS CS-1 37 X-4C bl-214 PS-214 PS-212 RA-223 AC-228 SR 89 SR 9C 0.929 VCT ESTAB 0.920 NCT cSTAB NCT ESTAB tJCT ESTAB 0 ~ 069 0.590 G ~ 190 C 04(
2/
4)
CD C3-0 G4 ED 56(
4/
4) 7 '7-10.79 C ~ 03(
2/
4)
C.GZ-G.
4 C.94(
2/
4)
CD G3" Go05 C 01(
1/
4)
C C1 0
01 C.26(
1/
4)
C ~ 26-0.2o C.Gd(
1/
4)
C.GB-0 08 2
VALtJES <LLG ANALYSIS PERFORMED 2
VALUES <LLO NILSOtJ RcScRVCIR TRJ Zc9-2?c NILSON RcSERVCIR TRt'59-275 WILSON RESERVCIR TRJ'59-275 HHEELER RES TRY 275-349
'iJYEELER RcS TRJ'?5-349 NI<SON RESERVCIR TRY 259-275 NILSON RESERVCIR TRY 259-2?5 0 ~ C4(
9 C3" 9.65(
E c1 0 ~(4(
0 ~ C4-G.C5(
G.CS" G.C1(
G.C1" 0.26(
0 ~ 20 O.Co(
G.CB-2/
2) 9.04 2/
2) 10 79 1/
2) 0 ~ 04 1/
2)
GROS 1/
2) 9 01 1/
2) 0 ~ 2o 1/
2)
G.GS 1/
2)
G ~ OZ 2/
2)
?o62 1/
2)
C ~ 95 1/
2) 0 ~ 94 1/
2)
Ce01 DES
<LLC G.02(
0 Go-7 ~ 61(
7 ~ 61-0.05(
0 ~ CS" 0,04(
0 ~ 94-Ge01(
0.01-2 VAL 2 VALUcS <Lt C 1

VAI.LcS

-i2ociRQc2zR REPG<TIttG P RI-w 1225 TYPc AttO TOTAL NUHBER OF AtiALYSIS 2iECQEhi2 GAHHA (GcLI LOwER LIMIT CF "ETECT Ot KI.L-.? ALL IhOIC "TGR LOCA/IGNS HEAti (F ) Uaaw LQLAIAQh 'd?ItI BIttliiZ Ahi984 L'ih~i 8 NAH8 HcAN (F) GliIhttli 65K OIBifiI95 Alki CONTRCL LCCATIOhS t'E A tt (F) Ngc Nt!rBER OF t>GKRCLiTINc RcPGRTcO riAkllRi"iBIR-CO-60 CS-134c CS-137 K-4C BI-214 BI-212 PB-214 PB-212 'A-226 RA-224 TL-203 AC-228 PA"234H SR 89 SR 9C G. C10 0.0c 0 O.CZG tCT c STAB G.C20 0.105 NCT FSTAB NCT ESTAB NCT ESTAB NCT ESTAB 0.020 G.CoG NCT ESTAB 1 500 0'G0 C.31 ( v/ o) C 27-0+36 C.14( 2/ c) C 1C-0 17 C ~ 90( "/ 6) C.78-1 '2 14 '2( 6/ o) 11.78-1o 82 1.37( 6/ o) 'CD 94-1.62< 01( 4/ 6) 1 86-2'6 1.55( 6/ 5) 1.21-1.65 1.49( 6/ o) 1.33" 1 '1 1.52( 2/ o) 1.51-1.54 1.69( 1/ o) 1.69-1 69 C.53( 6/ o) C.33" 0 61 1 '0( 6/ 5) 1 '7-1,94 3.4C( 1/ o) 40-3.4C VALUcS <t.LO Att>>LYSIS PERFORHEO VALUES <LLC ANALYSIS PERFORt'cO TRr 277 98 TRY 293.7 BFh OISCHARGc TRr 277 '8 TRr 277'8 TRr TRr 277.98 277 '8 TRr 2BB.?E TRP 277.98 TRH 277 '8 TRH 293 F 7 BF h DISCHARGE TRr 277.98 TRr 27? ~ 98 TRr 27'8 C.82( 0 v2-0.1.7( 0 17-G 95( G 78-15 54( 14 ~ co-1 ~ 49( 1 ~ 44-2.C6( 2.Co-1.64( 1 ~ c1 1 ~ 60( 1 ~ 38-1 ~ c4( 1 ~ c4-1 ~ 69( 1 ~ 69" 0 ~ 56( 0 c2 1 73( 1 '2 3'0( 3.40-1/ 2) 0'2 1/ 2) 0 ~ 17 .2/ 2) 1 12 2/ 2) 16 82 2/ 2) 1 '4 2/ 2) 2 05 2/ 2) 1 ~ 68 2/ 2) 1 ~ 81 1/ 2) 1 54 1/ 2) 1 ~ 69 2/ 2) 0.61 2/ 2) 1 ~ 94 1/ Z) 3'0 0.48( 0.30-1G 64( 7 ~ 91-1o11( 1 ~ 01-1 ~ 45( 1 ~ 3o" 1.25( 1 ~ 16-1 ~ 21( 1 ~ 18-1.11(
1. 01-1 ~ 28(
1 ~ 28-0.41( 0 ~ 38-1 22( 1 ~ 15- '2 VALLE 2/ 2) Ce65 2/ 2) 13.38 2/ 2) 1 '1 2/ 2) 1 ~ 5 2/ 2) 1 ~ 34 2/ 2) 1 ~ 24 2/ 2) 1 ~ 21 1/ 2) 1 ~ 28 2/ 2) CD 44 -2/ 2) 1 ~ 28 S <LLC 2 VALLCS <LLC 2 VALI.ES <LLC 0.02 ( 1/ 2) 0.02-C.02 2 VALUES <LLC a. Yoninal Lower Llnit of Detection (LLD) as described in Table 3. I b..'tean and range based upon detectable neasurenents only. Fracrion of detectable neasurenents at, specified locations is indicated in parentheses (F). c. The distribution of "- Co and Cs between indicator and control locations reported herein is conparable to the distribution reported in the preoperational nonitoring progran fron 1963 to nid-1973. The levels reported for the isotopes and for Cs are also conparable with levels 134 reported in sanples fron the Tennessee River in preoperational nonitoring prograns conducted, by TVA at other sites. TABL" 29 hAME CF FACILITY cg('tbbg PcgtII LOCATION OF FACILITY jAHgggggP RACIPACTIVITY Ih CLAM FLESI, FCI/C - C.057 BC/G (CRY 'r =IGFT) -nLksk "t" ~ cw 422ts~icaaR HO. cr --- or,r RcFORTIHG R=RICO TYPE Ati'0 TOTAL NUMBER PF ANALYSIS P~cRC23"k2 GAMMA (GcLI) 5 LCQE R LIMIT A c O=TECT.ON fLLik Al L INDICATOR LCCAbTICNS MEAN (F) sachs ~ LGHIIQh 81IV LIuOESI hhbU8L 5R Ah < HAy E vc AN (~) a:-1IAbCi 65K aiR:f,I198 COHTRCL LCCATIOHS ,MEAN ($ ) ds h 4Ly"cR NOhRO'.NE REP RT.C t(-4C BI-214 PB"214 PB-212 TL-20S AC-22S HOT ESTA3 NCT ESTAB NOT ESTAB NOT cSTAB NCT =STAB NOT STAB 3 VDLUcS <LLC 2.47( 3/ 3) 1 '6-3 'G 2.33( 3/ 3) 1 '8-2+75 C.26( 1/ 3) C ~ 26-0'o 3 VALVES <LLO VALVES <LLG TRy 277 ~ 9E TRM 277. 9E TRy 2cE. 7E 3'0( 3 ~ 6G-2e75( 2 ~ 75-0.26( C.26-1/ 1) 3'0 1/ 1) 2 ~ 72 1/ 1) 0 ~ 26. 2.06( 1.55-1 ~ 52( 0.85 ( G ~ 63-C.15 ( C ~ 15-C.07( 0 ~ 03-1 ~ 59( 1 ~ 39" 2/ 2) 2 ~ '27 2/ 2) 2'2 2/ 2) 1 ~ 07 1/ 2) C ~ 15 2/ 2) C ~ 1G 1/ 2) 1 39 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 parentheses (F). TABLc 30 CF F>>CIL IT I $ 3/'Ah/ c 2 >I LQ C A T I C h 0 F F ACILIT Y g I <lg $ I Q g> RAD 0 CTIVITY Itt CLAt'HELL CI/O 0 ~ 7 C/G (ORT Vt IGMT) OOCt(ET NO ~ 'AC=2>2c2(t2A2c~ TYPc ANJ TOTAL NUMBER OF AtiALYSIS BRBf935'2 GATV>> (GELI) 7 K-4C BI-214 PB-214 PB-212 RA-226 AC-228 SR 89 SR 9C LIH-T CF ETECTION NCT,=STAB O.C50 0+C50 hCT ESTAB 0.050 Ooeae 5 ~ cee 1 ~ COO INDIC C.OG( C.CO-C ~ 22( G.C7-C.28( G ~ 08-0.06( C ~ C4-C.er< C. C7-C.G7( C.C7-6 ~ 24( 6.24-1.14( 1.01-1/ 5) ri ~iu 3/ 5) 0 ~ 42 5/ 5) C ~ 5C 3/ 5) 0 ~ I 7 1/. 5) 0 ~ 07 1/ 5) 0.07 1/ 5) 6 F 24 4/ 5) 1 c4 ALL ATOR LCCAbTIC4S V At" (F) cb Bcbkv TRv 2=c ~ 78 TRV 29' 3 F h C I S C t'. A 2 G E TRV 277 '8 TRV 28c.78 TRV.288 '8 TRV 288 78 TRV 293 ' bFh DISCHARGE TRV 288'c C.CO( C. COG-C.IO< 0 ~ 1 7 0 5i( e '0-O.C6< GeC4-0 ~ C7( C C7-O.C7( Oo C7-6.24(" 0 ~ c>> 1.23( 1 ~ c1-1/ 2) 0.00 2/ ?) 3 42 1/ 1) G ~ 50 2/ 2) 0 ~ 07 1/ 2) 0 F 07 1/ 2) 0 07 1/ 2) 6'4 2/ 2) 1 '4 L908IIQh nIId =Itt~CSI khdQBi L~c8tt B'AV 8 VEAh (FT 'uIRI85Cs Eh'IBRCII2h BAb~: CONTROL LCCATI0>4S HcAN gFP us A Vl C.13( 1/ 2) G ~ 13-C ~ 13 C.15( 2/ 2) 0'6-Co23 0.18( 2/ 2) 0.06-C.29 0.02( 1/ 2) Oe02-CD 02 0'6( 1/ 2) G 06-0.06 0.07( 1/ 2) 0.07-C"07 2 YALLES <LLG' 16( 1/ 2) 1 ~ 16-1'16 NUVBER NCKRCUTINE RcPCRTc~ 5fka'liBf"aNIS a. Noninal r~-'er Lhit of Detection (LLD) as described in Table 3. b. Mean and range based upon detectable neasurements only. Fraction of detectable neasurenents at specified locations is indicated in paren'theses (F). Figure 11 R ESERVOI R MONITORING NETV/ORK 53 Etk River WHEELER DAM mile 274.90 mile 277.98 Rogersville 0 mite 282.6 mile 29l.76 Athens 0 ~mile 285.2 B.F. NUCLEAR PLANT 8 Champion Paper Co. ,0 Co'ur tland ile 288.78 mile 293.50 mile 295.T0 mite 305.0 Decatur ~ - Automatic Sam ler mile 307.52 Scale of Miles 0 Eigure 12 Cloo co li o o m JJ CJ th ekl Le C/' o o V 4J 'o c0Q Preoperational Phase l Operational Phase ANNUaL AveRase Bess Hva AcTtvm th MFacE ltaieR Rows FeRRv NUcL'eaR P~ Average: T Preoperational'hase 968 1 1 969 1970 1 971 1972 1973P 19730 197C 1975 1976 1977 19 6 1979 1980 1 $ 119 2 19 19 C a. No gross beta neasurenents nade in 1978. 55 Qualit Control A quality control program has been established with the Alabama Department of Public Health Environmental Health Administration l,aboratory and the Eastern Environmental Radiation Facility, Environmental Protection Agency, Montgomery, Alabama. Samples of air, water, milk, and vegetation collected around BFN are forwa'rded 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 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 daLa ana]ysis 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, air, milk, meat, vegetation, drinking water, and fish. Inhalation and ingestion 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, and by strontium-90 and cesium-137 which are long-lived radioisotopes found in fallout from nuclear weapons testing. 56 It is concluded from the above analysis of the data and from the trend plots presented earlier that there were, no.measurable increases in'he exposure to members of the general public attributable to the operation of. BFN. Indications of the presence of small quantities of fission products have been seen in aquatic media (for example, sediment). The levels measured'ere similar to levels reported in upstream sampl'es collected in conjunction with preopera'tional monitoring, programs being conducted by TVA at nuclear plant construction sites. ENVIRONMENTAL RADIOACTIVITYLEVELS BROMNS FERRY NUCLEAR PLANT ANNUAL REPORT - 1985 TVA/NUC SVS/RH TENNESSEE VALLEYAUTHORITY 5N 157B Lookout Place April 22, 1986 U.S. Nuclear Regulatory Commission Region II ATTN: Dr. J. Nelson Grace, Regional Administrator 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323
Dear Dr. Grace:

BROWNS FERRY NUCLEAR PLANT UNITS 1, 2, AND 3 ENVIRONMENTAL RADIOACTIVITY LEVELS ANNUAL REPORT 1985 Enclosed is a copy of the subject report prepared by the Tennessee Valley Authority pertaining to environmental monitoring at the Browns Ferry Nuclear Plant.
This monitoring program is specifically responsive to the recommendations and requests of the U.S. Fish and Wildlife Service.
Me understand

that, NRC-NRR will transmit five copies of the report to the Secretary of the Interior.

