ML18031B314

Environ Radioactivity Levels Browns Ferry Nuclear Plant Annual Rept 1986

ML18031B314
Person / Time
Site:	Browns Ferry
Issue date:	12/31/1986
From:	Gridley R TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8705180252
Download: ML18031B314 (64)

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REGULATORY Ih, NATION DISTRIBUTION SYSTEM (R IDS>

ACCESSION NBR: 8705180252 DOC. DATE: 86/12/31 NOTARIZED:

NO FACIL: 50-259 Brogans Ferry Nucleav Pouev Station>

Unit 1>

Tennessee 50-260 Brogans Fevrg Nucleav'over Station>

Unit 2>

Tennessee 50-296 Brogans Fev rg Nuclear Pouer S+ation>

Unit 3.

Tennessee AUTH. NAME AUTHOR AFFILIATION GRIDLEY> R.

Tennessee Valley Au+hov itM REC IP. NANE RECIPIENT AFFILIATION DOCKET 05000259 0 5000260 05000296 SUB JECT:

"Environ Radioactivitg Levels Bv otons Ferry Nucleav'lan+

Annual Rept 1986. " M/870508 ltr.

DISTRIBUTIDN CODE:

IEBBD CDPIES RECEIVED: LTR I

ENCL g SIZE:

TITLE: Environmental Monitoring Rep+

(per Tech Specs)

NOTES: Zeolinski 5 cg.

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05000259 05000260 05000296 INTERNAL RECIPIENT ID CODE/NANE JAMERSON, C QEARS> G ACRS AEOD/DSP/TPAB NRR/DEST/ADE REQ FTl

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LT1R 35 ENCL 34

TENNESSEE VALLEYAUTHORlTY CHATTANOOGA. TENNESSEE 37401 5N 157B Lookout Place MAY 08 t987 U.S. Nuclear Regulatory Commission ATTN:

Document Control Desk Washington, D.C.

20555 Gentlemen:

In the Matter of Tennessee Valley Authority Docket Nos, 50-259 50-260 50-296 BROWNS FERRY NUCLEAR PLANT (BFN) UNITS 1, 2, AND 3 ENVIRONMENTAL RADIOACTIVITYLEVELS ANNUAL REPORT 1986 Enclosed is TVA's Environmental Radioactivity Levels Annual Report.

This report is submitted pursuant to the requirements of BFN Technical Specifications Appendix B, Section 5.6.2.b.l.

In an April 30,

1987, telephone conversation with the NRC TVA Projects

Manager, a week's delay in the submission of this report was considered acceptable.

Please refer any questions or comments to M. J.

May, BFN Site Licensing, (205) 729-3566.

Very truly yours, TENNESSEE VALLEY AUTHORITY R.

ridley, rector Nuclear Safe y and Licensing Enclosure cc:

See page 2

An Bove: Ooportunity Fn1otoye;

U.S. Nuclear Regulatory Commission MAY 08 1987 cc (Enclosure):

Mr. J. A. Zwolinski, Assistant Director For Projects Division of TVA Projects Office of Special Projects U.S. Nuclear Regulatory Commission 4350 East West Highway EWW 332

Bethesda, Maryland 20814 Mr. G.

G. Zech, Assistant Director

. Regional Inspections Division of TVA Projects Office of Special Projects U,S. Nuclear Regulatory Commission Region II 101 Marietta St.,

NW, Suite 2900 Atlanta, Georgia 30323 Browns Ferry Resident Inspector Browns Ferry Nuclear Plant P.O.

Box 311

Athens, Alabama 35611

TENNESSEE VALLEY AUTHORITY ENVIRONMENTAL RADIOACTIVITYLEVELS BROWNS FERRY NUCLEAR PLANT ANNUAL REPORT-1986 RADIOLOGICAL CONTROL 8705180252 861231 PDR ADOCK 05000259 R

PDR

ENVIRONMENTAL RADIOACTIVITY LEVELS BROHNS FERRY NUCLEAR PLANT ANNUAL REPORT 1986 TVA/NUC SVCS/RC Apt 11 1986

CONTENTS List of Tables List of Figures Introduction Atmospheric Monitoring Terrestrial Monitoring Reservoir Monitoring Quality Control Data Analysis Conclusions iii iv

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LIST OF TABLES Table Tabl e Table Tabl,e Table Table 6-Table 7-Table 8

Table 9-Table 10 Table 11 Table 12-Table 13-Table 14-Table 15-Table 16-Table 17-Table 18-Table 19-Table 20-Table 21-Table 22 Table 23-Table 24-Table 25-Table 26 Table 27 Table 28-Table 29-Table 30 Table 31-Environmental Radioactivity Sampling Schedule Atmospheric and Terrestrial Monitoring Station Loca'tions 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

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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 Hater 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 34 35 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 18 Figure 3 - Local Monitoring Stations

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19 Figure 4 TLD Locations, Browns Ferry Nuclear Plant 20 Figure Figure 5 - Annual Average Gross Beta Activity in Air Filters, Browns Ferry Nuclear Plant

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21 6 - Annual Average Gross Beta Activity in Drinking Water, Browns Ferry Nuclear Plant 39 Figure 7 - Direct Radiation Levels, Browns Ferry Nuclear Plant 40 Figure 8 - Direct Radiation Levels, Browns Ferry Nuclear Plant (4-Quarter Moving Average) 40 Figure 9 - Direct Radiation Levels, Watts Bar Nuclear Plant 41 Figure 10 - Direct Radiation Levels, Watts Bar Nuclear Plant (4-Quarter Moving Average>

41 Figure 11 - Reservoir Monitoring Network 54 Figure 12 Annual Average Gross Beta Activity in Surface Water 55

ENVIRONMENTAL RADIOACTIVITY LEVELS BROHNS FERRY NUCLEAR PLANT ANNUAL REPORT 1986 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 a'nd 1,098 MHe.

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 shut down 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.

Radiological Control (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 (HARL) 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.

Gamma spectral analyses were performed with a Nuclear Data (ND) Model 6700 multichannel analyzer system utilizing germanium detectors, Specific analysis for I-131 in charcoal filters was performed using NaI(T1) well detector systems attached to single channel analyzers.

Starting in February, analysis for I-131 in charcoal filters was performed using a germanium detection system.

A TVA fabricated beta-gamma coincidence counting system was utilized for the determination of I-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 1nto 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 HYPERHET.

The detection capab1lities 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-7, K-40, B1-212, B1-214, Pb-212, Pb-214, Ra-226, 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 table of "

values

<LLD" for an 1sotope w1th 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 wh1ch values greater than the LLD 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.

Th1s program provides periodic cross-checks on samples of the type and radionuclide composition normally analyzed in an environmental radiological monitoring program, Routine sample handling and analysis procedures were employed in the evaluation of these samples.

The results received during calendar year 1986 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 Air Charcoal Station Looation Filter Filter Rain-Heavy Particle water Fallout River Mell Public Aquatic Life soil V~e station Milk Rater Mater Meter snd sediment Foods Muscle Shoals Lawrenceburg Rogersville Athens Decatur Courtland Site 1 (N)

Site 2

(NNE)

Site 3

(ENE)

Site 4

(NNW)

Site 5

(MSM)

Farm B

Farm Bn Farm L Farm E

Farm M

Control Farms Onsite Wells Wheeler Dam Tennessee River Champion Paper Co.

Various Local Farms M

M W

W W

W W

M W

M M

M M

W W

W M

W M

M W

W M

M M

M M

M M

M M

M M

M M

M M

M M

M M

M M

M A

A A

A A

A A

A A

A A

M M

M M

M M

M M

M M

M M

M M

M M

M M

M M

M Meekly M Monthly (every 4 weeks)

Q Quar terly 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 LH-1 BF, North LM-2 BF, North-Northeast LM-3 BF, East-Northeast LM-4 BF, North-Northwest LH-5 BF, West-Southwest PH-1 BF, Rogersvi lie, AL PM-2 BF, Athens, AL PH-3 BF, Decatur (Trinity), AL PH-4 BF, Courtland, AL RM-1 BF, Muscle Shoals, AL (Control)

RH-2 BF, Lawrenceburg, TN (Control) 1.0 Mile 0.9 Mile 1.0 Mile 1.7 Miles 2.5 Miles 13.8 Miles 10.9 Miles 8.2 Miles 10.5 Miles 32.0 Miles 40.5 Miles (1.6 kilometers)

N (65.2 kilometers)

NNW (1.4 ki lometers)

NNE (1.6 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 Farm Bn Farm B

Farm L

Farm E

Farm W

Farm N (Control)

Farm J (Control)

Farm C (Control)

Farm Cr* (Control)

Farm 0* (Control)

Farm Cb** (Control)

Farm H*** (Control) 7.0 Miles 5.0 Miles 6.1 Miles 6.9 Miles 27.0 Miles 40.0 Mlles 32.0 Miles 19.3 Miles 26.2 Miles 22.5 Miles 22.5 Miles (11.3 kilometers)

NW (8.0 kilometers)

NE (9.8 kilometers)

NE (11.0 kilometers)

NE (43.4 kilometers)

NW (64.4 kilometers)

NNW (51.5 kilometers)

N (30.9 kilometers)

ENE (41.9 kilometers)

E (36.2 kilometers)

E (36.2 kilometers)

ENE 4.75 Miles (7.6 kilometers)

N

'Sampling commenced November 1986.

• • Discontinued operations November 1986.

• • • Discontinued operations Duly 1986.

Table 3

DETECTION CAPABILI TIES FOR ENVIRONHENTAL SAHPLE ANALTSIS A.

5 ec IfIc Ana I scs NOMINAL LOWER LIMIT OF OETECTION (LLO)*

Alr Par t Icul ates

~CI/m 'harcoa I

Fal lout Water

~CI/m Ci/K KCi/L Vegetation and Grain

~ci/

O Soll and Sediment

~Ci/

0

Fish, Clam Flesh,

Plankton,

~CI/

Or

Foods, Heat, Clam Shel ls Poul try, Hilk

~Ci/

Or

~CI/K. lice OCI/L Gross a Gross S

H-3

'-131 Sr-89 Sr-90 0.005 0.01 0.005 0.001 0.01 2

0.05 2

330 10 2

0.05 0.20 0.25 0.05 0.35 0.70 1.5

0. 15

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0.1 O.i 0.5 0.1 0.7 0.7 5.0 I.O 25 40 8

0.5 10 2

• Ail LLD values for Isotopic separations are calculated by the method developed by Pasternack and Narley 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 LLO value for thc given sample.

The assumption Is made that el I samples are analyzed within one week of thc collection date.

Conversion factors:

I pCI 3.7 x 10 Bq; I mCI 3.7 x 10 Bq.

Table 3 (Continued)

DETECTIOH CAPABILITIES FOR ENVIROHMEHTAL SAMPLE ANALYSIS B.

Carrnra Anal ses HOMINAL LONER LIMIT OF OETECTIOH (LLO)

Cc-144 Cr-51 I-I 31 Ru-106 Cs-134 Cs-137 Zr-95 Hb-95 Co-58 M -54 Zn-65 Co-60 Fc-59 Ba-140 La-140 Air particu)ates Ci/m GeL 0.02 0.03 0.01 0.03 0.01 0.01 0.01 O.OI 0.0'I 0.01 0.01 0.01 0.02 0.01 Mater and milk Cl/L Ge LI 33 44 8

30 5

5 10 5

5 5

9 5

5 25 7

Vegetation and grain CI/

dr

~oGee~LI 0.22 O.47 0.09 0.51 0.33 O.O6 0.11 0.05 0.05 0.05 0.11 O.O6

0. 34 o.o8 Soil and sediment PCi/r dr

~Ge L~i

'0.06

0. Io 0.02

0. Il 0.08 0.02 0.03 0.01 0.01 0.01 0.02 0.01 0.07 0.02 Fish Cl/

dr HGe

~LI O.O6

0. 10 0.02 O.II 0.07 0.02 0.03 O.OI 0 F 01 0.01 0.02 0.01 0.10 0.07

0. 02 Clam flesh and plankton g>Ci/r dr)r

~Ge I+I 0'5 0.56 0.07 O.74 o.48 o.o8 0.15 0.07 0.07 o.o8 0.17 o.o8 0.30 0.10 Clam shells CI/

dry Ce Li 0.06 0.10 0.02

0. 11 o.o8 0.02 0.03 0.01 O.OI 0.01 0.02 0.01 0.07 0.02

Foods, (tomatoes po'tatocs

~ c'tc )

C'I/K wet Ge LI 33 44 8

4O 26 5

Io 5

5 5

9 5

25 7

that and poultry Cl/K wet Ge Li 4O 90 20 90 4O 15 20 15 IS 15 20 15 50 15

• Thc Gc(LI) LLO values are calculated by the method developed by Pasternack and Harlcy as described in HASL-300.

These LLO values are expected to vary depending on the actlvi ties of the components in thc samples.

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

Mater Is counted in either a 0.5-L or 3.5-L Marlnelll beaker.

Solid samples, such as sol I, sediment, and clam shells, are counted in a 0.5-L Marlnelll beaker

'as dry weight.

The average dry weight is 400-500 grams.

Air f liters and very small volurre samples are counted In petri dishes centered on the detector cndcap.

The counting system consists of a NO-6700 multichannel analyzer and germanlrmr detector having an efficiency of 20 percent.

The counting time is normally 4-15 hours.

All spectral analyses are performed using the software program HYPERMET. 2The assumption is made that all samples are analyzed within one week of thc col lection date.

Conversion factor:

I pCI ~ 3.7 x 10 Bq.

TABT.F. 4 RESULTS OBTAINEO IN INTERLABORATORY COHPARISON PROGRAH A.

Air filter (pCi/filter)

~CR~~lh~

EPA value TVA

~aa

~r~ a

~~rani ym-M EPA value TVA EPA value TVA

~+'Lo}

~v

~+pi hLvv

~aUu~>1 EPA value TVA M-+'Lcil 4/86 9/86 "15i9 14 22%9 21 47i9 66i9 51 18i3 13'8 22i3 20 10i9 22+9 ll 20 B.

