ML18029A462

Environ Radioactivity Levels,Annual Rept-1982. W/830519 Ltr

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)

Text

REGULATOR'f INFORMATION DISTRIBUTION SYS mrs im STE 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 ILI ATION BELVINgE, A ~ Tennessee Valley Authority 6 tvv-8 ~

RECIP ~ NAHE RECIPIENT AFFILIATION 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: IE25L COPIES RECEIVED LTR ENCL SIZE:

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

NOTESsNHSS/FCAF 1cy. 1cy NHSS/FCAF/PH.

OL ~ 06/26/73 NMSS/FCAF icy, icy NHSS/FCAF/PM, 05000260 OL;06/28/74 NHSS/FCAF icy, icy NESS/FCAF/PM ~ 05000296 OL:07/02/76 RECIPIENT COPIES REC IP IENT COPIES ID CODE/NAME, LTTR ENCL ID CODE/NAME LTTR ENCL NRR ORB2 BC 04 7 7'

,INTERNAL; ACRS . 11 AEOO 1 IE FILE 01 1 NRR/DF/EEB 08 1 1 NRR/OL/ORAB 09 1 1 NRR/OS I/HETB 2 2 10 1 1 RGN2/DRSS/EPRPB 1 1 RI"./DOAMI/MI8 1 1 EXTERNAL: LPOR 03 1 1 NRC PDR NOTES: 2 2

)OTAL NUMBER OF COPIES REQUIRED: LTTR 21 ENCL 21

~ ~

/

v '+'

'I "II,4 4@g g~fg

~~ j

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

~

1 iQ

~J r ~

U.S. Nuclear Regulatory Commission c/o Regional Administrator ~ ~w(z Region II Attention: Mr. A. L. Cunningham Suite 2900, 101 Marietta Street Atlanta, Georgia 30303

Dear Mr. Cunningham:

The enclosed report, "Environmental Radioactivity Nuclear Plane - Annual Report 1982," is furnishedLevels Brogans Ferry and use.

for your information Sincerely, E. A. Belvin, Chief Radiological Health Staff Enclosure 1 983- TVA 50'rH ANNlVERSARY An Equal Opportunity Employer

TENNESSEE VALLEYAUTHORITY ENVIRONMENTAL RADIOACTIVITY LEVELS BROWNS FERRY NUCLEAR PLANT ANNUAL REPORT " 1982 TVA/POWER/RHS RADIOLOGICALHEALTH STAFF

CONTENTS List of Tables ~ ~ ~ ~ ~ - ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 111 List of Figures. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ iv Introduction . ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

Atmospheric Monitoring ~ ~ ~ ~ ~ ~

Terrestrial Monitoring ~ I ~ ~. ~ ~, ~ 23 Reservoir Monitoring ~ ~ ~ ~ ~ ~ ~ ~ 4I Quality Control. ~ ~ ~ ~ ~ ~ ~ ~ ~ 53 Data Analysis. ~ ~ ~ ~ ~ ~ ~ ~ ~ 53 Conclusions. ~ ~ ~ ~ ~ ~ ~ ~ ~ 53

LIST OF TABLES Table 1- Environmental Radioactivity Sampling Schedule Table 2- Atmospheric and Terrestrial Monitoring Station 3

Locations - Browns Ferry Nuclear Plant 4 Table 3- Detection Capabilities for Environmental Sample Analysis Table 4- Results Obtained in Interlaboratory Comparison

.5 Program. ~ ~

Table~5- Maximum Permissible Concentrations for Nonoccupational Exposure 13 Table 6- Radioactivity in Air Filter 14 Table 7- Radioactivity in Rainwater. 15 Table 8- Radioactivity in Heavy Particle Fallout 16 Table 9- Radioactivity in Charcoal Filters 17 Table 10- Radioactivity in Milk . 26 Table,ll- Radioactivity in Vegetation 27 Table 12- Radioactivity in Soil 28 Table 13- Radioactivity in Well Water . 29 Table 14- Radioactivity in Public Water Supply. 30 Table 15- Environmental Gamma Radiation Levels 31 Table 16- Radioactivity in Corn . 32 Table 17- Radioactivity in Green Beans. 33 Table 18-

~

Radioactivity in Potatoes 34 Table 19- Radioactivity in Tomatoes 35 Table 20- Radioactivity in Turnip Greens 36 Table 21- Sampling Schedule - Reservoir Monitoring 43 Table 22- Radioactivity in Surface Water. 44 Table 23- Radioactivity in White Crappie (Flesh), 45 Table 24- Radioactivity in Smallmouth Buffalo (Flesh) 46 Table 25- Radioactivity in Smallmouth Buffalo (Whole) 47 Table 26- Radioactivity in Sediment 48 Table 27- Radioactivity in Clam Flesh 49 Table 28- Radioactivity in Clam Shell 50

'11.1

LIST OF FIGURES Figure 1 - Tennessee Valley Region 10 Figure 2 - Atmospheric and Terrestrial Monitoring Network. 18 Figure 3" - Local Monitoring Stations 19 Figure 4 TLD Locations, BFN 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 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) 39 Figure 11 - Reservoir Monitoring Network 51 Figure 12 - Annual Average Gross Beta Activity in Surface Water 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) radionuclide combinations such as 'u gamma spectroscopy were analyzed for 14 specific gamma-emitting radionuclides .and radionuclide combinations a . For these analyses, 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 the AIPHA-M least-squares

~Cs; Cs, 5Zr-Nb computer code:

Co; ~~Mn; Zn Fe

' Ce; Cr; Co; " K; and I; 'u; following radionuclides'and radionuclide combinations are quantified by Ba-La.

Table 1 ENVIRONHENTAL RADIOACTIVITYSAMPLING SGHEDDLE=

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

Station Location Filter Filter ates Failoet So I ~re statist'Ililk Water W ter Wat r d Sedieeet'oods Muscle Shoals Lawrenceburg W W M H,..

H A

A Rogersville W W H H Athens W M H A Decatur '

W W M H Courtland W W H H A Site I N W W 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 W W H H A Farm B Farm S Q Farm P ~

Q W Farm L Q W Contro Farms Onsite Well Wheeler Dam Elk River .

Tennessee River Champion Paper Co.

Various Local Farms 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 1.0 Mile (1.6 kilometers) N IM'-2 BF, North-Northeast 0.9 Mile (1.4 kilometers) NNE LM"3 BF, East-Northeast 1.0 Mile (1.4 kilometers) ENE LM-4 BF, North-Northwest;" 1.7 Miles (2.7 kilometers) NNW LM"5: BF, West-Southwest 2.5 Miles (4.0 kilometers) WSW PM;-1 BF., Rogersville,'AL. 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 ters)

(13.2 kilometers) SSE PM-4 BF,, Courtland, AL 10.5.'Miles -

(16.9 kilometers) WSW RM-1 BF, Muscle Shoals,AL.'Control)

32. 0 Miles (51. 5 kilome W RM-2 BF, Lawrenceburg, TH= 40.5 Miles (65.2 kilometers) NNW (Control)

Farm S 4.75 Miles (7.6 kilometers) N.

Farm B 7.0 Miles (11.3 kilometers) NNW Farm L. 5.0 Miles (7.0 kilometers) NE Farm T (Out of business'fter 7.0 Miles (11.3'i:lometers) ENE 1/18/82) .

Farm P 8 8 Miles (14.1 kilometers) '

Farm N (Control) 27.0 Miles (43.4 kilometers) NW Farm J (Control) 4'0.0 Miles (64.4 kilometers)

Farm C (Control) 32.0. Miles (51..5 kilometers) N Farm Ca (Control) 32.0 lliles (51.5 kilometers)

t

~ Table 3 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS A. S ecific Anal ses NOMINAL LOWER LIMIT OF. DETECTION LLD *

~J L

. Fish, t Air Vegetation Soil and clam flesh, Foods; meat, Particulates

~ci Charcoal

~C1 Fallout ct/r Water Cccttt and

~CI/

grain d

Sedidqent

~dt/ d plankton,

~dt/ dr Clam shells i

pC /C ~dr pC i/ kit poultry, Mi.lk

~Ci/I t Total a 0.4 0.01 1.5 Cross a 0. 005 2.0 0;05 0.35 0.1 0.7 Gross 8 0. 01 0.05 2.4 0.20 0.70 0.1 0.7 25 330 l

"Sr ill 0.005 0.02 10 0.25 1.5 0.5 5.0 40 0.5 10

'. 4Sr 0.001 2 0.05 0.3 0.1 1.0 8 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 Air Mater Vegetation Soil and Clan flesh Foods,(tomatoes Meat and particulates and milk and grain sedinent Fish and plankton Clam shells potatoes, etc.) poultry

~CE/o ~ci/I NCCI/ 'drr ~CI/ d ~Cl/ dr ~CS/ d ~CI/ dr Ci vet I NCCI//i 'se:

F 1*~de Li ** N I~GLI ll I ~de Li N I ~G/LI II .~GLI N I ~GLI NaI ~Ce Li NaI =

C~e Li Nai De(Lil 0

1 1 N 1 Ie ds Ce 0. 03 38 O. 55 0.35 0. 35 0.35 38 90

'1 0 Ir C 0. 02 33 0.22 0.06 0.06 0.35 0.06 33 4C s'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 44 200 90 1111 0.01 0.01 15 8 0.35 0.09 0.29 0.02 0.20 0.02 0.07 0.20 9.02 15 8 50 20

'1 0 C 1 0 1 N R 0.04 40 0.65 0.45 .p. 45 0.45 40 1.50 10CR li Cs 0.03 40 0.51 0.11 O.ll 0.74 O.ll 40 90 1

0.01 0.02 10 26 0.20 0.33 0.12 0.08 0.12 0.08- 9.48 0.12 0.08 10 26 40 50 C 0.01 0.01 10 5 0.20 0.06 0.12 . 0.02 0.'12 0.02 0.08 0.12 0.02 10 5 40 15 "Zr-W 0.01 10 0. 20 0.12 0.12 0.12 10 40 sszr O. 01 10 O.ll 0.03 '.03 0. 15 0. 03 10' 20 ssNb 0.01 5 0.05 0.01 0.01 0.07 0. 01 15 s0C 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 5 55 15 sCMn 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 5 40 15 Zn 0.02 0.01 15 9 0.25 0. 11 0.23 0.02 0.23 0.02 0.17 0,23 0.02 15 9 70 20 00C 0.01 0.01 10 5 0.17 0.06 O.ll 0.01 0.11 0.01 0.08 0.11 0.01 10 5 30 15 0.10 150 2.50 0.90 0.90 0.90 150 400 Ba-La 0.02 15 0.68 0.15 0.15 0.15 15 50 1008 0.02 25 0.34 0,07 0.07 0.30 0.07 25 50 1 00La

0. 01 7 0.08 0:02 0.02 0.10 0.02 7 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 <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. 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 EPA value TVA AVG. EPA value TVA AVG. EPA value TVA AVG. EPA value TVA AVG.

Date ~(+3a WARL EARL (+3a) WARL EARL ~(i3a WARL EARL ~(+3a WARL EARL 3/82 27+12 23 28 55+9 63 56 16+2'!6 16 15 23+9 24 24 9/82 32+14 28 28 67+9 57 52 20+2.6 . 17 'g14g 27+9 22 22 B. Tritium in Urine (pCi/L)

Date EPA Value (+3a) TVA AVERAGE WARL EARL 5/82 1300+575 1793 1650 12/82 3830+641 3510 4023

Table 4 (Continued)

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

Gross ha Cross Beta Strontium 89 -. Strontium - 90 Iodine -131 EPA value T~YAva. EPQ value TVA AVG EP* value TVA AVC. EPA value TVA AVC. EPA value TVA AVC. value Raa ~(3 WARL EARL ~3a 'ARL EARL ~33 llARL EARL '~3a MARL EARL ~3a WARL EPA EARL'3-TVA WARL AVC EARI, 1/82 24410 20 19 32'9 33 28 21a9 20 22 12+2.6 13 12 8 4eq 6h 8.7 7.3 2/82 1820+592 2007 1793 3/82 19+9 19 20 19+9 F 19 20 4/82 2860'624 2907 2923 62=11 61 61 5/82 27.5a12 27 38.3 2919 26 33 22a9 24 . 22 13+2.6 11 8 6/82 18301589 1620 1810 4.4=1.2 5.3 3.6 7/82 16 9 13 32 23 9 . 20 21 8/82 2890i624 2903 2793 9/82 29+13 26 f 40'9 38 24.5 9 30 21 14.5+2.6 13.8 14.A1 87=15 93 . 79 10/82 2560f606 2690 2510 11/82 19i9 19 15 24+9 22 23 12/82 1990+598 1943 1993 37=10 37 39 D. Ca~-Spectral Analysis of Water (pCi/L) a Chromium - 51 Cobalt - 60 Zinc - 65 Ruthenium - 106 Cesium 134 Cesium 137 Date va ue

(+3a)

TVA WARL A VCR.

EARL EPA

~3a val a T~VVr..

MARL EARL EPA

~3c value ~P WARL

~VG.

EARL EPA

~('3a value TVA llARL EARL AVC. EPA value 3a

~~Q, WARL EARL EPA

~3V value KARL EARL 2/82 0 <44 <35 21 22 )5'9 . 16 16 2019 <40 <30 22+9 21 19 23-9 24 22 6/82 23 9 44 35'0+9

<35 29x9 32 34 2669 29 26 0 <40 <30 35+9 31 32 25 9 24 27 10/82 51+9 55 "na9 18 21 24a9 25'd 25 30+9 39d <36 19i9 20'9 20d

Table 4 (Continued)

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

'8t9 Strontium 89 Strontium 90 Iodine - 131 Cesium - 137 . Barium - 140 Potassium~ Cobalt - 60 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

'PA Date ~3d WARL EARL ~3a IIARL ML ~(3 ",. IIARI. EARL ~3a WARL EARL ~3a WARL ML ~3a WARL ML ~3a 'IARL EARL 4/82 25+9 29 28 16e2.6 16 13 31 30 0 <29 <15 1500i130 1590 1413 30i6 . 32 29

',.7

~

7/82 5.4+1.4 5.'1 -.