Very truly yours, TENNESSEE V
LE A
HORITY R. L. Gridley, Director Nuclear Safety and Licensing Enclosure cc:
Director of Nuclear Reactor Regulation
(

Enclosure:

20)
Attn:
Mr. R.
M. Bernero, Director Division of BMR Licensing U.S. Nuclear Regulatory Commission Washington, D.C.
20555 An Equal Opportunity Employer
CONTENTS List of Tables List of Figures.
Introduction Atmospheric Monitoring Terrestrial Monitoring Reservoir Monitoring
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ll 23 43 equality Control.
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57 Data Analysis.
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57 Conclusions.
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LIST OF TABLES Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table 1
2 6
7 8
9 10ll 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 le I.on pie so Environmental Radioactivity Sampling Schedu Atmospheric and Terrestrial Monitoring Stat Locations - Browns Ferry Nuclear Plant Detection Capabilities for Environmental Sam Analysis Results Obtained in Interlaboratory Compari 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 Cabbage Radioactivity in Corn Radioactivity in Green Beans Radioactivity in Apples Radioactivity in Potatoes Radioactivity in Beef Radioactivity in Tomatoes 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 Plankton Radioactivity in Clam Flesh Radioactivity in Clam Shell
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13 14 15 16 17 26 27 28 29 30 31 32 33 35 t
36 37 38 45 46 47 48 49 50 51 52 53
LIST OF FIGURES Figure 1
- Tennessee Valley Region 9
Figure 2
- Atmospheric and Terrestrial Monitoring Network l8 Figure 3
Figure 4
Figure 5
- Local Monitoring Stations
- TLD Locations, BFN
- Annual Average Gross Beta Activity in Air Filters, Browns Ferry Nuclear Plant l9 20 21 Figure 6
- Annual Average Gross Beta Activity in Drinking Water, Browns Ferry Nuclear Plant Figure 7
- Direct Radiation Levels, BFN Figure 8
- Direct Radiation Levels, BFN (4-quarter Moving Average) 39 40 40 Figure 9
- Direct Radiation Levels, WBN 41 Figure 10 - Direct Radiation Levels, WBN (4-quarter Moving Average) 41 Figure 11 - Reservoir Monitoring Network 54 Figure 12 - Annual Average Gross Beta Activity in Surface Water 55
ENVIRONMENTAL RADIOACTIVITYLEVELS BROWNS FERRY NUCLEAR PLANT ANNUAL REPORT 1985 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 plant has been shutdown since March 1985.
The preoperational environmental radiological 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, comparisons were made between data for indicator stations (those near the plant) and control stations (those remote from the plant) in conjunction with comparisons with preoperational data'adiological Health (Office of Nuclear Power) and the Office of Natural Resources and Economic Development carried out the sampling program outlined in tables 1 and 23.
Sampling locations are shown in figures 2, 3, 4, and 11, and table 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 in Muscle Shoals, Alabama.
Alpha and beta analyses were performed on Beckman Low Beta II, low background proportional counter or a Tennelec LB-5100.
Nuclear Data (ND) Model 6700 system, in conjunction with germanium detection

systems, were used to analyze the samples for specific gamma-emitting radionuclides.

Specific analysis for iodine-131 in charcoal filters was performed using NaI(Tl) well detector systems attached to single channel analyzers.
A TVA fabricated beta-gamma coincidence counting system was utilized for the determination of iodine-131 concentrations in milk.
Analysis for low-energy beta emitters such as tritium was performed using Packard Tri-Carb Model 3255 and 4000 series liquid scintillation systems.
Data were entered in computer storage for processing specific to the analysis conducted.
The data obtained by germanium detectors were resolved by the appropriate analyzer software and the software program routine HYPERMET.
The detection capabilities for environmental sample analyses given as the nominal lower 1imits of detection (LLD) are listed in table 3.
All photopeaks found in germanium spectra were identified and quantified.
Many of the isotopes identified by germanium spectral analysis are naturally occurring or naturally produced radioisotopes, such as Be,

4oK, Bi, Bi, Pb, Pb, Ra, etc.

LLDs for radionuclides identified by Ge(Li) analysis were calculated for each, analysis and nominal values are listed in table 3B.
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 WARL participates in the Environmental Radioactivity Laboratory In ercomparison Studies Program conducted by EPA-Las Vegas.
This program provides periodic cross-checks on samples of the type and radionuclide composition normally analyzed in an environmental radio-logical monitoring program.
Routine sample handling and analysis pro'-
cedures were employed in the evaluation of these samples.
The results received during calendar year 1985 are shown in table 4.
The +30 limits based on one measurement were divided by the square root of 3 to correct for triplicate determinations.
Station Location Muscle Shoals Lawrenceburg Rogersvilie Athens Decatur Courtland Site 1 (N)
Site 2 (NNE)
Site 3
(ENE)
Site 4
(NNW)
Site 5
(WSW)
Farm B
Farm Bn+
Farm ~
Farm L Farm E
'W M
M W
M M
'W M
M M
M W
M M
W M
M W
M M
W M
M W
"M W
M W
M M
A M
A M
A M
A M
A A
M A
M A
M M
M W
'W W
Table l ENVIRONMENTAL RADIOACTIVITYSA.'PLIVO SCNEDL'LE Air Charcoal Rain-Heavy Particle River
'Well Public Aquatic Life FllcFllc t
F ll c
5 kl V~eel Milk I; t lb<
I: c d 5 df r d
Farm W
Control Farms Onsite Well Wheeler Dam Elk River Tennessee River Champion Paper Co.
Various Local Farms M
'W S
W - Weekly M - Monthly (every 4 weeks)
Q - Quarterly S - Semiannually A - Annually

Sampling commenced November 1985 eeDiscontinued operation October 1985

Table 2
Atmospheric and Terrestrial Monitoring Station, Locations Browns Ferry Nuclear Plant Sam le Station Approximate Distance and Direction from Plant RM-1 BF, RM-2 BF)
Farm Bn>>
Farm B
Farm L Muscle Shoals, AQ (Control)
'awrenceburg, TN (Control)
Farm P-'-
Farm E Farm W
Farm N:(Control)
Farm Farm J (Control)
I C (Control)
Farm Ca (Control)
Farm Farm Cb (Control)
M (Control)
LM-1 BF, North LM-2 BF, North-Northeast LM-3 BF, East-Northeast LM-4 BF, North-Northwest LM-5 BF, West-Southwest PM-1 BF, Rogersville, AL PM-2'F, Athens, AL PM-3 BF, Decatur (Trinity),
PM-4 BF, Couri.land, AL 1.0 Mile 0.9. Mile 1.0 Mile 1.7 Miles 2.5 Miles 13.8 Miles 10.9 Miles AL 8.2 Miles 10.5 Miles, 32.0 Miles 40.5 Miles 4.75 Miles 7.0 Miles 5.0 Miles 8.8 Miles 6.1 Miles 6.9 Miles 27.0 Miles
$0.0 Miles 32.0 Miles 32.0 Miles 22.5 Miles 22.5 Miles (1.6 kilometers)
N (1.4 kilometers)
NNE (1.4 kilometers)
ENE (2.7 kilometers)
NNW (4.0 kilometers)
WSW (22.2 kilometers)
NW (17.5 kilometers)
NE (13.2 kilometers)
SSE (16.9 kilometers)
WSW (51.5 kilometers)
W (65.2 kilometers)
NNW (7.6 kilometers)
N (11.3 kilometers)
NW (7.0 kilometers)
(14.1 kilometers)
E
( 9.8 kilometers)
NE (11.0 kilometers)
NE (43.4 kilometers)
NW (64.$ kilometers)
NNW (51.5 kilometers)
N (51.5 kilometers)
W (36.2 kilometers)
E (36,2 kilometers)
ENE
>> Sampling commenced November 1985
>>>>Discontinued operations
.October 1985
Table 3
DETECTION CAPABILITIES FOR ENVIRONHENTAL SAMPLE ANALYSIS A.
S ecific Anal ses NOHINAL LOWER LIHIT OF DETECTION (LLD)*
Air Particulates
~cl/ 'harcoal pCI/m'a1 lout mCI/Km Vegetation Water and Grain
~CI/I yp~CI/ i, Dry Soil and Sediment i>C i/cC,~Dr

Fish, Clam Flesh,

Plankton, DCCi//

D

Foods, Heat, Clam Shells

Poultry, Hiik

~CI/
Dr
~Ci/K WDC.DCi/1 Gross a Gross 8
H-3 I-i31 Sr-89 Sr-90 0.005 0.01 0.005 0.001 0.01 0.05 10 2
0.25 0.05 2
0.05 2
0.20 330 0-35 0.70 1.5

0. 15 0.1 0.1 0.5 0.1 0.7 0.7 5.0 1.0 25 40 8

0.5 10 2

All LLD 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 the given sample.
The assumption Is made that all samples are analyzed within one week of the collection date.
Conversion factors:
I pCi DD 3.7 x 10 Bq; I mCi ~ 3.7 x 10 Bq.
Table 3
DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS B.
Galena Anal ses NOHINAL LOWER LIHIT OF DETECTION (LLD)
Ce-144 Cr-51 1-131 Ru-106 Cs-134 Cs-137 Zr-95 Nb-95 Co-58 Hn-54 Zn-65 Co-60 Fe-59 Ba-140 La-140 Air particu)ates Ge LI

0.02 0.03 0.01 0.03 0.0]

0.01 0.01 0.01 0.01 0.01 0.01 0.01 0.02 0.01 Water and milk
~Ct/I Ge Li 33 44 8
30 5
5 10 5
5 5
9 5
5 25 7
Vegetation and grain Ci/
dr MGe L~i 0.22 o.47 0.09 0.51 0.33 o.o6 0.11 0.05 0.05 0.05 0.11 o.o6 o.34 o.o8 Soll and sediment pCi/<
dr
~Ge L~I o.o6 0.10 0.02 0.11 o.o8 0.02 0.03 0.01 0.01 0.01 0.02 0.01 0.07 0.02 Fish Ci/
dr
~Ge L~i o.o6
-0. 10 0.02 0.11 0.07 0.02 0.03 0.01 0.01 0.01 0.02 0.01 0.10 0.07 0.02 Clam flesh and plankton pCi/
, d Ge Li 0.35 o.56 0.07 o.74 o.48 o.o8 0.15 0.07 0.07 o.o8 0.17 0.08

0. 30 0.10 Clam shells Ci/

d
~oGee~LI o.o6

0. 10

0. 02

0. 11 o:o8 0.02 0.03 0.01 O.DI 0.01 0.02 0.01 0.07 0.02

Foods, (tomatoes

potatoes, etc.)

Ci/K, wet Ge Li 33 44 8
4o 26 5
Io 5
5 5
9 5
25 7
Heat and poul try pCi/K wet Ge Li 40 90 20 90 4o 15 20 15 15 15 20 15 50 15
+ The Ge(Li)
LLD values are calculated by the method deve)oped by Pasternack and Har'ley 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-L Harinelli beaker as dry weight.
The average dry weight is 400-500 grams; Air filters and very smal I volume samples are counted in petri dishes centered on the detector endcap.
The counting system consists of a ND-6700 multichannel analyzer and germanium detector having an efficiency of 20 percent.
The counting time is normally 4-15 hours.
Al I spectral analyses are performed using the software program HYPERHET.
The assumption is made that all samples are analyzed within one week of the collect'ion date.
-2 Conversion factor:
I pCi ~ 3.7 x 10 Bq.
Table 4
RESULTS OBTAINED IN INTERLABCFZ..C:PY COMPARISON PROGRAM A.
Air Filter (pCi/Filter)
Date Gross Alpha EPA value
(+3a)
Gross Beta EPA va I ue TVA
(+3~)
~Av Strontium-90 EPA value TVA
(+3a)
~Av.
Cesium-137 EPA value TVA
~(A v)
~Av l 1/84 3/85 8/85 15+9 10+9 13+9 15
]1 12 52+9 61 3 +9 40 44+9 45 21+3 21 15+3 16 18+3 16 10+9 6+9 8+9 10 6
9 Date 4/85 7/85 B.
Tritium in Urine (pCI/R)
EPA value
(+3a) 3056+622 2444+610 TVA AvcV.v 2687 2280 C.
Radiochemical Analysis of Water (pCI/g)
Date 4/84 1/85 2/85 3/85 4/85 4/85 5/85 6/85 7/85 8/85 9/85 10/85 5+9 6+9 12+9 11+9 8+9 9
12 Gross Alpha EPA value TVA
~(+3
)
~Av 15+9 15+9 72+9 11+9 8+9 8+9 19 17 69 14 12 Gross Beta EPA value TVA
(+3o)
~Av.
10+9 39+9 9d 49 20+9 26 Strontium-89 EPA value TVA
(+3e)
AvcV.
23+9 22b 3+9 10 Stronium-90 EPA value TVA
(+3a)
~Av 26+3 26 30+3 29 Tritium Iodine-131 EPA value TVA EPA value TVA
(+3o)
~Av
(+3<)
~Av
~
3796+634 3817 355"+630 3347 7.5+1.4 7.3 15+3 15+3 7+3 16 13 2416+608 2257 4480+776 4127 33 +10 29 5
1974+598 1880
Table 4 (Continued)
RESULTS OBTAINED IN INTERLABORATORY COMPARISON PROGRAM (Continued)
D.
Gamma-Spectral Analysis of Water- (pCI/!I,)
Date Chromium-51 EPA value TVA
(+3(r)
~Av Cobalt-60 EPA value TVA
(+3cr)
Avcv.
Zinc-65 EPA vali.'e TVA
(+3(r)
Avcv.
Ruthenium-106 EPA" value TVA
(=3(r)
~Av.
Cesium-1 EPA value TVA
(+3(r)
Avcv.
Cesium-137
(+3cr)
~Av 4/84 2/85 4/85'/85 10/85 48z9 4ir+9 21+ 9 45 40b 40 3N:9 30 20-'9 20 55+5 53 15'9 16 14 9
14 47+9 48 20 9 21 19<-9 20 E.
P'ood (pCi,/Kg., Mob Weight) 9 62='9 20 9 40b 53 25 3L<:9 27 35-+9 32 15+9 15 35+9 34 20+9 18 26+9 27 25+9 25 12+ 9 13 20+ 9 19 20+9 20 Date 1/85 7/85 Strontium-89 EPA value TVA
(+3(r)
~Av.
34+9 37 33+9 34 Strontium"90
(+ 3cr )
Avg.
3734f EPA value
(+3cr)
TVA Avg.
35+10 35+10 33 36 I od inc-131 Cesium-137 EPA value TVA
(+3ci)
Aver.
29+9 28 29+9 31 Potassium 40
~(e a
~AV 1 '.82+208 1270 1514+132 1567 F.
Milk (pCi/R,r Strontium-89 Strontium-90 Iodine-131 Cesium-137 Potassium-40 Date 3/85 6/85 11+9 13
(+3(r)
Avcv.
EPA value TVA
(+3cr)
~Av 11+3 11 EPA value
(+3(r) 9+1.6 11+10 TVA Avg.
11hll 11+9 12 EPA value TVA
(+3o)
P.vg.
EPA value TVA
(+-3(r)
~Av e
1525+132 1680 a.
Laboratory perfcrmance evaluation study.
Results received from EPA ir April 1985.
b.
Below LLD.

c. Labortory performance evaluation study.

d.
The analysis was reviewed.
Cause for high results could not be identified.

e. Values reported as mg K/kg.

f. Possible error due to nonhomogeneity of sample.