Radiochemical Analysis of Mater (pCi/IJ T

i EPA value TVA EPA value TVA hxa EPA value TVA 6m, EPA value TVA EPA value TVA hm.

11/85 I/86 2/86 2/86 3/86 4/86'/86 5/86 6/86 7/BG 8/86 9/86 10/86 10/86~

11/86 13i9 7i9 Bi9 35i9 15i9 18i9 8+9 51+9 20i9 14 8

12 3I 16 22 10 7+9

<10'6 40 10i9 20 4i3 5227i906 4643 3125i624 2777 5973il034 5330 9i10 9

9il0 8

45i10 48 C.

Gamma-SpeCttai AnalySIS uf'oatel. (pCI/L)

EPA value TVA EPA value lVA EPA value fVA CPA value TVA EPA value TVA EPA value TVA

~a

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~2gl IL g LQ~a

!kg

~BI Eye 2/86 4/86" 6/86 10/86

=

10/86" 38i9

<44 Oi9

<44C 59i9 58 ISi9 IOi9 66+9 3li9 2dg9 19 Ia 66 31 25 40i9 86i9 85+9 63 7B Oi9 40c 3(I/9 4,9 50>9 48 74>9 73 28i9 12i9 28 6

46 26 11 22i9 Si9 10i9 44i9 Bi9 2I

TABLT'. 4 (continuecl),

0.

Food (pCi/Kg, Wet Weight)

EPA value TVA EPA value TVA EPA value TVA EPA value TVA EPA value TVA Duke

~+

~+

bra.

~+

beau. ~

hxa

~+o hza 1/86 25g9 16 10+3 12 20')0 17 15'7 950g248 1073 7/86 30g9 31 19g3 21 30g10 27 20+9 22 1150')00 1257'.

Hilk (pCi/L)

EPA value TVA EPA value TVA EPA value TVA EPA value TVA EPA value TVA I!ate

~+'&

@ca

~+~) lLva

~o

@ca

~Kl ILm ~

ILca 10/85 48g9 63" 26i3 26 42' 0 41 56g9 55 1540g)33 1533 6/86 Og9

<10~

16'6 41'0 42 31'4 1600g139 1677 11/86 9L9 13 Op3

< 2 49')0 48 39y9 43 1565g135 1633 a.

The low results for Sr-90 were associated with a poor chemical yield due to chemical separation problems.

b.

Laboratory performance evaluation study.

c.

Below LLD.

d.

The cause of the low gross beta results could not be clearly identified.

However, problems appear to exist with a large percentage of the other participating laboratories not being able to obtain agreement with the EPA method of calculating the known gross beta activity for LPES cross-checks.

e.

Values reported as mg K/Kg.

f.

Temperature variations can produce minor gain shifts in the detection systems.

The low abundance and low counting efficiency for the 1460 KeV line used for identification of K-40 combined with a minor gain shift <<ill produce results with a large bias.

g.

Values reported as mg K/liter.-

h.

Resu)ts were investigated, but the source of the high result for Sr-89 could not be clearly identified.

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- BELLEFONTE NUCLEAR PLANT BROWNS FERRY NUCLEAR PI.ANT G EORG I

A tootSVA.LE TENNESSEE VALLEY REGION (TVA NUCLEAR PLANT SITES)

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LEGEND

Atmos heric Honitorin The atmospheric monitoring network is divided into three groups identified as local, perimeter, and remote.

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

One additional station is located at

-the point of maximum predicted offsite concentration of radionuclides based on preoperational meteorological data (see figures 3 and 4).

Four perimeter air monitoring stations 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.

The locations of these monitoring stations are shown in figure 2.

The remote stations are used as control or baseline stations.

At each local station, 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 stations, the system has been modified so that air is continuously pulled through a

1-7/8-inch diameter glass fiber particulate filter at a flow rate of about 2 ft'/min.

In series with, but downstream of, the particulate filter is a charcoal filter used to collect iodine.

Each station 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 monitoring stations 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 transmitted via radiotelemetry to 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 3 days'he samples 'are composited monthly for analysis of specific gamma-emitting radionuclides and quarterly for Sr-89 and Sr-90 analysis.

Because of potential fallout as a result of the Chernobyl nuclear reactor accident, two sets of weekly samples were analyzed for gamma-emitting radionuclides.

Increased levels of I-131, Ru-103, Cs-137, and Cs-134 were identified in these samples.

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

These data are presented in table 6.

During this reporting period, eight samples were not obtained because of equipment malfunction, 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 1968-1986 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 max1mum permissible concentrations (MPC) specified in 10 CFR 20 for nonoccupational exposure.

Rainwater Rainwater 1s collected monthly and a 3.5-liter sample analyzed for specific gamma-emitting radioisotopes and tritium.

One extra set of samples was collected in an effort to detect potential fallout as a

result of the Chernobyl accident.

Increased levels of I-131 and traces of Ru-103 were identif1ed in these samples.

The highest I-131 value measured was approximately 20 pC1/L.

The results of these and other analyses are summarized in table 7.

During this reporting period, one sample was missed because of equipment malfunct1on, two samples were not collected because of personnel

error, seven samples were m1ssed due to insufficient rainfall, and three gamma and two tritium analyses could not be performed due to insufficient quantity of sample.

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 report

period, one sample was destroyed during analysis.

Charcoal Filters Charcoal filters are collected weekly and analyzed for radioiodine.

Samples collected following the accident at the Chernobyl nuclear power stat1on exhibited increased levels of I-131, The highest level reported was 0.21 pCi/m', or about 10 times background.

The results are shown in table 9.

During this reporting per1od, eight samples were not taken because of equipment malfunction.

Table 5

MAX1MUM PERMISSIBLE CONCENTRATIONS FOR NONOCCUPATIONAL EXPOSURE 13 Alpha Nonvolatile beta Tritium 137C6 103 106Ru 144( e "Zr-9SNb 140Ba 140L 131I 6SZn S4Mn 60Co 89Sr 90Sr S1Cr 134( 6 S8CO S9Fe In Water Ci/l-"

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 50)000 MPC In Air Ci/m3:"

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

'"l pCi = 3.7 x 10"2 Bq Source:

10 CFR, Part 20, Appendix B, Table II.

NAME OF FACILITY Qgpggg EEQEI LOCATION OF FACILITY LJQEQIPQE TABLE RADIOACTIVITY IN AIR FILTER PCI/F(3) - 0 037 BD/M(3) 8L898L'8 10=22242894228 REPORTING PERIOD 1258 TYPE AND TOTAL NUMBER OF ANAt.YSIS PERFORMED GROSS ALPHA 52 GROSS BETA 564 GAMMA (GELI) 165 LOITER LIMIT OF DETECT ICN (LLD)

SEE BQIE 1

5 OOE-03 1.00E-02 ALL INDICATOR LOCATIONS MEAN (F)

RANGE SEE BQIE 2

0 VALUES <LLD

.ANALYSIS PERFORMED 2 57E-02( 459/ 460) 1.03E 1 '9E-01 LMZ BF NORTH 0 ~ 9 PILE NNE 2.90E-02(

1.25E-02 51/

51) 1 11E-01 LQE8IIQH HIIU dIPUEEI 888Q8L "E88 NAME MEAN (F)

DISTANCE AND DIRECTION RANGE SEE UQIE 2

CONTROL LOCATIONS MEAN (F)

RANGE SEE UQIE 2

5Z VALUES <LLD 2 '9E-02(

104/ 104) 1.09E 1 '5E-01 NUwBER Of NONROUTINE REPORTED MEASUREMENTS RU-103 CS-134 CS-137 K-40 I-1 31 BI-214 BI-21 2 PB-214 PB-212 BE-7 TL-208 AC-228 SR 89 SR 90 NOT ESTAB 1

CCE-02 1

OGE-02 NOT C.STAB 1

COE-02 Z OCE-02 NOT ESTAB 2.00E-02 NOT ESTAB 5 CCE-02 NOT ESTAB NOT ESTAB 5 CCE-03 42 1

OGE-03 42 1.33E-02(

1.20E-C3 1 91E-02(

1 04E-C2 2.54E-02(

1 26E-CZ 2 86E-02(

1.60E-03 1 79E-02(

1.02E-C2 5.02E-02(

3 28E-G2 1r57E-C1(

1 '8E-01 3 87E-02(

2.CSE-OZ 49E GZ(

1.COE-04 9.93E-02(

1 5 ZCE-02 1.8eE-02(

COE-C4 1.03E-02(

3.00E-04 5 33E-03(

5 '3E-03 34 VALUES ANALYSIS PER 19/ 135) 2.66E"CZ 9/ 135) 2 39E-02 18/ 135) 4 19E-02 37/ 135) 2.93E-C1 8/ 135) 2 33E-CZ 6/ 135) 8 45E-02 1'. 5) 1 67E-01 11/ 135) 8.16E-GZ 26/ 135) 1 65E-01 26/ 135) 1 '6E-C1 8/

1 35) 5 89E-GZ 11 / 135) 5 19E-02 1 /

34) 5.33E-03

<LLD FORYED DECATtrRr AL 8 ~ 2 PILES SSE ROGERSVI(.LEr AL 13 8 MILES N'k ATHEVSr AL 10 9 MILES NE LM2 BF NORTH 0.9 PILE NNE DECATURr AL 8 ~ 2 WILES SSE LM1 BF NORTHHEST 1 ~ 0 MILE N

ROGcRSVILLEr AL 13.8 MILES Ne LM2 BF NORTH 0.9 MILE NVE ROGERSVILLE r AL 13 ~ 8 MILES POGERSVILLEr AL 13 8 MILES Ntt LMZ BF NORTH 0 ~ 9 F ILE NNE LH1 df NORTHHEST 1 ~ 0 KILc N

ATHENSr AL 10 ~ 9 MILES NE 1 77E-02(

1 27E-02 2 39E-02(

2.39E-02 3 04E-02(

1 ~ 91E-02 6 ~ 87E 02(

1r76E-02 2.33E-02(

2r33E-02 5.86E-02(

3+28E-02 1 '7E-01(

1~e7E 01 5 45E-02(

3.38E-02 5.65E-02(

3 '0E-04 1 ~ 14E-01 (

8.74E"02 4 '5E-02(

4.15E-02 3.3SE-02(

3 'SE-02 5.33E-03(

5.33E-03 2/

15) 2.27E-C2 1/

15) 2.39E-02 2/

15) 4 16E"G2 6/

15)

2. 93E-01 1/

15) 2 33E-02 2/

15) 8 45E-G2 1/

15) 1 67E-G1 3/

15) 8 '6c-02 3/

15) 1 '5E-01 4/

15) 1.7CE-C1 1/

15) 4 '5E-02 1/

15) 3SE"02 1/

~

4) 5.33E-C3 8.5CE-03(

8/

30) 1 'CE 2 '38-CZ 1 '4E-02(

2/

'30) 1 7CE 1 77E-02 2.79E-OZ(

3/

30) 1.60E 3.4eE-02 7 68E-03(

5/

30)

Z~SCE-03 1.10E-02 1

7SE-OZ(

2/

30) 1 '8c 02 -

2 AROSE-02 30 VALUES <LLD 30 VALU S

<LLD 3r VALUES <LLD 8.5CE-03(

8/

30) 1 ~ OOE-04 3 '9E-OZ 1.07E-01(

28/

30) 6+82E-GZ - 1~58E-01 5 'GE-03(

5/

30) 3.0CE"04 -

1 54E"02 3 47E-0'(

3/

30) 2.00E 8.20E-03 8

VALUES <LLD 8

VALUES <LLD NOTE:

NOTE:

1 ~ NOMINAL LOHER LIMIT CF DETECTION (LLD) AS DESCR'IBED IN TABLE 3 ~

2 IIEAN AND RANGE BASED UPON DETECTABLE MEASUREMENTS ONLY FRACTIOV OF IS INDICATED IN PARENTHESES (F) ~

DETECTABLc MEASUREMENTS 4T S>ECIF TED LOCATIONS

RANE GF FACILITY QBQhhh EGBdY LOCATION OF FACILITY LI5EEIQBE TABLc 7

RADIOACTIVITY IN RAINMATER PCI/L -

0 ~ 037 EO/L bL81858 DOCK T

NO ~ 20:222c2(l04225 REPORTING PERIOD JPQQ TYPE AND TOTAL NUNBER OF ANALYSIS PERFORMED GAHC.'A (6ELI )

141 K-40 I-1 31 8 I-214 pe-214 PB-212 LOME R LI HIT Oc DETECTION (LLD)

EE BQIE 1

NOT ESTAB 8

OOE+OG NDT ESTAe NOT ESTAB NOT ESTAe 3c-7 TRIT IUN NOT ESTAB 3 30E+02 131 4 21E+01(

7.77E+GO 1

23E+C1(

8.43E+CG 9 '4E+CG(

4.42E-C2 35E+01 (

6 93c-C2 2 OOE+00(

3 46E-02 4 '5E+01(

2 ~ GOE+01 107 VALUES ANALYSIS PER 3/ 115) 8 41E+01 11/

115) 1 ~ 76 i+01 40/

115) 1 64E+02 19/ 115) 1 64E+02 31/ 115) 5 '0E+OC 19/ 115) 6 62E+01

<LLD FORHED ALL INDICATOR LOCATIONS NEAN (F)

RANGE GEE BQIE 2

COUPTLANDw AL 10 ~ 5.IILES MSM LH4 BF TRAILER 1 ~ 7 PILES Nile LH5 BF DAVIS f 2 ~ 5 l ILcS MSM LH5 BF DAYIs F

2 5 rILEs MsM ATHENS'L 10 ~ 9 MILES NE LNZ BF NORTH C.9 r.ILE hNE S ~ 41 E+01 (

8.41 c+01 1 ~ 59E+01 (

1 42E+01 2 '3E+01(

2 25E-01 8.26E+01(

1 15E+00 Za91E+00(

1 51E+00 6 '2E+01(

6 62Et01 1/

13) 8 ~ 41E+01 2/

12) 1.76E+01 6/

12) 1.64E+02 2/

12) 1.64E+02 2/

13) 4 '1E+CO 1/

13) 6 '2E+01 LQE8IIQ8 HIIH UIGUE5I 85808L 5E8U NAHE MEAN (F)

DI STANCE AND DIRECTION RANGE

$ EE )QIE CONTROL LOCATIONS MEAN (F) cANGE GEE HQIE 2

Z6 VALUES <LLD 1

98E+01(

1/

26) 1.98E+01 1.98E+01 1 '2Ey01(

10/

26) 7 04E 8 80E+01 2 OOE>01(

7/

26) 1 31E+00 9 99E+01 1 83E+00(

8/

26) 1 13E 3 39E+00 4 16E+01(

6/

26) 3 '7E+01 -

4 '8E+01 24 VALUES <LLD NU.IBER OF NONROUTINc REPORTED HcASUREHENTS NOT:

1 ~

NONINAL LONER LIPIT OF DETECTION (LLD) AS DESCRIBED IN TABLE 3 ~

ROTi:

2,:-NEAN AND RANGE BASED UPON DETECTABLc hEASURENENTS ONLY F RACTION OF DETECTABLE NEASUREHENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) ~

TABLE 8 RADIOACTIVITY IN HEAVY PARTICLE FALLOUT MCI/KM(2) - 37000000.00 Ba/XM(2)

NA<E OF FACILITY Qggggg foff gg LOCATION OF FACILITY gggfggggj

$g$ g$ g$

DO

'(ET NO-20=2224259cRRk REPORTING PERIOD 19g{t TYPE AND TOTAL NUMBER OF ANALYSIS PERFORMED GROS )

BETA 142 LOllER LIMIT OF bETECTION (LLD)

SEE HQIE i 5

OOE 02 ALL INDICATOR LCCATIONS MEAN (F)

RANGE SSR Shit.s 1 '9E-Cf( 114/

116) 5 '5E 2e945-01 Lf)ESITf)8 ffIIff ffIQUERi 65huhl hk&U NAME MEAN (F)

DISTANCE AND D) RECT IOH RANGE

.SEE BQIE 2

COURTLANDr AL 1 ~ 56- 01(

13/

13) 10 ~ 5 WILES wSV 9 5'.E 2.>4E-Of CONTROL LOC AT ION S MEAN (F)

RANGE EKE 8QIE

?