10/82 0 <10 <10 18.6+2.6 19.5 12.8 42+10 43 42 34i9 . 34( 35 0 <25 <20 1560+135 1563 1639 F. Foods (pCi/kg, 'Wet Weight)

Strontium 89 Strontium - 90 Iodine 131 Cesium '137 Barium 140 Potassium EPA value TVA AVC. EP* v I

• TvA Ava. EPA el 3WA AVG. EPA el e lvA AVC. 'PA val e I~VVG EPA value 328 Date ~(+3a WARL EARL ~(3a IIARL EIIRL ~(~3a WARL ML ~3a WARL EAIIL ~A3a WARL EARL ~(3e WARL EARL ~

7/82 26+9 30 28 20e2.6 268'7 94e15 98 98 20i9 24 26 0 <25 <14 2400e208 28109 27339 11/82 0 10 <40d 27.8-2.6 30.6 24~ 25A10 20. 29 27+9 28 27 0 <25 <14 2780i242 2670'903 Western Area Radiological Laboratory, Muscle Shoals, Alabama b

Eastern Area Radiological Laboratory, Vonore, Tennessee c explanation.

Ho known Investigation underway.

Analysis completed after report date e after report date Equipment malfunction, analysis completed 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 Iill study.

i Experimental detection limit is being reviewed.

Potassium values are mg/1 or mg/kg.

k of procedure is in progress.

Review

LOOISVA.Lf N D.

f I

'c tvANSVA.LE TENNESSEE VALLEY PEGION

'~T (TVA NUCLEAR PLANT SITES) V A VO+ENSGONO 1

M 0.,=

I PAOVCAH I

K BOWLING GREEN E N T U C K Y

~,M

/ V~

r'

(

5 I

~ /

.(, . PBN rI

/V~~ / r~I r

NASHVILL I /.JI I I OAIC RIOGE l

+p r r I

rACHSONi f 1 I

I kskPt is / Jl I CHATTANOOGA~ I rJ MOSCLE SLN

+HvNTGVILLE

/ ~,-

J

-I I S C A R.

SHOALS h+

LEGEND

- HARTSVILLE NUCLEAR PLANT fggij -PHIPPS BEND NUCLEAR PLANT M S S. l~ ~-CLINCH RIVER BREEDER I

A L A B A'M A G EORG I A REACTOR

-WATTS BAR NUCLEAR PLANT

-SEOUOYAH NUCLEAR PLANT .

-BELLEFONTE NUCLEAR PLANT

- FERRY NUCLEAR PLANT

- BROWNS 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 filter is radioiodine.'he 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 In. Water In Air"

~Ci/I* gCi/m

• Alpha

'Nonvolatile bet p Tritium',

I

~

3,000 3;000,000 30

'00 ' '00,000 137C 20,000 500

$ <5Rg 100000 200

) 44 10,000 200

'9 5Zr 9 5Nb 60,000 1',000 140ga 140L '0,000 1,000 I

13)Z ~ 300 100

~

.55Zn 100,000 ".2,000 "Hq 100,000 1,000 60( o 30,000 300 "Sr 3,000 .300 9 OS~ 300 30 I

I 51cr ~ )

2s000s000 80,000 134CS 9,000 400 58CO 90,000

'0000

• 1pCi- 3,7 m 10 'q.

TABLE 6 R'AOIOACTIVITY IN AIR FILTER PCI/H (3) 0~ 037 BO/H (3)

NAHE OF FACILITY LOCATION OF FACILITY BROUNS ~FRRY ggM~~Qf ~lA II 4 DOCKET N0t REPORTING PERIOD

~5~~9~~0$

1~9/

~9 TYPE AND LONER L IMI7 ALL CONTROL NUMBER OF TOTAL NUMBER OF INDICATOR LOCATIONS N l(ITM MIG~HST ANN~~M~A LOCATION) NONROUTINE OF ANAL'YS IS DETECTION HEAN (F ) NAHE HEAN (() MEAN (F) REPORTED P~RFDRllm GROSS ALPHA 0

~D)

'05 RANGF.

0 RAtfgJ; F 01( 1/ 51) f M AQU~RHfNT8 51 0 F 01- 0 01 GROSS BETA 0 '10 0 '2( 426/ 468) DECATUR'L 0 02 ( 47/ 52) 0002(

F 96/ 103)

GAHHA (NAI) 571 0~ 01- 0 '4 8 ' HILCS SSE 0

~

~ 01- 0 ~ 04 0 F 01- 0 '4 83 CE-141m 144 00030 0 ~ .05 ( 2/ 67) LH2 BF NORTH 0~ 05( 1/ 7) 16 VALUES <LLO K-40 0 '00 67 0 F 04" 0 VALUCS <LL'0

'5 0 ~ 9 NILE NNE 0~ 05-' 05 0 '2( 1/ 16)

I 0 ~ 12- 0 ~ 12 FE-59 NOT ESTAB 0 ~ 00( 6/ 67) DECATUR'L 0~ 00( 1/ 8) 16 VALUES <LLO 0 ~ 00 0 F 00 8 ~ 2 HILES SSE 0 ~ 00 0 F 00 1-131 0~ 010 G~G2( 4/ 67) DECATUR'L 0 02 (' '1/ 8) 16 VALUES <LLD BE-7 NOT ESTAB 0

0

~

'7(

01- 0 '2 67/ 67) 8 ' MILES SSE ATHENS'L 0~

~

~

02-08(

Oa02 8/ 8) 0 '7( 15/ ,16) 0 ~ 01- 0 ~ 1G 10 ~ 9 MILES NE Oi05- 0 ~ 10 0 '5- F 11 GAHHA (GCL I )

60 K-40 -NOT ESTAB 0 0F

'2(00-32/

'4 50) LH4 BF TRAILER P 1 ~ 7 MILES NNV 0

0

'2(02-3/

0 '4 5) 0 0

'2(00-8/ 10) 0 '310) 0 ~ F 8 I-21 4 0 ~ 020 0 F 05( 3/ 50) ROGERSVILLE ~ AL 05( 1/ 1) 0~03(

'3- I/

PB-214 '20 0 F 04-0 F 04(

0F 3/

05 50) 13 ~ 8 HILES NV ROGCRSVILLC ~ AL D~

0 0F F 05 04(

0 1/

'5 7) 0 10 VALUES <LLO 0 '3 PB-212 0

NOT ESTAB 0 ~ 03-0 00( "

0 26/

'450) 13 ~ 8 MILES NN DECATUR'L 0

0

'4 0

'0(0- 2/ 00 5)

'4 0 F 00( 4/ 10) 0 F

F

'2(

00- 0 F 00 8 ' HILCS SSC ,0 ~ 0 0 F 0 F 00- 0 '2 RA-226 NOT ESTAB 0 5/ 50) COURTLANDt AL 0~04( 1/ 5) 10 VALUES <LLD 0 F 00- 0 '450) 10 ~ 5 MILES IJSU 0 '4" 0 F 04 BE-7 '50 06( 20/ LH5 BF DAVIS F 0 07( 1/ 5) 06( 5/ 10)'

TL-208 0

NOT ESTAB 0

0F 0

F 05-

~ 00l 0~

15/

07 50) 2~5 MILES MSM LH4 BF TRA1LER P 0 F

0 ~ 07-

~ 00l D~

1/

01 5)

G ~

G ~

'500( Oe10 5/ 1G) 0 F 00- 0 ~ OG 1~7 MILES NNV 0~ 00- 0 F 00 0+00- 0F 00 AC-228 NOT ESTAB 0 F 01( 2/ 50) ATHENS'L 0<<OI( 1/ 5) 10 VALUES <LLD 0 F 00- 0 F 01 10 ~ 9 MILES NE 0 ~ 01- 0 F 01 SR 89 0 ~ 005 36 VALUES <LLD 8 VALUES <LLO 44 ANALYSIS PERFORHED SR 90 0 ~ 001 36 VALUES <LLO 8 VALUES <LLD 44 ANALYSIS PERFORHEO

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)..

TABLE 7 RADIOACTIVITY IN RAINVATER PCI/L - 09037 80/L.

NAME OF FACILITY BROVNS FERRY SOCKET NO 52 2~59 26II 292 LOCATION OF FACILITY~~~Q~ 'EPORTING PERIOD $ 982 TYPE ANO LOVER LI HIT ALL CONTROL NUMBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCATION( NONROUTINE ANALYSIS (f (F) 'EAN (F)

OF P~Rf ORMS j)

GAHHA (NAI)

~L DETECTION LD)

HEAN RANGE

) NAME I STANCE AND DIRECT'ION HEAN RANGE b P~AGIE REPORTED SEA~SOS IIENTS 119 FE-59 NOT ESTAB 2 76( 14/ 97) LM3 BF NORTHEAST 4O95( 2/ 10) 5 65( 4/ 22)

BE-7 0

~

'10 54/

F 50 1 ~0 MILE ENE 4 '0- 5950 '5 0 '0- .. 9 '0 NOT ESTAB 36 64( 97) LH5 BF DAVIS F F 71( 7/ 10) 4S 95( 14/ 22).

GAHHA (GELI) 1970- 71 'O 2 ~ 5 MILES 'V SV 30+00- 66 '0 15

~

'0-. 84 ~ 60 24 K-40, NOT ESTAB 4 '5( 2/ 20) ROGERSVILLEo .AL 6 F 71( 1/ 2) I ~ 76( 1/ 4)81-214 NOT ESTAB 1 ~

0931(

38-1/

6171 20) 13 ' HILES NV ROGERSVILLE ~ AL 6 ~ 71-

'1( 6 1/

'1 2) 1 ~ 76- 1 '6 VALUES <LLO 0 '1- 0931 13 ~ 8 MILES t(V 0

0~ 31- 0 31 4

3 '8(

~

PB-212 12/ 20) 7 '1( 1/ '6(- 2/-

'1 4)

NOT ESTAB LH2 BF NORTH =

1) :2 0'924- Te31 0 ~ 9 HILE NNE TO31- 7 '1 2o31- 2 BE-7 NOT ESTAB 53 '2( 3'/ 20) ROGERSVILLEO AL 75 36( 1/ 2) VALUES <LLO AC-228 15 ~ 000 31o55-17990(

7S ~ 36 1/ 20) 13 ~ 8 HILES ttV LH3 BF NORTHEAST 17

~

75936-

'0( 75 1/

'6 3) 4 VALUES <LLD 17 '0- 17 '0 1 ~ 0 MILE ENE 17 ~ 90- 17 '0 TRITIUM 330 F 000 117 VALUES <LLD 26 VALUES <LLD 143 ANAL'YSIS PERFORHEO

. 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 HCI/KH(2) 37000000 ~ 00 BQ/KH(2)

NAHE OF FACILITY QROVNS QfRRY DOCKET NO. ~o-g~~kOo.22k LOCATION OF FACILITY~QHfSTONQ ALABAHA . 'EPORTI NG PERIOD ) 982 CONTROL NUMBER OF TYPE ANO LOVER LIMIT ALL

=

TOTAL NUMBER OF INDICATOR LOCATIONS gg~TQN~VTH HjGH~~S4I~JM Al IIE4H NONROUTINE LOCATION[

OF ANALYSIS DETECTION MEAN (f ) NAME HEAN R~AE" QF~ MEAN (K) REPORTEO EfJKQEBQ? (LU}l ~MQE D~E52~4ILQLRHIlM Q~Ajjf

'0( 23/ 23)

Zr.aruWRm<Zs 0.050 0121( 107/ 107) 0 31 ( 12/ 12) 0 GROSS BETA 130 0 05- 0 COURTL ANOt AL 10 5'ILES 'VSV

~

~

0 14-

~ . 0 '4 0 07 n ~ 41

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 LOCATION OF FACILITY LIMESTONE ffuff A~A/AHA REPORTING PERIOD 19BP TYPE AND TOTAL NURSER 'F 'INSE LOVER LIHIT . ALL IHOICATOR LOCATIONS ~IICAT O~MH TH NBBK~uuu!IL~Au CONTROL . NUMBER OF

=

.LOCATIONS NONROUTINE OF ANALYSIS DETECTION MEAN l() NAHE . MEAN HBAN (F)b REPORTED

~LRI b

0 020; uesT<<cf Am ufmzee~ RAuuei/3'eufuuMfu Rangy IODINE IN AIR ~ OM03( 39/.467) ROGERSVILLE% AL . OH,03( 12/ .52) 0~ 03L '10/ 102) 569 0.02- 0.07. 13.e MILES NV ... 0.02- ..0.07 OM 02 0~ 06

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 PM-IBF WHEELER ROG"PSVILI <

FLORENCE OAM ATHENS PM-28F FFIEL MUSCLE SHOALS BROWNS FERRY HUNTSVILLE RM-I BF NUCLEAR PL NT LEIGHTON TUSCUMBIA COURTLAN0$

PM-4 F OECAT R PM-38F0 IO MILES jRUSSELLVILLE T SV IL HARTSELLE OAM HALEYVILLE CULLMAN 45 MILES CI ENVIRONMENTAL MONITORING STATION NOTE: THE FOLLOWING SAMPLES ARE COLLECTED FROM EACH STATION:

AIR PARTICULATES RAINWATER RADIOIODINE SOIL HEAVY PARTICLE FALLOUT

PigUL e 3

.. LOCAL MONITORING STATIONS 19 BROWNS FERRY NUCLEAR PLANT .

ATHENS US HWY 72 BFN ALA. HWY 20 Legend 0 Air Monitor DECATUR Autom'atic Well Sampler H Dairy Farm Scale 0 I .2 S O 5 Miles

p =(

r( -.> ~<<II <<A,r rl;r

• 1" ~

20 -Figure 4

/7 n~r

(

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

('tl

'i,(J./ a 'I

'tf ~'I( (I

(

~

TLD Locations  ! (t pt II BFN

.1 'I

~ I t ~,(I A

~

p l Jg l~ I . i Il}i;

( ~ ~

I

~

• I

~

I ~ I ~ I III I rc 1 w

l n'. ((rr}I 0.

~'C'

. ~ ~

lN.

(

)(I t . >'1 ~

I

".~ ~

~

-~tl

I, (II I I

~

,1( ~

I I~ r ~ rr I

i ~ 'i,(II, .