EPA used dog food ccntaining bone rreal in the preparation of the food cross-check.

g. Values reported as mg K/I<..

h. Results were investigated.

No source, of error was determined.

. I'igh bias on result due to broader ing of the peak used for identifying K-40.

The low abundance and low cour<'.!.-0 efficiency for the 1460 Kev line inflated the small positive bias'aused by temperature variations.
K E
N T
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g 1.:
TENNESSEE VALLEY REGION Ci
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)
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~ -WATTS BAR NUCLEAR PLANT XS -SEOUOYAH NUCLEAR PLANT
- BELLEFONTE NUCLEAR PLANT
.-. BROWNS FERRY 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 off-site concentration of radionuclides based on preoperational meteorological data (see figures 3 and 4).
Four perimeter air monitors are located in communities out to about 13 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 local monitor, air is continuously pulled through a Hollingsworth and Voss LB5211 glass fiber particulate filter at a flow rate of about 3 ft~/min.
At perimeter and remote monitors the system has been modified so that air is continuously pulled through a 1-7/8 diameter glass fiber particulate filter at a flow rate of about 2 ft3/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
horizontal 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 perimetep station.
t Each of the local air monitors is fitted with a GM tube that continuously scans the particulate filter.
The disintegration rate of the atmospheric radioactivity is continuously recorded at each station and radiotelemetered into the plant, Air Filters Air filters are collected weekly and analyzed for gross beta activity.
Adequate time is allowed for decay of radon daughters between collection and analysis of samples.
This time is typically three days.
The samples are composited monthly for analysis of specific gamma-emitting radionuclides and quarterly for Sr and Sr analysis.
The results are combined for each station to obtain an annual average.
These data are presented in table 6.
During this reporting period, two samples were not obtained because of equipment malfunction, two samples were damaged beyond use, one sample was destroyed during

analysis, and one sample was lost during sample change.

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 1968-1985 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) specified in 10 CFR 20 for nonoccupa-tional exposure.
12 Rainwater 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.
During this reporting period, four samples were
,not available due to insufficient rainfall and three samples were not collected due to human error.
Fallout 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.
Charcoal Filters 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, five samples were not taken because of equipment malfunction or filter damage and one sample was destroyed during analysis.
13 Table 5
HAXIMtJM PERMISS IBLE CONCENTRATIONS FOR NONOCCUPATIONAL EXPOSURE Alpha Nonvolatile beta Tritium 1 37Cs 103~ 106R 144(e "Zr-96Nb 1
0Ba 140La 131Z 65Z
'4Mn "Co 09S 90Sr "Cr "4C 6sG 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
~Ci/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.

TaBLE 6 RADIOACTIVITY IN AIR FILTER PCI/N(3) 0 ~ 037 BQ/H(3)
NANc OF FACILITY $ 89UU5 EEBllI LOCATION OF FACILITY l,?UESI9UE 8l.858U8 DOCKET NO-59=252/?69c?oR REPORTING PERIOD TYPE AND OTAL NUHBER IF ANALYSIS PERFORHEO
!OSS ALPHA 52 IOSS BETA 566 IHNA (GELI) 145 LONE R LI HIT OF DETECTION (LLO) cE UQIE 1 5 'OE-03 1.0GE-02 ALL INDICATOR LOCATIONS HEAN (F)
RANGE KEE U9IE
?
1 '4E-02( 449/ 462) 1.00E 4 '3E-02 OECATURr AL 8 ~ 2 NILES SSE 2.13E-02 (
50/
52) 1.18E 3.o9E"02 l 998II9U HINDU UIGUEDI 8UUll8l. UE8U NAHE MEAN (F)
DISTANCE ANO DIRECTION RANGE GEE U9EE 2
CONTROL LOCATIONS cAN (F)
RANGE 5EE h9IE 2
6.73E-03(
1/
52) 6 '3E 6.738-03 2 '9E"02( 103/
l v) 1 ~ 10E 3.64E-02 NUMBER OF NONROUTINE REPORTco EASUREHckTS
'-40 II-21 4 SI-21 2
~8-?14
}8-212 lE-7 rL-208 AC-228 R 90 NOT ESTAB 2.00E-02 NOT ESTAB 2.00E-02 NOT ESTAB 5 'OE-02 NOT ESTAB NOT ESTAB 5 ~ OOE-03 44 1 'OE-03 44 1 '1c-02(
43/ 117)
C.COc-O3 - 3.53E-OZ 2.42E-02(
2/ 117) zi16E 2!68E-02 1 '7E-02(
1/ 117) 1.47E 1.47E-02 2 '2E-02(
2/ 117) 2 36E 3 OBE-02 3' 6E-04(
19/ 117) 1.00E 1.00E-03 8'9E-02(
94/ 117) 5 60E 1 '5E-01 1 'oc-04(
5/ 117) 1 ~ Ooc 2 'OE-04 2'2E-05(
12/ 117) 7.00c 04 - 7 '0E-03 36 VALVES <LLD ANALYSIS PERFORHED 36 VALUES <LLD ANALYSIS PERFORMED LH1 SF 40RTHWEST 1 ~ 0 NILE N
LH3 BF NORTHEAST 1 ~ 0 MILE ENE LH3 BF NORTHEAST 1 ~ 0 NILE ENE LH3 BF NORTHEAST 1
0 NILE ENE LN3 BF NORTHEAST 1 ~ 0 HILE ENE DECATURr AL 8 ~ 2 NII.ES SSE RGGERSVILLEr AL 13 ~ 8 HILES NN ATHENSr AL 1'0 e 9 NILE S NE 2 CZE-02(
9 90c-03 2.68E-02(
2 '8E-02 1 47E-02(
1 '7E 02 3.0BE-02(
3 OBE-02 5 00 -04(
5 ~ OOE"04 1 02E-01(
5 '6E-02 2 OOE"04(
2.00E-04 5 OOE-03(
5.00E-03 7/
13) 3 ~ 26E-02 1/
13) 2'8E-02 1/
13) 1 47E-02 1/
13) 3.088-02 1/
13) 5.00E-OC 1/
15) 1 ~ 34E-01 1/
13)
F 008-04 1/
15) 5.00E-03 8 'SE-03(
11/
26) 1 '0c 1.C38-02 26 VALUES <LLD 25 VALUES <LLD VALUcS <I I 0 3.00E-04(
3/
26) 2 ~ OOE-04 5 '0c 0
1 '1E-01(
22/
26) o.31E-O2 - 1.438-01 Doc 04(
2/
26)
F 008 7 ~ OOE-04 9.5CE-OC(
2/
26) 9 'OE-OC -
1 'GE-G3 S
VALVES <I.LD VALU"S <'O VOTE:
1 ~
NOMINAL LOIIER LINIT OF DETECTION (LLD) AS 0 SCRIBED IN TABLE 3 ~
NOTE:
2 HEAN ANO RANGE BASED UPON DETECTABLE HEASUREHENTS ONLY~
FRACTION OF DETECTABL MEASUREMENTS AT Sc CI. I 0
LOCATIONS IS INDICATED IN PARENTHESES (F) ~
NAHE OF FACILITY kjfQtt55 ffBBI LOCATION OF FACILITY LIMDIQUf TABLE 7 RADIOACTIVITY IN RAINWATER PCI/L -
0 ~ 037 80/L DOCKET ttO.
$ Q252c25Q4230 REPORTING PERIOD 12'>
TYPE ANO TOTAL NUHBER OF ANALYSIS PERFORMED GAMMA (GELI) 13o K"40 8 I-21 4 PB 214 PB-?12 7
TRITIUM 136 LOWER LIMIT OF DETECTION (LLD) off HQIf 1 NOT cSTAS NOT FSTAB NOT ESTAB NOT ESTAB NOT ESTAB 530.00 ALL INDICATOR LOCATIONS ttEAN (F)
RANGE 5ff UQIf 2 20.64<
4.02 -
65.94 5'2(
59/ 112) 0.36 -
29+58 5'4(
35/ 112) 0.33 -
Z1 F 05 1o70(
29/ 11?)
0'1
6.05 58 12<
24/ 112) 24.G9 -
197'o 112 VALVES <LLD ANALYSIS PERFORMED ATHENSr AL 10 9 MILES NE LH5 BF OAVIS F
2 ~ 5 HILE5 XS)t LH5 BF OAVIS F
2 ~ 5 HILES XSW LH5 BF OAVIS F
2 ~ 5 MILc5 XS LM1 SF NORTHWEST 1 ~ 0 MILE N 35.62(
5'0 9'3(
0'5 9'0(
1 ~ 58 2.83(
0'3 78.56(
37'2 2/
12) 65.94 o/
13) 29.38 3/
13) 21.05 4/
13) o.05 6/
13) 197.75 2 ~ 18(.
0.59 6.60(
1 0.04 5.58(
Oo 51 2 ~ 39(
0 ~ 05 54.56(
z1 AD ?2 24 VALVcS 2/
24) 3 ~ 6'7 2/
24) 20e32 4/
24) 7'4 7/
24) 5o97 8/
24) 106.55
<LLD CONTROL L.Qgbr?Qtt )tIIO UK(tUfDI BUUQbl. t)fSU LOCATIONS NAHE MEAN (F)
MEAN (F)
DISTANCE ANO DIRECTION RAtt E
RANGE Xff LtQIf 2 off bQIf 2
NUHSE'R OF NONROVTINE REPORTED EASURcMENTS NOTE:
1 ~
NOMINAL LOWER LIMIT OF DETECTION (LLO)
AS OcSCRIB 0 Itt TABLE 3 ~
NOTE 2 ~
HEA t ANO RA tG BASED UPON GcTECTABL MEASUREMENTS ONLY ~
FRACTION OF DET CTABLE MEASUREMENTS AT SPECIFICO LOCATIONS IS'NDICATED IN PARENTHESES (F) ~
NAHE OF FACILITY ggQUU$
LOCATION OF FACIlITY.gjUgggQUP TABLE 8
RADIOACTIVITY IN HEAVY PARTICLE FALLOUT HCI/KH('2) - 3/000000 00 BQ/KH(2)
DOCl(ET NO ~ 29=2>2c?CQcR2k REPORTING PERIOD TYPE AND fOTAL NUHBER
)F ANALYSIS PERFORHEO tOSS BETA 143 LONER LIHIT OF DETECTION (LLO)
GEE UQIf 1 0.05 ALL INDICATOR LOCATIONS HCAN (F)
RANGE ZcE UQIt; 2 0 16( 10S/ 117) 0.06 -
O.SS LP4 BF TRAILER P
1 ~ 7 'HILES NNM LQC4IIQU UZIU UKQUEKI SUUQBL UEBU RANE HEAN (F)
DISTANCc ANO OIRcCTION RANGE APE UQ..E 2
0,31(
13/
13)
Dodo
Oe88 CONTROL LOCATIONS HEAN (F)
RANGE RF~c UQIR 2-0 ~ 11 (
25/
26) 0.05 -
0.20 NUHBER OF NONROUTIitE REPORTED HEASURE"ENTS VOTE:
1 ~
NOHINAL LOitER LIHIT OF DETFCTION (LLO)
AS DESCRIBED IN TABLE 3 ~
VOTE.
2 ~
HEAN AND RAtlGE BASED UPOlt DETECTABLE HFASUREHENTS ONLY~
FRACTION OF DETECTABLE HEASUREHENTS AT SPCCIFIcD LOCATIONS IS INDICATED IN PARENTHESES (F) ~
NAHF OF FACILITY $ QQWQk EEggy LOCATION OF F ACILIT Y i.I5 c5IQHE TABLE 9 RADIOACTIVITY IN CHARCOAL FILTERS PCI/M(3) - 0 ~ 037 8Q/M(3)
DOCt(ET NO ~
NQ:252c25QA?25 REPORTING PERZOO 1$ ES TYPE ANO TOTAL NUMBER OF AiNALYSIS PERcORMED IODINE-131 566 LOitER LIMIT OF DETECTION (LLO) cc gQIE 1
0.01 ALL INDICATOR LOCATIONS MEAN (F)
RAtlGE SEE UQIE 2
0'2(
6S/
452) 0.01 -
0.13*
i.QQ81IQ5 BIIU >?ltd)EKI 85598!.
t)E64 NAHE HEAtl (c)
DISTANCE AND DIRECTION RAilGE SEE UQIE 2
LF1 BF NORTH)tEST 0+02(
12/
52) 1 ~ 0 MILE N 0 ~ 01 -
0.13+
CONT ROL LOCATIOtlS MEAN (F)
RAtlGE 5EE BQIE 2
0.01(
15/ 104) 0 ~ 01 "
0.02 NUMBcR OF NONROUT INE REPORTED MEASUREMcNTS NOTE:
1 ~
tlOMINAL LO'E'ER LIHIT OF DETECTION (LLD)
AS OESCRIEEO Ztl TA8LE 3 ~
NOTE:
2 ~
MEAN ANO RANGE BASED UPON OETECTA8LE HEASUPEHENTS ONLY~
FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIEO LOCATIONS IS INDICATEO ZN PARENTMEScS (F).
n This value is inflated because of radon interference.
18 Figure 2
- -ATMOSPHERIC AND TERRESTRIAL MONITORING NETWORK RM.2BF LAWRENCEBURG yPULASKI FAYETTEVILLE WILSON FLORENCE PM-IBF WHEELER ROBE SVILL OAM ATHENS PM-2BF FFIEL MUSCLE SHOALS RM-IBF LEIGHTON TUSCUMBIA COURTLANO PM-4 F
pRUSSELLVILLE BROWNS FERRY NUCLEAR PL NT OECAT PM-3BF0 10 MILES HARTSELLE HUNTSVILLE IL GUNT SV OAM HALEYVILLE
~CULLMAN 45 MILES RAINWATER SOIL Q-ENVIRONLKNTAL MONITORING STATIN NOTE: THE FOLLOWING SAMPLES ARE COLLECTED FROM EACH STATION:
AIR PARTICULATES RADIOIODINE HEAVY PART]CLE FALLOUT
LOCAL MONITORING STATIONS BROWNS FERRY NUCLEAR PLANT 19,"
ATHENS U S HWY 72 BFN ALA. HWY 20 Legend 0
Air Monitor AUtomatic Well Sampler Dairy Farm Other Firm" N
DECATUR-Scale 0
I 2
3
. 4 6
Miles
20 Figure 4
sr JC Cp ~ r t>>~,t <<.$ V,+
. ~
II TLD Locations 8FN p Ssp
)
tl
/
I
= i I
~r ~.
C 4!
dJ /Q ; 'I II I
I I
I
) tltr~
ti p
'PQg
'g'-- '1
~ P~"
I r
Ir
~ ~
~ ~ t t t
~
C,'.
IW 7
\\
~
I C t
, ~.
1 !I I
'Y t
j
~CC t
~
I It
',t'Q
'.7 r
I C
'I yF~i' Il 1tt
. l
,t,"
I ~
2 tC'>>
<
t f.
I
, L~~",
"-'I.ir tti 4
~
J
)1 v-<<.
IwIC I
r'I I
>>tt
'. ~ <<.
t c,
~
i I'
r rr 1
r
~I
~I<<
Ey
'I t);
<<I Q
II 4
~I
Figure 5
.30 25 Preoperational Phase I
Operational Phase Wmu AVaeeE 6ROSS 8ETA ACTIVITY IN AIR FILTERS BRANS FERRY Nrem Pusan'20
.15 enoIl 0 o
1J IJ C
4J tC 4 Vn Ave~ra e:
Preo~erational Phase
.10
.05 69 19 971 1972 1973P 19730 1968 19 70 1
1974 1975 1976 1977 1978 1979 1980 1981 1 82 1983 I.984 In85
23 Terrestrial Monitorin Terrestrial monitoring is accomplished by collecting environ-mental media within the general area of the plant for indicator locations, and at remote locations for controls.
These media sampled include milk, vegetation, soil, ground water, drinking water, and food crops.
In addition, environmental gamma radiation levels are determined by strategic placement of thermoluminescent dosimeters.
Twice each year a land use survey is conducted to determine milk producing animal census and location.
Land Use Surve The land use surveys were 'conducted in June and September of 1985.
The fall survey revealed that a dairy operation had resumed at a location previously used as a milk sampling point.
This location was added to the environmental sampling program.
After the land use survey was completed and during routine sample collection run, a dairy operation from which samples had routinely been collected ceased operation.
This location was removed from the sampling schedule.
In compliance with plant technical specifications, a Special Report was submitted to the Nuclear Regulatory Commission on November 26, 1985.
Milk Milk was collected from three farms within a 10-mile radius of the plant (see figure 3), and from at least one of six control farms.
During this report period, one indicator dairy farm ceased operation with the last sample being collected October 28, 1985., At about the same time, operations were resumed at a dairy formerly used as an indicator location.
This location was added to the milk sampling program with the first sample collected on November 4, 1985.
II Raw milk samples are collected from indicator and control