9o89E-02(

26/

26) 5 '2E 2 '3E-01

!vJMB=R GF NON40UT Ihf REPORTED HEASUREMENTS NOTE:

NOTE:

1 ~

NC "IDEAL LOilER LIMIT CF DETEITION tLLD)

AS DESCRIBED IN T4BLE 3

2

>BAN ANb RANGE BASED UPON DETECTABLE NEASUREPENTS ONLY. FRAG>I)N OF DETECTABLE "EASUREMENTS AT SPECI~I D

LOCATIONS IS INDICATED IN PAREhTNESES (F) ~

NAHE CF FACILITY o3Qgggf ERgI LOCATION OF FACILITY LOPE/IQQE TABL=

9 RADIOACTIVITY IN CHARCOcL CILTFRS PCI/P(3) - 0.037 EcO/H(3)

AL8QAYS VCR 59=252c?('4Qc?2l'4 REPORTING PEoIOD 1/$ 6 TYPE AND TOTAL hUHBER OF ANALYSIS PEPFOR'lED IODINE-131 65 GAHHA (GELI) 499 K-40 I-1 31 81-21 4 BI-212 Po-214 PB-212 BE 7

TL-203 AC-228 LONER LIP IT OF DETECTION (LLD)

SEE BQIE 1 1

OOE-02 VOT ESTAB NOT ESTAB NOT ESTAP NOT ESTAB OT ES~A NOT ESTAB NOT ESTAB NOT ESTAB NOT cSTAB ALL INDICATCR LCCATIONS HEAN (F)

RANGc SEE 5QIE 2

1.65E-C2(

18/

53)

C3E-C2 -

3 88E C2 3 '9E-01(

8'7l 407) 5.05E-C2 7 '2E-C1 8 ~ 37E-G2(

33/ 407)

CD 2CE-C3 - 2.06E-01 3 06c-02(

132/ 407) 1 2CE-C3 -

1 '4 - '1 2.73E-01(

3/ 407) 7 28E-02 5,CSE-01 2.53E-C2(

190/

407) 1 60E 3 97E-02 1 20E-02(

112/ 4"7) 1 COE-OC 4 '0E-01 3 55E-Oi(

2/

C07) 3 53E 3 6GE-02 2 13E-02(

14/ 407) 3 00E 1 71E-01 1 '6E-02(

6/ 407) 4 '0E 03 -

5 'Cc 02 ATHE 4Sr AL 10 9 HIL8S Nic ATHENSr AL 10 9 "ILES hE DECATURr AL 4 ILES SSc LH2 BF NORTH 0.9 PILE NNE ATHENSr AL 10 9 FILES NE LH2 BF NORTH 0.9 PILE NNE LP2 BF NORTH Ce9 l"ILE NNE LH2 BF NORTH 0

9 PILE NNE ATHENS/

AL 10.9 HILES NE 4 ~ 75c Cl (

2 35E-01 1 20E-01(

4.33E-02 4 '4E-02(

1 'oE-02 5.48E-01(

5 ~ 4SE-01 3.11E-02(

1.60E-03 6 1'7c-02(

1 50E-03 3.6GE-02(

oOE-02 8 60E-02(

1 '0E-03 5 60E-02(

5 60E-02 15/

Co) 7 '2E-C1 3/

46) 1.95E-C1 16/

46) 1 ~ 14c C1 1/

46) 5 '8E-C1 22/

Co) 7 55E-C2 9/

46)

C.70E-C1 1/

46) 3'0c-02 2/

46) 1 71E-C1 1/

46>

5 60E-C2 l QEAIIQll )fIIU JIQLJE51

>LZUQ4ll L'E45 NAHE vEAN (F)

DIST<<hCE AND DIRECTION RANGE 5EE 5QIE 2

2 '0E-02(

3/

6) 1 '0c 02 3 '8E C2 COiVTPOL LOCATIONS HEAN (F)

RANGE SEE 3QIE

?

1 '9E-02(

5/

12) 1.25E 2.25E-C2 3 61E-01(

27/

92) 6 '7E 7 27E-01 3 68i-02(

7/

92) 1 79E-02 "

1 96E-01 2 '5E-02(

37/

92) 4 'CF 1 02E-01 92 VALUES <LLD 2.49E-02(

42/

92) 4 'OE 8 91E-02 3.75E-03(

30/

92) 1 OCc 1 '2c-02 92 VALUES <LLD 6 20E-03(

2/

92>

3 80E 03 8 60E-03 1 56E-02(

3/

92) 8.20E 2 '6E-02 "4UHBER OF NOhPOUTINE REPORTED "ECSUREHENTS NOTE:

1 ~

NOt'INAL LONER LIHIT OF DETECTION (LLD) AS DESCRIBED IN TABLE 3 ~

VOTE:

2 HEAN AND RANGE BASED UPOh DcTECTABLE HEASUREH NTS ONLY ~

FRACTION OF DETECTABLE HEASUREVENTS AT SPECIFIED LOCATIONS IS INDICATED IV PARENTHESES (F)

18 Figure 2

ATMOSPHERIC AND TERRESTRIAL MONITORING NETWORK RM-2BF LAWRENCE BURG yPULASKI FAYETTEVILLE+

WILSON FLORENCE PM-IBF WHEELER ROBE SVIL OAM ATHENS PM-2BF FFIEL MUSCLE SHOALS RM.IBF LEIGHTON TUSCUMBIA COURT LANOf PM-4 F

pRUSSELLVILLE BROWNS FERRY NUCLEAR PL NT OECAT PM-3BFO IO MILES HARTSELLE HUNTSVILLE UNT SVIL OAM 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

LOCAL MONITORING STATIONS BROWNS FERRY NUCLEAR PLANT ATHENS U S HWY 72 BFN ALA. HSY 20 Legend

~

Air Monitor A

Automatic Nell Sampler 8

Dairy Farm Other Ferns DECATUR Scale 0

I 2

p 4

5 Miles

20 Figure 4

r ~

I r

TLD Locations 8FN

" ((

~

!t ses

~ I I II t

~ ~

(

~

~

'/YI'I

~

~

~

S

~

~

(

/

~

I

~

~,

I sbrC ss

~'I

~I

~

SI I I'r

~ t

'1 1-I

-J 0

~I IIV

'R

'V

~,

~

)t ")

it Is t

('$

T-tP;t' C':~'I

, Of I

I (I

~'r'i+/sr r) l~

~4 I

Sl V \\

't '}~

~

~

~,r. ~

t f

r t

I~ II C

~ '

I It;-,

H 1

I ss r

,mrs

~I~ ~"

r A

~'" )

l

~r Wl I

ss ff I s

~

~/

ad)

E.

~ I

~

~

r I

WI 1

I 5"'

1

~I

~

Igg' I

IS I ss I/

I I

IV ),

)

tl

'i)~

I r

sl rr r

/C I

qi

'E I

~

II

~

~

~I I c" 1 tt

~

I I

h I

~

I

+,

}

~I

~

'I Iv I

~ 'I

!:::'4",:t/l t(

W ~

I

~

~

Figure 5

Annual Average Gross Beta Activity Air Filters (pCi/cubic meter)

Browns Ferry Nuclear Plant 0.25 0.2 0.1 5 Preoperational Phase

~ Indicator H Control Operational Phase Preoperational Average 0 '

0.05 68 69 70 71 72 73p 73o 74 75 76 77 78 79 80 81 82 83 84 85 86

23 Terrestrial Hon1torin Terrestrial Monitoring is accompl1shed by collecting environmental media w1thin the general area of the plant for ind1cator locat1ons and at remote locations for controls.

Those media sampled 1nclude milk, vegetation, soil, groundwater, drinking water, and food crops.

In addition, environmental gamma radiat1on levels are determined by strategic placement of thermoluminescent dosimeters (TLDs).

Twice each year a land use survey 1s conducted to determine milk producing an1mal census and locat1on.

Land Use Surve The land use surveys were conducted in Hay and July of l986 to locate milk producing animals within a 5-mile radius (8 kilometers) of the plant site.

There exists only one such location, a dairy, within that range;

however, two other dairies are within 7 miles (ll kilometers).

These three dairies are considered ind1cators and routinely provide milk samples.

Milk Milk was collected from three dairies within a 7-mile radius of the plant (see figure 3) and from at least one of six control farms.

During this report period, two control dairies ceased operations and two replacement dairies were added to the sampling schedule Raw milk samples are collected weekly from indicator and control farms and are analyzed weekly for I-131 and monthly for gamma-emitting

isotopes, Sr-89, and Sr-90.

Analytical results are summarized in table 10.

Increased levels of I-131 were identif1ed 1n samples collected following the Chernobyl accident.

The highest I-131 concentration measured was 29.5 Ci/L at one of the control stations.

During the l986 reporting period, five samples were not available for collection and four samples spoiled and were unusable.

Yeceetation Vegetation is sampled monthly at five indicator farms (three dairies and two farms with one milk producing animal), at each air monitoring station, and at five control farms (two control farms ceased operation in 1986).

The monthly samples are analyzed for I-131 and gamma-emitting isotopes with analys1s for Sr-89 and Sr-90 performed on the last monthly sample of each quarter.

Table ll summarizes analytical results.

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

24 environment.

An auger or a "cookie cutter" type sampler is used to obtain samples of the top 2 inches (5

cm) of soil.

These samples are analyzed for gamma-emitting radionuclides, Sr-89, and Sr-90.

The results are given in table 12.

Ground Water An automatic sequential-type sampling device collects groundwater from a well downgradient from BFN.

A compos1te sample from this well is analyzed for gamma-emitting radionuclides monthly and composited quarterly for determination of tritium.

The quarterly composites were also analyzed for strontium content.

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

The results

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

Drinkin Water Potable water 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-89, and Sr-90 analyses.

The first potable water supply downstream from the plant is equipped w1th an a sequent1al type sampling device.

Composite samples are collected and analyzed weekly.

The sampler 1s located on the water 1ntake 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

addit1on, 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 th1s reporting period, three weekly samples were not collected because of automatic sampling equipment problems.

Figure 6 shows the trends in gross beta activity in drinking water from 1968 through 1986.

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 R1ver in preoperat1onal monitoring programs conducted by TVA at other sites.

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

Hn) TLDs are placed at 16 stations around the plant near the site boundary, at the perimeter and remote air monitors, and at 19 add1tional stat1ons out to approx1mately 5 miles from the site to determ1ne the gamma exposure rates at these locations.

The dosimeters, located inside energy compensating shields to correct for energy dependence, are placed at approximately 1 meter above the ground,

25 with three TLDs at each station, They are annealed and read with a Yictoreen model 2810 TLD reader.

The values are corrected for gamma

response, self-irradiat1on, and fad1ng, w1th 1nd1vidual gamma response calibrations and self-1rradiat1on factors determ1ned for each TLD.

The system meets or exceeds the performance specifications outlined 1n Regulatory Guide 4.13 for environmental appl.ications of TLDs.

The TLDs are exchanged every 3 months.

The quarterly gamma radiation levels determ1ned from these TLDs are given in table 15, which indicate 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 construct1on sites where the average radiat1on levels onsite are generally 2-6 mR/quarter higher than levels offs1te.

The causes of these differences have not been completely isolated;

however, 1t is postulated that the differences are probably attributable to combinat1ons of influences such as natural variat1ons in environmental rad1ation 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 l976 through 1986.

To reduce the variations present in the data

sets, a 4-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 two times the levels reported herein.

Those data are not 1ncluded in this report.

Therefore, for comparison

purposes, figures 9 and 10 depict the environmental gamma radiation levels measured during the construction of TVA's Hatts 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 h1gher 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.

During this sampling period, samples of apples,

cabbage, corn, green

beans, potatoes,

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

The results are given in tables 16 through 22.