.) hI

~ l I

!t

~ l N

<<N IL

( /

jl N

i (

N

.J N N N '

NN J ... It}

I ~ I i 1~

N I ,j~( ~

~ (

~ (

I('+

'I Q

I - ~,

I

~ } ~ 1 (N

~ -(

1

Figure 5 Aeeu. AVERAGE

.30 6ROSS BETA kTIVITY

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

Preoperational Phase I Operational Phase

.25 Cl C"

0 tO H C JJ 0 t

.20 E4 JJ IJ JJJ JO F< ',

JJ tJ Qt 0A JJ K

0 0 tJ C

C 0

.15 wO Jt 8

Ave~ra c: Preo~erational Phase O

0

.10

.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 analy'ses of these samples.

ll gives the results obtained from the laboratory 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 levels at onsite stations are approximately 3-5 mR/quarter higher than 'verage 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, postulated that the differences are probably attributable to combinations of it is 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 in this report. Therefore, for comparison purposes, figures 9 and 10 not'ncluded 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 hAHC OF FACILITY QROUNS FERRY ALA/AHA DOCKET NO ~

REPORTING PERIOD

~P~A~~9 LOC( T 104 OF FACILITY J,Q~HQ/ON~ 1~9 TYPE 'ND LOVER LI)(IT ALL CONTROL NUMBER OF TOTAL iNUHBEo OF INDICATOR LOClglONS LOCATIONS NONROUTINE

~~H OF GAHHA ANALYSIS fj}

(NAI)

DETECTION LLLQl

'.HE AN (g )

RANGC MEAN (F )

RANGE RCPORTCD H~A1!EK~HNIS 83 CS-137 10.000 11 '0(

10-1/ 42) PAGE FARH '

I 75 MILES 11 11

~ 10(

10 1/

II 10) 10 41 VALUES <LLO 11 11 F 10 E K-40 150eDOO F

1306e32( 42/ 42) otGr FARM 1373 '1(

F ~

10/ 10) 1297 F 16( 41/ hl)

'0

~

694+00- 1553 6~ 75 MILES E 1156 F 80- 1455 F 50 1036 F 80- 1451e60 IOOINC-131 0 F 500 212 VALUES'LLO 204 VALUES <LLD 416 ANALYSIS PERFORHED GAMMA tGELI) 2G CS-137 F 000 6 ~ 31(

5o50-3/ 11) PAGE FARH 75 HILES 6 '2(

5 ~ 93-2/

7.51

3) 9 VALUES <LLO 7 F 51 K-40 NOT CSTAB 1269 F 10(

747 '1 ll/'311) 1499 8 ~

LOONEY FARM FAR E

5 ~ 75 'MILES ENE 1354 '6(

1209 10-.

2/

1495+&3

2) 1256 1175

'7(

'6- 9/

1362 '5 9) 49 '9(

~

81-2)4 I ESTAB 49 '9( 2/ 11) SMITH FARM 2/ 3) c VALUES <LLO PB-214 NG NOT ESTAB 38 ~ 29 le 25(

~

61 ~ 69 2/ 11) 4 ~ 75 HILCS SMITH FARM N 38 '9 41 '5t 2/

69 02( 2/ 9)

PO ~ 76- 61+74 4 ~ 75 MILES N 20 '6 61 ~ 74

&~

7 '2- 8 ~ 82

'3( 3 '4(

PB-212 AC-228 NOT ESTAB NOT CSTAB 1 ~ 69(

0.06= -

11 VALUES <LLD 6/ 11) 4.08 BROOKS FARH 7 ' MILES NN)t 2

I ~ 58 2/ 3) 4 F 08 I 94

~

3 '3(

F 85-

'/ ')

3/

5 '9 3 '1 c)

'SR 89 10.000 53 VALUES <LLO 50 VALUES <LLO 103 ANALYSIS PERFORHEO 90 2 ~ 000 4(3P( 45/ 53) SHI TH "( 5465( 12/ 13) 3 '9( 46/ 50)

SR 103 2p09- 10 F 14 4 ~ 75 HILES N 3 '6- 10 F 14 F 08- 9 '2

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 PCI/G 0 ~ 037 80/G (ORY VE IGHT)

NAME OF FACILITY RROVNS FERRY DOCKET t)DE 50-259a260 ~ 296 LOCATION OF FAC IL I TY QQH~S~TNQ Aj ABAHA RI.PORTING PERIOD 1/$ 2 TYPE AND LOVER LIMIT ALL CONTROL NU!(BER OF TOTAL tkUNBEP OF INDI'CATOR LOCATIONS LOCATIONS NONROUTINE OF ANALYSIS "DETECTION HEAN ([) NAME rEAN (F) o MEAN t F )b REPORTED f

PQt OR 4Q)

GROSS BETA LLJ 0

D

'00 23 '2(RANGf 17/ 17) THRASHER FARH 69 F 43( I/ 1) 30 RANGEb

'3( 16/ 16)

MEASURfHfNTQ 33 3 '9 69 '3 7 ~ 0 MILES ENE 69 ~ 43 69 ~ 43 F 80- 57 '4 GAHNA (G:L I) 33 CS-137 0 '60 0 13( 4/ 17) SMITH FARH 0 18( I/ 4) 0 07( 3/ 16)

K-4 0

~

0 F 14 '2(

07- 0 '8 17/ 17) 4 ~ 75 'HILES A 0

~

~ 1 6 ~ 2o o-1/

0~ 18 0

~

~ 07- F 08 NOT ESTAB TNR ASHER F ARM 1) 20 F 70( 15/ 16)

BI-214 1 ~ 87 46 29

~ 7 ~ 0 NILES ENE 46 '910( 46 1/

'9 4 '5 46 F 06 0 F 100 0 '0- 1/ '017)

F 10(

0 SHITH FARN 4 ~ 75 MILES N 0

0

~

~ 10- 0 10

4) F 16(

0 ~ 16 1/

0 16) 16 81-212 NOT ESTAB 17 VALUES (LLO

~

0 0

'1(

31-I/

0

~

16) 31 PB-214 NOT ESTAB 0 0

'9(

F 01 8/

0 '3 17) SHITH FARM 4~ 75 HILES N 0 0 '2(

09 3/

0 '3 4) 0 '7l

~

0 ~ 00-8/

0

~

16) 18 0 '6(

~

PB-212 NOT ESTAB 00-15/ 17) 16 SNITH FARN 4 ~ 75 MILES F 07(

00-4/

16

4) 0 '6(

0 ~ 02-12/ 16) 0 0 N 0 0 F 11 RA 226 NOT ESTAB 0~

F II( 8/

~

'0 17) PAGE FARM

'5 0 '6(

~

'2 2/

~

4) 07( 9/ 16)

BE-7 NOT ESTAB 0

5 02-

'6(

F 0 17/ 17) 8 MILES E BROOKS FARN 0

7 '2( 0 4/

~ 50 4) 0 0

F

~ 01-

'7( 0 '6 15/ 16) 0 '3- ~

15 '6 7 ~ 0 MILES NNV 2 35-. 15+06 4

0 92- 4F 89 TL-208 NOT ESTAB 0 F 02( 11/ 17) Tt(RASHER FARN 0

~

04( I/ 1) 0 '4(

~

10/ 16)

AC-228 NOT ESTAB 0

0 F 00-

'7( 0 12/'7)

F 06 7(0 MILES'NE THPASHER FARM

~

F 0 ~ 04-1 ~ 15(

0 1/

F 04 1) 0 0

~ 01-14(

0 '6 8/ 16) 0 ~ 02- 1 ~ 15 7 ~ 0 MILES ENE I ~ 15- I ~ 15 0 '3

~

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 RADIOACTIVITY IN SOIL PCI/G - 0 ~ 037 80/G (ORY.)JEIGHT)

NAtlE OF FACILITY ~RQ~P DOCKET NOe~~agtt(tAg~

REPORTING PERIOD LOCATION OF FACILITY LIHESTONE ALABAMA 19~8 TYPE ANO LOVER I.IHIT. 'LL CONTROL NUMBER OF TOTAL NUMBER OF INDICATOR LOCATIONS QOCA~TON itl H H GH T QgfJ fA~MAQ LOCATION) NONROUTINE OF ANA(.YSIS DETECTION 'EAN (E) MEAN C () REPORTED HEQMG? ~lJJ}1 RANGE NGf RANG HfAS~R HfQTS GAMMA'GELI )

CE-144 ll Oo060 9 VALUES <LLD '2( 1/ 2) 0

,0 '217( 0 '2 CS-137 0 '20 0 ~ 40 ( 9/ '9) ATHENS'L 1~ 17(

I'i17-1/

17

1) 1 ~

01-2/

1 ~ 33 2)

,0 F 05 lo.17 10 ~ 9 MILES NE 1~ F

'7(

=

K-40 0 '50 ,5 '2( 9/ 9) LM4 BF TRAILER P Be13( 1/

'3 1)1) 4

'7-2/

'T 2) 3 '6- -

8 ~ 13 1 ~ 7 MILES tJNIo 8 ~ 13- 8 4 5 MN-54 Oe010 0 '2( 2/ 9) LH5 BF OA VIS F 0 '2( 1/

'2 1). 2 VALUES <LLO BI-214 0F 01-91(

0 '2 9/. '9) 2 5 MILES VSit LH4 BF TRAILER I 0~ 02-18(

0 1/ 81( 2/ 2) 0 ~ 050 0 0 '5- ~

1 ~ 18. ~ 7 tlILES NNII 1 ~

lol8 1o18 0

0 '3-F 0 '9 2/ 2)

BI-212 0 F 100 1~ 33l; 9/ 9) LH4 BF TRAILER P 1~ 78( 1/ 1) 1~ 03(

Oe68 1 ~ 78 1 ~7 MILES NNIJ 78- 1 ~ 78 0 91- 1 ~ 15 PB-214 0 F 050 d o02(,9/ 9) LH2 BF MORT)I 1 ~

1 ~ 33( 1/ 1) 0 '0(

'3- 2/ 2)

'7 65- 1 ~ 33 0 ~ 9 MILE NNE .1 ~ 33- 1 33 0 0 PB-212 NOT ESTAB 0 ~

09( 9/ 9) LH4 BF TRAII.ER P 1 ~ 45( 1/

~

1) 0 '6( 2/ 2)

'2 2) 1 ~

0 '2- F 45 1~7 'ILES tJNU 1 ~ 45- 1 ~ 45 0~ BG- 0 RA 226 0 ~ 050 0 '1(

55-9/ 9) LH4. BF TRAILER P 1 ~ 18(

1 ~ 18-1/ 1) 0F 81(

'3- 2/ '9~2) 2/

1 ~ 18 1 ~ 7 tlILES NNlt 1 ~ 18 0 0 RA-223 NOT ESTAB 0 F

'1( 6/ 9) LH3 BF NORTHEAST 0 '7( 1/

'7 1)1) ~ 97C

'0-1 ~

3 '4 RA-224 0

0 '4-

'9( 4/

0 '7 9) 1~0 HILE LH4 BF TRAILER P ENE 0 ~ 37- .

'2(

0 1/

0 2

~

VALUES <LLD NOT ESTAB 0 1 Oo53- 1 ~ 42 7 tlILES tJNiJ 42" 1 ~ 42 BE-7 0 '60 9 VA'LUES <LLD 1 1 ~

0 '1( 2/ '2 2)

'0- 0 0

TL-208 0 '20 36( 9/ 9) LH4 BF TRAILER 45( 1/ 1) 0 '0( 2/ 2) 0 0 '0- " '5

~

0 1 ~ 7 tlILES tJN'M 0~

0 ~ 45- 0 '5 1)' 0 28- 0 '3 AC-228 0 '60 I ~ 12( 9/ 9) LH4 BF TRAILER lo51( 1/ 88( 2/ ,2) 0 '0- 'o51 1 7 MILES NNv F 51 ~ 51 0F 0 '9- '

~ 98

'2 81( 4/ 9) LH5 BF DAVIS F F 15( 1/ 1) 38( 1/ 2)

PA-234H NOT ESTAB 2 '4-F 82(

'F 15 1/ 9) 2 ~ 5 MILES )JSV ATHENS'L 3 ~ 15-I' 82 (

3 1/

'5 1) 1 ~

1~ 38-'

2 VALUES <LLD

~ 38 89 o500 SR SR 90 ll 1 0 ~ 300 1 ~

lo82-9 VALUE'S <<LLO lo82 10 ~ 9 HILES NE lo82- 1 ~ 82 2 VALUES <LLO 11 ANALYSIS PERFORMED

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 NAME OF FACILITY BROMNS FERRY DOCKET NO ~ 0-259 260 296 LOCATION. OF FACILITY~~QQf. REPORTING PERIOD )9ag TYPE ANO LOMER LIMIT ALL CONTROL .NUHRER OF TOTAL NUHBER OF INDICATOR NONROUT1NE HEANLOCATIONS LOCATIONS OF ANALYSIS

~P~~RH GAHHA (NAI)

Q ~~

DETECTION

)

~

RANG/

Cg ) IIEAN llj) REPORTED Hf~A ~R uENTS 19 FE-59 NOT ESTAB 8 VALUES <LLO 4 '5(

'0- 2/ 11) 2 F 80 15 '0(

I-131 15 ~ 000 8 VALUES <LLD 1/ 11) 15 20-

~ 153 20 GAHHA (GELI) 7 BI-214 NOT ESTAB 14 '6(

'6- 1/. 5) BFN MELL ¹6 14 '6( 1/ 5) 2 VALUES <LLD'

'6 '6 14 14 '6= 0~02 MILES M 14 14 PB-212 NOT ESTAB 1~ 58( 2/ 5) BFN MELL ¹6 1~ 58( 2/ 5.) ~ 99( 2/ 2)

Io25- I+90 0~ 02 MILES M "1 s 25- I ~ 90 0.'78- 1.20 TL-208 NOT ESTAB 2 '5( 2/ 5) BFN MELL ¹6 2 '5( 2/ 5) 2 VALUES <LLO TR IT IUH 330 F 000 I ~ 85 3 VALUES <LLO

'6 0 ~ 02 HILES M 1~ 85- 3 '6 4 VALUES <LLO 8 ANALYSIS PERFORHEO

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).