farms, and are analyzed weekly for iodine-131 and monthly for gamma-emitting isotopes and radiostrontium.

Analytical results are summarized in table 10.
During the 1985 reporting period, 7 samples were not available for collection, and one sample was inadvertently destroyed prior to analysis for radiostrontium.
V~eetation Vegetation is sampled monthly at five indicator farms (three dairies and two farms with one milk-producing animal),
and at each air monitoring station.
quarterly vegetation samples are collected at four control farms (one control farm ceased operation in August).
The monthly samples are analyzed for iodine-131 and gamma-emitting isotopes with analysis for radiostrontium performed on the last monthly sample of each quarter.
Samples collected quarterly are analyzed for gamma-emitting isotopes.
Table ll summarizes analytical results.
'uring this reporting period, three samples were inadvertently destroyed before iodine analysis was done.
24 Soil Soil samples are collected annually near each monitoring

station to provide an indication of long-term buildup of radioactivity in the environment.

An auger or a "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, strontium-89, and strontium-90.
The results are given in table 12.
Ground Water An automatic sequential-type sampling device collects grouhdwater from a well downgradient from BFN.
A composite sample from this welk is analyzed for gamma-emitting radionuclides monthly and composited quarterly for determination of tritium.
A grab sample is also taken monthly from a control well'pgradient from the plant.
The results of the analysis of well water are shown in table 13.
During this report period one sample was not available for gamma analysis.
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 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 into the water treatment facility.
Two additional supplies downstream and one public water supply upstream are sampled by taking monthly grab samples of treated water at user points.
In addition, the surface water sample collected by an automatic water sampler upstream from the plant is included as a control for drinking water.
Table 14 indicates the results from the analysis of drinking water samples.
During this reporting period, two weekly samples were not collected because of automatic sampling equipment malfunction.
Figure 6 shows the trends in gross beta activity in drinking water from 1968 through 1985.
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

'eported 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 approx-imately five miles from the site to determine the gamma exposure rates at these locations.
The dosimeters, located inside energy compensating shields to correct for energy dependence, are placed at. approximately one meter above the ground, with three TLDs at each station, They are
25 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 2-5 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 construction 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 1985.
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 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 monitoring program are up to 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'he construction of TVA's Matts 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.
Food Products Food products raised in the vicinity of BFN and at control locations are sampled as they become available during the growing

season, and analyzed for gross beta activity and for gamma-emitting radionuclides.

During this sampling period, samples of apples,

cabbage, corn, green beans,

potatoes, beef, and tomatoes were collected and analyzed for specific gamma-emitting radionuclides.

The results are given in 'tables 16 through 22.
TABLE 10 NAME OF FACILITY gg{}UUQ PfggI LOCATION OF FACILITY LIUE/IQUE RADIOACTIVITY IN MILK PCI/L - 0 ~ 037 BQ/L DOCKET NO ~ -29=222A2(lQc22{i REPORTING PERIOD TYPE ANO TOTAL NUHBER OF ANALYSIS PERFORMED OD IN E-1 31 434 AHHA (GELI) 108 cs.-13r K-40 BI-214 PS-214 P8-212 TL-208 AC-228 R 89 107 R 90 107 LONER LIHIT OF DETECTION (LLO)
Sff UNTIE 1
0'0 F 00 NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB HOT-ESTAB NOT ESTAB 10 F 00 F 00 ALL INDICATOR LOCATIONS MEAN (F)
RANGE kff UQIE 2
156 VALUES <LLD ANALYSIS PERFORHED 8 F41(
6/
39) 6 29 -
9'8 1193 '9(
39/
59) 768 95 -
1686.67 7 ~ 41 (
31/
39) 0'9 -
35'8 7.85(
13/
39) 1 '6 -
26'5 2.00(
8/
39) 0.39 -
3'0 1.35(
6/
39)
Oe12 =
3 '3.
8.52(
3/
39) 5 F 08 -
13'6 39 VALOES <LLO ANALTSIS PERFORHEO 3'0(
38/
39) 2'5 -
5 44 PAGE FARH 8 ~ 75 HILES E
LOONEY FARH 5 ~ 75 MILES ENE SMITH/BENNETT FA 4 ~ 75 MILES N
LOONEY FARH 5 ~ 75 MILES ENE LOONEY FARH 5%75 MILES ENE PAGE FARH 8.75 HILES E
PAGE'ARM 8 75 HILES E
8 41(
6'9 1264 '3(
1058 '4 9 98(
8.41 10 02(
1 36 F 00(
F 00 2 25(
0'7 10+23(
7.21 6/
11) 9 98 13/
15) 1435 68 2/
2) 11 '5 4/
13) 26 95 1/
13) 3.00 2/
11) 3.63 2/
11) 13'6 8 F 59(
2/
59) 5 84 -
11 '4 1297 44(
69/
69) 781.33 -
1925 '4 6.93(
38/
69) 0'2 -
21 '7 7'8(
27/
69) 0'4 -
29 F 05
'1.98(
12/
69) 0.56 -
6.27 0'7(
13/
69) 0.01 -
2.r8 5.20(
9/
69) 0'2 -
11 '6 68 VALVES <LLO SHITH/BENNETT FA 4 ~ 75 NILES N
4 ~ 12(
2/
2) 3 77 -
4'8 3 70(
56/
68)
F 00 -
6'1 CONTROL L9C8IIOU hIIU UIfiUEH 8UUll8L UE8U LOCA1'IOHS NAHE HEAN (F)
MEAN (F)
DISTANCE AND DIRECTION RAilGE RAHGc SEE UOLTE 2
SEE UQIE 2 278 VALUES <LLO NUMBER OF NONROUTINE REPORTED HEASUREHENTS NOTE:
1a NOHINAL LONER LIMIT OF DETECTION- (LLO)
AS DESCRISED IN TABLE 3 ~
NOTE:
2 ~
MEAN AND RANGE BASED UPON DETECTABLE HEASURENENTS ONLY~
FRACTION OF DETECTABLE HEASUREHcNTS AT SPECIFIce LOCATIONS IS IHDICATEO IN PARENTHESES (F) ~
TABLc ll RADIOACTIVITY IN VEGETATION PCI/G - 0 ~ 037 BQ/G (ORY WEIGHT)
NAHE OF FACILITY EBQBHB ffBBI LOCATION OF FACILITY ling EIQ5f aiaaaLB NO ~ 29=222c2kQc22(i REPORTING PERIOD
$ PB$
SR 89 SR 90 65 65 TYPE AND TOTAL NUMBER OF ANALYSIS PERFORHED IODINE-131 208 GAMMA (GELI) 226 C0-60 CS-137 K-40 BI-214 BI 212 PB-214 PS-212 BE-7 TL-208 AC"228 LOWER LIMIT OF DETECTION (LLO)
SEE UQIE 1 NOT ESTAB 0 ~ Oe 0 ~ 06 NOT ESTAB 0 ~ 10 NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB 0'5 0 ~ 05 ALL INDICATOR LOCATIONS MEAN (F)
RANGE EE BQIc 2
0 00(
85/ 183) 0.00 -
0 ~ 02 0 ~ 49(
1/ 185) 0.49 -
0 ~ 49 0'3(
14/
1 85) 0'7 -
0'7 15 56( 182/ 185)
F 04 "
43'1 0'2(
93/ 185) 0'0 0 F 60 0'8(
2/ 185) 0 27 -
0 50 0.16( 167/ 185) o.oo -
o.ee 0.07( 126/ 185) 0 00 -
0 ~ 43 7'3( 184/ 185) 0.61 -
25'2 0 ~ 04 (
78/
1 85) 0 ~ 00 -
0 ~ 14 0.20(
73/ 185) 0 F 02 -
0 ~ 79 57 VALUES <LI.O ANALYSIS PERFORMED 0 20(
53/
57) 0 ~ 06 -
0+56 LM1 BF NORTHWEST 1 ~ 0 HILE N
PAGE FARH 8 ~ 75 MILES E
PAGE FARM 8 ~ 75 MILES E
PAGE FARH 8 ~ 75 MILES E
PAGE FARM 8 ~ 75 MILES E
EVANS FARH 6 ~ 1 HILE5 HE EVANS FARM 6 ~ 1 MILES NE SMITH/BENNETT FA 4 ~ 75 HILES N
EVANS FARM 6 ~ 1 MILES NE PAGE FARM 8 ~ 75 MILES E
0.49(
0'9 0~27(
0 ~ 27 25.86(
5'6 0:39(
0 ~ 13