NAME OF FACILITY QPQ'g5E EEBEI LOCATION OF FACILITY LIBEEIQBE TAMIL=-

10 RADIOACTIVITY IN MILK PCI/L - 0 037 BO/L DOCKET NO ~ 59=252425942-(l REPORTING PERIOD 1298 TYPE AND TOTAL NUMBER OF ANALYSIS PERFORIIED K-40 I-1 31 BI-214 PB-21'B-212 TL-208 AC-2ZE LOMER LIMIT OF DETECTION (LLD)

SEE UQIE I 5

OGE"01 5

GOE+00 NOT cSTAB S.OOE+00 NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB NC~

ESTAB SR 89 SR 9" 1 ~ OOE+01 99 2

OCE+00 0 9 IODINE-131 395 GAMMA (GELI) 10C CS-137 ALL INDICATOR LCCATIONS MEAN (F)

RANGE BEE HQIE 2

3 76E+GC(

14/ 157) 5 08E 1 ~ 61E+01 5

ZSE+CG(

1/

3o) 5 '8E+OC - 5.28E+GC 1.24E+03(

39/

39) 7.90E+02 - 1.75E+03 39 VALUES <LLD 1

34E+01(

23/

39) 4 3SE C2 7 c6cq01 1.14E+G1(

20/

39) 3.69E 7.3".E+01 1 '7E+CC(

12/

39) 4 ~ 7CE 5 09E+OC 2.29E+OC(

2/

39) 2 '4E-C1 -

4 '22+BC 1 ~ 86Ei00(

1/

39) 1 '6E+GG -

1 '6E+OC 39 VALUES <LLO ANALYSIS PERFOF.WED 3.C9E+GO(

25/

39) 2.03E+00 4

93E+GG SYI TH/BENNETT F A 4

75 FILES N

SNITH/BENNETT FA 4 ~ 75 MILES N

5.28E+00(

1/

13) 5.28E+00 - 5.2SE+CC 1.Z6c+G3(

13/

13) 1 07E+03 -

1 '5E+03 LOONEY FARY 5~75 MILES iNE LOONEY FAR" 5'5 MILES ENE SMITH/BENNETT F A 4

75 MILES N

SHIT+/BENNETT FA 4

75 "ILES N

LCGNEY FA'Rl'

'3 MILFS ENE 2.06E+01(

8 17E-01 1 39E+01(

3 69E-01 2 20E+00(

4 70E-02 4.28E+00(

4 2cE+OG 1 '6E+00(

1 86E+00 9/

13) 7.56E+01 9/

13) 7 38E+01 5/

13) 5 09E+CO 1/

13) 4 2cE+CG 1/

13) 1 o 86EiCC SYITH/BENNETT FA 4

75 MILES N

3 ~ 25E+00(

10/

13) 2 34E+00 -

4 93E+00 LQf4IIQB HIIU UIQUEEI 88898L uE88 NAME

'lEAN (F)

DISTANCE AND DIRECTION RANGE SEE UQIE 2

BRCOKS FARY 6 30c+00(

5/

52) 7 0

MILES NNM 6.0SE-01 1

61E+01 CONTROL LOCATIONS MEAN (F)

RANGE BEE UQIE 2

c 84E+00(

28/ 238) 7 56E Z.95E+')1 o.16E+00(

4/

61) 6 ~ 61E+00 -

1 ~ 04E+01 1 '3E+03(

51/

61) 8 '5E>02 1.80E+03 9 72E+00(

ZI 61) 8 07E+00 - 1.14Et01 8 34E~OO(

26/

61) 9 02E 4 36E+01 7 70E+00(

13/

61) 9.04E 2 03E>01 3 '6E+OC(

13/

61) 1 '9E 1 23E+01 1 55E+00(

8/

61) 1.5GE 3.44E+GC 9 '1E+OC(

8/

61) 2 32E+00 -

1 58E+01 60 VALUES <LLD 3 31=+00(

38/

60) 2 ~ 03E+00 -

5 71E+00 NUMBER OF NONROUT INE RcPORTED MEASUREMENTS ROTc-NOT =:

!sCNINAL LOMER LIMIT CF DETECTION (LLD)

AS DESCRIBED IN TABLE 3 ~

"EAN A4D RANGE BASED UPON DETcCTABLE MEASURE>ENTS ONLY ~

FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)

MA'Ic OF FACILITY UBQhUS EEBBY LOCATIOM OF FAC ILITY LIUESIQUE TABLE 11 RADIOACTIVITY IN VEGETATION PCI/G -

0 ~ 037 BD/G (DRY WEIGHT) bLbQbUb Do CK T

MO SQ=

SRc?SQC,?2(I REPORTING PERIOD 125(I-TYPE AND TOTAL HUNGER OF ANALYSIS PERFORMED IODINE-1 31 (SEE NOTE 3)234 GANNA (GELI) 236 RU-103 CS-137 K-40 I-131 BI-214 3 I-21 2 PB-214 PB-21 2 BE-7 TL-208 AC"228 SR 89 73 SR 90 73 LOWER LIPIT CF DETECTION (LLO)

Sff UQIE 1 MOT ESTAB 2 OOE-01 6 OGE-02 HOT ESTAB 9+OOE-02 1

OGE-01 NOT ESTAB MOT ESTAB MOT ESTAB MOT ESTAB NOT ESTAB NOT ESTAB 2 50E-01 5.0GE-GZ ALL INDICATOR LOCATICMS NEAN (F)

RANGE SEE UQIE 2 1 ~ 29E-02(

57/

181) 5 ~ GOE-G6 -

1 '1c-01 3.14E-C1(

13/ 182) 2 05E 4 38E-01 1.87E-G1(

32/

182) 6.02E-GZ -

4 16E-01 1 ~ 50E+01(

181/ 182) 8 ~ 94E 5 '8E+01 6.83E-01(

12/ 182) 3 61E 1 19E+CC 2.23E-G1(

86/

1 82) 1 GOE 8 32E-01 5 92E-01(

1/ 182) 5 92E 5 92E-01 1 '6E-01( 152/ 182) 3o50E 7 16E-01 6 53E-02(

119/

182) 1 GOE 5 92E-01 6 '6E+00( 179/

182) 7 79E 3 24E+01 4 01E-GZ(

57/

18Z) 8 COE 04 2

16E 01 1 85E-01(

66/ 182) 1 '3E 6+47E-01 3 '0E-01(

1/

56) 3 50E 3 '0E-01 1 91E-01(

53/

56) 5.03E-G2 -

1 '4E+GC LQEbIIQU UIIU U NAMc DISTANCE AMD D I BROOKS FARN 7

G PILES NMW ATHEksi AL 10' MILES ME LOOMEY FARH 5 ~ 75 MILES EME LOONEY FARY 5

75 MILES ENE LOONEY FARM-5 75 MILES ENE BROOKS FARM 7 0 MILES Nt u WISER F ARN 6 ~ 9 MILES NE BROOKS FARY 7 ~ 0 NILES NNW LMZ BF NORTH 0 ~ 9 rILE NNE ROGERSVILLEi AL 13 8 MILES NM LN2 3F NORTH 0 ~ 9 PILE MME LN2 BF NORTH 0

9 PILE NNE LOONEY FARM 5

75 MILES ENE ROGERSVILLEi AL 13 ~ 8 MILES Nll IQUESI bUUUbL LfbU NEAM (F)

RECTION RANGE

SEE, UQIE 2

CD 45E-02(

3/

13) 2 24E 1 31E-01 1/

13) 4 '8E-01 1/

13) 4 16E-01 13/

13) 5 '8E+C1 1/

13) 1 19E+CG 7/

13) 8 '2E-01 1/

13) 5 92E-01 12/

13) 7 16E-01 9/

13) 5 92E-01 13/

13) 1.50E+01 C/

1 3) 2 '6E-01 5/

13) 6.47E-G1 1/

4) 3 50E-01 3/

4) 1.14E<00 4.38E-01(

4 '8E-01 4 16E"01(

4 16E-01 2 OCE+01(

3 19E+00 1 '9E+00(

1.19E+00 3.20E-01(

1 18E-01 5 '28-01(

5 '2E-01 2 16E-01(

5 17E-02 1 36E-01(

7 40E-03 7 68E+00(

1 84E+00 9 06E-02(

3.50E-03 2.49E-01(

1 ~ 17E-01 3 50E-01(

3 50E"01 C 70E-01(

1 34E-01 3 '3E-01(

3.18E-01 1 ~ 86E-G1 (

6 01E-02 1 '7E+01(

1 '2E+00 6 '9E-01(

4 26E-01 1 '4E 01(

1 ~ 01E-G1 3 14E-01(

14E-01

'I 18E-01(

4 'GE 04 5 30E-02(

2 50E-03 7 36E+00(

1 41E+00-3 62E-02(

1 8CE-03 1

77E-O1<

2.43E-02 2+67E-01(

2 '7E-01 1 65E-01(

5.51E-02 3/

54) 4.44E-G1 13/

5C) 4.49E-01 54/

54) 3 '6E+01 4/

5C) 9 '2E-01 20/

5C) 4 '0E-01 1/

54) 3 14E-01 38/

54) 4 41 E-01 33/

54) 2 05E-01 54/

54) 1 '9E+01 14/

54) 9 99E-02 13/

54) 3 55E-01 1/

17) 2 '7E-01 16/

17) 3 16E-01 CONTROL LOCATIONS MEAN <F)

RANGE

--- SEE UQIE 2

6.31E-03(

21/

53) 1 '0E 3 39E-02 MU IB R

CF MONcOUTIME RcPDRTED MEASURE IENTS NOTE:

MO'Ic)

NOTE:

1.

MOrINAL LOWER LIMIT OF DETECTION (LLD) AS DESCRIBED IN TABLE 3

2 MEAN AMD RANGE BASED UPON DETECTABLE MEASURE EHTS ONLY FRACTION OF IS INDICATED IM PARENTHESES (F) 3.

1-131 VALUES REPORTED AS PCI/G, WET WEIGHT.

DETECTABLE NEASUPEMEMTS AT SPECIFIED LOCATIONS

VAtlE OF FAC ILITY-QBQItB$ IEBBI LOCATION OF FACILITY LI15E/IQIIE TABLE

'12 RADIOACTIVITY IN SOIL PCI/G -

0 037 3Q/G (DRY HEIGHT) 84868(18 DOCK=T REPORTI NO.

SQ=252c26gc2oE NG PERIOD TTPE AND TOTAL KUHBER OF AHVALYSIS PERFORIIED G4tlHA (GELI) 11 CS-137 W-40 BI-Z14 3 I-21 2 PB-Z14 PB-212 RA-226 RA-ZZl o c<<7 TL-Zoe AC-226 PA-234'R c

11 SR 90 11 LOWER LIMNI T OF DETECTION (LLD)

BEE 5QIE I 2.00E"02 2 50E-01 5

OCE-02 1 ~ OOE-01 5.00E-02 NOT ESTAB 5 ~ OQE-02 NOT ESTAB 1.60E-i)1 2 OQE-02 o OOE-02 NOT ESTAB 1 '0E+00 1

50E-01 3 '2E-01(

1 '9E-01 5 '3E+CC(

3 Z1E+CG-1 G4E+GC(

6.84E-01 1.28E+OG(

8.13E-01 1

15E+GC(

7 ?6E-01 1 09E+00(

6 '4E-C1 1 '4E+GC(

6 84E 01 1.20E+OC(

87E-01 3.32E-G1(

1 '1E-01 3 82E-01(

2.26E-C1 1 12E+00(

7 15E-C1 2 34E+OG(

1.40E+CG 9

VALUES ANALYSIS PER 2 ~ 10E-01 (

1.79E-C1 8/

9) 7 ~ 16E-G1 9/

9) 8 '3E+00 9/

9) 1 ~ 41E+OC 9/

9) 1.8?E+QC 9/

9) 1 ~ 5CE+OC 9/

9) 1 638+00 9/

9) 1 41E+00 8/

9) 1 '4E+QC 3/

9) 4 '5E-01 9/

9) 5 51E-01 9/

9) 1 59E+00 2/

9) 3 '8E+GC

<LLD FORl'ED 4/

9) 2 56E-G1 ALL IVDICATCR LOCATIONS HEAN (F)

RANGE-5EE IIQIE 2

ATHE"lSs AL 10-9 NILES NE LH1 BF NORTHWEST 1 ~ 0 RILE N

LH4 BF TRAILER P

1 7 NILE 5 HNll DECATUR'L 8.2 t'ILFS SSE LH4 3F TRAILER P

1 ~ 7 >ILES HNM DECATUR'L 8.2

%ILES SSE LH4 BF TRAILER P

1 ~ 7 FILES NHM DECATUR'L 8

2 "ILES SSE ROGERSVILLEi AL 13 8 tIILES NH DECATUR'L 8~2 NILES SSE DECATUR'L 8

2 HILES SSE LH3 BF NORTHEAST 1.0 t'ILE ENE 7 '6E-01(

7-16E-01 8-43E+00(

8.43E+00 1.41E<00(

1 41E+00 1.878400(

1.8?E+OG 1

5OE>00(

1 '0E+00 1.63E+00(

ie63E+00 1

41 E+00 (

1 ~ 41E+00 74E+00(

1 74E+00 95E-01(

4 95E-01 5 51E-01(

5 ~ 51 E-01 1

59E+00(

1 59E+00 3 '8E+00(

3 ZSE>00 1/

I) 7 ~ 16E-C1 1/

1 )

8 43E+CO 1/

1) 1 41E+00 1/

1) 1 '7o+CO 1/

1) 1.50E+CC 1/

1) 1-63E+CC 1/

1 )

1 41 E+CG 1/

1) 1 74c+CO 1/

1) 4 '5E-C1 1/

1) 5 51E-01 1/

1) 1 59E+00 1/

1) 3.28E+CO LH2 BF NORTH 0

9 "ILE NNE 2.56E-01 (

1/

1) 2 56E-C1 -

2 56m-C1 I QEbIIQB hfIIU IIIlt4ESI 888gbL

~E4U NAHE tlEAN (F)

DISTANCE AND DIRECTION RANGE SEE IIQIE 2 CONTROL LO 4T IONS tIEAN (F)

RANGF

'SEE tIQIE 2

7 '9E-01(

2.218-01 4 54E+00(

4 26E+00 9

SCE-01 (

8 72E 01 1

09E+00(

9.02E-01 1.09E+00(

9 ~ 90E-01 67E-01(

8 '0E-01 9

BCE 01(

8 '2E-01 4CE-01(

3.7CE-01 2

VALUES 2/

2) 1.30E+')0 2/

2) 4 '3E+00 2/

2) 1 09E+00 2/

2) 1.27E+00 2/

2) 1.20E+00 2/

2) 1.10EtOC 2/

2) 1 09E+00 2/

2) 1.01E+00

<LLD 2

VALUES <LLD 3

46E-G1 (

2/

2) 2 '3E-O'I -

4 '9E-01 9.84E-01(

2/

2)

ST 82E-01 "

1 09E+OG 1

87E+00(

1/

2) 1 87E+00 - 1.87E+00 2

VALUES <LLD NUHBER O<

'VONROUT'V REPORTED t.EASUREHEHTS VOTE:

NOTE-i. NO~IVAL LOllER LIIIIT OF DETECTION (LLD) AS DESCRIBED IH TABLE 3.