'C TABLE 14 RADIOACT IVIT'Y "IN PUBLIC I(ATER SUPPLY I/L 0 G37 BQ/L NAME OF FAC ILITY Q~RU EEBBX DOCKET NO ~ 50 PQ9AP{iOX2~k LOCATION OF FACILJT'Y LJ~ESIOK ALAPAHA REPORTING PERIOD~)9 g TYPE ANO LONER L IHIT ALL i CONTROL NUMBER OF

.TOTAL NUMBER OF INDICATOR LOCATIONS I OQA~TQ ~It TH EITHER~'BIIIIil,LfA5 (t LOCATIONS NONROUTINE OF ANALYSIS DETECTION MEAN (F P HEAN (F REPORTED (l lR) RAh(gf HfgQU~R HQNQS RANG/

'7(

~

GROSS BETA 2 ~ 400 .3 ~ 60 ( 51/ 76) CHAHPION PAPER 3 '3( 42/ 50)

'3 2 '8-2 3/

'7 13) 89 2 +42- 13+53 TRM, 282 ' F 47- 13 3 GAHHA (t(A I)

FE-59 70 NOT ESTAB 3 ~ 85( 6/ '2)

'0 SHEFFIELO ~ AL ROB 6 '0(

'C I/ ll) 6+60 8 VALUES CLLD I 00" 6 TRH 254 6 GAHHA (GELI)

K-40 19 NOT ESTAB. 1 ~ 04( I/ 14) CHAMPION PAPER I ~ 04( I/ 10) 9 '6(

'6- 1/

'6 5)

,1 o 04- 1 ~ 04 TRM 282 ' 1 ~ G4- 1 ~ 04 9 9 PB-214 NOT ESTAB 8 47( 1/ 1'I) CHAMPION PAPER 8 ~ 47( 1/ 10) 5 VALUES <LLD 8+47 8 ~ 47 TRt( 282 ' 8 ~ 47- Gq47 PB-212 3+GB( 9/ 14) MHEELER OAHe AL 3%98( 1/ 2) 78( 3/ 5)

NOT ESTAB 1 ~ 03- F 09 TRM 274 9 3 ~ 98- 3 '8 I/ 2) 1 ~

1 ~ 32- 2 '7 TI.-208 NOT ESTAB 0 '2( 5/ 14) WHEELER OAHt AL TRu 274 '

0 ~ 63(

63- 63 1 ~ 29l

+70-2/ 5) 1 ~ 88 Or25= 0 F 88 0 ~ 0 F 0 SR 89 10 F 000 12 VALUES (LLD 4 VALUES (LLO 16 'ANAL'YSIS PERFORHEO SR 90 F 000 12 VALUES lLLO VALUES (LLO 16 ANALYSIS PERFORMED 395 F 05( 2/ 419+24( 1/ 4) VALUES (LLO TRITIUH 16 330 000 370 F 86- 419 '412) CHAMPION PAPER TRu 282 ' 419 '4" 4.19 ~ 24

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 Avera e External Gamma Radiation 'Levels b miles 0-1 20;8 + 1.1-.'.. 20.3 + 1.7 21.3 + 1.5 21.9 + 1.6 1-2 18.6'+ 2.0 16.8 + 3.2 18.1 + 2.1. 16.3 +

4.0'5.8 17.9 + .I.7 16.3, + 1.5 17;5 + 1:8 + 3.8 4-6 ,17.4 +. 1.6 16.1 + 1.4 17.6 + 1.6 ,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) 20.3 + 1.6 19.4 + 2.6 2.0.5 + 2.1 20.5 + 3.4 Average,

>2 miles.

'(Offsite), '17.6+ 1.9 16.2 + 2.0 17.5 + 2'.2 15.6 + 3.4

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

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

TABLE 16 RADIOACTIVITY IN CORN PCI/KG - 0 '37 BO/KG CMET MEFGHT)

NAHE OF FACILITY QROMNS FLURRY DOCKET NO ~ ~0 2599~60 22)

LOCATION OF FACILITY I,~IH STONf, ALABAMA REPORTING PERIOD 1982 TYPE ANO LOMER I IHIT ALL CONTROL NUMBER OF TOTAL NUHBER OF INDICATOR LOCATIONS ~OA~TON MI TM HIIGMQST ANNUA~LM AN LOCATION( hONROU TINE IF ) l Fb) HEAN t g) REPORTED

')

OF =ANALYSIS DETECTION HE A,N NAME HE AN P~RQ~OR H ~JI D) 25 000 3667 '2(

RANGE 1'/

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

MILES 3667 ~ 62( 1/ 1)

R~Af, 4983 F 14( 1/ 1)

Hf AggffMfNJS GROSS BETA 2

F 3667 '2-. 3667 '2 7 NNM 3667 62- 3667 '2 4983 F 14- 4983 '4 GAHHA IGELI) 2 K-40 1990035( 1/ HILES 1990 '5( 1/ 1) -2040 ~ 72( 1/ 1)

PB-212 NOT ESTAB NOT ESTAB 1990 ~ 35- 1990 I ~ 38( 1/

'5 1)1) 7 NNlJ 7 MILES NNM 1990 '5" 1 ~ 38C 1990 1/

'5 1) 2040 ~ 72 2040+72 1 VALUES <LLO 1%38 1038 I ~ 38 1 <<38 TL-208 NOT ESTAB 0 ~ 03( 1/ I) 7 MILES NN)J 0 '3{

03-1/ 1) VALUES <LLO 0 ~ 03- 0 ~ 03 0 ~ 0 ~ 03

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 17 RAOIOACTI V I TY IN GREEN BEANS FLURRY PCI/KG - 0 ~ 037'O/KG (MET MEIGHT)

NAHE OF FACILITY BROVNS LOCATION OF FACILITY QJH/STONQ ALABAHA OOCKET NOe~0-/~~29/

REPORTING PERIOD 1982 TYPE ANO LOVER LI HIT ALL CONTROL NUHBER OF TOTAL NUHBER OF INDICATOR LOCATIONS NONROUTINE OF ANALYSIS OETECT ION

~~l IL>

HEAN ([) REPORTEO .

ZKEEIEQf2 kMif LLLiIhEKE A NQ 21EQ;ILIA RMAK. MBfid' QQAQQQf;~H QQS GROSS BETA 25 F 000 4257 ~ 41 l 4257 '1- I /..

4257 '1 I ) HILES NNM "'.

4257 ~ 41( I/ I) 4751 ~ 82t I/, I) 2 4257 ~ 41- 4257e4 1

. 4751 ~ 82- 4751 ~ 82 GAHHA (GEL I) ~

2 K-40 NOT ESTAB 1900 ~ 30(

'0- 1/ I) 7 HILES 1900 '0( I/ '2( 1/ I)

NNM

'0 1)1) 2034 1900 1900' 30 1900p30 1900 2034 F 02 2034 '2 PB-212 NOT ESTAB I ~ 68(

1 ~ 68-1/

I ~ 68

1) 7 HILLS NNM I ~ 68(

68-1/

I ~ 68 4 '8(

08-I/ 1) 1~ F 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)

NAHE OF FACILIT'Y QROVNS FfRRY DOCIIET NO,~O-EDRRERRRE 9 LOCA TION OF FAC'ILITY~IQfSTONf ALABAHA REPORTING PERIOD 19112 TYPE AND LOVER LIHII ALL CONTROL NUHBER OF TOTAL NUHBER OF INDICATOR LOCATIONS LOCATIO)JJS NONROUTINE OF ANALYSIS DETECTION HEAN Jg) HEAN REPORTED t.'f RERE5f tl 5373 00(

REMif I/ I)

~f HILES AN~QRfC jgQN 5373900(

'~A 1/ 1) '9l IFf'280 1/ I)

HfAQQ~R Hfg7S 7280 '9-GROSS BETA 25 F 000 F 7 NNM 2 5373 F 00- 5373900 5373 F 00- 5373 'O 7280 F 19 GAHHA <GELI)

K-40 2

NOT ESTAB 3549.88( 1/ 1) 7 BILES NNM 3549 F 88(

'8- 1/ 1) 3337 '7( 1/ 1) 3549 '8 3549 F 88 3549 3549 F 88 333'7- 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).

TABLE 19 RADIOACTIVITY IN TOHATOES PCI /KG - 0 ~ 037 BO/KG (MET ME IGHT)"

NAME OF FACILITY QROVNS, ffRRY DOCKET NO ~ 50-2599 60 296 LOCATION OF FACII.I.TY L~HSTONQ ALABAHA REPORTING PERIOD 1982 TYPE AND LOMER LIMIT ALL CONTROL NUMBER OF TOTAL NUHBER OF INDICATOR LOCA/IONS LOCATION VITH HIGHEST ANNUAL HEAN 'LOCATIONS NOhROUTINE OF ANALYSIS DETECTION MEAN (g ) NAHE MEAN (F)o MEAN ([) . REPORTED Pffft)RHfQ BETA

~(ie) 25 000

~MQf1/

3987 89( 1).

QJQTQMg~aN~QIIIQQT 7 MILES NNM J~QANge I) 3987 ~ 89( .1/

~(~A/f 4577 '5( I/ I) ~HC.QQP E ~H

%ROSS 2

F 3987 '9- 3987+89 3987 '9- 3987 '9 4577 '5- 4577 '5 GAHHA (GELI )

2 K-4 0 2172+52( 1/ 1) 2172+52( 1/ 1) '4( 1/

PB-212 NOT ESTAB NOT ESTAB 2172~52- 2172 F 52 2 54( 1/ 1) 7 7

MILES HII.ES NNM NNM 2172 '2-2 '4(

2172 1/

'2 1) 2158 2158 '4 4~76(

2158 1/

'4 1)1) 2 '4- 2 '4 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 RADIOACTIVITY IN TURNIP GREENS PCI/KG - 0 ~ 037 80/KG (VET VEIGHT)

NAHE OF FACILITY BROVNS FERRY DOCKET NO ~ 50-2~59 2~0296 LOCATION OF FACILITY Q~~Qf REPORTING PERIOD 1982 CONTROL NUHBER OF TYPE AND LOVER L I HI 7 . ALL INDICATOR LOCATIONS LOCATIONS NONROUTINE TOTAL NUHBER ,OF, OF ANALYSIS DETECTION HEAN (F ) HEAN .(F)b RANGLb REPORTED Pf RQQRHQQ (I I n) RANGE BETA 25 ~ 000,7719 '7- 47( 1/ '1) 7 HILES NNV 7719 47( 1/ 1) ~

GROSS I 7719

~

7719 '7 7719 ~ 47- 7719 ~ 47 GAHHA (GELI )

I I) 1/ I) HILES NNV 7p03( 1/

CS-137 5 ~ 000 ~ 7 ~ 03 (.

"7 ~ 03- 7 '3

~ 7 7 ~ 03-3209 '1(

7 '3 K-40 3209 '1( 1/ 1) '7 HILES NNV 1/ 1) 3209 '1 32 09q2l NOT ESTAB 3209 21- 3209 '1 PB-212 NOT ESTAB 7 '8(8- 1/ '8 1)

~

7 HILES NNV F 48(

7 ~ 48-1/

7848 1) 7 ~ '4 7 BE-7 NOI ESTAB 105s52(

'/

1) 7 HILES NNV 105 '2(,

105 '2-,

1/

I 05 '2 1) 105 ~ 52- 105 52 15( 1/

TL-208 NOT 'ESTAB 2 2

~

~

15(

15-1/

2 '5 1) 7 HILES NNV F 2~ 15- 2 '5 1)

~

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

t J 1

'NNIAL AVERAGE. k Operational 'ROSS HEFA ACTIVITY P

Preoperational Phase Phase IN HRI Nil t5 HATER 3JPPLIES.

CO o

O CC BOWN FERRY Nua.EAR MhT" o

JJ ttt o

CJ CJ P

co ttt CJ Cp CO P 0

cr ctl 0 P Ct

'o c o o.

~ J I I" Q

I' PC P

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 Onstte

'\ 'IL I 1 C7 18

\

1 / 1 LI Jt I 'i

'// -1 1

1 9 p, CC e".P1 ~ o I 'gr I ~

/'L l I '1 e

I '5 '1 0 0 ~

/

d.

16 0

I

<Of fst te 12 1 970 ~

1977 1978 .197g 1988 1981 1982 Ptsure 8 Oirect Radiation Levels Bi owns Ferr y Nuclear Plant 8-Quarter Moving Average 22 OILst te rO.,R

s. 18 8

/ /

.o.

o P:

,/

Offstte 1975 'g77 1978 1979 1988 1981 1982

39 Fttture 9

,2W Oirect Radtatlon Levels Mot ts Bor Nuclear Plant 22 ty I

C e Onstte I

/

C 18 I P~

ot I Otfsi teo I I s~ o-.e.~

s 9-o., 9 t I jtti o

~

I '.

I \

I/

~

I O.

b 12 19?5 1977 1978 1979, 1988 1981 1982 Ftgure 10 Otrect Radtotlon Levels Motts Bor Nucleor Plont

'1-Quarter Moving Average 22 Onstte t.

18 ,/

a 8 I 0 e ~ ~ ~o o~ 0 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 )

Zooplankton, chlorophyll, Benthic =

Water. Samples River/river mile phytoplankton 'auna Sediment Fish (collected monthly).

.Tennessee 277.9 X X Tennessee 285.2 "Tennessee 288.7 X X Tennessee 291.7 X Tennessee 293.5 Tennessee 293.7 c-(discharge area)

Tennessee 305.0

. (Control) b'ennessee 307.5 X (Control)

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.

TABLE 22 RaOIOACTIVITY IN SURFaCE VATER TOTAL PC I/L - 0~ 037 80/L NAHE OF FACILITY PROVNS F/RRY LOCATION OF FACILITY~lttrSTOQf.