0. 50(-

0'0 0 21(
0 F 06 0'3(
0 01 10 28(
6 ~ 47 0 07(
0.01 0 29(
0'3 1/
1/
11/
4/
1/
12/
9/
5/
6/
2/
13) 0 49 11) 0 ~ 27 11) 43'1 11) 0'0 11) 0.50 13) 0 42 13) 0'0 5) 15.56 13) 0.11 11) 0 ~ 45 ROGERSVILLEi AL 13 ~ 8 MILES NW 0 35(
4/
4) 0.16 -
0.56 l QCGIZQU liIIU UIQi)EEI 685M8l ilfilU NAME MEAN (F)
DISTANCE ANO DIRECTION RANGE Kff BQIE 2
DECATURr AL 0 01(
6/
12) 8 2 MILES SSE 0.00 -
0 02 CONTROL LOCATIONS HEAN (F)
RANGE SEE HQIE 2
0 00(
10/
25) 0+00 -
0+01 41 VALUES <LLD 0 12(
3/
41) 0 ~ 06 -
0 ~ 15 15 ~ 87(
40/
41) 1 43 -
40 34 0.20(
14/
41) 0'1 -
0.46 41 VALUES <LLD 0.12(
33/
41) 0 ~ 01 -
0 ~ 40 0 ~ 04(
18/
41) 0'1 -
0 11 7'4(
41/
41) 0097 -
18'5 0 02(
11/
41) 0 F 00 -
0.05 0 ~ 16(
12/
41) 0'5 "
0 ~ 30 8
VALUES <LLO 0+21(
8/
8) 0 09 "
0.41 NUMBER OF NONROUT INE REPORTED HEASUREHENTS 1
(Note 3)
NOTE NOTE:
Note:
1 ~
HOMINAL LOWER LIMIT OF DETECTION (Ll.O)
AS DESCRIBED IN TABLE 3 ~
2 ~
HEAN AND RANGE BASED UPON DETECTABLE MEASUREHENTS ONLY~
FRACTION OF DETECTABLE HEASUREHENTS AT SPECIFIEO LOCATIONS IS INDICATEO IN PAREhTMESCS (F) ~
3.
A report was submitted to the Nuclear Regulatory Conmisslon on June 14, 1985, outlining the high value.
The single, isolate4 occurrence of cobalt-60 in vegetation, the absence of other fission and activation products in the sample, and the lack of an increase in cobalt-60 releases from the plant prevented an Identification of the causes for the presence of the isotope in the sample.
Subsequent samples showed no indication of the presence of cobalt-60.
TABLE 12 RADIOACTIVITY IN SOIL PCI/G - 0.037 Sa/G (DRY HEIGHT)
TYPE AND TOTAL NUHBER OF ANALYSIS PERFORHED CONTROL LQQGIIQS HIIU UIQUESI BHUllhl. Ufhu LDCATIDNS NAHE HEAN (F)
MEAN (F)
DISTANCE AND DIRECTION RANGE RANG(
GEE 8QIE 2
Eff hQIE 2
AHMA (GELI) 11 CS-1 37 K-40 BI-214 BI-212 PB-214 PS-212 RA-226 RA-224 2/
2) 0'7 2/
2) 4 '9 2/
2) 0'4 2/
2) 0'4 2/
2) 1 04 2/
2) 0.87 2/
2) 0.94 2/
2) 0'3 1/
2) 0'2 1/
2) 0.11 2/
2) 0.29 2/
2) 0 F 87 2/
2) 3.33
<LLO 0.46(
0.02-5'8(
2 ~ 89-1 '8(
0 ~ 63-1 '1(
0 ~62-1o17(
0 67-1 ~ 04(
0 ~ 52-F 08(
0.63-1.11(
0'2 0'1(
0 ~ 18 9
VALUES 9/
9) 1 '3 9/
9) 7'4 9/
9) 1 43 9/
9) 1 ~ 55 9/
9) 1 '8 9/
9) 1.35 9/
9) 1 '3 7/
9)
F 47 2/
9) 0 24
<LLD 9/
9) 0 ~ 47 9/
9) 1 '8 4/
9) 2'4
<LLD FORMED 4/
9) 0'8 0'2 LH5 BF OAVIS F
2.S MILES WSM LH1 BF NORTHWEST 1+0 MILE N
LM2 SF NORTH 0 '
MILE NNE
-LI'.2 SF NORTH 0 ~ 9 MILE NNE LM1 BF NORTHNEST 1 ~ 0 MILE N OECATURr AL 8.2 HILES SSE Lr2 SF NORTH 0 ~ 9 MILE NNE LH3 BF NORTHEAST 1 ~ 0 MIl.E ENE DECATURr AL 8 ~ 2 MILES SSE 1 43(
1 ~ 43 7 ~ 24(
7 24 1 ~ 43(
1 43 1/
1) 1a43 1/
1) 7 24 1/
1) 1 '~
1/
1) 1'5 1/
1) 1'8 1/
1) 1e35 1/
1) 1 43 1/
1) ie47 1/
1) 0'4 0+38(
0.20-4.D3(
3 ~ 17 0'0(
0.87-0 91(
089-0.96(
0 ~ 88-0.8S(
0 ~ 83-0.90(
0.87 0.87(
Oo80-0 22(
0.22 0 11(
0 ~ 11 0 28(
0'7 0.85(
0.83 2.59(
1.44 2
VALUES 0'5 0 F 05 Oe10 1 55(
1 '5 1 ~ 48(
1 ~ 48 0 F 05 NOT ESTAB 1 '5(
1 '5 1 ~ 43(
0 F 05 1
43 1 ~ 47(
NOT ESTAB 1 '7 0 ~ 16 SE-7 TH"227 TL-208 AC-228 PA-234M 0 24(.
0 ~ 24 NOT ESTAB 0 36(
0 ~ 19 1 ~ 06(
0'5 2.18(
1 '3 Oa02 DECATURr AL 8 ~ 2 HILES SSE OECATURr AL 8
2 MILES SSE ROGERSVILLEr AL 13.8 r.ILEs Nv 1/
1) 0.47 1/
1) 1o38 1/
1) 2'4 0 ~ 47(
0 47 1 ~ 38(
1 '8 2.74(
2'4 0.06 NOT ESTAB 9
VALUES ANALYSIS PER 0 ~ 24(
0 ~ 20-1 ~ 50 R 89 R
90 0 ~ 15 0.28(
0 ~ 28 1/
1) 0 ~ 28 LMS BF DAVIS F 2.5 MILES NSV 2
VALUES <LLO NAME OF FACILITY ggQgQ$ ffgg7 DOCKET NO ~
NQ 2$ gc25Qc2$ $
LOCATION OF FACILITY LIQEEIQgf gggfggg
'EPORTING PERIOD LOIIER L IMIT OF DCTECTION (LLO)
EEE 5QIE I NUMBER OF NONROUTINE REPORTED MEASUREMENTS NOTE:
1 ~
NOHINAL LONER LIMIT OF DETECTION (LLO)
AS DESCRIBEO IN TABLE 3 ~
NOTE:
2 ~
MEAN ANO RANGE BASED UPON DETECTABLE MEASUREMENTS ONLY~
FRACTION OF-DETECTABLE=HEASUREHENTS AT SPECIFIEO LOCATIONS IS INOICATEG IN PARENTHESES (F) ~
NAHE OF FACILITY EBQHUR EfESI LOCATION OF FACIlITY IIUEKIQUE TABLE 13 RADIOACTIVITY IN NELL kATER PCI/L 0 ~ 037 BO/L 8I8E8U8 DOC<ET NO ~ 59=212c259c225 REPORTING PERIOD 1252 TYPE ANO TOTAL NUHBER OF ANALYSIS PERFORHEO LONER LIHIT OF DETECTION (LLD)
SEE UQIE 1
ALL INDICATOR LOCATIONS HEAN (F)
RANGE Kff UQIE 2
IQI8ITQU UIIU UIQUERI 8UU98I UE8U NAHE MEAN (F)
DISTANCE ANO DIRECTION RANGc SEE UQIE
?
CONTROL LOCATIONS HEAN (F)
RANGE Kff UQTE 2
NUHBER OF NON ROUTINE REPORTED HEASUREMENTS GAHHA (GEL!)
25 K-40 BI-214 PB-214 PB-212 TL-208 AC-228 TRITIUH NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB S30.00 8 ~ 92(
1/
13) 8'2 -
8'Z 9'6(
12/
13) 1
%3 -
17 22 12 F 08(
9/
13) 2'7 -
18'7 F 80(
4/
13) 0'1 -
4'4 13 VALUES <LLO 7'9(
1/
1S) 7'9 -
7'9 4
VALUES <LLD ANALYSIS PERFORHEO BFN kELL N6 0 ~ 02 HILES k BFN MELL N6 0 ~ 02 HILES.X BFN MELL P6 0 ~ 02 HILES W
BFN NELL P6 0
OZ HILES BFN MELL P6 0 ~ 02 HIlES 8 92(
8.92 9 36(
1 ~ 43 12 08(
2 ~ 97 F 80(
0 71 1/
12/
9/
4/
13) 8'2 13) 17'Z 13) 18 ~ 27 13) 4 54 7 ~ 09(
1/
13) 7 09 -
7'9 4'7(
2/
1Z) 1+06 -
8.09 175 '2(
12/
12) 40'7 -
680'5 177 10(
12/
12) 43'4 682 '2 3'7(
3/
12) 1.63 -
6'6 0.33(
2/
12) 0'8 "
0'8 12 VALUcS <LLD 4
VALUES <LLO NOTE:
1 ~
NOHINAL LONER LIHIT OF DETECTION (LLD)
AS OESCRIBEO IN TABLE 3 ~
NOTE:
2 ~
HEAN ANO RANGE BASED UPON DETECTABLE HEASURcHENTS ONLY'RACTION OF DETECTABLE HEASUREHENTS AT SPECIFIEO LOCATIONS IS INDICATED IN PARENTHESES (F) ~
TABLE 14 RADIOACTIVITY IN PUBLIC WATER SUPPLY PCI/i - 0 037 BQ/L NA!IE OF FACILITY 5 HQHUf ffBBX DOCKET NO ~ 2Q=222C25QA22k--------
l.PCATIPN OF FACILITY gggfggggf 8L85858 -------REPORTING PERIODgggf iR 90
'RITIUH 20 20 TYPc AND TOTAL NUHBER OF ANALYSIS PERFORMED ROSS BETA'02 AHMA (GELI) 102 K-40 BI-214 PB-214 PB-212 TL-208 AC-228 R 89 20 LOVER LIMIT OF DETECTION (LLD) off HQIf 1 F 00 NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB 10 00 F 00 330 F 00 ALL INDICATOR l.OCATIONS HEAN (F)
RANGE off UQIf 2 3'3(
55/
76) 2.05 -
6.58 14.82(
12/
76) 2'2 -
42'6 5.45(
39/
76) 0'7 -
19.73 4 86(
24/
76) 0.38 "
17'9 1.76(
15/
76) 0'1 -
8'8 1 02(
12/
76) 0 F 00 -
2 38 5'6(
9/
76)
Oe13 -
11 '9 12 VALUES <LLD ANALYSIS PERFORHED 12 VALUES <LLO ANALYSIS PERFORHED

12. VALUES <LLD WHEELER DAHr AL TRH 274 '

NHEELER DAHr Al TRH 274 '
SHEFFIELDr AL ROB TRH 254 '
HHEELER OAHr AL TRH 274 '
CHAMPION PAPER TRM 282 '
SHEFFIELDrAL ROB TRM 254 '
23 ~ 86 (
11 ~40-7.39(
1 s51 7 29(
0'6 4 ~ 10(
4e10-1 ~ 05(
Oe00 -'
~ 49(
9.49-3/
13) 42 16 7/
13) 14.32 3/
13) 17 79 1/
13) 4'0 8/
50) 2'8 1 /
13) 9 ~ 49 LQQhIIQU III'IQBffIhUUQhl UfBU NAHE McAN (F)
DISTANCE ANO DIRECTION RANGE off UQIR 2 3%38(
40/
50) 2.08 -
6.58 CONTROL LOCATIONS HEAN (F)
RANGE off HQIf 2 2'3(
22/
26) 2.04 -
5+62 333e48(
333'8 1/
8) 333.48 0 ~ 47(
1/
26) 0'7
=
0'7 9 22(
12/
26) 0.13 -
47o47 5.62(
7/
26) 0 ~ 47-18 90 1 '9(
6/
26) 0'9 -
2~72 26 VALUES <LLD 8'8(
4/
26) 0.93 -
27.49 8
VALUES <LLD 8
VALUES <LLD NUMBER OF NONROUTINE REPORTED MEASUREMENTS NOTE 1 ~
NOMINAL LOMER LIMIT OF DETECTION (LLO)
AS OESCRIBEO IN TABl.E 3 ~
NOTE:
2 ~
MEAN AND RANGE BASED UPON DETECTABLE HcASUREHcNTS ONLY ~
FRACTION OF OcTECTABLE MEASUREMENTS AT SPECIFIEO LOCATIONS IS INDICATED IN PARENTHESES (F) ~
Table 15 ENVIRONMENTAL GAMMA RADIATION LEVELS Average External Gamma Radiation Levels at Various Distances from Browns Ferry Nuclear Plant for Each Quarter - 1985 mR/Quarter Distance miles Avera e External Gamma Radiation Ievels b 4th uarter 0-,1 1-2 2-4 4-6
>6 18.0 + 2.5 16.2 + 2.6 15.1 + 1.4 14.8
+ 1.3 14.4
+ 1.3 19.4 + 0.8 17.7 + 1.8 15.9
+ 1.5 16.1
+ 1.7 15.8 + 1.5 21.8 + 3.7 17.9 + 3.8 16.1 + 3.0 16.5
+ 3.2
'5.2 + 2.4 21.0
+ 2.1 18.1
+ 2.4 18.2 + 2.7 17,6 + 2.2 17.4 + 1.9

Average, 0-2 miles (Onsite)

Average,

>2 miles (Offsite) 17.6
+ 2.5 14.8 +
1
~ 3 18.9
+ 1.3 15.9 + 1.5 20.8 + 4.0 16.0 + 2.9 20.3 + 2.4 17.6 + 2;2 a.
Data normalized to one quarter (2190 hours0.0253 days 0.608 hours 0.00362 weeks 8.33295e-4 months ),

b. All averages reported +la (68 percent confidence level).

TABLE 16 RADIOACTIVITY IN CABBAGE PCI/KG- = 0 ~ 037 BO/KG (MET MEIGHT)
NAHE OF F AGILITY QBQBUK EtBBI LOCATION OF FACILITY Qggf5IQgf
=
SaaaSBS DOCKET NO ~
$ Q-2$gg2$ QA2$ $
REPORTING PERIOD ],Pgg TYPE ANO OTAL NUMBER
>F ANALYSIS PERFORHEO

OSS SETA 2

iHMA (GELI) 2

-40 LONER LIMIT OF DETECTION (LLO)

Rff 5QIf I 25.00 NOT ESTAB ALI.
INDICATOR LOCATIONS HcAN (F)
RANGE ff gQIf 2
3764.15(
1/
1) 3764 15 -
3764.15 LQQ8IIQU liIIU tfIQUfKI hBUQhl. UfBB NAME MEAN (F)
DISTANCE AND DIRECTION RANGE Bff UQl=
2 3764 ~ 15(
1/
1) 3764 ~ 15 -
3754.15 CONTROL LOCATIONS MEAN (F)
RANGE Sff hQIh 2
3440 ~ 65 (
1/
1) 3440.55 -
3440.55 1652.54(
1/
1)
PAGE FARH 1652 ~ 64 -
1652
~ 04 8.75 MILES E
1652.54(
1/
1) 1569.45(
1/
1) 1552 ~ 64 -
1652 ~ 54 1569 ~ 45 -
156? ~ 45 NUMBER OF NONROUTINE RcPORTED ASVREHcNT lOTE:
1 ~
NOMINAL LOVER LIHIT OF DETcCTION (LLD)
AS DESCRISEO IN TABLE 3 ~
IOTE:
2 ~
MEAN AND RANGE BASED UPON DETECTABLE HEASUREM'ENTS ONL'Y ~
FRACTION OF DETECTABLE HEASUREHENTS AT SPECIFIED LOCATIONS IS INOICATEO IN PARENTHESES (F ) ~
TABLE 17 RAOIOACTIVITT IN CORN PCI/KG 0 ~ 037 SQ/KG (llET ilEIGMT)
OOCKET tlO 5{}=222c2{tQA22fi RcPORTItlG PERIOO 12/i NAME OF FACILITY EEQVS> riaar LOCATION OF FACILITY {,IUEKIQUE SLSQhhh CONTROL t.OCATIONS MEAN (F)
RANGc KEc 5QEE 2
3807 '4(
1/
1) 3807 '4 -
3807.94
,TYPc ANO TOTAL NUMSER OF ANALYSIS PcRFORHEO LOitER LIMIT OF OETECT ION (LLO)
SEE 5QIE 1
25.00 ALL INOICATOR LOCATIONS MEAN (F)
RAtlGE hiE 8QIE 2
4152.57(
1/
1) 4152
~ 67 -
4152.67 GROSS SETA 2
GAMv4 (GELI) 2 K-40 2153+31(
1/
1) 2153 ~ 31 -
2163.31 1
VALUES <LLO 2518 ~ S6(
1/
1) 7 MILES NNu 2518 '6
2518 '6 10 ~ SS(
1/
1) 7 MILES NNN 10'8 -
10'8.
2518 86(
1/
1) 2518.86 -
2518.86 10 58(
1/
1) 10'o -
10.58 NOT ESTAB NOT ESTAB P8-214 LQQ4XIQB hII5 UiltUEKI AQttQS{. 5EA5 NAME MEAN (F)
~-
OISTANCE ANO DIRECTION RANGE
%RE UQ1%
2 7 HILES NN'N 4152 67(
1/
1) 4152 '7
4152.67 NUMBER OF tlONROUTINE RcPORTEO MEASUREMENTS VOTE:
1 ~
iVOMINAL LOltER LIMIT OF OETECTIOtl (LLO)
AS 0ESCRIS 0
IN TABLE 3 ~
NOTE:
2 ~
MEAiV ANO RAtiGE BASEO UPON DETECTABLE M ASUREHENTS ONLY ~
FRACTION OF OET CTASLc MEASUREMENTS AT SP CIFIEO LOCATIONS IS INOICATEO IN PARENTHESES (F) ~
TABLE 18 RADIOACTIVITY IN GREEN BEANS PCI/KG 0
03.7 BQ/KG (WET rlEIGHT)
DOCKET NO 19=222ckkGA220--------
REPORTING PERIOD 1252-NUMBER OF NONROUTINE REPORTED MCASUREMENTS ALL INDICATOR LOCATIONS MEAN (F)
RANGE 5ff UQIf 2 3823 47(
1/
1) 3823.47 -
3823 '7 TYPE AND
'OTAL NUMBER IF ANALYSIS PERFORMCO CONTROL LOCATIONS l EAtr (F)
RANGE off hQIf 2 5150 ~ 78(
1/
1) 5150 ~ 78 -
c150.78 LOWER LIMIT OF DETECTION (LLO)
Rff UQjf 1 25 F 00 L9liAIIQ8 HII~ ~Il'lUfkI SuHQEL UfhH NAME MEAN (F)
'DISTANCC AND DIRECTION RANGE 5ff 59] f 2 7 MILES NNW 3823.47(
1/
1) 3823 '7 -
3823 ~ 47 l'OSS BETA 2
IMMA (GELI) 2