2 ~

t'E4N A'ID RANGE BASED UPOh DETECTABLE HEASUREHENTS ONLY FRACTION OF DETECTABLE HEASUREHENTS AT SPECIFIED LOCAT IS INDICATED IN PARENTHESES (F) ~

TABLE 13 RADIOACTIVITY IN NELL NATER PCI/L O.G37 SO/L hANE OF F AC ILITY 98QhHS EEBBI LOCATICH OF FACILITY LI5ESIQHE

-- hL8Q8~~-

DOCKET NO ~ S9=2S242694220 REPORTING PERIOD

],'Pg$

TYPE AHD TOTAL FIUNBER OF ANALYSIS PERFORNED LONER LIPIT Of DETECTICM (LLD)

SEE UQIE I ALL INDICATCR LOCATIONS BEAN (F)

RANGE SEE 5QIE 2

LQt'SIIQU bIId UIQUESI bUB!lSL LEST HANE NEAH ( F)

DISTANCE AKD DIRECTION RANGE SEE ttQIE 2

CONTROL LOCATIONS NEAH (F)

RANGE SEE 5QIE 2

NU ISE R Cc NONo JTIHE REPORTED I<<EASUPihiNTS GANNA (GELI)

Z6 K-40 8 I-214 PB-214 PB-212 AC-228 SR 89 SR 9.0 TR ITIUN NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB 1.00E+01 2

OOE+00 3 '0E+02 Z.42E+C1(

2/'3) 6 63E+GG -

4 18E+01 2 '2F+01(

11/

13) 4.54E+CC -

5 17E+01 2 27E+01(

11/

13) 3 '7E+00 -

5 '48+C1 Z

05E+OG(

5/

13) 1 '2E 6 '9E+OC 76E+00(

1 /

13) 1.76E+GG -

1 76E+00 4

VALUES <LLD ANALYSIS PERFORPED 4

VALUES <LLD ANALYSIS PERFORNED 4

VALUES <LLD ANALYSIS PERFORNED Bfh NELL r6 0

GZ NILES N

BFN bELL r6 C.02 NILES N

BFN NELI. A6 0.02 WILES w

BFH

<<ELL r6 O.GZ IILES SFN NELL r5 0 02 ".ILES N

42E+01 (

6 63E+00 2 '2E+01(

4 54E+00 2.27E+01(

3 '77E+00 2 '5~+00(

1 12E-01 1 '6iy00(

1 76E+00 2/

13) 4 18E'+G1 11/

13) 5 17E+01 11/

13) 04E+G1 5/

13) 6 19E+GO 1/

13) 1.76E+00 13 VALVES <LLD 2 ~ 766+02(

13/

13) 1 80E+01 6 42E+02 2.68E+02(

13/

13) 1 '6E+01 -

6 '1E>02 13 VALUES <LLD 13 VALUES <LLD 4

VALUES <LLD 4

VALUES <LLD 4

VALVES <LLD NOTE:

1 ~

NO>INAL LONER LI.".IT CF DETECTION (LLD) AS DESCRIBED IH TABLE 3 ~

NOTE:

Z ~

NEAH AHD RANGE BASED UPON DETECTABLE MEASURENENTS ONLY~

FRACTION OF DETECTASLE NEASURENENTS AT SPECIFIED LOC4TIONS IS INDICATED IN PARENTHESES (F) ~

TABLc 14 MANE OF FACILITY 9EQMbl EEBPI LOCATION Of fAC ILITY LIPvEEIQBE RADIOACTIVITY IM PUBLIC dATER SUPPLY PCI/L - 0.037 BD/L BLBQBLB DOCKET NO 50:252c250422D--------

REPORTIMGi PERIOD J/QD TYPE AND TOTAL NUi(BER OF ANALYSIS PERFORNED GPOSS BETA 101 GAMMA (GELI) 101 LONER LIHIT OF DETECTION (LLD)

SEE BQIE 1

2 OOE+00 ALL INDICATOR LCCAT IOMS NEAM (F)

RANGE EEE BQIE 2

3 36E+00(

52/

75) 2 OOE+OC - 7 48E+OG LQEBIIQU htIIH 5JSUEEI BIt5IIBL LEBU NAME PEAN (F)

DISTANCE AND DIRECTION RANGE GEE ItQIE 2 CHAMPION PAPER 3 46E+00(

43/

C9)

TRH 282.6 2.24E+00 -

7 CSE+00 CONTROL LOCATIONS MEAN (F)

RANGE 5EE HQIE 2

3.17E+00(

2.17E+00 6 25E+00 NU."BcR OF NONROUTINE REPORTED NEASUREHENTS K-40 BI-214 PB-21 4 PB-212 TL-208 AC-ZZ8 SR 89 SR 90 Tci IT IUv 20 2C 2C MOT ESTAB NOT ESTAB NOT ESTAB MOT ESTAB VOT ESTAB NOT ESTAB 1.00E+01 2.0Gc+OC 3 'CE+02 Z ~ 05E+C1(

3/

75) 1 07E+C1 -

3 67E+01 6.9CE+GC(

34/

75) 2 ZOE 4.93E+01 6

19E+OC(

27/

75) 3 '8E-01 4 '0E+01 1.76E+OG(

23/

75) 5 90E-OZ -

6 66E+OC 7 39E-C1(

3/

75) 1 13c 1 'cE+OC 6 OSE+00(

9/

75) 1 3SE+OG -

2 17E+01 12 VALUES <LLD ANALYSIS PERFORvEi) 12 VALUES <LLD ANALYSIS PEPFORI ED 12 VALUES <LLD ANALYSIS PERFORNED CHAMPION PAPEc TRN 282 6

CHAHPION PAPcR TRH 282.6 CHAHP ION PAPER TRN 282 6

WHEELER DAHw AL TRH 274.9 CHANPIOM PAPER TRN 282.6 CHAHPI ON PA~ER TRN 282.6

2. 37E+01 (

2/

C9) 1 07E+01 -

3 ~ 67E+01 8 02E+00(

20/

49) 2v ZOE C 93E+01 7 37E+00(

17/

49) 4.00E C.90c+C1 Z-56F+00(

3/

13) 5 9GE 3.81E+CO 7.39E-01(

3/

49) 1 '3E 1.22E+00 6.09E+00(

8/

49) 1.38E+GO -

2 '7E+01 C 36E+01(

1/

25) 4 36E+01 -

4 36E+G1 5 09E+00(

11/

26) 2 '9E 1 '5E+01 3.41E+00(

9/

26) 1 '7E 01 -

9 '0E>00 1.26E+00(

9/

25) 1 65E-01 2 '6c+00 1

9CE+00(

2/

26) 1-01E+00 79E+"-0 6 AD OBE+00(

6/

26) 3 81E+00 8 05E+00 8

VALUES <LLD 8

VALVES <LLD VALUES <LLO NOTE:

1 NCNINAL LONER LIHIT CF DETECTION (LLD)

AS DESCRIBED IN TABLE 3 NOTc:

2 HEAli AhD RANGF BASED UPOh DETcCTABLE MEASUREMENTS ONLY FRACTION OF DET CTA<LE HEASURENENTS AT Sc CIFI.D LOCATI "NS IS INDICATED IM PARENTHESES (F).

Table 15 ENVIRONMENTAL GAMMA RADIATION LEVELS 31 Average External Gamma Radiation Levels at Various Distances from Browns Ferry Nuclear Plant for Each Quarter -

1986 mR/Quarter'istance Miles Avera e External Gamma Radiation Levels'st uarter 4th uarter 0-1 1-2 2-4 4-6

>6

Average, 0-2 miles (onsite)

Average,

>2 miles (offsi te) 19.3

'.0 17.0 -'.3 15.6 1.8 15.9

'.6 15.3 1.7 18.7

'15.7 '.6 16.9 2.7 15.4 -'.7 14.8 '.2 14.3 '.5 14.5

~ 5 16.5 -'.5 14.5 -'.4 19.4 '.1 16.2 '.4 14.8 '.2 14.5 '.5 13.9 -'.2 18.6 '.4 14.4 -'.4 19.7 '.4 17.9 2.0 17..2 1.8 17.0 '.7 16.0 '.5 I

19.2

'.3 16.7

'.7 a.

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

b.

Averages of the individual measurements in the sec

+1 standard deviation of the set.

MA~E OF FAC ILITY /Egad(bf fELHI LOCATION OF FACILITY LJQE$ IggE TABLE RADIOACTIVITY IN CABBAGE PCI/KG 0 ~ 037 BO/KG (LET JEIGHT)

DOCKET NO. gg-Zfgc2$ ggZPQ aaaabab RcPORTIMc PER IvD ICEk TYPE AMO TOTAL NUMBER OF ANALYSIS PERFORMED GROSS BcT4 c

GAMMA (GELI) 2 K-40 BI-214 PB-21~

c'B 21 c LOVER LIMIT OF DETECTION (LLD)

BEE HQIE I 2.50E+01 NOT ESTAB MOT ESTAB MOT ESTA8 MOT ESTAB ALL INDICATOR LOCATIONS MEAN (F)

RANGE SEE BQIE 2

3.93E+03 (

1/

1)

~.93E+C3 -

3 9 ciG'

~ 6SE+03(

1/

1) 1 ~ 68E>C3 -

1 ~ 68E+03 VALUcS <LLD 1

VALUES <LLD 2.42E-G1(

1/

1) 2 42E 2 42E-C1 7 PILES NMv 1.68E403(

1/

1) 1 ~ 68E>03 -

1 68E+C3 7 0'ILcS NMM 2 'cE-01(

1/

1) 2 '2E-01 2 '2E-31 l.QCBIIQ5 i(IIM llIGllEEI-BBllll&L-5Ebtt NAY="

MEAN (F)

DISTANCE AND DIRECT IBM R4NGE iEE UQIE 2

7 PI'S NMV 3 938+03(

1/

1) 3 93Ep03 - 3.93E+C3 CONTROL LOCATIONS MEAN (F)

RANGE GEE UQIE 2

3 22Ec03(

1/

1) 3 22E+03 - 3.22E+03 1.38E+03(

1/

1) 1.38E+03 -

1 38E+03 5 26E+00(

1/

1) 5.26E>00 -

5 26E+00 4CE+00(

1/

1) 3 40E<00 - 3 '0E400 4 24E-01(

1/

1) 4.24E 4.24E-01 NUMBER OF NONROUTINE REPORTED MEASURENEMTS NOT=:

NOTE:

1 MO IhAL LOVER LIMIIT OF DETECTION (LLD) AS DESCRIBED IN TABLE 3 2 ~

MEA:. AND RANGE BiASi =O UPON DETEC TABLc M

ASUR=MEMTS ONLY FRACTION OF DETECTABLc MEASUREMENTS 4T SPECIFIED LOCATIOMS IS INDICATED IM PARENTHESES (F) ~

TABLc 17 RADIOACTIVITY IN CORN PCI/KG - 0 03'7 80/KG (lET Nc IGHT) hAME Cc FACILITY 38QBUS EERBI LOCATION OF cACILITY LJ(IESIQQE bLbQbdb os SQ=U2r.26Q42 0

REPORTING PERIOD I'PEO TYPE AND TOTAL NUMBER OF ANALYSIS PERFORMED GROSS BETA 2

GAMMA (GELI) 2 K-40 8 I-21 4 PB-214 PB-212 TL-208 LOMER LI~IT OF DETECTION (LLD)

SEE BQIE 1

2 SCE+G1 NOT ESTAB NOT ESTAB NOT ESTAB NOT cSTAB NOT ES>4B ALL INDICATOR LOCATIONS MEAN (F)

RANGE SEE BQIE 2

3.C2E+C3(

1/

1) 3.02E+C3 -

3 02E+03 2 ~ C3E+G3(

1/

1) 7 PILES NNh 2 03E+03 -

2 '3E+03 1

VALUES <LLD 2 G3E>03(

1/

1) 2 03E+0

- 2i03E+03 1

VALUES <LLD 1

VALUES <LLD 1

VALUES <LLD LQHIIQ8 HII~ BIQUESI bUtlQbL P~Eb8 NAME MEAN (F)

D.STAVCE AND DIRECTION RAVGc SEE BQIE 2

7 MILES NVIII 3.02E+03(

1/

1) 3.02E+03 -

3 02E+03 CONTROL LOCATI04S MEAV (F)

PANG=

SEE BQIE 2

76E>03(

1/

1) 2.76E+03 -

2 '6E+03 1

81F+03(

1/

1) 1 ~ 81E+03 -

1 ~ 81E+03 2 71E+00(

1/

1) 2 71E+OC -

2 ~ 71E+00 2.93Ei00(

1 /

1) 2 93c+00 -

2 '3E+00 2.3CEi00(

1/

1) 2 'CE+00 -

2 '0E+OC 1 '8c+OC(

1/

1) 1 68E+00 -

1 '8E+00 NUVBER OF NOVROUT IN =

REPCRTEcD MEASUREMENTS NOTE:

1 NOMINAL LOMER LIMIT OF DETECTION (LLD)

AS DESCRIBED IH TABLE 3 ~

NOTc.