00'LL LIMIT TYPE AND LOVER CONTROL NUHBER OF TOTAL NUHBER OF INOICtTOR LOCATIONS LOCATION VITH HIGHEST ANNUAL HEAN LOCATIONS NONROUTINE OF ANALYSIS BET EC T I ON uCAN (F)b NAt!E HEAN (f ) HCAN (F)b RCPORTCD RANGE b DISTANCE At)O DIRECTION RANGE RANGE HEASUREHCNTS

'9( 35/

'539) 28' '1 l 12/ '3( 20/

GROSS GAHHA BETA (NAI) 65 2 ~4 3 2 '7- 8 TRH 4 2 '2- 13) 8 ~ 35 3

2 42- 6 '526) 44 FE-59 NOT ESTAB 5 ~ 40(

F 70-3/ 24) 10 F 70 ~

TRH 293 ' 10 F 70(

10 '0- 1/

10 '0 7) 4 F

'8l 00-5/

F 50 20) 1-131 15 F 000 16 ~ 70( 1/ 24) TRH 293 ' 16 '0( 1/ 9) 2C VALUES <LLD 16 ~ 70- 16(70 BFN DISCHARGE 16 70-

~ 16+70 GAHHA (GCLI) 21 LA-Iit0 7 ~ 000 13 '4( 1/ 15) TRH 293 ' 13 '4( 1/ 4) 6 VALUES <LLD 13 ~ 64- .13 o64 BFN DISCHARGE 13 ~ 64- 13.64 K-40 NOT ESTAB 19 '8(

'0- 2/ 15) TRH 285o2 22076( 1/ 5) 13 '5( 1/ 6)81-214 NOT ESTAB 16 4 '5( 22 '6 1/ 15) TRH 293 ~ 5 22 ~ 76-

'5( 22 F 76 1/ 6) 13 F 75-2 '1( 13 1/

'5 6) 4 '5- 4 '5 4 4~ 25- 4+25 F 51- 2 F 51 PB-214 NOT CSTAB 15 VALUES <LLO 11 ~ 96 l I/ 6)

PB-212 16( 4/ 15) '3l I(t 11 ~ 96-2 F 51(

11 '6 5/ 6)

SR 89 NOT ESTAB 10 F 000 12 F

1 ~ 55- 2 VALUES <LLO

'9 TRH BFN 293e7 DISCHARGE 2

2 '3- ' '3 4) 2 '5 2(76 8 VALUCS <LLO 20 ANAL.YSIS PERFORHCO SR 90 F 000 12 VALUES <LLO 8 VALUCS <LLO 20 ANALYSIS PCRFORHEO TRIT Il)H 330 F 000 351 '8(

'3- 5/ 12) TRH 293 ~ 7 362 '2( 2/ 4) 370 '3( 2/ 8) 2 IJ 336 37u ~ 86 BFN DISCHARGE 353 ~ 57- 370 F 86 351 '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)

NAHE OF FAC ILITY QR~~

LOCA TION OFFACII.ITY L IHQSTONQ ff RRY ALABAHA DOCKET NO+~0-/~9 REPORT!NG.'PERERRATE

~0 0

296 TYPE 'AND LOVER LIHIT ALL CONTROL . NUHBER OF TOTAL NUHBER OF INDICATOR LOCATIONS KOMZlQ~UTgMIQBfkIM~NN

' hl. HEAD .LOCATIONS NONROUT INE OF ANALYSIS DETECTION HEAN (F) NAHE. .HEAN (F) ~ HEAN (F)b REPORTED (l I 2) RANGE PEST~AN E ANQJQR~TETTN RANEE RA GROSS BETA 0 ~ 100 34 29

'3(

'2-

~

4/

40 '

4) MILSON RESERVOIR TRP 259-275 34 ~ 93(

29 '2- 2/

40 55

2) 32~76(

24 ~ 33-.

2/

4 19 2) 6 . 1 ~

GAHHA (GELI )

CS-137 6

0 '20 :0~13(

0 ~ 10-4/,4 0 17

) MILSON RESBRVDIR TRH 259-275 0~

0 14('/

10- F 17

2) 0~13(

0 ~ 10~

2/

0 ~ 16

')

K-40 15 '5(

~

4/ 4) liHEELER RES. 15 '5(

~

2/ 2) 14 '6( 2/ 2):

NOT ESTAB'OT 14 58-

~ 16 '0 TRH 275-349 15 '4-

'1( 16 '6 .

13 F 45- '5sk6 1/')

PB-212 ESTAB 0 F 01( 3/. 4) IIHEELER RES 0 2/ 2) 0 F 01(

=

0 01- 0 01 TRH 275-349 Oa01- 0 ~ 01 0+01 F 01 RA-226 NOT ESTAB 0

~

F 02(

02-2/

~

4) VHEELE,R RES TRH 275-349 0

. 0~

'2(

02"

. '2/

'2 2) 2 VALUESC'LLO 0 ~ 0 ~ 02 0

, 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 LOVER L IHIT ALL CONTROL NUHBCR OF TOTAL NUHBER OF INDICATOR LGCATIONS LOCATION) NONROUT INE OF ANALYSIS OETECTIONa HEAN ([) b HEAN (F) REPORTED Pf,~RQRH~ (l L.k) RANGE RANGE 4/ '8( 2/ PI 2) 22 ~ 56( 4) 24

'1 2) 22+51 100 VHEELER RES (

GROSS BETA 6

0~

18 '9- 29 '1 TRH 275-349 19 '6 29 21 '6 23 F 77 GAHHA (GEL I)

CS-137 6

0 '20 0 '4( 3/ 4) VHEELER RCS 0 ~ 04l . 2/ 2) 0 '7(

'6- 2/

'9 2) 04- TRH 275-349 0 ~ 04- 0 ' 0 0 NOT ESTAB 0 F

'6-l 11 ~ 04 GAGS 4/

'0 4) VHEELCR RES 275-349 11 10

'5l 60-2/

12 '9 2) 9 '7(

9 '0-2/

9 '3 2)

,7 13 TRH ~

PB-214 NOT ESTAB. =0 01( 1/ 4) VHEELER.RCS 0F 01( 1/ 2) 2 VALUES <LLD PB-212 0 '1 F

'1(

0 3/

F 01 4)

TRH 275-349 VHECLER. RES 0~

0 01-02(

0 1/

F 01 2). 2 VALUCS <LLD NOT,ESTAB 0 0 F 00- 0 '2 TRH 275-349 0 '2

'2(

0~02 1/

BE-7 NOT ESTAS 0~

0 32l

'2- 1/ 4) 0 '2 VHEELER RES TRH 275-34'9 0

0 ~ 32- 0 '2 2) 2 0

VALUES <LLO VALUES <LLD SR 89 0 F 500 2 VALUES <LLO ANALYSIS PERFCRHEO SR 90 0 F 100 2 VALUCS <LLO 0 VALUES <LLD ANALYSIS PCRFORHED

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 Ff RRY DOCKET NO ~ 50-259~26~0296 LOCATION OF FACILITY~QH~JOgf AL At)~HP REPORTING PERIOD )982 TYPE AND LOVER LIHIT ALL 'NUMBER OF TOTAL NUHBER INDICATOR LOCAtIONS LOCATION R(ITH HIGHEST ANNUAL HEAh OF ANA(,YSIS OETEC OF I ION HEAN (F) NAHE HEAN (F)43'ONTROL LOCATION(

HEAN (g) hOhgvUTITGE REPORTED PERFORHEO ~(lQ) RANGEb O~GTARC~AR OIRECTJOk RARGE RANGE HEASUREHENTS GROSS BETA 0 100 17 60( 4/ -4) VHEELER RES 20 ~ 13( 2/ '2) 17 '9( 2/ 2)

GAHHA (GCLI )

6 14 '4- 20 '3 TRH 275-349 . 19 '3- 20 F 16 ~ 81-18 ~ 56 ~

6 CS-137 '20 '3( 3/ '4( '

0 0 0 ~ 02-6 '8(

0 '4 4) VHEELER RES TRH 275-349 0

0 F 03(

02-

'8(

~

2/

0 2/

~ 04

2) 0

'3- 2/

0 '4 2)

NOT ESTAB VhiELER RES 7 2) 6O37( 2/ 2)

O'I-214 020 4O75-08(

. 7 '9 2/ 4)

TRH 275-349 7 ~ 56-12(

7 '9 I/ 2) 5 '2-

'4( 7 1/

'3' 0~ 0F VHEELER RES 0 ~ . 2)

PB-214 NOT ESTAB 0.03-0 '2( 1/

F 12 4)

TRH 275-349 VHEELER RES 0~ 12

'0 ~ 02(

0 1/

~ 12 2) 0 04-2 F 0 VALUES CLLO

'4 PB-212 0 ~ 02-01(

0 4'/

'2 'TRH 275-3I)9 0~ 02-

'2(

0002 2/

NOT ESTAB F 4) I'HEELER RES 0 .. 2) 01( 2/ 2)

RA-226 0 ~ 01-2/

0~ 63 4)

TRH 275-349 0 F 01-12(

0 1/

'3 0 0

F F 01- Oo01 1/

'2 2) 2)

NOT ESTAB OOOB( VMEELER RES u ~ 0 ~ 04(

0~ 03- 0 ~ 12 TRH 275-349 0 ~ 12- 0 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).

TABLE 26 RADIOACTIVITY IN SEDIMENT PCI/G - 0 ~ 037 DO/G (DRY MEIGHT)

NAHE OF'ACILITY /ROMPS ffRRY DOCKET NO ~ 50-&$9tgg~0 $ 96 LOCATION OF FACILITY~IHfSTONQ ALAPAHA REPORTING PERIOD ~9 TYPE ANO LOMER LIN IT ALL CONTROL NUMBER OF Atilt'tf TOTAL NUMBER OF INDICATOR LOCATIONS LK4719< HM' IIIMEX~~t>>: L K-5~ LOCAT lot(S NONROUTINE OF ANALYSIS DETECTION HEAN (() NAME MEAN ([) HE AN (( )P REPORTED PgR f,OR~M GAMMA (GELI )

(Len) R 0909(

ANGE.'RHAg g f~tt QQS T Q //~RE I ~Ot 8 R~Ag f, 8

CE-144 '60 20( 2/ 6) 293 ' 20( 2/ 2) 2 VALUES <LLD c

0 Q ~

G ~ 15- 0 '6 BFN DISCHARGE

'8 0~

0 ~ 15- 0 '6 '3(

0 '10 1/

4444(

0 ~ 32( 2/ 2) 2)

C0-60 G ~ 23(

'/ '9 6/ 6) 288 0 TRH

'3- '3

=

0 ~ CG- 0 ~51 0 ~ 13- 0 F 51 0 0 CS-134 080 6). 293e7 6~ 09l 1/ 2) 2 VALUES <LLD c

0F A 0 ~ 09- 3 TRH BFN DISCHARGE

'6 0 ~ 09-I ~ 94(

0 2/

'9 2) 16( 2'/ 2)

CS-137 Qi020 1 ~ 35( 6/ 6) 277 0 0 ~ 91- '9 TRN lu- 2 '9 '4-

~

0 18 K-40 NOT ESTAB 14 ~ 57l 12 ~ 4$ -

2 6/ 6) 15+7)

TRH 277 '8 ll 16-15 1 ~

~

2/

15 '1 2) 0 15 '1(

14aGT-2/

16

~

'5 2)

ZN-65 0 ~ 020 Oq08( 1/ 6) TRM 293 ' Ci06( , 1/

n

2) 2 VALUES <LLD 08- Qa08 BFN DISCHARGE GB-81-214 0 '20 0 ~

I ~ 30(

13-6/

1 45

6) TRM 277 '8 .

0~

I ~ 35(

1 2--

2/

1 ~ 45

2) 1 ~

1 22(

0"-

2/

1 '0 2) 1 ~ ~

2/ 2/

BI-212 0 F 100 1085(

-1 61-6/

2 '6 6) TRH 288078 1 ~

1 ~

89l 78- 2 '1 2) F 75(

I ~ 39- 2 '1 2)2)

PB-214 NOT ESTAB

~

1 ~ 36( 6/ 6) TRH 277 '8 I ~ 53(

),4e-2/

I ~ 57

2) 1 ~ 31(

I ~ 15-2/

46 0 ~ 97- F 57 1 ~

PB-212 NOT ESTAB 1 ~ 56( 6/ 6) TRN 277a98 1 ~ 78( 2/ 2) I ~ 47( 2/ 2) lt20- 1 ~ 89. 1 ~ 67- 1 ~ 89 1 ~ 30- 1464 RA-226 NOT ESTAB 1 ~ 30( 6/ 6) TRM 277~98 1 ~ 35( 2/ 2) 1 ~ 22( 2/ 2) 13- I ~ 25- i+45 05- +40 RA-223 NOT ESTAB 1 ~

0 '8( 3/

1 ~ 45

6) TRM 293 ' 0 '3( 2/ 2) 0 'ol 1 ~

29-1/

1 2) 6 ~ 56- 0 F 89 OFN DISCHARGE 0 ~ 56- ~

0.89 0 ~ 0 ~ 29 RA-224 NOT ESTAB F 83( 5/ 6) TRH 293 ' 1 ~ 94l 1/ 2) I ~ 72( 1/ 2) 1+43- 2+02 BFN DISCHARGE 94- 94 le72- 1 ~ 72 TL-208 0.020 0 ~ 56(

44-6/

'0 ~ 61

6) TRH 277 '8 0 0

1 ~

'0(

'9 1 ~

2/

0 ~ 61

2) 0 0 '5

~ 49l 2/

0 '3 2)

AC-228 0 '60 0 ~

li62( 6/ 6) TRM 277+98 1 '0( 2/ 2) I 51(

~

I ~ 29-2/ 2) 1+37- 75 I 65- 1 ~ 75 1 ~ 73 PA-234N NOT ESTAB 3 ~ 20( 1/

1 ~

6) TRM 293+7

~

3 '0( 1/ 2) 4 '4( 1/

'4 2) 3 ~ 20- 3 "1/ 6)

'0 BFN DISCHARGE 293 '

3 1/

~ 20 4 ~ 64-, 4 SR 89 I F 500 F 13(

2413- 2 '3 TRN BFN DISCHARGE 2~

2~

13(

13- 2 '3 2) 2 VALUES <LLD SR 90 0 '00 6 VALUE <LLD S CD 0

34(

'4- 1/

0 '4 2)

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 TION OF FACILITY LIMESTONE ALABAHA ~

DOCKET NOo~P~~Q~

REPORTING PERIOD 1982 TYPE ANO LOVER LINIT ALL CONTROL NUMBER OF TOTAL NUMBER ANALYSIS OF, INDICATOR LOCATIONS NONROUTINE OF DETECTION NEAN ($ ) NANE NEAN CFb) . ~ -HEAN (Fb) REPORTED ZKEFQBHKD GAHNA (GELI)

~llQl RANGE 0$ 8TA~f ~IIQ,QQRfQT/QN RAmf, ~RA Gf, HEASUREHENTS 6

C0-60 F 080 0 0

'8(

24-2/

0 ~ 53

4) TRH BFN 293 '