-.40 1659 47(

1/
1) 7 MILES NNW 1659 '7 -
1659.47 1
VALUES <LLD 2003 r 71(
2003.71 5 ~ 70(
3 70-2 ~ 14(
2.14 NOT ESTAB 1659 47(
1/
1) 1659'7 -
1659 '7 1/
1) 2003
~ 71 1/
1) 3'0 1/
1) 2 ~ 14 SI"214
'B-214 NOT ESTAB 1
VALUES <LLD NOT ESTAB NAME OF FACILITY gggggr'l ffgfJ LOCATION OF FACILITY l LUffIQuf 6l 6N58 lOTE:
1 ~
NOMINAL LOWER LIMIT OF DETECTION (LLO)
AS DESCRIBED IN TABLc 3 ~
IOTE:
2 MEAN AND RANGE BASED UPON DETECTABLE MEASUR MENTS ONLY ~
FRACTION OF DETECTABLE MEASVR MENTS AT SrrcCIFIED LOCATIONS IS INDICATED IN PARENTHcSES (F) ~
TA 8 LE 19 RAOIOACTIVITY IN Aol LES PCI/KG - 0.057 BO/KG ('lET WT)
NAHF.
OF FACILITY llgQ115E EEEBZ LOCATION OF FACILITY LIQEJIQllE hLBEMS OoCKET NO ~
XQ=222A2OQA22O RcPORTING PERIOO TYPc ANO TOTAL NVHBER OF ANALYSIS PERFORHEO GROSS BETA 2
GAHMA (GcLI) 2 LONER LIMIT OF Oc TECTI ON (LLO)
SEE 8QIE I 25 F 00 AI.L INDICATOR LOCATIONS MEAN (F)
RANG" GEE SQIE 2
1695
~ 72(
1/
1) 1695.72 -
1695e72 l,QQhILQll XIII VIQdEDI 83Ullhl. llEhki NAHE MEAN (F)
DISTANCE ANO DIRECTION RANGE SEE 5QIE 2
PAGE FARH 1695e72(
1/
1) 8.75 MILES E
1695.72 -
1695.72 CONTROL LOCATIONS MEAN (F)
RANGE KEE UQIE 2
1618 ~ 79(
1/
1) 1618e79 -
1618.79 NUMBER OF NONROVTINE REPORTEO MEASUREMENTS K-40 BI-214 PB-214 AC-228 NOT ESTAB NOT 'STAB NOT ESTAB NOT ESTAB 1080.23(
1/
1)
PAGE FARH 1080+23 -
1080.23 8.75 HILES E
1 VALUES <LLO 1
VALUES <LLO 1
VALUES <LLO 1080 ~ 23(
1/
1) 1080.23 -
1080.23 862.72(
862. 72 8o47(
8.47 3.62(
3.62 2 70(
2I70-1/
1) 862 '2 1/
1) 8.47 1/
1) 3'2 1/
1) 2 70 NOTE:
1 ~
NOMINAL LONER LIMIT OF OETECTION (LLO)
AS OESCRIBEO IN TABLc 3 ~
NOTE:
2.
MEAN ANO RANGE BASEO UPON OETECTABLE HEASUREMENTS ONLY~
FRACTION OF O
T CTABLE MEASUREMENTS AT SPECIFIEO LOCATIONS IS INOICATEO IN PARENTHESES (F) ~
TABLE 20 RADIOACTIVITY IN POTATOES PCI/KG - 0 ~ 037 BQ/KG (itET HEIGHT)
NAHE OF FACILITY ggQ}JUL ffgg7 LOCATION OF FACILITYLIUE5IQUE BLBftBUB DOCKET NO ~
$ Q:7$ oc7$ {}c2$$
REPORTING PERIOD TYPE ANO l'OTAL NUHBER
)F ANALYSIS PERFORHEO lOSS BETA 2
NHA (GELI) 2
'-40 LONER LIHIT OF DETECTION (LLD)
Zff UQZE 1
25.00 NOT ESTAB ALL INDICATOR LOCATIONS MEAN (F)
RAtlGE Xff UQIE 2
6048 '6(
1/
1) 6048'6 6048 '6 3408 F 85(
1/
1)
PAGE FARH 3408 ~ 85 -
3408 ~ 85 E 75 MILES s 3408.85(
1/
1)
S408.85 -
3408.85 LQQBXIQU UIIU UIQUEDI BUUQBL UEBU NAHc HEAN (F)
DISTANCc AND DIRECTION RANGC MA+
7 Gff UQ~ c PAGE FARH e048.46(
1/
1) 8 ~ 75 HILLS c 6048.4e -
6048.46 CONTROL LOCATIONS HEAtl (F)
RANGE off UQIE 2
6564 '8(
1/
1) 6564.38 -
6564.38 3694 e1 (
1/
1) 3694.61 -
3694.61 NUHBER OF NONROUTINE cPORTED HCASUREHENTS lOTE 1 ~
NOHINAL LONER LIHIT OF DETECTION (LLO)
AS OESCRIBEO IN TABLE 3 ~
(OTE) 2 ~
HEAW AND RANGE BASED UPON DETECTABLc HEASUREHENTS ONL'Y FRACTION OF DETECTABLE HEASUREHENTS AT SPECIFIcO LOCATIONS IS INDICATED IN PARENTHESES (F) ~
TABLE 21 RADIOACTIVITY IN BEEF PCI/KG 0 ~ 037 BQ/KG (NET FREIGHT)
OF FACILITY hggg55 EEEBZ LOCATION OF FACILITY LIPEEI9UE BlBEB~B DOCKET NO ~ 19=22242694226 REPORTING PERIOD TYPE ANO TOTAL NUMBER OF ANALYSIS PERFORMED GROSS BETA 2
GAHHA (GELI) 2 K-40 PB-214 PB-212 LONER LIMIT OF PETcCTION (LLO) 5EE 59IE 1
25 ~ 00 NOT ESTAB NOT ESTAB NOT cSTAB 1838 '2(
1838 '2 0'0(
0.10 0.33(
0'3 1/
1) 1838 '2 1/
1) 0.10 1/
1) 0.33 ALL INDICATOR LOCATIONS MEAN (F)
RANGE Xff 59IE 2
4397.55(
1/
1) 4397s55 -
4397.55 LOONcY FARH 5'5 MILES ENE LOONEY FARM 5 ~ 75 H ILES ENE LOONEY FARH 5 ~ 75 MILES ENE 1838 ~ 92(
1/
1) 1838 92 -
1838.92 0 ~ 10(
1/
1) 0 ~ 10 -
Oo10 0 33(
1/
1) 0'3 -
0.33 L99BII98 III'IQUEXIBBUllBl HEBE NAHE HEAN <F)
DISTANCE AiVO DIRECTION RANGE REE 89IE 2
LOONEY FARM 4397 55(
1/
1) 5 ~ 75 NILiS ENE 4397 e 55 4397 ~ 55 1384 '5(
1384.55 1.21(
1e21 O.rr<
Oo 77 1/
1) 1384 ~ 55 1/
1) 1 ~ 21 1/
1 )
0.77 CONTROL LOCATIONS MEAN (F)
RANGc EEE UNTIE 2
3768.67(
1/
1) 3768'7
'3768 ~ 57 NUMBER OF NONROUTINE REPORTcD HEASUREHENTS NOTE:
1 ~
NOHINAL LONER LIMIT OF DETECTION (LLD) AS DESCRIBED IN TABLE 3 ~
NOTE:
2 ~
MEAN ANO RANGE BASED UPON DETECTABLE MEASUREMENTS ONLY~
FRACTION OF DETECTABLE HEASUR MENTS AT SPECIFIED LOCATIONS IS INOICATcD IN PARENTHESES (F) ~
TABLE 22 RAOIOACTIVITY IN TOHATOES PCI/KG - 0~037 BO/KG (NET <<EIGHT)
NAHE OF FACILITY fgQllg> ffgfI LOCATION OF FACILITY l,jgf$IQgf Sl.kf855 DOCKET NO ~ 19=?22c?6Qc225 REPORTING PERIOD 1$ fjg TYPE ANO TOTAL NUMBER
)F ANALYSIS PERFORMED ROSS BETA 2
AHHA (GE LI) 2 K-40 BI-21 4 PB-214 LONER LIMIT OF DETECTION (LLD) hff UQIE 1 25.00 NOT ESTAB NOT ESTAB NOT ESTAB 21 03 ~ 35 (
2103 ~ 35 "
6.31(
6.31 2'0(
2'0 1/
1) 2103.35 1/
1) 6 ~ 31 1/
1) 2'0 ALL INDICATOR LOCATIONS MEAN (F)
RANGc ff BQIE 2
4228 '7(
1/
1) 4228 87 "
4228.87 7 HILES NNN 7 MILES NNN 7 HILES NNN 2103.35(
2103.35 6.31(
6 ~ 31 2 20(
'2 ~ 20 1/
1) 2103m 35 1/
1)

6. 31 1/

1) 2.20 l.QCBIIQB hIIU tlIGUESI BHHQBL BEAU NAHE HEAN (F)
DISTANCE ANO OIRcCTION RANGE Rff 5Q:f 2
7 MILES NNM 4228 ~ 87(
1/
1) 4228.87 -
4228.87 2103'9 (
2103.69 8.97(
8 ~ 97'-
3 ~ 10(
3 ~ 10 1/
1) 2103.69 1/
1) 8'7 1/
1) 3o10 CONTROL LOCATIONS HcAN (F)
RANGE off BQIE 2
3786.61(
1/
. 1) 3786.61 -
3786.61 NUMBER OF NONROUTINE REPORTED MEASUREMENTS NOTE:
1 ~
NOHINAL LONER LIMIT OF DETECTION (LLD)
AS DESCRIBED IN TABLE 3 ~
NOTE:
2 ~
MEAN AND RANGE BASED UPON DETECTABLE MEASUREMENTS ONLY~
FRACTION OF 0
TECTABLE HEASUREHENTS AT S> CIFIED LOCATIONS IS INDICATED IN PARENTHcSES (F) ~
Figure 6
0 1J o
'O rr o
JJ C0 'Po IJ 4J C 0 tlJ ~
CO COC0 rr rl CA 4J Ch oIJ ev0 V
'44l
'P C pQ Preoperational Phase Operational Phase ANNIALAVERAGE 6ROSS 8ElA kTIVIIY IN HRI N<1% MATER SUPPLIES BOWN FERRY NuCLEAR fLANT Average:
Preooerational phase 1
.WiI 11 I
g1:i I'9 8
19 9
19 0 1
1 19 2
19 3P 19 30 19 4 1
5 19 6 1
7
,19 8 19 9 19 0 1 81 82 1 83 1
4 198'
40 24.
Fl ure 7
Direot Radiation Levele Browne For ry Nuolear Plant
+h
<to D OFFono 20.
1976 1977 1978 1979 1980.
1981 1982.
1983.
1984 1985.
1986.
24.
22.
Figure 8 Direot Radiation Levele Browne Ferry Nyolear Plant 4-Quarter Moving hverago
+
Onomato D OFFoce 14.
12.
1976.
1977.
1978.
1979.
1980.
1981.
1982.
1983.
1984.
1985.
1986.
26.
24.
22.
FlguFe 9 Direot Radiation Levels Watts Bar Nuolear Plant Onelto p OFFeite bl 16 14.
12 1976.
1977 1978 1979 1988 1981 1982 1983 1984 1985 1986.
26.
Figure l0 24.
22.
,Direot Radiation Levele Watte Bar Nuolear Plant 4-Quarter Moving Average Oneite p OFFeite 16.
14.
12 1976.
1977.
1978 1979 1980 1981.
1982 1983-1984.
1985.
1986.
43 Reservoir Monitorin Samples are collected from various Tennessee River cross sections as detailed in table 23.
Samples collected for radiological analysis include water and 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 gross beta and gamma-emitting radionuclides.
Further P
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 24.
Figure 12 presents a plot of the gross beta activity in surface water from 1968 through 1985.
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 reservoirs--Wilson,