2 ~

MEAN AVD RANGE BASED UPOh DETcCTABLE MEASUREMENTS OhLY ~

FRACTION OF DETECTABLc MEASUREMENTS AT SPECIFIED LOCATIGNS IS INDICATED IN oARENTHESES (F) ~

NANE OF FACILITY QBQllbg EEBBI LOCATION OF FACILITY LIQEEZQgE TABLE 18 RADIOACTIVITY Ih GREEN BEANS PCI/KG -

0 037 BO/KG (NET wEIGHT) 8l.898L8 DOCKET NO 29 2224'(l04?9(l REPORTIHG PERIOD 12BR TYPE AND TOTAL NUNBER OF ANALYSIS PERFORNED GROSS BETA 2

GAHNA (GELI) 2 K-40 PB" 212 AC-228 LOWER LI1.IT OF DETECTION (LLD)

SEE BQIE 1

Z ~ 50E+01 NOT ESTAB NOT ESTAB 1

50E+01 2 51E+03(

2 51E+03 2 66E+CC(

Z 66E+CO 1

52E+01(

1.5ZE401 1/

1) 2 51E>03 1/

1) 2 66E+OC 1/

1) 1.5ZE+01 ALL INDICATOR lCCATIONS NEAN (F)

RANGE SEE HQIE 2

5 89E+03(

1/

1) 89E403 -

5 89E+03 7 NILcS NNM 7 NILES NNii NILE5 HNN 2 '1E+03(

2 51E>03 2 66E+00(

2 '6E+00 1.52E+01(

1 52E+01 1/

1) 2 51E+03 1/

1) 2.66E+00 1/

1) 1 52E+C1 l,QEBIIQ8 ltIIU UIQBEBI htIBU8L "E88 NAHE NEAN (F)

DISTANCE AND DIRECTION RANGE SEE BQIE 2

7 NILES HNN 5 89E+03(

1/

1) 5 89E+C3 - 5.89E+03 CONTROL LOCATIONS NEAN (F)

PANGE, SEE 5QIE 2

4 39E+03(

1/

1)

4. 39E+03 -

4 39E+03 2.03E+03(

1/

1) 2 03E>D3 2 03E+03 1

VAlUES

<LLD 1

VALUES <LLD NUNBc P.

OF NOHROUTINE REPORTED NcASURENENTS NOTE NOTE' MONINAL LOWER LINIT OF DETECTION (LLD) AS DESCRIBED IN TABLE 3 ~

2 ~

YEAH AND RANGE BASED UPON DETcCTABLc NEASURENENTS ONLY ~

FRACTION OF DETECTABLE NEASURENENTS AT SPcCIF IED LOCATICNS IS INDICATED IN PARENTHESES (F).

TABLE 19 RADIOACTIVITY IN APPLES PC I/KG 0 ~ 037 9R/KG

('>>ET MT)

NAME OF FACILITY QBQhb5EEBBX LOCATION OF FACILITY Lg>EEIQQE 4L49554

'Q=222cskQc225 REPORTING >E>I)D ],Pg$

TYPE ANO TOTAL NUBBER OF ANALYSIS PERFORMED GROSS Bc T'A c

GANNA (GEL!)

2 K-43 "I-214 PB-214 PB-212 AC-228 LONER LIYIT OF DETECTION (LLO)

GEE UQIE 1

Z.50E+01 NOT ESTAF NCT ESTAB VCT ESTAB NOT ESTAB NOT ESTAB 8.70E+C2(

8 '0E+02 3 93E+"G(

3 93E+00 6 43F+CC(

6 43E+OC 4 88E-01(

C.88c-C1 S

94E+GG(

8.94E+OC-1/

1) 8 70E+02 1/

1) 93E+OG 1/

1) 6 '3E+OG 1/

1) 4 88E-01 1/

1) 8.ANCE+00 ALL I'VDICATOR LOCATIONS BEAN (F)

RANGE SEE UQIE 2

2 10E+03(

1/

1) 2 10E>G3 -

2 1CE+G3 7 PILES NN>>

7 <<ILES 7 PILES NN>>

7 YILE5 VNK 7 NILES NNh 8 70E+02(

8 70E+02 3.93E+00(

3.93E+00 6

C3E+OC(

6 43E+00 4.88E-01(

C BSE-C1 8 94E+00(

8 94E+00 1/

1) 8 70E+C2 1/

1) 3 938+00 1/

1) 6'3E+00 1/

1)

C.SSE-G1 1/

1) 8.9CE+CO LQS SIIQS NIId "I~BE%I eBUQAL "E41 NAB FEAh (F)

PISTAhCE AhO DIRECTION RANGE EEE 8QIE 2

7 t ILc5 NN'l 2

10E+03 (

1/

1) 2.10E+03 -

2 10E+C3 CONTROL LOCATIONS BEAN (F)

RANGE SEE BQIE 1 ~ 49E+03 (

1/

1) 49F+C3 1.49E+03 7 ~ 61E~ ic(

1/

1) 7 61E+02 - 7 ~ 61E+02 1

VALUES <LLO 1

VALUES <LLO VALUES <LLD 1

VALUES <LLO NUVBcR c

NONROUTIiVE RE>CRTcD VEASURcHchTS NOTE:

1 ~

NC".IVAL LOVER Lit!IT OF DETECTION (LLD) AS OESCRIBEO IV TABLE 3 ~

NOTc 2

NEAN AVO RANGE BASED-UPON DETECTABL" HEASURENcNTS ONLY ~

FRACTION OF DETECTABLE'EASURE>ENTS AT SPECIFIED LOCATIONS iS INDICATEO IN PARcNTHESES (F) ~

TABLE 20 RADIOACTIVITY IN POTATOES PCI/KG - 0 037 BQ/KG (MET MEIGHF)

NANt OF F ACILITY QQQgtlg fEgg/

LOCATION OF FACILITY LIQK$1gllK 8L898tl8 NO ~ 59=222c2k~c2'2D REPORTING PERIOD TY>E AND TOTAL NUNBER OF ANALYSIS PERFORNED GROSS BETA GANJA (Gci I) 2 C S-137 K-4i)

BI-214

>8 Pa-212 AC-228 LOitER LIMIT OF DE T E CT ION (LLD)

SEE t!QIE 1 2

50E+01

5. OOE F00 NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB 1 '0E+01 ALL INDICATOR LOCATIONS MEAN (F)

RANGE EEE HQIE 2

6 97E+C3(

1/

1) 6.97E+03 -

6 97E<03 1

VALUES <LLD 3 88E+03(

1/

1) 3 88E>03 - A BBE+03 7

OOE+OC(

1/

1) 7 CCE+OC 7

CCE+OC 8 '9E-01(

1/

1) 8+39E-C1 - 8.39E-G1 1

VALUES <LLD 1

VALUES <LLD BROOKS FARY 7

0 NILES NNM BROOKS FARt'

~ 0 PILES NNM BROOKS FARt'

~ 0 PILES NNM BROOKS FARY 7 0 PILES NNM 3.88E+03(

3.88E+03 7.GGE+OG(

7.GOE+00 5 ~ 39E-01(

8.39E-01 1/

1) 3 ~ 88EIC3 1/

1) 7.CCE+CC 1/

1) 8 39t-C1 LQE8IIOll HIIll UIEllEKI 8iUU8!

5E4h NANE NEAN (F)

DISTANCE AND DIRECTION RANGc SEK (tOIE 2

6 '7E+03(

1/

1) 6.97E>03 - 6.97E+C3 COVTROL LOCATIONS NEAN (F)

RANGE SEE llQIE 2 7 2cE+03(

1/

1) 7 23E+03 - 7.23E+03 18E+00(

1/

1) 9 ~ 1EE+00 - 9.18E+00 3 37E+03(

1/

1) 3.37E+03 -

3 '7E+03 6.12F-01 (

1/

1) 6 ~ 12E "01 - (

I 2E" G1 1

VALUES <LLD 2 94E-01 (

1/

1) 2 '4E 2.94E-01 2 '7E+01(

1/

1) 2 ~ 17E+01 -

2 ~ 17E>01 NUNBER OF NONROUTIVE REPORTED NEASURENENTS NOTE:

1 VC~INAL LOMEP LINIT CF DETECTION (LLD) AS DcSCRIBED IN TA LE 3

NOTE:

2 PEAN AHD RANGE BASED UPON DETECTABLE NEASUREPENTS ONLY FRACTION OF DETECTABLE NEASURENENTS AT SP CIFIFD LOCATIOt'S IS INDICATED IN PARENTHESES (F) ~

RANE OF FACILITY QBQltBS EEBBI LOCATION OF FACILITY QI5ESIQBE TABLE 2l RADIOACTIVITY Ih BEEF

~CI/KG -

0 0~7 vC/KG (MET MEIGHT) 8L898L8 DocK=T No. SQ-2S2c26Qc22('l-REPCRTING PERIOD I(CS TYPE AND TOTAL NU'lBER OF ANALYSIS PERFORMED GROSS BETA 2

GANNA (GELI) 2 K-40 BI-214

~B-214 LOllER LI"IT OF DETECTION (LLD)

SEE HQIE I 2.50c+01 MOT ESTAB NOT ESTAB NOT cSTAB ALL INDICATOR LOCATIONS NEA'l (F)

RANGE SEE SQIE 2

5 '3E+03(

1/

1) 5.73E+03 5 73E+03 2 53E+03(

1/

1) 2.53E+C3 -

2 53E+03 1

VALUES <LLD 1

VALUES <LLD LQE8IIQH BJIN UIGUESI 85BM8L ~E89 MANE l'EAN (F)

DISTANCE

'ND DIRECTION RANGc SEE HQIE 2

LOONEY FARY 5 73E+03(

1/

1) 5.75 NILES EhE 5 ~ 73E+03 - 5.73E+03 LOONEY FARY 2.538+03(

1/

1) 5.75 PILES E'E 2 53E+03 -

2 53E+03 CONTROL LOCATIONS "lEAM (F)

RAhGE SEE HQIE 2

2.71E+03(

1/

1) 2 71E>03 2 '1E+03 1 '2E+03(

1/

1) 1+02E+03 - 1+02E+03 2 41E+00(

1/

1) 2.41E+00 -

2 '1Et00 2 36F+00(

1/

1) 2 '6c+00 -

2 36E+00 NUNB=R OF NONROUT INc REPORTED NEASURENcNTS NOTE:

1 ~

NONINAL LOllER LIl".IT OF DETECTION (LLD) AS DESCRIBED IN TABLE 3 ~

NOT=:

2 NEAh AND RANGc dASED UPON DETECTAcLc NcASUREPEhTS ONLY~

FRACTION OF DETcCTABLE NEASURENENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) ~

TABLE 22 RADIOACTIVITY IN TCNATOES PC I/kG - 0.037 BQ/KG (la ET WEIGHT)

MANE OF FACILITY QEQggg fE8E9 LOCATION OF FACILITY CIQEQIQQE Pl $ 98L'B DOCkcT 40-59=22242('tQ42

('t RePORTING PERIOD

],Pg$

TYPE AND TO~AL hu~aER OF AHAI.YSIS PERFORNED GROSS BETA 2

GAMMA (

ELI)

2 k-40 BI 214 PB-21c LOWER LIP IT OF DETECTION (LLD)

SEE BQIE I 2>>50E+01 NOT ESTAB NOT ESTAB NOT ESTAB ALL INDICATOR LOCATIONS NEAN (F)

RANGE BEE UQIE 2

C 62E+C3(

1/

1) 4 62E+C3 -

4 '2E+03 2.61E+C3(

1/

1) 2.61E+03 - 2.61E+03 1

VALUES <LLD 1

vALUES <LLD 7 FILES NNW 2.61E+03(

\\/

1) 2 '1E+03 -

2 61E+03 LQESIIQU Slit IIQtjEKI 83bVSL t)E85 NANF MEAtJ (F)

DISTANCE AKD DIRECTIOJJ RANGE SEE HQIE 2

7 MILES NNt 6ZE+03(

1/

1) 4.62E+03 - 4.62E+J3 2 '1E+03(

2 51E+03 CSEE-01(

7.8EE-01 3.35E<00(

3.35c+00 1/

1) 9 ~ 51 e4 03 1/

1) 7 CASSE-01 1 /

1) 3.35E+00 CONTROL LOCATIONS BEAN (F)

RANGE GEE HQIE 2

C 5TE+03(

1/

1) 4 578+03 -

4 57E+03 NUNBER Oe NON oO(lI INE RcPORTED 4E4SURE'CeNTS NOTE:

'JOT c.

1

'JC".INAL LOWER LINIT OF DETECTION (LLC)

AS DESCRIBED IN TABJ.E 3

PEAJJ AND RANGE BASED UPOh DETECTABLE NEASURc."ENTS ONLY FRACTION GF DETECTABLE ttEASURENENTS AT SPECI F IED LOCCTIONS IS INDICATED IN PAREhTNESES (F)

Figure 6

Annual Average Gross Beta Activity Drinking Water (pCi/liter)

Browns Ferry Nuclear Plant

~ Indicator I Control Preoperational Phase Operational Phase Preoperational Average 68 69 70 71 72 73p 73o 74 75 76 77 78 79 80 81 82 83 84 85 86

40 24.

22 Figure' Direct Radiaticn Lovole Browne Ferry Nucl eor Plant

+

Onomato p Offoite 20.

18.

16.

14.

12 1976. 1977. 1978. 1979. 1988. 1981. 1982. 1983. 1984. 1985. 1986. 1987 Figure 8

22.

Direct Radiaticn Lovole Browne Forr y Nuclear Plont 4-Quarter Moving Average

+ Onoito p Offokto 28.

18.

16.

14.

12 1976. 1977. 1978. 1979. 1988. 1981. 1982. 1983. 1984. 1985. 1986. 1987.

26.

24 22e Figure 9

Dir ect Radiation Lovolo Watto Bar Nuclear Plant

+ Onsito p Offeito 28.

8 18.

16.

14.

12.

1976. 1977. 1978. 1979. 1988. 1981. 1982. 1983 1984. 1986. 1986. 1987.

Figure 10 26.

24.

Direct Radiation Levels Watto Bar Nuclear Plant 4-Quarter Moving Average

+ Quite p Offoito g 20.

8 18.

16.

14.

121976. 1977. 1978 1979. 1980. 1981. 1982 1983. 1984. 1985. 1986 1987.

43 Reservoir Honitorin 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.

Hater Hater 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.

Results are displayed in table 24.