0 ISCHARGE 0 ~ 53(

0 ~ 53-1/

0 53

2) 2 VALUES <LLD CS-137 0 F 080 0 0

'7l

~

17-1/

0 '7 4) TRH 288 '6 0 ~ 17C 0 ~ 17-1/

0~ 17

1) 2 VALUES <LLO K-4 0 NOT ESTAB 2 '7(

ll- 4/ 4) TRH 293o7 2 '2( 2/ 2) 2 ~ 34 ( 2/ 2) ll 1 ~ 4 ~ 53 BFN DISCHARGE 1~ 4 ~ 53, 2 ~ 24- 2 ~ 45 ZN"65 0 F 170 1 ~ 33( 2/ 4) TRH 293 ' 1067( 1/ 2) 2 VALUES <LLO 0 ~ 98- 1 ~ 67 BFN DISCHARGE 1~ 67- 1 ~ 67 81-214 NOT ESTAB '2( 3/ 4) TRH 288 F 78 76( 1/ 1) '9( 2/ 2)

PB-214 NOT ESTAB 0

0 0

01-

'9(

~ 0 4/

'6 4) TRH 288 '8 0F 0076 0 F 80(

0 1/

'6 1) 0 0 ~ 02 0 '4(

0 '7 2/ 2)

PB-212 NOT ESTAB 0021-0%66(

0 2/

F 80

4) TRH 288 '8 0 ~ 80-0 87(

0 1/

F 80 1)

Ooll-0 '2( 0 1/

'8 2)

RA-226 NOT ESTAB 0 ~ 45-39l 0

2/

'7 4) TRH 288o78 0 ~ 87-0 '6(

0 1/

F 87 1) 0 2

~ 22 0 ~ 22 VALUES <LLO TL 208 NOT ESTAB 0

0 0

~

~ 01-13(

0 3/

'6 4) TRN 288 '8 0 ~ 76-F 18(

0 1/

'6 1) 0 16( I/ 2)

AC-228 NOT ESTAB 0

~

10-

'1(

~ 0 2/

'8 4) TR'l 288o78 0 ~ 18-0 41(

0 '8

'1/ 1) 0 '6-

~

0 2 VALUES <LLD

'6 0

0021- 0 '1 ~

Oo41 0 '1

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 LOCATION OF FACILITY QROllNS FACILITY'IHfSTOAT/

jjRRY Aj.ABAHA REPORTING PER TOO~9//

LOMER LIHI ALL CONTROL NUMBER OF TYPE ANO t-OC>7 ION it 1TH HIGHEST At'NUAL MEAN LOCATIONS NONROUTINE I'F TOTAL NUMBER INDICATOR LOCAbTIOtiS OF ANALYSIS DETECTION" MEAN ($ ) NAHE MEAN (IF) MEAN (F)b REPORTED t'ISTANCE ANO DIRECTION RANGE RANGE HEASUREHEttTS Pf RfQRHQ) lQLQ) RANGE GAHHA (GELI )

8 CO-60 Oe010 0~ 08( 2/ 6) TRH 293 ' 0 ~ 13( I/ 2) 2 VALUES <LLO 02- 13 BFt DISCHARGE 0 13- 0 13 K-40 NOT ESTAB 0

0

~

~ 22l C ~ 15-9~

3/

9 ~ 30

6) TRH 288 '8 0 0 ~

22(

15-2/

0

~

~ 30

2) 1~51(

1 ~ 51-1/

I ~ 51 2)

BI-214 0 '50 0 ~ 17(

07-5/ 6) TRH 288 ~ 78 0 ~ 28(

~ 10-2/

45

2) 0 ~ 87(

0~67-1/

0 87 2) 45 0 0 ~

PB-214 0 '59 0

0

~

'2(

9

.5/

~

6) TRH 288 F 78 0 ~ 40( 2/

~

2) 0 '7(

07-2/ 2) 07-. 68 0+13" 0 68 0 ~ 0 87 PB-212 NOT ESTAB 0

0

~

~ lll 0 5/

~

6) TRH 288 '8 0 '1( 2/

~

2) 0 '2(

'2-F I/ 2)

'2 0 ~ 04- 0 ~ 29 0 ~ 12 0. 29 0 0 RA-226 Gi050 F 17( 5/ 6), TRH 288o78 0 ~ 28( 2/ 2) , 2 VALUES <LLO G ~ 07- 45 0 ~ 10- 0 ~ 45 TL-208 0 ~ 020 0 '5(

02-0 5/

~

6) TRH 288 '8 0 F 05(

0 F 05 2/

06

2) 2 VALUES <LLD 9 06 0 ~

AC-228 0 ~ 060 G ~

0 ~ 18( 5/

~

6) TRr 288.78 0 '7( 2/ 2. 0 ~ 10( I/ 2) 0 09- 0 30 9 ~ 24- 9 ~ 30 CD 10- 0 ~ 10 5 '5(

~ ~

SR 89 F 000 5 '5(

25-1/

5 '5 6) TRH 277~98 5 '586( 1/

5 '5 2) 2 VALUES <LLO 5 ~

90 000 I ~ 66( 6/ 6) TRH 288 F 78 1 ~ 2/ 2) 1 ~ 36( 1/ 2)

SR 1 F 1 ~ 19- 2 '0 I ~ 63- F 10 I ~ 36- I ~ 36

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 51 E

ESERVOI R MONITORING NETWORK R

N Elk River WHEELER DAM mile 274;90 mile 277.98 Rogersyille 0

mile 29l.76 mile'82.6 Athens 0

~mile 285.2 8;F.. NUCLEAR PLANT S

Champion Paper Co.

ile 28878 mile 293.50 mile 305.0 0

Courtland.

mile 293.70 0

Decatur mile 307.52 Scale of Miles

~ - Automatic Sam ter

Figure 12 Aweu. AVERAGE Operational BeSS fhW MlvtTY CO C preoperational O CII Phase tH SURFACE tlATER Phase

~ I oo CI IJ 8RQlOS FERRY IIUClEAR P4OT ca Ci CI CO oI r4

~

IC 0 Q LI

'tS C

'o o Average:

w0 Preoperational Phase' T

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 RADIOACTIVITY LEVELS 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 RADIOACTIVITY LEVELS BROWNS FERRY NUCLEAR PLANT ANNUAL REPORT -

PR/RH

<1984'VA/NUC Ayril 1985

TENNESSEE VALLEY AUTHORITY CHATTANOOGA. TENNESSEE 32401

~;- 400 Chestnut

'2 Street Tower II 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 ~ ~ ~ ~ ~ ~ 3.1X List of Figures. ~ ~ ~ 0 ~ 1v Introduction Atmospheric Monitoring Terrestrial Monitoring ~ 0 ~ 1 23 Reservoir'onitoring Quality Control. ~ ~ ~ ~ ~ ~ ~ ~ 0 ~ 55 Data Analysis.

Conclusions. 55 11

4

<<~

LIST OF TABLES Table I - I'.nvironmental 1(adioactivity Sampl.ing ScheduJe Table 2 - Atmospheric and Terrestrial Monitoring Station Locations - Browns Ferry Nuclear Plant .

Table 3 - Detection Capabilities for Environmental Sample Analysis Table 4 - Results Obtained in Interlaboratory Comparison Program Table 5 - Jfaximum Permissible Concentrations for Nonoccupational Exposure 13 Table 6 - Radioactivity in Air Filter 14 Table 7 - Radioactivity in Rainwater 15 Table 8 - Radioactivity in Heavy Particle Fallout . 16 Table 9 - Radioactivity in Charcoal Filters 17 Table 10 - Radioactivity in Milk 26 Table Table ll 12 Radioactivity Radioactivity in in Vegetation Soil 27 28 Table 13 - Radioactivity in Well Water 29 Table 14 - Radioactivity in Public Water Supply 30 Table 15 - Environmental Gamma Radiation Levels 31 Table 16 - Radioactivity in Cabbage 32 Table 17 - Radioactivity in Corn 33 Table 18 - Radioactivity in Peaches 34 Table 19 - Radioactivity in Peas 35 Table 20 - Radioactivity in Potatoes 36 Table 21 - Radioactivity in Poultry 37 Table 22 - Radioactivity in Tomatoes 38 Table 23 - Sampling Schedule - Reservoir Monitoring 45 Table 24 - Radioactivity in Surface Water 46 Table 25 - Radioactivity in White Crappie (Flesh) 47 Table 26 - Radioactivity in Smallmouth Buffalo,(Flesh) 48 Table 27 - Radioactivity in Smallmouth Buffalo (Whole) 49 Table 28 - Radioactivity in Sediment . 50 Table 29 - Radioactivity in Clam Flesh . 51 Table 30 - Radioactivity in Clam Shell 52

h LIST OF FIGURES Figure 1

- Tennessee Valley Region ]0 Figure 2 - Atmospheric and Terrestrial Monitoring Network 18 Figure 3 - Local Monitoring Stations 19 Figure 4 - TLD Locations, BFN 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 7 Direct Radiation Levels, BFN 40 Figure 8 - Direct Radiation Levels, BFN (4-Quarter Moving Average) 40 Figure 9 - Direct Radiation Levels, WBN 41 Figure 10 - Direct Radiation Levels, WBN (4-Quarter Moving Average) 41 Figure ll - Reservoir Monitoring Network 53 Figure 12 - Annual Average Gross Beta Activity in Surface Water 54

V V

ENVIRONMENTAL RADIOACTIVITY LEVELS 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 Laboratory (WARL) located in Muscle Shoals, Alabama.Area'adiological 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 RADIOACTIVITY SAMPLING SCHEDULE Air Charcoal Rain- Heavy Particle River Well Public Aquatic Life Station Locations Filter Filter water Fallout Soil V~oototioo Milk Water Water Water and Sediment Foods Muscle Shoals M Lawrenceburg M Rogersville M Athens M Decatur M Courtland M M Site 1 (N) M M Site 2 (NNE) M M Site 3 (ENE) M M A Site 4 (NNW) M M A Site 5 (WSW) M M A Farm B Farm S""

Farm P W Farm L W Farar E Farm W Control Farms Onsite Well Wheeler Dam Elk River Tennessee River Champion Paper Co.

Various Local Farms W - Weekly M - Monthly (Every 4 Weeks) 9 - quarterly S - Semiannually A - Annually

""Discontinued operation November 19B4

Table 2 ATHOSPHERIC AND TERRESTRIAL MONITORING STATION LOCATIONS BROWNS FERRY NUCLEAR PLANT Approximate Distance Approximate Direction Sam le Station From Plant From Plant LM-1 BF, North 1.0 Mile ( 1.6 kilometers) N LH-2 BF, North-Northeast 0.9 Mile ( 1.4 kilometers) NNE LM-3 BF, East-Northeast 1.0 Hile ( 1.4 kilometers) ENE IA-4 BF, North-Northwest. 1.7 Hiles ( 2.7 kilometers) NNW I.H-5 BF, West,-Sout,hwest. 2.5 Hiles ( 4.0 kilometers) WSW PH-1 BF, Rogersville, AL 13.8 Hiles (22.2 kilomct,crs) NW PH-2 BF, Athens, AL 10.9 Hiles ,(17.5 kilometers) NE PH-3 BF, Decatur (Trinity), AL 8.2 Hiles (13.2 kilometers) SSE PH-4 BF, Courtland, AL 10.5 Hiles (16.9 kilometers) WSW RH-1 BF, Muscle Shoals, AL 32.0 Miles (51.5 kilometers) W (Control)

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

Farm S"" 4.75 Miles ( 7.6 kilometers) N Farm 8 7.0 Hiles (11.3 kilomet,ers) NW Farm 1. 5.0 Hiles ( 7.0 kilometers) NE Farm P 8.8 Hilcs (14rl kilometers) E Farm E 6.1 Hi les ('9.8 kilomct,ers) NE Farm W 6.9 Hiles (11.0 kilomctcrs) NF.

I'a rm N (Control) 27.0 Hilcs (43.4 kilomctcrs) NW Farm J (Cont,rol) 40.0 Miles (64.4 kilometers) NNW Fa rm C (Control) > 32.0 Miles (51.5 kilometers) N Farm Ca (Control) 32.0 Miles (51.5 kilometers) W Fa rm Cb (Control 22.5 Hilcs (36.2 kilometers E H (Control) 22.5 Miles (36.2 kilometers) 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)*

Fish Air Vegegation Soil and Clam Flesh, Foods, Meat, Particulates Charcoal Fallout Water and Grain Sediment Plankton, Clam Shells Poultry, Milk

~cr/ 1

~cr/ 1 ci/K 1 . Kcr/1 I>~Ci i~Dr ~ci/ D ~Ci/ Dr ~Ci/ Dr ~cj/K D r Kci/1 Gross a 0.005 2.0 0.05 0.35 0.1 0.7 Gross B 3H 0.01 0.05 . '.3 '.20 0.70 0.1 0.7 25 330 1311 0.02 0.05 89Sr 0.005. 10 0.25 1.5 0.5 5.0 40 10 9OSr 0.001 2 0.05 0.3 0.1 1.0 8 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 LIMIT OF DETECTION (LLD Air Water Vegetation Soil and Clam flesh Foods, (tomatoes 'Meat and particulates and milk and grain sediment Fish and plankton Clam shells potatoes, etc.) poultry

~CI NaI*

/

Li ** NaI

~ct/I Li

~ct/ L day Li)

N~ci/ dna Lf

~Ci/ ~dr)/

Lt

~>~Ci/ ~drZ

~GLI

~Ci/ ~dr)N I Lt Li

~Ge ~Ge - NaI ~Ge NaI ~Ge NaI ~GG Nai ~G* NaI Ge(Li) NaI ~Ge 141>> 144Ce 0. 03 38 0.55 0. 35 0.35 0.35 , 38 90 144ce -

O.O2 33 0.22 0.06 0.06 0.35 0.06 33 40 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 44 200 90 3

103N106Ru 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 8 50 20 Oa04 40 0.65 0.45 0.45 0.45 40 150 106Ru 0.03 40 0.51 0.11 0;11 0.74 0.11 40 90 4Cs 0.01 0.02 10 26 0.20 0.33 '0:12 0.08 0.12 0.08 0.48 0.12 0.08 10 26 40 50 Cs 0.01 0.01 10 5 0.20 0.06 0.12 0.02 0.12 0.02 0.08 0.12 0.02 10 5 40 15 96Zr-Nbo. 01 10 0.20 0.12 0.12 0.12 10 40 9szr O.O1 10 0.11

• 0.03~,, 0.03 0.15 0.03 10 20 0.01 5 0.05 0.01 0.01 0.07 0.01 5 15 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 5 55 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 5 40 15 Zn OG02 Oaol 15 9 0 25 Oa 11 Q 23 P 02 0 23 OG02 Oa 17 OG23 Oa02 15 9 70 20 60co 46K 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 5 30 15 0.10 150 2. 50 0. 90 0;90 0.90 -

150 400 1<<Ba-La O.OZ 15 0.68 0.15 055 0.15 15 50 14oB 140La 0.02 0.01 25 0.34

0. 08 0.07 0.02 j 0.07 0.30 0.07 25 50 7 -

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 ese LLD vava1 ues are expected to vary depending on the activities of the components fn the as~plea. These figures do not represent the LLD values a ues ac eva ble on given samples.

achiev 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 Marinelli beaker as dry weight. The average dry weight is 400-500 grams. Air filters and very small volume samples are co in a 0 5 L centered on-the detector endcap. The counting system consists of a ND-6620 multichannel analyzer and germanium detector 20 Percent. The counting time is normally 4-15 hours. All sPectral analysis is Performed using the software Program etector havi fff av ng an efficiencyf of am HYPER. p f is made that all .samples are analyzed wit'hin one week of the collection date. ~ ~ Th assumption The Conversion factor: 1 pCi x.7 x 10 2 Bq.