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'he 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 25, 26, and 27.
Sediment Sediment samples are collected semiannually from Ponar dredge hauls made for bottom fauna.
Gamma radioactivity and Sr and Sr content are determined in composite samples collected from each of four stations.~
Locations of these stations are shown in table 23.
Results are shown in
'table 28.
Plankton Net plankton (all phytoplankton and zooplankton caught wit'.h a l00 4 mesh net) is collected for radiological analyses at each of three stations by vertical tows with a l/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 analvsis, and when quantities are sufficient for 89 7
gamma activity and Sr and 9 Sr content.
During this reporting period, samples collected during the first half of the year contained insufficient volume for any analysis.
During the second half of the year, sufficient quantities of plankton were collected for only one gross beta analysis.
Results are presented in table 29.
Bottom Fauna The flesh and shells of Asiatic clams collected semiannually from the cross sections at fonr stations ]table 23) are analyzed for gamm'a-emitting radionuclides.
Levels of 9Sr 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.
Results are given in tables 30 and 31 'lams from one location were not available; and from two locations, insufficient quantities were collected to permit analysis of clam flesh.
Table 23 SAMPLING SCHEDULE - RESERVOIR MONITORING Biolo ical sam les (collected semiannuall
)
Zooplankton, chlorophyll, River/river mile phytoplankton Benthic fauna Water Samples Sediment Fish (collected monthly)
Tennessee 277.9 Tennessee 285.2 Tennessee 288 '
Tennessee 291.7 Tennessee 293.5 X
X K,
Tennessee 293.7 (discharge area)
X Tennessee 305.0 (Control)
Tennessee 307.5 (Control)
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 24-RADIOACTIVITY IN SURFACE WATER TOTAL PCI/L - 0 ~ 037 BO/L NAME OF FACILITY EB9855 EEBBI DOCKET NO ~ >9=252A259c22(t LOCATION OF FACILITY LISEEIQUE------------hLh98L----"--"
TYPE AND TOTAL NUMBER OF ANALYSIS PERFORMED

ROSS ALPHA 1

(ROSS BFTA 65 iAMHA (GELI) 65 LOWER L IH IT pc DETECTION (l.LD)
BEE 89IE 1
F 00 Ze00 ALL INDICATOR LOCATIONS MEAN (F)
RANGE SEE UQIE 2
0 VALUES <LLD AtlALYSIS PERFORHED 3 ~ 13(
35/
39) 2 ~ 13 -
4o37 TRH 293 '
3.27(
12/
13) 2'7 -
4.31 L994II98 hIIU-UIQUEKI 6859hL 5E65 NAHc HEAN (F)
DISTANCE AND DIRECTION RAtlGE GEE UNTIE 2 CONTROL LOCATIONS MEAN (F)
RANGE 5EE NQIE 2
1 VALUES <LLO F 24(
22/
26) 2 07 -
5o49 NUMBER OF NONROUTINE REPORTED PlEASUREHENTS K 40 BI"214 PB-214 PB-212 AC-228 iR 89 iR 90 tRITIUM 20 20 20 NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB 15 F 00 10 F 00 F 00 330 F 00 11 ~ 52 (
1/
39) 11e52 -
11.52 7.02(
11/
39) 0.34 -
23.29 F 08(
6/
39) 0.'78 -
6'0 1 '4(
6/
39) 0'2 -
3'7 39 VALUcS <LLD 12 VALUES <LLD ANALYSIS PERFORMED 12 VAl.UES <LLD ANALYSIS PERFORMED 334 '1(
1/
12) 334.51 -
554 ~ 51 TRH 293.7 BF tl DISCHARGE TRM 285 '
TRH 293 '
BFN DISCHARGE TRH 285 '
TRH 285 '
11.52(
11 '2 9.47(
0'4 4 66(
2 07 3 47(
5.47 1/
13) 11 52 5/
13) 22'3 3/
13)

6. 30 1/

13) 5 ~ 47 334 51(
1/
4) 354.51 -
554 ~ 51 27.D4(
20.68 10.56(
0 13 7 29(
De47-1 57(
0'9 27.49(
27e49 8
VALUE 3/
26) 39.53 17/
26) 44 F 09 15/
26) 18 90 10/
26) 3 ~ 11 1/
26) 27.49 S
<LLO 333 48(
333 ~ 48 1/
8) 333.48 8
VALUES <LLO NOTE:
1 ~
NOMINAL LO'WER LIHIT OF DETECTION (LLD) AS DESCRIBcD IN TABLE 3 ~
NOTE 2 ~
HEAN AND RANGE BASED UPON DETECTABLE HEASUREHENTS ONLY ~
FRACTION OF DETECTABLE MEASUREMENTS AT SP CIFIED LOCATIONS IS INDICATED IN PARENTHcSES (F) ~
TABLE 25 RAOIOACTIVITY IN WHITE CRAPPIE (FLESH)
PCI/G - 0 ~ 037 BO/G (ORY WEIGHT)
HAKE OF FACILITY EEQHUR EEHBZ LOCATION OF FACILITY LIUESIQUE hLSEMB OOCKET NO ~ 2Q=252c2(tQc225 REPORTING PERIOO TYPE AHO TOTAl. NUHSER OF ANALYSIS PERFORHEO GROSS BcTA 6
GAHHA (GELI) 6 CS-137 K-40 BI-214 PB 214 PB-212 LOWER LIHIT OF OETECTION (LLO)
SEE UQIE 1
0 ~ 10 0.02 HOT ESTAB 0'2 NOT ESTAB NOT ESTAS 0.08(
0'6 14 F 03(
10'1 4
VALUES 0 ~ 02(
0,02 0 F00(
0 ~ OG-4/
4) 0'1 4/
4) 16 '1
<LLO 1/
4) 0.02 1/
4) 0 F00 ALL INOICATOR LOCATIONS HEAN (F)
RANGE SEE UQIE 2
32 66(
4/
4) 27.58 -
37.75 WILSON RESERVOIR TRH 259-275'ILSON RESERVOIR TRH 259-275 0 09(
2/
0 F 07 -
0,11 14~25(
2/
2) 13'8 -
14'2 WHEELER RCS TRH 275-549 WHEELER RcS TRH 275-349 0'2(
1/
2) 0.02 -
0.02 0 00(
1/
2) 0.00 -
0 00 I QtihIIQU liIIU UIQUEGI 8UUMhl UEhU
'h AHE HEAN (c)
OISTANCE ANO OIRECTION RANGE SEE UQIE 2
32'7(
2/
2) 27.58 -
37.75 Oe09(
Os09 15 ~ 15(
14 ~ 59 0 ~ 02(
0 F 02 0 01(
0.01 2
VALUES 2/
2) 0 ~ 10 2/
2) 15 ~ 71 1/
2) 0 02 1/
2) 0 ~ 01
<LLO CONTROL LOCATIONS HEAK (F)
RANGE'EE UQIE 2
29.20(
2/
2) 28'7
29o75 HUHBCR OF NONROUTINE REPORTEO HEASURcHENTS NOTE:
1, H'OHIHAL LOWER LIHIT OF OETECTION (LLO)
AS OESCRISEO IN TASLE 3.
2 ~
HEAN ANO RANGE BASED UPON OETECTABLE HEASUREHENTS ONLY~
FRACTION OF OETECTABLE HEASUREHENTS AT SPECIFIEO LOCATIONS IS INOICATco IN PARENTHESES (F) ~
TABLE 26 RADIOACTIVITYIN SHALLHOUTH BUFFALO (FLESH)
PCI/G - 0 037 SQ/G (DRY WEIGHT)
NAME OF FACILITY gllQguggfggI LOCATION OF FACILITY gjgfQTQllf DOC<ET NO ~ 20=222c20Qc220 REPORTING PERIOD TYPE AND TOTAL NUMBER OF ANALYSIS PERFORHED GROSS SETA 6
SAMHA (GELI) 6 CS-137 K-40 SI-214 PB-214 PB-212 SR 89 SR 90 LOWER LIHIT OF DETECTION (LLD)
Rff HQIE 1 0 ~ 10 0'2 NOT ESTAB 0 ~ 02 NOT ESTAB NOT ESTAB 0'0 0 ~ 10 ALL INDICATOR LOCATIONS MEAN (F)
RANGE BEE 5QIE 2
19 33(
4/
4) 16'2 -
20'8 Oa03(
2/
4) 0'3 -
0 03 9 95(
4/
4) 8.65 -
11 90 4
VALUES <LLD 0 ~04(
1/
4) 0'4 -
0 04 0 00(
2/
4) 000-001 2
VALUES <LLO ANALYSIS PERFORHED VALUES <LLO ANALYSIS PERFORHED WILSON RESERVOIR TRM 259-275 WHEELER RES TRH 275-349 0 ~ 03(
1/
2) 0.03 -
0'3 10'4(
2/
2) 9.37 11.90 WILSON RCSERVOIR TRH 259-275 WHEELER RES TRH 275-649 004 (
1/
2) 0.04 -
0 ~ 04 0'1(
1/
2) 0'1
0.01 l QQIIIQB dIIB UIQUESI BUUllhL BEST NAHE MEAN (F)
DISTANCE AND DIRECTION RANGE Sff 5QIE 2
WHEELER RES 20 ~ 16(
2/
2)
TRH 275-349 20+07 -
20'5

CONTROL, LOCATIONS HEAN (F)

RANGE Kff HQIE 2
20'6(
2/
2) 18'9 "
21 '2 0+03(
1/
2) 0 ~ 03 -
0 F 03 9.20(
2/
2) 7 49 -
1oe90 0 F 07(
2/
2) 0.04 -
0.10 0 06(
2/
2) 0.04 "
0.08 0 F 00(
1/
2) o.oc -
o oo 0 VALUES <LLD 0 VALUES <LLO NUHBER OF NON ROUTINE REPORTED HEASURCMENTS NOTE:
NOTE:
1 ~
NOMINAL LOWER LIMIT OF DETECTION (LLD)
AS DESCRIBED IN TABLE 3 ~
2 ~
MEAN ANO RANGE BASED UPON DETECTABLE MEASUREMENTS ONI Y ~
FRACTION OF DETECTABLE MEASUREMENTS AT SPECIPIEO LOCAT TONS IS INDICATED IN PARENTHESES (F) ~
TABLE 27 RAOIOACTIVITY IN SHALLMOUTH BUFFALO (rrHOLE)
PCI/G 0 ~ 037 BQ/G (ORY MEIGHT)
NAME OF FACILITY EllQllllE EEEBZ LOCATION OF FACILITY l,jl)EJIQUE 8! Bl!Br58 OOCKET NO ~
5Q=222c2BQA22B REPORTING. r ERIOO 12!i>
TYPE ANO TOTAL NUHBER OF ANALYSIS PERFORHCO GROSS BETA 5
GAMMA (GcLI) 6 CS-137 K-40 BI-214 PB-214 PB-212 LONER LIMIT OF 0 ET ECT ION (LLO) 5

r. 5QIG 1

0 ~ 10

0. 02 NOT cSTAB 0'2 NOT ESTAB NOT ESTAB 0 ~ 03(

0'2 7 F 08(
6'5 0.04(
0'4 0'3(
0'1 0'1(
0 F 00 2/
4) 0.03 4/
4) 8 F 00 1/
4) 0.04 4/
4) 0'4 3/
4) 0'1 ALL INOICATOR LOCATIONS HEAN (F )
RANGE iff UQIE 2
17'9(
4/
4) 14+48 -
20.02 MHEELER RES TRH 275-349 NILSON RESERVOIR TRH 259-275 rrHEELER RES TRH 275-349 rrHEELER RES TRM '275-34'9
'HHEELER RES TRH 275-349 WILSON RESERVOIR TRH 259-275 0 F 05(
0'2 7'9(
6'7 0.04(
0.04 0 F 03(
0'3 0'1(
0'1 2/
2) 0 03 2/
2) 8 00 1/
2) 0+04 2/
2) 0.04 1/.
2) 0 01 l QGBI?QU lrIIU UIQtlfKI BHUQBt. tlfBh NAHE MEAN (F)
OISTANCE ANO OIRECTION RANGE SEE VQIE 2 17'S(
2/
2) 1'7 35 -
18 52 2
VALUES <LLO 11 '4(
7 ~ 37-0~04(
0+04-2 VALUES 2/
2) 14 70 1/
2) 0'4
<LLO 2 VALUES <LLO CONTROL NUHBER OF LOCATIONS NONROUT INE HEAN (F)
REPORTEO RArrGE HcASUREHENTS SEE lrQIE 2 19'9(
2/
2) 17.54 -
21.64 NOTc-1 ~
NOMINAL LOrrER LIHIT OF OETECTION (LLO)
AS OcSCRIBEO IN TABLE 3 ~
NOTE.
2 ~
HEAN ANO RANGE BASEO UPON DETECTABLE HEASUREMENTS ONLY~
FRACTION OF OETECTABLE MEASUREHENTS AT SPECIFICO LOCATIONS IS INOICATEO IN PARENTHESCS (F) ~
TABLE 28 RADIOACTIVITY IN SEDIMENT PCI/G - 0 ~ 03?
BQ/G (DRY HEIGHT)
NAME OF FACILITY QBQBUet EEBBI LOCATION OF FACILITY l.IHEGIQHE-- -
BLJlQMdl-DOCKET NO eJQ"252C26QC226-REPORTING PERIOD gggeJ TYPE AND TOTAL NUHBER OF ANALYSIS PERFORHEO r AMMA (GELI) 14 CO"60 CS-134 CS-13?
K-40 ZN-65 BI-214 BI-21 2 PB-214 PB"212 RA-226 RA-224 BE 7
TL-208 AC-228 PA 234M SR 89 SR 90 LOJJER LIMIT OF OET ECTION (LLD)
REf HQZE 2
0 ~ 01 Oe08 0.02 NOT ESTAB 0'2 0'2 0 ~ 10 NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB 0'2 0 ~ 06 NOT ESTAB 1 '0 0 ~ 15 ALL INDICATOR LOCATIONS HEAN (F)
RANGE BEE UQIR 2
0 15(
9/
10) 0'2 -
0'3 0'1(
5/
10) 0 F 08 -
0'8 0.79(
10/
10) 0 F 04 -
1 '7 13'5(
10/
10) 7.92 -
16e?2 0'4(
2/
10)
Oe02 "
Oe07 1 '2(
10/
10) 0'6 1 '1 1 '9(
10/
10) 0'8 -
1 '7 1 '2(
10/
10) 0'0 "
1 '9 1.44(
10/
10) 0 43 -
1 '6 1 '2(
6/
10) 0.36 -
1.34 1 '0(
5/
10)
. 0.35 -
1.86 0 ~ 18(
2/
10) 0.16 -
Oe20 0'0(
10/
10) 0'5 -
Oed8 1 '4(
10/
10) 0'4 -
2'2 2'4(
2/
10) 2.18 -
2'1 6
VALUES <LLO ANALYSIS PCRFORMEO 0'5(
4/
6) 0'8 -
0'5 TRM 293 '
BFN DISCHARGE TRM 293 '
BFN DISCHARGE TRH 288'8 TRM 288'8 TRM 293 '
BFN DISCHARGE TRH 288 '8 TRM 28S.O TRM 25'8 TRM 288'8 TRH 28' TRM 285 '
TRH 292e7 TRH 288'8 TRH 288'8 TRH 291
~ 76 0 ~ 21(
0.17 0 12(
0 F 08 1 ~ 08(
0 ~ 59 16e23(
15'3 0'7(
0 F 07 1 '1(
1 '9 1 ~ 59(
1 '9 1 '6(
1 '3 1.75(
1'0 1.34(
1 e34 1 86(
1 '6 0'0(
0'0 0'5(
0'3 1 79(
1 '7 2'1(
2 ~ 91.
3/
3/
3)
Oe23 3) 0 ~ 18 2/
2) 1 ~ 27 2/
2) 16.72 1/
3) 2/
1/
2/
2/
1/
1/
1/
2/
2/
1/
0 0?
2) 1e82 1) 1.'39 2) 1e99 2) 1 ~ 96 1) 1'4 1)
F 86 1) 0'0 2)
Oe6S 2) 1e91 1) 2 ~ 91 TRH 277'b 0 ~ 41(
0.36 2)
Oe 45 LQQBI?QU llIIU UIQllESI ht/U!lhl. UESU NAHE HEAN (F)
DISTANCE ANO DIRECTION RANGE li'ee,e e
CONTROL LOCATIONS MEAN (F)
RANGE KEf. 5QIE 2
4/
4) 0.51 4/
4) 13'9
<LLO 0 ~ 30(
0 ~ 1 7 13 ~ 00(
11.76 4
VALUES 1 12(
0.98 1 '5(
1.05 1 19(
1 ~ 01 1 2?(
1 ~ 1?
1 09(
0'5 1.50(
1.48 Oe 27.(
0 17 0'4(
0'2 1 ~ 32(
1 ~ 15 4.27(
3'6 2
VALUES 4/
4) 1'2 4/
4)

1. 4?