Figure 12 presents a plot of the gross beta activity in surface water from 1968 through 1986.

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 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 gross beta and gamma-emitting nuclides.

The composite samples contain approx.imately 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.

An extra set of samples was taken in August.

Gamma radioactivity and Sr-89 and Sr-90 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.

44

Plankton, Net plankton (all phytoplankton and zooplankton caught with an 80-micron 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-89 and Sr-90 content.

During this reporting period, one gross

beta, one

gamma, and one strontium analysis was missed because of sample unavailability.

Four gamma and five strontium analyses could not be performed because of insufficient volume of sample available.

-Results are presented in table 29.

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-89 and Sr-90 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.

45 Table 23 SAMPLING SCHEDULE RESERVOIR MONITORING Biolo ical Sam les (Collected Semiannual 1

)

River/River Mile Tennessee 277.9 Tennessee 285.2 Tennessee 288.7 Tennessee 291.7 Tennessee 293.5 Zooplankton, Chlorophyll, Benthic t

X X

Sediment Fish'ater Samples (collected monthl

)

Tennessee 293.7 (discharge area)

Tennessee 305.0 (Control)

Tennessee 307.5 (Control) a.

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

Samples of fish are collected from Guntersville,

Hheeler, and Hilson Reservoirs.

b.

Automatic sampler.

NOTE:

An extra set of sediment samples was collected in August.

NAHE OF FACILITY QBQMHE EEBB1 LOCATION OF FACILITY LIQEEIQUE TABLE 24 RADIOACTIVITY IN SURFACE'ATER TOTAL PCI/L - 0 037 BO/L DOCKET NO ~ )9:?22cfs59c?2k REPORTING PERIOD 1$ E{j TYPE AND TOTAL NUMBER OF ANALYSIS PERFORHED GROSS BETA 39 GAMA (GELI) 39 LONER LIHIT OF DETECTION (LLD)

BEE HQIE 1

2 OOE+00 ALL INDICATOR LCCATIONS HEAN (F)

RANGE SEE BQIE

?

3o42E+CC(

26/

26) 2 03E+00 - 5.87E>OC L,QEbTIQH 'HIIB 81EBEEI 888!lbL JE88 NAHE 'EAN (F )

DISTANCE AND DIRECTION RANGE SEE HQIE

?

TRH 285 '

3 55E+00(

13/

13) 2 03E+00 -

5 87c+CO CONTROL LOCATIONS HEAN (F)

RANGE BEE HQIE

?

3 64E+00(

11/

13) 2 '5E+00 6 25E+00 NUHBER OF NONROUT INE REPORTED HEASUREHcNTS K-40 B I-214 PB-214 PB-212 SR 89 SR 90 TRIT IU<

NOT ESTAB NOT ESTAB NOT ESTAB hOT ESTAB 1 ~ OOE+01 12 '

OOE~OO 12 3 30E+02 12 26 VALUES <LLD 2 47E+00(

6/

26) 1 29E+OG -

5 40E+00 6 12E+OG(

3/

26) 6 '8E 1.45Ei01 2.24E400(

3/

26) 2 42E-C1 -

~ 86E>00 8

VALUES <LLD ANAL'YSIS PERFORHED 8

VALUES <LLD ANALYSIS PERFORHED 8

VALUES <LLD ANALYSIS PERFORPED TRN. 293 ~ 5 TRH 293 '

TRH 285.2 3.37E+00(

1 '3E+OG 8 84E+00(

3 ZOE>00 3 '5c+00(

2.63E+00 3/

13) 5 40E+CO 2/

13) 1 45E+01 2/

13)

- 3.86EiCO 4.36E+01(

1/

13) 4 36E+01 -

4 '6c+01 4.26E400(

5/

13) 2 59E 1.15E+01 3 85E+00(

6/

13) 1 27E 9 ~ 10Ei00 1

1EE+00(

4/

13) 1 65E-01 2 09E+00 4

VALUES <LLD 4

VALUES <LLD 4

VALUES <LLD NOTE:

NOT c.

1 NOH NAL LONER LIHIT OF DETECTION (LLD) AS DESCRIBFD IN TABLE 3 ~

2 HEAh AND RANGE BASED UPON DETECTABLE HEASUREPENTS OhLY FRACTION OF DETECTABLE HEASUREHENTS AT SPECIFI D LOCATIONS IS INDICATED IN PARENTHESES (F)

NAME OF FACILITY gllgggg jfBllI LOCATION OF FACILITY LILEEIQSE TABLE 25 RADIOACTIVITY IN NHITE CRAPPIE (FLESH)

PCI/G 0.037 BD/G (DRY H IGHT)

ALbgAFA DOC<ET NO ~ 59=2224209422b RFPCRTI'4G 4cRIOD IPgg TYPE AND TOTAL hURBER OF ANALYSIS PERFCR"ED GROSS SETA 6

GAMMA (GELI) 6 CS-137 K-40 BI-214 PS-214 PB-212 LONER LIMIT OF DETECTION (LLD) fff 5QIE 1

1 OOE-01 2 OOE-02

'(OT ESTAB 2 OOE-02 NOT ESTAB NOT ESTAB ALL INDICATOR LOCATIONS MEAN (F)

RANGE fff UQIE

?

3.10E+01 (

4/

4) 2 '0E+01 -

3 36E+01 1 '8E-01(

4/

4) 7 '8E-GZ -

1 47E-G1 1 '2E+C1(

4/

4) 1 38E+01 -

1 76E+01 4

VALUES <LLD 4

VALUES <LLD 4

VALUES <LLD IHEELcR RES TRM 275-349 WHEELER RES TRM 275-349 1 'l1E-01(

2/

2) 7 48E 1 47E-01 1 '7E+01(

2/

2) 1 38E+01 -

1 76E+01

!.QEbIIQB I(III BJQUEGI bBUUbl Lfbb NAME MEAN (F)

DISTANCE AND DIRECTION RANGE SEE 9QIE 2

MILSON RESERVOIR 3 ~ 15E+01(

2/

2)

TRM 259-275 2 93E+01 -

3 36E+01 CONTROL LOCATIONS MEAN (F)

RANGc Eff BQIE 2

3.28E+01(

2/

2) 3.06i+01 - 3+50E+01 7.BEE-CZ(

2/

2) 4 86E 1 09E-01 1.60E+01(

2/

2) 1 50E+01 -

1 '0E+01 3.64E-OZ(

1/

2) 3.64E 3 64E-OZ 2 50E-02(

1/

2) 2.50c 2.50E-OZ 3 OCE-04(

1/

2) 3 OCr.

04 3

OOE 04 NUMBER OF NDNROUTI!4E REPORTED McASURcMENT-NOTE:

1.

NOMINAL LONER LIMIT OF DETECTION (LLD) AS DESCRIBED IN TABL 3 ~

NOTE.

2

<EAN AND RANGE BASED UPON DETECTABLE MEASUREi ENTS ONLY FRACTION 0F DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIOhS IS INDICATED IN PARENTHESES (F) ~

TABLE, 26 RADIOACTIVITY IN SNALL)10UTH BUFFALO (FLESH)

PCI/G -

0 ~ 037 BD/G (DRY HEIGHT)

RANE OF FACILITY QEQjfhE EEjjgI LOCATION OF FACILITY LIQEQIQ5E BLBQBLB DOCKET NO.

10=252c2BQc22B REPORTING PERIOD TYoE AND TOTAL NUNBER OF ANALYSIS PERFORNED GROSS BETA 6

GAMBA (GELI) 6 CS-137 K-40 8 I-214 oB-Z1C PB-212 LOWER LINIT OF DETECTION (LLD)

SEE BQIE 1

1.00E"01 2.00E-02 NOT ESTAB 2

OOE-02 NOT ESTAB NOT ESTAB 2.eeE-02(

2 66E-02 1.01E+01(

8 07E+GC 1 ~ 54E-01 (

1 '48-01 8 808-03(

8.8GE-G3 9 '0E-03(

9 10E-03 2/

4) 3 09E-02 4/

4) 1.39E+01 1/

4) 1 54E-C1 1/

4) 6.80E-03 1/

4) 9 'GE-03 ALL INDICATOR LOCATIONS NEAN (F)

RANGE DEE HQIE 2 2.04E+01(

4/

C) 1 '9E+01 -

2 '4E+01 WHEELER RES TRP. 275-349 WHEELER RES TRN 275-349 WILSON RESERVOIR TRN 259-Z75 WILSON RESERVCIR TR." 259-275 WILSON RESERVOIR TRll 259-275 3.09E-02(

1/

2) 3.09E-OZ - 3.09E-02 1.15E+01(

2/

2) 8 99E+OG - 1.39E+01 1 54E-01(

1/

2) 1 54E"01 -

1 '4E-01 8 80E-03(

1/

2) 8.80E 8.8GE-C3 9.10E-03(

1/

2) 9 10E 9.10E-03 l.QSBIIQB l(IIG OIQjlESI BBBllBL LEBU NANE NEAN (F)

DISTANCE AND DIRECTION RANGE SEE UQIE ?

WHEELER RES 2 '2E+01(

2/

2)

TRN 275-349 1.90E+01 - 2.54E+01 CONTROL LOCATIONS NEAN (F)

RANGE BEE BQIE 2

1 87E+01 (

2/

2) 1 ~ 86E+01 -

1 88E+01

4. 71E-02 (

1/

2) 4 71E 4 71E-02 1 ~ GSE+01(

2/

2) 9 '6E+00 1 'CE+01 2

VALUES <LLD 2

VALUES <LLD 5 70E-03(

1/

2) 5 70E-03 5.70E-03 NU'lBER OF NONROUTINE REPORTED NEASURENENTS NOTE:

1 i"FINAL LO'WER LI lIT OF DETECTION (LLD) AS DESCRIBED IN TABLE 3e NOTE:

2

"= CV AND RANGE BASED UPON DETECTABLE NEASUREYENTS ONLY'RACTION OF DETECTABLE MEASURE"ENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)

TABLE 27 RADIOACTIVITY IN SPALLHOUTH BUFFALO (VHOLc)

PC I/O - 0 037 8

/G (DRY HE!CHT)

NAtlE OF FACILITY QBQllHS EEBBI-LOCATION OF FACILITY LItlESIQUE aLAQ8L8 DOC<<T << ~

SQ=2S2426Q422(t REPORT

'tG >EcIOD 1PB{'t TYPE AND TOTAL NUHBER OF 4NALYSIS PERFORHED GROSS SET4 GANJA (CELI)

CS-137 c;-40 PS-214 PB-212 LO'MF R L IH IT OF DETECTION (LLD)

SEE 5QIE 1

1 OOE-G1 2 OOE-32 NOT ESTAB "tOT ESTAB NOT ESTAB ALL INDICATOR LCCAT IONS HEAN (F)

RANGE SEE BQIE 2

1 78E+C1 (

4/

4) 1 34E+01 -

2 11E+C1 2 20E-02(

1/

4) 2.20E-G2 -

2 2CE-02 OBE+OC(

4/

4) 5 75E+00 - 7 '9E+OC 2 1SE-02(

3/

4) 3 90E 4 33E-02 1 19E-02(

3/

4) 4 30E 1 94E-02 WILSON RESERVCIR TRH 259-275 WILSON REScRVOIR TRH 259-275 HILSO4 RESERVOIR TRtl 259-275 WHEELER RES TRH 275-349 2 20E-02(

2 20E-02 7.3OE+00(

6 61E+OG 3 07E-02(

1 B1E-02 1 94E-02(

1 94E-OZ 1/

2) 2.20E-C2 2/

2) 7 99E+00 2/

2) 4 33E-C2 1/

2) 1 94c-G2 LQSBIIQlI ltIIU tlIQUESI 88tlM8!

BE8ll NAVE VEAN (F)

DISTAVCE AND D IRcCT ION RAttGE cE UQIE 2

1 89E+01 (

Zl 2) 1 67E+C1 - 2.11E+C1 CONTROL LOCATIONS HEAN (F)

RANGE SEE tlQIE 2

1 55E+01 (

Zl 2)

OZE+01 -

2 09E+01 2 59E-02(

2/

2) 2.51E 2.65E-02 7.3CE+00(

2/

2) 6 '9c+00 9 '2E+00 6 'Cc-03(

1/

2) 6 70E 6.70E-03 2

VALUES <LLD NUHSER OF NONROUTINE REPCRTcD VEASUREHEVTS NOTE.

1 ~

NC<INAL LONER LIHIT OF DETECTION (Ll.D)

AS DESCRIScD IN TABLE 3

NOTE:

2 YEAN AND RANGE BASED UPON DETECTABLE HEASUREH NTS ONLY FRACTION OF DETECTABLE HEASUREHENTS AT SPECIFIED L CATIONS IS INDICATED IN PARENTHES S (F) ~

NAME OF FACILITY QBQllBS-EEBBI LOCATION OF FACILITY LI5ESIQBE TABLE 28 RADIOACTIVITY Ih SEDIMENT PCI/O -

G C37 BQ/G (DRY HEIGHT)

Al bQbtlb DOCt(ET NO S9=252c269c22(?