Na

TABLE 4 RESULTS OBTAINED IN INTERLABORATORY COMPARISON PROGRAM A. Air Filter (pCi/Filter)

Gross Al ha Gross Beta Strontium-90 Cesium-137 EPA value TVA EPA value TVA EPA value TVA EPA value TVA Date (+3o) ~AV ~ (+3a) ~Av . (+3a) ~Av . (+3a) ~Av .

a 11/83 19+9 <1 50+9 40 15+3 16 21+9 20 3/84 15+9 18 51+-9 60 21+A 20 11+9 10 8/84 17+9- 17 51+9 60 18+& N/A 15+9 15 B. Tritum in Urine (pCi/1)

Date EPA value (+30) ~TVA Av 2/84 2383+608 2466 11/84 2012+598 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)

Gross Al ha Gross Beta Strontium-89 Strontium-90 Tritium Iodine 131 EPA value TVA EPA value TVA EPA value TVA EPA value TVA EPA value TVA EPA value Date (i3o) ~Av . (+3a) ~Av (+3a) ~Av . ~3a) ~A ~3a . ~Av . ~(AAa 1/84 10+9 10 1219 15 36+9 39 24i3 '23 3/84 5+9 6 20+9 20 4/84 3508+630 3580 6+0.8 6 5/84 3+9 6k9 6 25i9 32 5i3 6/84 3081+622 2770 7/84 6i9 6 13f9 16 8/84 2817+617 2607 34+10 36 9/84 519 5 16i9 12 34k9 41 19i3 18 10/84 2810+617 10/84 11/84 1419 7+9 ll8 64+9 20+9 60 22 ll+9 12 12i3 13 2517 12/84 31821624 3400 36+10 33 D. Gamma-Spectral Analysis of Water (pCi/1)

Chromium-51 Cobalt-60 Zinc-65 Ruthenium-106 Cesium-134 Cesium-137 EPA value TVA . EPA value TVA EPA value TVA EPA value TVA EPA value TVA EPA value TVA Date (i3a) ~Av (+Ma) ~Av . ~(~3a ~A (+3a)

~Av . ~(~3 a ~A (+3o) ~Av .

2/84 ~ 4019 <44 10+9 11 50+9 50 61+9 53 3119 29 16i9 15 6/84 66+9 72 3+9 32 63%9 66 29i9 <40 47+9 44 37+9 37 10/84 4019 43 20+9 22 14749 151 47i9 48 31+9 29 24+9 26 10/84 14+9 17 2+9 <5 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 EPA value TVA EPA value TVA EPA value TVA EPA value TVA EPA value TVA Date (+3a) ~Av . (+3a) ~Av . (i3a) ~Av . (i3a) ~Av . (+3a) ~Av .

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

S troat ium-89 Strontium-90 Iodine-131 Cesium-137 Potassium-40 f value value TVA Date EPA

(+3a)

TVA

~Av .

EPA

(+3a) 'Av . EPA

~(33a value TVA

~Av .

EPA

~(3a value TVA

~A EPA

~(33a value TVA

~A 3/84 6+0 9 6 6/84 25-9 24 17+A 18 43 bio 39 35'-9 34 1496+-130 1483 10/84 22+9 26 16+3 - 15 4)+10 - 40 32+9 30 1517+132 1563

d. Values reported as mg K/kg.

e. Lost in sample preparation.

f. Values reported as mg K/1.

LOVISVLLE IN 0. TENNESSEE VALLEY REGION (

c (TVA NUCLEAR PLANT SITES)

VOWENSBORO V A 1

(

~r K E N T U C K Y P4OVC4 v

/ BOWLING GREEN V (

~

M /

j.i,. M I

'I ~

} -

t

~/ V~~4r / I

/ 4SNVILL ORII RIGGED N iN E S S N rC A R.

I VRCNSONg ( I/ ~Vlf

(~r r 1 I

NENRNIS I

\

I NVSCLE SNORLS BLN gNVNTSVILLE

(

tq SON

/

7 CH4TTANOOG4m

'Y')

1 I

e S

/ Jl C A

~

R LEGEND

/

M I SS.

I I

A L.A B A

/J M A G EORG I A

~X8 -WATTS BAR NUCLEAR PLANT

-SEOUOYAN NUCLEAR PLANT

- BELLEFOHTE NUCLEAR PLANT

-. 8ROWNS FERRY NUCLEAR PLANT

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 exposure.

nonoccupa-'ional

'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 MAXIMUM PERMISSIBLE CONCENTRATIONS FOR NONOCCUPATIONAL EXPOSURE In Mater 'n Air

~Ci/1* ~Ci/m

• Alpha 30 Nonvolatile beta 3, 000 100 Tritium 3,000,000 200,000 1 37Cs 20,000 500 103>106R 200 10,000'0,000 44Ce 200 Zr- Nb 60,000 1,000 140Ba 140L 20,000 1,000 131I 300 100 6sZn 100,000 2,000

'4Mn 100,000 1,000 6 0(o 30,000 300 "Sr 3,000 300 90Sr 300 30 "Cr 2,000,000 80,000 134C 9,000 400 0Co 90,000 2,000 1

• 1 pCi = 3.7 x 10 Bq.

TABLE 6 RADIOACTIVITY IN AIR FILTER PC I/M (3) - 0 ~ 037 8 0/V. (3)

NAME GF FACILITY EBQBJQEEBBJ DOCKET NO ~ 29=222c209c22E LOCA TION Of FACILITY tIIUEBIQHE-TYPE AND LONER LZHZT ALL CONTROL NUMBER OF TOTAL NUMBER CF INDICATOR LOCATIONS LQt hIIQb MIIU bISJESI hbUQSL HE'S~ LCCAT IOTAS NONROUTINE OF ANALYSIS DETECTION HEAN (F)b NAM c MEAN ([) MEAN (F) REPORTED EEBE985EQ ILL92 8889Eb QI~~IBUQE 889-QIBEQII95-----BASGE----- 8689E EPKQBELEHIE GROSS ALPHA 0 ~ 005 0 01( 1/ 50) 5C 0 ~ 01- G 01 02( 437/ 466) ATMENSr AL 02( 50/ 52) 0 02( 96/ 102)

GROSS BETA 568 0 ~ 010 C C ~ 01- OeC4 1C 9 HILES NE 0

O.C1- G.O4 0 ~ 01- 0 '4 GAHHA (GELI)

,1 43 K-40 NGT ESTAB Ceoz( 58/ 117) LM2 BF NORTH 0 C2( 5/ 13) 0 ~ 01( 12/ 26)

G GO- 0 C4 0 ~ 9 MILE NNE 0 ~ C1- 0 04 0 ~ 01- C~ 02 BI-214 O.GZO CD 02( 1/ 117) LH1 BF NORTHilEST 0 C2( 1/ 13) 0 ~ 02( 1/ 26)

C.OZ- O.oz 1 ~C MILE N 0 ~ C2- 0 02. 0 ~ 02- G ~ 02 BI-212 NOT ESTAB 0 '1(

C.01:-

1/ 117) 0 01 RCGERSVILLEr AL 13 ~ 8 HILES NN 0 01(

0 G1--

1/

0 13) 01 26 VALUES <LLD PB-214 " O.C20'- CD 02( 2/ 117) LV1 BF NORTHMEST 0 ~ C2( 1/ 13) 0 '2(

0>>02-1/ 26)

CD 02- 0 ~ 02 1 ~C MILE N 0 ~ C2- 0 ~ 02 G~ 02 PB-212 NDT ESTAB 0+00( 21/ 117) LV5 BF DAVIS F 0 ~ CO( 2/ 13) 0 00( . 6/ 26)

C.oo- 0 ~ GG 2 ~ 5 MILES bSN 0 ~ CO" 0 00 0 ~ Oo- 0 00 BE-7 0 '50 C ~ 06( 85/ 117) ATHENSr AL O.C7( 10/ 13) 0 F 07( 18/

'2; 26)

CD 05- 0 '1<< 10 9 MILES NE 0 ~ C5- 0 ~ 10 0 F 05- 0 TL-208. NGT ESTAB C.OO( 19/ 117) COURTLANDr AL 0 ~ Co( 1/ 13) 0 F 00( 6/ 26) 00- 0 F 00 1G ~ 5 HILES NSQ =0 ~ Co- 0 00 0 F 00- 0 00 AC-228 NOT ESTAB C~

G 00( 8/ 117) LV3 BF NDRTHEAsT 0 ~ CO( 1/ 13) 0 '1(

0 ~ 00- -

2/ 26)

AGO- 0 ~ Co 1 AC HZLE ENE Oo 00- 0 00 0 ~ 01 PA-234M NOT ESTAB CD 18( 2/ 117) ROGERSVILLEr AL 0 ~ 19( 1/ 13) 26 VALUES <LLO C ~ 17- 0 19 13 ~ 8 HILES NM 0 ~ 1 9-. 0 ~ 19 SR 89 0 F 005 36 VALUES <LLO 8 VALUES <LLC ANALYSIS PERFORHEO SR 90 0 '01 3e VALUES <LLD 8 VALUES <LLC ANALYSIS PERFORHED

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 RACIOACTIVITY IN RAINMATcR PCI/L - 0 ~ 037 80/L NAHE OF FACILITY BEQll8S EEEEI DOCK T NO ~ SQ=2S2c24Qc220 LOCATION OF FACILITY LIUrSIQllE REPORTING PERIOD 12SB TYPE AND LOME R LIMIT ALL CONTROL NUHSER OF TOTAL NUHBcR CF INDICATOR LCC4TIONS I QQBIIQll llLIU bIQllESI BhllQBl llCBU NOhRCUTINc OF ANALYSIS DETECTION HEAN (F) NAME HEAN (FT MEAN (F) REPORTED EEEEQEHEQ LLLQ? EBtlQC QISIBllQ= BllQ QIEEGIIQU BBQQE h EBllQEb 5EBSQECLE5IS GAHHA (GELI) 132 K-4C NOT ESTAB 22 33(

'7" 9/ 108) LH1 BF NORTHMEST 38 ~ 51 ( 1/ 12) 27 '2(

'5 2/ 24)

BI"214 NOT ESTAB 6

~

93(

45 '8 52/ 108) 1 ~ 0 MILE h CCURTLANDr AL 38 ~ 51-7 6(

38 ~ 51 11/ 12) 21

'5( 33 F 00 14/ 24) 0 '3-5 28 '8 10+5 MILES MSM 0 ~ 77- 28 ~ 18 6

0 '0" 28 '8 PB-214 NOT ESTAB 4 '8( 29/ 108) COURTLANDr AL 6 20( 8/ 12) 9 '9(

'2- 5/ 24) 24 '3 PB-212 NCT ESTAB C~ 07-

'0( 20 '1 35/ 108) 1C ~ 5 HILES ATHENSr AL MSM 1 ~

2 46-46(

20 ~ 11 5/ 12) 3 F 80( 5/ 24)

'2 0 '9 '4 1

18" 4 o2 10 ~ 9 HILES NE 1 e20 4 3 45 '9(

CD BE-7 NOT ESTAB 49 37( 28/ 108) RCGERSVILLEr AL 58 F 88( 4/ 12) 8/ 24) 29 '6- 99 '0 13mB MILES NM 42 ~ 48- 99 '0 38 '5- 71 '9 TRITIUM 330 F 000 108 VALUES <LLD 24 VALUES <LLD 132 ANALYSIS PERFORHED

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 RADIOACTIVITY Ih HEAVY PARTICLE FALLOUT 8"'AME MCI/KH(2) 570COOOO ~ 00 EQ/KV(2)

OF FACILITY EBQHHE EEBBI DOCKET NO >Q=2%2c28Qc228 LOCATION OF.FACILITY t,IgEEIQHE 8L6E886 - REPORTING PERIOD $ QE$

TYPE AND LONER LIMIT ALL CONTROL NUMBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LQE6IIQB HIIU EIQtfEEI 8h5Q6L UE88~ LOCATIO)lS NOhROUTINE OF ANALYSIS DETECTION MEAN (F)

-b NAPE MEAN (() HEAN ([)P REPORTED BE8El!BELEUZE Lt LQX B859R QI I85QE 85Q QIBEQIIQB B889E B8UQE BEBEQBHEQ GROSS BETA 0 '50 0 '2(

C.06-114/ 11 6) 1.25 LM4 SF TRAILER P MILES 0%46(

0 '1" 12/

'512) 0 ~ 16(

0 '6- 25/

0 '626) 142 1 ~7 NNM 1

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 RADIOACTIVITY IN CHARCOAL FILTERS PCI/M(3) " 0 ~ 037 BQ/M(3)

NAME OF FACILITY gggggg ffggg DOC<ET NO ~ ZQ=222c2ftQc22fj LOCATION OF FACILITY gggfgIQHf I Pfogg RcPORTINu PERIOD TYPE AND LONER LIMIT ALL CONTROL NUMBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LQG'BIiQb 8!IU UIGUf5I dhUllhL Hf BH LOCATIONS NONRCUTINE OF ANALYSIS DETECTION a MEAN (F) b NAME MEAN (F) E MEAN (F) REPORTED B689f b QISISHQf QIBEGIIQU BhUGf BBHG~gb 5f hf QBf f fHID I

Rf BEQSBf Q ODIN E-1 31 1LLQ?