4/
4) 1 ~ 40 4/
4) 1 '6 3/
4) 1 22 2/
4) 1 51 3/
4) 0 46 4/
4) 0.47 4/
4) 1 ~ 41 2/
4) 4*~ 87
<LLO 0.34(
0.34-1/
2) 0.34 0.03(
2/
4) 0.02 -
0.03 4
VALUES <LLD NUMBER OF NONROUTINE REPORTED HEASUREHENTS NOTE:
1 NOHINAL LOlfER LIt'.IT OF DETECTION (LLO). AS DESCRIBED IN TABLE 3 ~
NOTE:
2 ~
HEAN AND RANGE BASED UPON DETECTABLE MEASUREHENTS ONLY ~
FRACTION OF -DETECTABLE HEASUREHEtJTS AT SPECIFIEO LOCATIONS IS INDICATED IN PARENTHESES (F) ~
NAHE OF FACILITY QUQUU$ Efgpg LOCATION OF FACILITY LJUE/IQUE TABLE 29 RADIOACTIVITY IN PLANKTON (SAHPLE 1)
PCI/G - 0 ~ 037 BQ/G (DRY HEIGHT)
DOCKET NO ~ 29=212c20Qc225 REPORTING PERIOD 1Pgg TYPE AND TOTAL NUHBER OF ANALYSIS PERFORMED GROSS BETA 1
LOIIER LIMIT OF DETECTION (LLD) off UQIE 1 NOT ESTAB ALL INDICATOR LOCATIONS HE'AN (F)
RANGE Xff UQIf 2 SEE LQfiBIIQU UIIU UIQUEGI BUUQBL UEBU NAHE HEAN (F)
DISTANCE ANO DIRECTION RANGE off UQIE 2
NOTE 3 CONTROL LOCATIONS MEAN (F)
RANGE Kff UQIE 2
34 71(
1/
1) 34'1 -
34'1 NUHBER OF NONROUT INE REPORTCD MEASUREMENTS NOTE:
1 ~
NOHINAL LONER LIHIT OF DETECTION (LLD) AS DESCRIBED IN TABLE b ~
NOTE 2 ~
HEAN ANO RANGE BASED UPON DETECTABLE HEASUREHENTS ONLY~
FRACTION OF DETECTABLE MEASURE.iENTS AT SP CIFIEO LOCATIONS IS INOICATEO IN PARENTHEScS (F) ~
NOTE:
3.
Insufficient sample available for analysis.
TYPE AND TOTAL NUHBER OF ANALYSIS PERFORMED LONER LIHIT ALL OF INDICATOR LOCATIONS DETECTION MEAN (F)
(LLO)
RANGE 5EE BQIf 1
$ff UQIE 2 NAME OF FACILITY QgQggg fpagI LOCATION OF FACILZTY L,IgggIQgj TABLE 30 RADIOACTIVITY IN CLAH FLESH PCI/G - 0 ~ 037 80/G (ORY WEIGHT) aiaa8~8 DOCi(ET NO ~
RQ=Z22c26Qc22D REPORTING PERIOD gggf CONTROl.
LOCATIONS HEAN (F)
'RANGE SfE UQIS 2
LQQ&IIQ8 hIIU UIQUEKI hllUQBI UEEU NAHE HEAN (F)
DISTANCE AND DIRECTION RANGE Gf c gQIh 2
NURSER OF NONROUTINE REPORTED MEASUREMENT
)AHHA (GELI) 12 CO-60 z-40 ZN-65 BI-214 PB-214 PB-212 TL-208 AC-228 0'8 NOT ESTAB 0 ~ 17 NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB NOT. ESTAB 0.16 (
016-F 00(
0'9 1 '9(
0.64-2'0(
0 ~33-2'1(
0 ~30-Oo10(
0 04 0 ~03(
0'2 0 16(
0 15-1/
8) 0 ~ 16 5/
8) 12 F 43 4/
8) 1 ~ 81 8/
8) 7'2 8/
8) 6'6 5/
8) 0'1 3/
8) 0 F 05 2/
8) 0 17 TRH 293 '
BFN DISCHARGE TRH 288 '8 TRH 293 '
BFN DISCHARGE TRM 288 '8 TRM 277'8 TRM 277'8 TRH 291.76 TRM 293 '
BFN DISCHARGE 0.16(
0.16 12 43(
12'3 1 53(
1 '4 4 90(
.4 ~ 90 2 96(
2'6 0 21(
0 21 0.05(
0'5 0.16(
0 15 1/
1/
2/
1/
1/
1/
1'/
2/
3) 0 ~ 16 1) 12'3 3) 1 ~ 81 1) 4'0 1) 2 ~ 96 1) 0 21 1) 0 05 3) 0 ~ 17 4
VALUES <LLD 1.45(
0 2~-
1 ~ 40(
0 ~ 12 0 ~ 20(
0 ~ 11 0'2(
0 ~02-0 ~ 14(
0 ~ 14 4/
4) 4'6 4/
4) 4 ~ 98.
3/
4) 0'5 1/
4) 0 02 1/
4) 0 14 2'2(
4/
4) 0.90 -
5.49 4
VALUES <LLO 1
(Note 3)
NOTE:
NOTE:
NOTE:
1 ~
NOMINAL LOMER LIHZT OF DETECTION (LLD) AS DESCRIBED IN TABLE 3 ~
2 ~
HEAN AND RANGE BASED UPON DETECTABLE HEASUREMENTS ONLY~
FRACTION OF DETECTABLE MEASUREM NTS AT SPECIFIED LOCATIONS IS INOICATEO IN PARENTHESES (F) ~
3.
Zinc-65 in clam flesh reported to the Nuclear Regulatory Commission on, June 25, 1985.
Samples collected in November contained no evidence of fission or activation products.
NAME OF FACILITY QBQ855 EREBUS LOCATION OF FaCILITY I~IIEKIQBE TABLE 31 RADIOACTIVITY IN CLAH SMELL PCI/G - 0 ~ 037 BQ/G (DRY WEIGHT) 8LBQBlh DOCKET NO ~ 09=222cgkQc225 REPORTING PERIOD TYPE ANO TOTAL NUMBER OF ANALYSIS PERFORHEO GAMMA (GELI) 12 CO-CIO K-40 BI-214 BI-212 PB-214 PB-212 Ra-226 TL-208 AC-228 SR 89 SR 90 0'1 NOT ESTAB 0 F 05 Oe10 0 F 05 NOT STAB 0 F 05 0.02 0'6

5. 00 F 00 001 (

1/
8) 0.01 -
0.01 0 13(
6/
3)-
0 01 -
0'9 0'6(
6/
8) 0'9 -
0'8 0'2(
1/
8) 0'2 -
0'2 0 17(
7/
8) 0 ~ 0? -
0'4 0'6(
8/
8) 001 -
016 0 ~ 11(
2/
8) 0 ~ 10 -
0.12 0 ~ 05(
3/
8) 0.02 -
0 ~ 08 0 ~ 20(
7/
8) 0'7 -
0'0 4
VALUES <LLD ANALYSIS PERFORHEO F 09(
1/
4) 1.09 -
1.09 LONER LIMIT ALL OF INDICATOR LOCATIONS DETECTION HEAN (F)
(LLD)
RANGE GEE UQI 1
SEE UQIE 2
TRH 293.7 BFN DISCHARGE TRH 277 '8 TRM 288 '8 TRM 292 '
TRH 288 '8 TRM 288'8 TRH 293.7 BFN DISCHARGE TRH 288.78 TRM 258'8 0 01(
0 ~ 01 0 ~ 22(
Oe 22 0.25(
0 ~ 25 0.12(
0 ~ 12 0'7(
0 ~ Z7 0 ~ 16(
0 ~ 16 0 ~ 12(
0 ~ 12 0.08(
0 ~ DB 0+40(
0'0 1/
3) 0'1 1/
1) 0 F 22 1/
1) 0 ~ 25 1/
1) 0 ~ 12 1/
1) 0 ~ 27 1/
1) 0 ~ 16 1/
3) 0'2 1/
1)
O.oe 1/
1) 0.40 4
VALUES <LLO 0 ~ 14(
0'9 0.19 (
0'9 4
VALUES 0.17(
0'9 0 ~ OZ(
0'1 VALUES 2/
4) 0'0 3/
4) 0.35
<LLO 3/
4) 0.32 3/
4) 0.04
<LLO 4
VALUES <LLO 0 13(
3/
4) 0'1 -
Oo14 2
VALUES <LLD TRH 293 '
BFN DISCHARGE 1 09(
1/
2) 1 ~ 09 -
1 ~ 09 1.02(
1 ~ 02 1/
2) 1.02 CONTROL I.QQ8IIQH hIXU UTQUENI 85HQBL UfaU LocaTIo~s NAME MEAN (F)
MEAN (F)
DISTANCE tND DIRECTION RANGE RANGE SEE 5QIZ
?
ICE HQIi 2 i
NUHBER OF NONROUTINE REPORTED MEASUREMENTS NOTE:
1 ~
NOMINAL LOw R l.IHIT OF DETECTION (LLO)
AS OESCRISEO IN TABLE 3 ~
NOTE 2 ~
MEAN AND RANGE BASED UPON DETECTABLE HEASUREilENT5 ONLY ~
FRACTION OF DETECTABLE MEASUREHENTS AT SPECIFIED LOCATIONS IS INOICATEO IN PARENTHESES (F) ~
.g4 Figure 11 R ESERVOIR MONITORING NETWORK Elk River N
WHEELER DAM mile 274.90 rnite 277.98 Rogersville 0
mite 282.6 mite 29).76 Athens 0
~mile 285.2 B.F. NUCLEAR PLANT S
Champion Paper Co.
0 Cour tland ite 28878 rnite 293.50 mile 293.70 0
Decatur mile 305.0 mite'307.52 Automatic Sam ter Scale of Miles 0
Figure 12 mn0 4l o 4l lJ CA CIJ Ls CC oIJ 0 o Jl C
C 0 w V Preoperational Phase Operational Phase ANMNL AVERAGE 6ROSS HETA ACTIVITY IN SURFACE )IATER 1hOWS FERRV i%CLEAR Pusan Average:
Preoperational Phase 1968 1969 1970 1971 1972 1973P 19730 1974 1975 1976 1977 1 78 1979 1980 1
1 19 2
19 19 4
a.
No gross beta measurements made in 1978.
57 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 Anal sis The results from each sample are compared with the concentra-tions from the corresponding control stations and appropriate preopera-tional and background data to determine influences from the plant.
During this report period, concentrations in two samples were found to exceed the reporting levels as outlined in the plant Environmental Technical Specifications.
Cobalt-60 was identified in one vegetation sample collected near the site boundary in April.
No indication of the presence of.
cobalt-60 was observed either at the control stations or at any of the other stations around the plants.
Subsequent samples showed no indication of the presence of cobalt-60.
This single, isolated occurrence, the absence of other fission and activation products in
'the sample, and the lack of an increase in cobalt-60 releases from the plant prevented an identification of the causes for the presence of the isotope in the sample.
In May 1985, zinc-65 was identified in one sample of clam flesh taken from the Tennessee River approximately one-half mile downstream from the plant discharge.
No fission or activation products had been identified in this medium during the previous report period.
Followup samples collected in June revealed zinc-65 at these downstream

stations, with highest value being about two-thirds and the other values about one-third of the concentration reported in May.

No fission or activation products were found in clam flesh samples collected in the November sample period.
The exposure to an individual consuming clam with the highest activity was calculated to be less than 0.01 mRem/year, or 0.03 percent of the annual exposure limit.
However, to the best of our knowledge clams from the Tennessee River are not harvested for human consumption, therefore, even this small exposure is unlikely to take place.
Dose estimates were made from concentrations of radioactivity found in samples of environmental media.
Media sampled include, but are not limited to, air, milk, food products, drinking water, and fish.
Inhalation and ingestion doses estimated for persons at the indicator locations were essentially identical to those determined for persons at control locations.
Greater than 95 percent of those doses were contributed by the naturally occurring radionuclide potassium-40, and by strontium-90 and cesium-137 which are long-lived radioisotopes found in fallout from nuclear weapons testing.
Conclusions It is concluded from the above analysis of the data and from the trend plots presented earlier that there were no measurable increases in the exposure to members of the general public attributable to the operation of BFN.
Indications of the presence of small quantities of fission and activation products have been

seen, especially in aquatic media.

Although the levels reported sometimes exceed the values reported at the corresponding control stations, they are similar to levels reported in samples collected in conjunction with preoperational monitoring programs being conducted by TVA at nuclear plant construction sites upstream from Browns Perry.
, The radioactivity reported herein may be the result of fallout, fluctuations in the existing environment, or computer program artifacts, and may include small contributions from plant operations.
Any activity resulting from plant operations which may be present is generally difficult to distinguish from background.

ML18029A462

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Dear Dr. Grace:

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ML18029A462

Text

SUBJECT:

Dear Mr. Cunningham:

Dear Dr. Grace:

Enclosure:

Dear Dr. Grace:

Enclosure:

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