REPORTING PERIOD 225t)

T YPE AND TOTAL NU"lBER OF ANALYSIS Pc R FORMED PB-212 RA-226 Rf-

~

~

'i-7 TL-ZCS AC-228 PA 34'OWER LIMIT OF DETECTION (LLD)

SEE llQIE 1 1

OOE-02 8

OOE-02 2.00E-02 NOT ESTAB 7 ~ OGE-02 1

GGE-01 NOT ESTAB HOT ESTAB NOT ESTAB NOT eSTAB NOT ESTAB 2 ~ OGE-02 6

OOE-02 VOT ESTAB SR 89 SR 1

50E+00 12 1

5CE-01 1Z GAMMA (GELI) 12 C 0-60 C S-134 CS-137 K-40 9 I-214 BI-212 PB-214 ALL INDICATOR LOCATIONS MEAN (F)

RANGE SEE HQIE 2

1 '5E-C1(

5 84E-02 1

C2E-C1(

8 86E-02 1 '4E+00(

6.96E-G1 1 '8E+01(

17E+01 1 58E+00(

1 C7E+GC 1

91E<OC(

1 '7E+00 1

71E+CC(

1 '6E+CO 1

66E+GG(

1 24E+GG-68E+00(

1 38E>00 1

93E+OG(

1.62E+CG 9

VALUES 9/

9) 2-28E-01 3/

9) 1.21E-01 9/

9) 1.97E+GC 9/

9) 1 75E+01 9/

9) 2.035+OC 9/

9) 2 '1E+00 9/

9) 2 26E+OC 9/

9) 2 03E+OC 6/

9) 2 '3E>GC 5/

9) 2 54E+GC

<LLD 5 94E-01(

9/

9) 4 57E 7 GSE-01 1.65E+00(

9/

9) 1.26E+00 -

1 82E+GC 7 58E+CC(

1/

9) 7 58E+OC -

7 58E+GC 9

VALUES <LLD ANALYSIS PERFORt'cD 2.47E-C1(

4/

9) 1 '1E 3 '6c-01 TRH 293.7 BFN DISCHARGE TRM 288 '8 TRM 288.78 TRM 288 78 TRtl 277'8 TRH 293 '

BFN DISCHARGE TRH 277.98 TRM 293 F 7 BFN DISCHARGE TRM 277 98 TRtl 277'8 TRH 277'8 TRM 288.78 TRH 293 '

eFN DISCHARGE TRM 277 98 1

39E-01 (

1 66 E-01 1.21c-01(

1.21E-01 1.22E+00(

6.95E-01 I 50E+01(

1 '9E+01 1.51E+00(

1 '7E~GG 2.09E+GG(

1.68E+00 1.76E+00(

1 16E+00 1.'70E+00(

1 61E+00 1 8SE+00(

1.72E+00 2 OSE+00(

Z.CSE+00 6 06E-01(

4 57E-01 1.73E+00(

1.62E+00 7.58E+GG(

7 5SE+00

=2 '6E-01(

2 86E-01 3/

3) 2.00E-01 1/

>)

1 21E-01 3/

3) 1.97E+00 3/

3) 1 ~ 75E+01 3/

3) 2.03E+OC 3/

3) 2.71eqCO 3/

3) 2.26E+CC 3/

3) 1 '6E+CO 2/

3) 2 '3E+CG 1/

3)

Z ~ CSE+CC 3/

3) 7.08E-01 3/

3) 1.82E+CO 1/

3) 7 '8E+00 1 /

3) 2 86E-01 2 18E-02(

2/

3) 1.89E 2.47E-"2 3

VALUES <LLD 3.25E"01(

2 '8E-01 1.22E+G1(

1 ~ 10E+01 1.09E+00(

9 85E-01 1.36E+00(

1.06E+00 1 '1E+00(

1 07E+00 1

24E+00(

1 ~ 1 5 E+00 1

09E+00(

9 '5E-01 1.36i+00(

1 ~ 19c+OG 1 ~ 4GE-01 (

1 4CE 01 4.23E-01(

3.88E-01 1

27E+00(

1 '5E>00 7cE+00(

3 ~ 79E+OG-3 VALUE 3/

3) 4 '6c-01 3/

3) 1 29E+01 3/

3) 1 '8E+CC 3/

3) 65E+00 3/

3) 1.29c+0 3/

3) 1 '8E+00 3/

3) 1 18E~C3 2/

3) 1 53E+00 1/

3) 1 '0c-01 3/

3) 4 89E-01 3/

3) 1 '3ei00 1/

3) 3 '9E+GG S

<LLD

2. 48 E-01 (

1/

3)

Zo48E 2 '8E-01 CONTROL l.QfbIIQ5 lfIILJ llIQBESI bttB!lbl. LEbtl LOCATIONS NAME MEAN (F)

MEAN (F)

DISTANCE Ahn.DIRECTION RANGE RANGE SEE HQIE 2

SEE llQIE 2 NU'lBFR OF NONROUTINc REPORTED MEASUREMENTS VGT=:

NOTE-1 NOMINAL LOMER LIMIT OF DETECTION (LLD) AS DESCRIBED IN TABLE 3

2 MEAN AND RANGE BASED UPON DETECTABLE MEASUREMENTS ONLY ~

FRACTION OF IS INDICATED IN PARENTHESES (F) ~

DETECTABLE MEASUREMF VTS AT SPECIFIED LOCATIONS

MANE OF FACILITY QEQlf5S EESBI LOCATION OF FACILITY LI5ESIQBE TABLE 29 RADIOACTIVITY IN PLANKTON (SAMPLE 1)

PCI/O - 0<<037 BO/G (DRY NEIGHT)

Bt.89858 DOCKET NO XQ:ZXRcZBQc225 REPORTING PERIOD I'R55 TYPE AND TOTAL NUMBER OF ANALYSIS PERFORNED GROSS BE1'A 5

GAMMA (GELI) 1 K-40 8 I-21 4

>B-214 PB" 21 2 LONER LIPIT Of DETECTION (LLD)

SEE UQIE NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB ALL INDICATOR LOCATIONS MEAN (F)

RANGE SEE HQIE 2

8 51E+CG(

3/

3) 1 '5E+00 -

1 74E+01 LQEBIIQH )tIIU OIQUESI BHBUBL ="E88 NAME MEAN (F)

DISTANCE AND DIRECTION RANGE SEE HQIE 2

TRN 291 76 1

20E+01(

2/

2) 6 60E+00 - 1.?4E+01 8 36E+00(

8.36E+00-2 ~ 07E+00(

2.07E400 1

80E+00(

1 80E+00-2 ~ 18E-01(

2 1EE-01 1 /

1)

ST 36E+00 1/

1) 2 '7E+00 1/

1)

O BOE+00 1/

1) 2 ~ TSE-01 CONTROL LOCATIONS MEAN (F)

RANGE SEE BQIE 2

1 32 E+01 (

2/

2) 6 36E+00 - 2.00E+01 NUMBER Of NONROUTIhE REPORTFD HEASUREHENTS MOTE.

1 NOMINAL LONER LINIT Of DETECTION (LLD) AS DESCRIBED IN TABLE 3 ~

NOTE:

2 ~

BEAN AND RANGE BASED UPON DETECTABLE HEASURENENTS ONLY'RACTION OF DETECTABLE NEASURENENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F)'

NA~E OF FACILITY gggggg IEB"I LOCATIGV OF FACILITY LIQEEIQQE TAELE 30 RADIOACTIVITY IN CLAl'LiSH PCI/G - 0 ~ 037 PC/G (DRY ilEIGHT)

DOCKET NO. 50=222c26Qc22O 8L898L8 REPDRTIVG PERIOD

~Pc AND TD 4L NUMBER OF AVALYSIS PEPFOR,'lED GAllMA (GELI) 8 4

BI-214 P

PB

>1c AC-LONER LIMIT OF DETECTION (LLD) qif uQIE 1

NOT ESTAB VOT ESTAB NOT ESTAB NOT ESTAB VOT ESTAB ALL I VDICATOR LC CATI ONS MEAN (F)

RANGE SEE BQIE 2

6 01 E+OC (

2/

6) 4 '1c+CC 7 62E+Oi 1.38E+CO(

6/

6) 4 'ZE-C1 -

2 '95+CC 1.73E+OC(

6/

6) 4.36E 3 69E+OC 1 '5E-01(

3/

6) 6 '1E 2.P3E-01 6

VALUES <LLD TRM 277 98 TRY 277.98 TRM 277.98 TRM 277 98 7.62E+00(

7 62E+Cv 1

90E+00(

9 25E-01 2 56E+00(

1-43E+00 2 63E-01(

2 63E"01 1 /

2) 7.6ZE+Cv 2/

2) 2 '9E+00 2/

2) 3.69E+00 1/

2) 2 63E-01 LQE8IIQU t(IILl UIGVESI 88UQ8L 5E8h

'VANE MEAN (F)

DISTANCE AND DIRiCTION RANGE SEE HQIE 2

1. 95 E+00 (

1.95E 00 6 33E-01(

6 33E-01 7 ~ 48E-01 (

7 '8E-01 7.8SE-OZ(

7.'85E-02 os 54E-01(

c' 54E 01 1/

2) 1 '5c+00 1/

2) 6.33E-01 1/

2) 7 48E-01 1/

2) 7 85E-02 1/

2) 8 '4E-01 CONTP.OL LOCAT IUVS MEAN (F)

RANGE SEE 5QIE 2

NUMBER 0<

VONROUTINc REPORTcD MEASUREMEVTS 1 ~

NOl'INAL LONER LIPIT OF DETECTION (LLD)

AS DESCRIBED IN TABLE 3 ~

2.

YEAh AVD RANGE BASED UPON DETECTABLc MEASUREl ENTS ONLY FRA" TION OF DETECTABLE bEASURE<ENTS AT SPECIFIED LOCATIOV IS INDICATED IN PARENTHESES (F).

NAME OF FACILITY gRQ'iHS EEBSI LOCATION OF FACILITY LIUESIQHE TABLE 3l RADIOACTIVITY IN CLAM SHELL PCI/G -

G ~ 037 BO/8 (DRY NFIGHT)

BLBS8~8 DOCl(ET NO-SQ=2S2425Qc22('l REPORTING PERIOD

$ 'P "{j LOMER LIMIT OF DETCCTI 4

(LLD)

SEE BQIE 1

NOT ESTAB 5

OOE-OZ 5 COE-02 NOT ESTAB 2

OCE-02 6 COE-02 SR 89 SR 90 5.00E+OC 1

OOE+00 8

TYPE AND TOTAL NU<dER OF ANALYSIS PERFDRr.ED GAMMA (GELI) 8 l(-40 BI-214 PB-214 PB"212 TL-208 AC-228 ALL INDICATOR LOCATIONS MEAN (F)

RANGE Sff BQIE 2

4.01E-01(

1/

6)

~

4 G1E-C1 - 4.01E-01 1.56E-01(

5/

6>

8 32E-C2 -

3 58E-01 1

78E"C1(

6/

6) 1 '2E 2 '38-01 5.81C-G2(

4/

6) 2.95E 8 '58-02 4 46E-CZ(

3/

6) 3 74E 5.57E-02 3.49E-01(

3/

6) 1~78E-C1 -

4 38E-01 6

VALUES <LLD ANALYSIS PERFORMED 1

20E+00(

6/

6) 1.00E+OC -

1 62E+00 TRr 293.7 RFV DISCHARGE TRM 277. 98 TRM 277 98 TRM 288+78 TRM 288 78 TRM 288'8 4 01E-01(

4 ~ 01 E-01 58 E-01 (

3 58E-01 2.19E-01(

1~84E-01 8 '5E"02(

8 15E-02 5 '7E-02(

5.67E-02 4 '1E-01(

4 31E-01 1/

2) 4 01E-01 1/

2) 3.58E-C1 2/

2)

- '2 53E-C1 1/

2) 8.15E-02 1/

2) 5 67E-02 1/

2) 4 31E-01 TRM. 277.98 1

31 E+00 (

2/

2) 1.00E+00 1 '2E+00 LQCBZ:Qo VSru uICufSZ Bvuuai I>EBu NA III MEAN (F>

DISTANCE AND DIRECTION RANGE SEE 8QIE 2

CONTROL LOCATIONS MEAN (F)

RANGE SfE HQIE 2 2

VALUES <LLD 6 17E-OZ(, 1/

2>

6.17E 6.17C-02 6 38E-02(

1/

2) 6.38E 6 38E-02 1 12E-02(

1/

2) 1 '2E 1 '2E-02 2

VALUES <LLD 8+ZCE"02(

1/

2) 8 20E 8 20E-02 2

VALUES <LLD 1 ~ 00E+00(

1/

2) 1.00E+00 -

1 OOE+00 NUMBER OF NONROUTINE REPORTED MEASUREMENTS NOTE:

1 ~

NOl'.INAL LOVER LIl'IT GF DETECTION (LLD) AS DESCRIBED IN TABLE 3 ~

NOTE:

2 ~

MEAN AND RANGE BASED UPON DETECTAPLE MEASUREl'ENTS ONLY FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) ~

g4 Figure 11 R ESERVOIR MONITORING NETWORK Elk River 0/HEELER DAM mile 274.90 mile 277.98 Rogersville 0

mile 282.6 mile 29I.76 Athens

~mile 285.2 B.F. NUCLEAR PLANT' Champion Paper Co.

0 Cour tland le 288.78 mile 293.50 mile 293.70 mile 305.0 Decatur mile 307.52

~ - Automatic Sam er Scale of h1iles

Figure 12 Annual Average Gross Beta Activity Surface Water (pCi/liter)

Browns Ferry Nuclear Plant Preoperational Phase

~ Indicator El Control Operational Phase Preoperational Average 68 69 70 71 72 73p 73o 74 75 76 77 78*79 80 81 82 83 84 85 86

• 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 Rad1at1on Facility, Env1ronmental 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 concentrations from the corresponding control stations and appropriate preoperational and background data to determine 1nfluences from the plant.

During this report period, indications of the presence of Cs-134,

,Cs-137, and Co-60 were seen in aquatic media.

Cs-137 was identified in fish samples from both indicator and control locations, and Cs-137 and Co-60 were identified in sediment samples both upstream and downstream from the plant.

Concentrations of Cs-134 less than two times the lower limit of detection were reported in downstream sediment samples.

No increases of radioactivity have been seen in water samples.

Dose estimates were made from concentrations of radioactiv1ty found in samples of environmental media.

Media sampled

1nclude, 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 K-40 and by Sr-90 and Cs-137 which are long-lived radioisotopes found in fallout from nuclear weapons testing.

Increased levels of I-131 were reported in samples of a1r, milk, and rainwater following the accident at the Chernobyl nuclear power

~.

station.

In addition, Ru-103, Cs-137, and Cs-134 were 1dentified in air particulates, and traces of Ru-103 were found in rainwater.

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 operations 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 con]unction with preoperational monitoring programs be1ng conducted by TVA at nuclear plant construction sites upstream from Browns Ferry.

The radioactivity reported herein may be the result of fallout, fluctuations. in the existing environment, releases from other industries, or releases from BFN.

Any activ1ty which may be present as a result of plant operations does not represent a

significant contribution to the exposure of members of the public.