0 020 CD 02( 27/ 463)

BUQ LY2 BF NORTH 0 ~ C3( 2/ 52) 0 '2(

'2- 10/ 1C2)

'3 565 0 02- 0 '4 0 ~ 5 MILE NNE 0 ~ 02- 0 03 0 0

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 PM-IBF WHEELER ROBE SVIL OAM OAM ATHENS FLORENCE PM-2BF FFIEL MUSCLE HUNTSVILLE BROWNS FERRY SHOALS NUCLEAR PL NT RM-I BF LEIGHTON TUSCUMBIA COURTLANO PM-4 F OECAT R PM-DBFO IO MILES pRUSSELLVILLE GUNT SVIL HARTSELLE OAM 25 HALEYVILLE CULLMAN 45 MILES Q- ENVIRONMENTAL MONITORING STATION NOTE: THE FOLLOWING SAMPLES ARE COLLECTED FROM EACH STATION:

AIR PARTICULATES RAINWATER RADIOIODINE SOIL HEAVY PARTICLE FALLOUT

Figure 3 LOCAL MONITORING STATIONS BROWNS FERRY NUCLEAR PLANT ATHENS U.. HWY 0

0 ALA. HWY 20 Legend 4 Air Monitor DECATUR A AUtomatic Well Sampler H Dairy Farm Other Forms Scale 0 I 2 Miles

20 Figure 4 I

') I TLD Locations ~

I, BFN p>>gg

)

~ I

>>I<<

<<L~wak. s)

Nl

,>>II I )/ ~

~(,<<p, I

r... D L

'I ~ ~ 11 N I '1>> >>>>, f<<

fr. I I

I

("I '.$

I q)C ~II w'C III I

II r /II

, +o) A I) )~1 r

,r

~ I I rr

) ,'), /"

~ r I

'/ L, ) <<1,)1)) I I

I N. r

/ I,

~

wIW

,(I

~I 4 l~

j,'c" "

I Ql IN ". ~

I"'

! ) 'N N o I'C<<

C<<,

NI 'k L'I 1

w C wl N 1>> ' I

) r O' I, .'ICC ). 'i C I

I I)

• ) ) ) 0'I

~ I

~<,

)(

Ir ~

I I

))

I I' C.II gkc'

'L ~

Ig

. -t" I'r 1~

( k'.

,/ Ir. 1,)

I

Figure 5 heauu AVERAGE

.30 6ROSS SETA ACTIVITY IN AIR FILTERS Hearn FERRY NUCmu< PLANT Preoperational Phase I Operational Phase

.25 C

O Cl C

o H

'. 20 C 4l C cO C C

A Ch o I lJ A C O O Ll Q

C C o

.15 Ave~ra e: Preo~erational Phase

.10

.05

.1 C I

1973P 197 30 1974 1975 1976 19 7 1978 1979 1980 1981 1 82 1983 1984 1968 1969 1970 1971 19 72

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 for specific gamma-emitting radionuclides. The results are and'nalyzed given in tables 16 through 22.

f

TABLE 10 RADIOACTIVITY IN HILK PCI/L - 0 ~ 037 BQ/L NAME OF FACILITY BBQUUS fEBBI DOCKET NO ~ 5Q=2S2c25Qc22(!

LOCATION OF FACILITY LIUESIQUE SI.BEBUNG iREPORTING PcRICO //BED TYPE AND LONER LIMIT ALL CONTROL NUMBER OF TOTAL NUHBER CF INDICATOR LOCATIONS l.QEIIIQU UJIU UIQUESI hhUllhl BEAU~ LOCATIONS NONROUT INE OF ANALYSIS DETECTION a MEAN (F)b NAPE MEAN ($ ) HEAN ([)b RcPORTcO b

EEBEQBUEQ SLl.kl BBUQE QESISUQE 6UQ QTBEQITQU BOUSE .BBUQE UESSQBE" EUIS IODINE-1 31 0 '00 195 VALUES <LLD .302 VALUES <LLC 497 ANALYSIS PERFORMED GAMMA (GELI) 124 CS-1 37 5 ~ 000 7 55(, 7/ 48) PAGE FARM 8 20( 4/ 12) 67( 1/ 76) 5 '5-

~

11 '1 8 75 MILES E

~

5 15- 11 ~ 01 5

5

~

67- 5 '7 K-40 NOT ESTAB 1271.95( 48/, 48) SMITH FARH 1337 93( 10/ 10) 1 270 F 05( 76/ 76) 881 '9" 17o7 99 4 75 HILES N 1155 58- 1787 ~ 99 789 '9- 1839 '6 11 '5(

~

BI-214 NOT ESTAB 27/ 48) PAGE FARH 19 15( 10/ 12) 7 43( 55/ 76) 19 '7 F

0.47- 126 o7 8 ~ 75 HILES E 1 ~ 11- 1?6 67 0 36-214

• NCT ESTAB 19 05( 13/ 48) 39 ~ E6( 4/ 12) 6 '6( 38/ 76)

PB F 00- 140 '0 PAGE FARH 8 ~ 75 HILES E ,0 '0- 140 '012) 0 '2" 25 '4 PB-212 NOT ESTAB C~

2 21(

0 F 80-10/ 48) 3 80 PAGE FARM Bi?5 HILES 2 '3(-

231" 2/

274

'9(

0 '2-1 22/ 76) 4 '1 TL"208 NOT ESTAB 0 '1( 11/ 48) SMITH FARH E

22( 5/ 10) 0 '3-1 33( 20/ 76)

'9 0 '2" 1

AC-228 21( 5/

3 '148) 4 ~ 75 MILES N 037-1/

331

13) '9( 2 7/ '?6)

NOT ESTAB LCCNEY FARF 13+36( 5 8~

2 '3- 13 '6 5%75 MILES ENE 13m 36- 13 ~ 36 Oe?2- 25 '2 SR 89 10 000 46 VALUES <LLO 76 VALUES <LLD 122 ANALYSIS PFRFORHED

90. 41/ 10/ 88( 71/

SR 122 2 COO 4 2

26(

23- 7 29

46) SHITH FARH 4 ~ 75 HILES N 5~ 10(

3 ~ 49 7 ~ 29

10) F 2e'07- 8 '976)

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 VEGETATION PCI/G '- 0 037 BC/G (DRY hEIGHT)

NAME GF FACILITY EBQ}{t{S EEBBI DOCKET NO ~ SQ=2SRA28Q4228 LOCATION OF FACILITY LIHESI{}5E 8L8{}8t{8 REPORTING PERIOD TYPc AND LOWER LIHIT ALL CONTROL NUMBER OF TOTAL NUMBER OF INDICATOR LOCA)IONS LQC8IIQ1 }{IIU }{IQUESI 85t{ll8L }{E8t{ 8 LOCATIONS NCNROUTINE OF ANALYSIS DETECTION a HEAN (F) NAMc MEAN (F) HEAN (F)b REPORTED BEBEQB}{EQ Il LQ2 B8HQE QISI85CE 85Q QIBECIIQ}{ -B8}{QE b B8}{QEb UE8SMBELE}{IS GROSS ALPHA 0 ~ 050 0 05( 1/ 1) SHITH FARH 0 ~ C5( 1/ 1) 1 Ce05- Oeo5 4 ~ ?5 HILES N 0 ~ G5- 0 05 GROSS BETA 0 ~ 200 7 ~ 94( 1/ 1) SMITH FARM 7 ~ 94( 1/ 1) 1 7 94- 7 94 4 75 'MILES N 7 ~ 94- 7 ~ 94 IODINE-131 0 00( 161/ 194) 13/ 00( 19/

0 ~ Co(

'113) 26)

NOT ESTAB LM1 BF NORTHWEST 0 220 0 F 00- 0 01 1 ~C HZLE N 0 Co- 0 0 ~ 00- 0 01 GAHHA (GELZ) 235 C0-60 0 ~ 060 0 ~ 14( 1/ 193) LH1 BF NORTHWEST 0 ~ 14( 1/ 13) 42 VALUES <LLO 0 ~ 14 0 14 1 ~C HILE N 0 ~ 14- 0 ~ 14 CS-137 0 ~ 060 0 ~ 08(

0 06-11/ 193) 0 ~ 15 SMITH FARM 4e?5 HILES N 0 ~ 15(

0 ~ 15-1/ 13) 0 ~ 15 0 '2(

0 ~ 07-5/ 42) 0 ~ 25 K-40 NOT ESTAB 10 '5(

~

193/ 193) LH2 SF NORTH 14 35( 3/ 13) 13 '2( - 42/ 42)

BZ-214 0 ~ 100 e.46-0 ~ 17(

40 ~ 10 57/ 193) 0 9 HZLE NNE ATHENSr AL 1 ~ 25-0 25(

1 34 '3

.1/ 13) 0 82-0 '9(

~ 39 '4 14/ 42) 0 ~ 10- 0+43 1C ~ 9 HILES NE 0 ~ 25- 0 ~ 25 0 '1- 0 '8 BI-212 NOT ESTAB 0 '7(

e.o6-10/ 193) WISER FARH 0 ~ 37( 1/ 13) 0 '?( 3/ 42) 0 ~ 38 6 ~ 9 HILES NE 0 ~ 37- 0 37 0+25 0 ~ 48 PB-214 NOT ESTAB 0 08( 167/ 193) 0 ~ 00- 0 40 EVANS FARM HILES NE 0 '1(

0 01-13/

'0 13) 0 '0( 35/ 42) 6%1 0 0 00 0 ~ 42 0 '6(

~ F PS-212 NOT ESTAB 0 F 04( 136/ 193) LH4 SF TRAILER. P 0 CB( 12/ 13) 25/ 42) 0 ~ 00- 0 27 1a? HILES NNW 0 ~ C2- 0 ~ 16 0 00-F 0+27 RA-223 NOT ESTAB CD 12( 1/ 193) LH5 BF DA VIS F 0 ~ 12( 1/ 13) 42 VALUES <LLO 0 1 2- 0 ~ 12 2 ~ 5 MILES leSW 0 ~ 12- 0 12 SE-7 NOT ESTAB 5 F 88( 192/ 193) ROGERSVILLEr AL 9 ~ 71( 12/ 12) 6 53( 42/ 42) 0 ~ 21- 25 72 13 ~ 8 HILES NW 1 ~ 23- 25 ~ 72 0 88- 1?e23 TL-208 NOT ESTAB 0 ~ 02( 114/ 193) LH3 BF NORTHEAST 0 ~ C4( 6/ 13) 0 02( 21/ 42) e.oo- 0 ~ 10 1 C HILE ENE 0 Co- 0 ~ 10 o.oo- e.1o AC-228 NOT ESTAB 0 ~ 11( 111/ 193) ATHENSr AL 0 31( 4/ 13) 0~11( 18/ 42)

C~ 00- 1 ~ 15 10 ~ 9 HILES NE 0 Ce- 15 Oeeo- 0 ~ 33 PA-234H NOT ESTAB 3 64(

2 ~ 78-4/ 193) 4 96 LH1 SF NORTHWEST C HILE N 4 ~ 96(

4 ~ 96-1 1/

4 96

13) 2 '3(

2 03-1/

2 '3 42)

SR 89 0 '50 CD 48( 5/ 46) LP4 BF TRAILER P 0 ~ Ee( 1/ 3) 6 VALUES <LLC 52 0 ~ 29 0 ~ 80 1 ~7 HILES NNW 0 ~ 80- 0 80 SR 90 0 ~ 050 0 ~ 26( 45/ 46) ROGERSVZLLEr AL 0 75( 3/ 3) 0 46( 6/ 6) 52 0 05- 1 G5 13 ~ 8 HILES NW 0 ~ 63- 0 ~ 86 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 RADIOACTIVITY IN SCIL PCI/O C ~ 037 BC/G (CRY MEIGl;T)

RANE CF FACILITY f fQjjgg DOCKET NO ~ $ Q=f$ 2cfyQcggy L'OCATION OF FACILITY $ $ 5fgZQDf BLkf858: REPORTING PERIOD $ 2fg TYPE ANO LOWER LIMIT ALL CONTROL NUMBER OF TOTAL NUNBER CF, INDICATOR LOCATIONS I QQP IIQh HIXU UIQUfBI k hUllBt 5f hB LCCAT ION) NONROUTINE OF ANALYSIS DETECTION MEAN (F) b NAME HEAN (F) ~ HEAN (F) REPORTED Ef EEQBBf Q SLLQ} 885Qf QISIhUQf 65Q QIBfQIIQH BBHQf BhHQf 5fhkQBf LfUI5 GAHHA (GELI) 11 CS-134 0.080 CD 16( 1/ 9) LN1 BF NORTHMEST 0 ~ 16( 1/ 1) 2 VALUES <LLC 0 16" 0 ~ 16 MILE N 0 ~ 16- 0 16 CS-137 0 '20 C 39(

C ~ 06-9/

1 ~ 03 9) 1 ~C LM5 BF DAVIS F 2 5 HILES LSW 1 '3(

1 ~ C3-1/

1 ~ 03

1) 0 0

51(

'6- 2/

0 '6 2) 0.250 5.28( 9/ 9) LM4 BF TRAILER P 7 ~ 29( 1/ 1) 4 63( 2/ 2) 3 ~ 32- 7 ~ 29 1 7 HILES NNM 7 ~ 29- 7 29 4~ 15- 5 ~ 11 BI-214 F 00( 9/ 9) 30( 1/ 1) 06( 2/ 2) 0 ~ C50 G ~ 61- 1 ~ 30 1 LH1 BF NORTHWEST

~C MILE N 1 ~

1 ~0- 1~0 1

0 '0- 1 '1 2)

BI-212 0 '00 1.24( 9/ 9) LN1 BF NORTHMEST 1 89(

89-1/ 1) 1 30(

'5- 2/

'5 2)

C 75- .1 ~ 89 1 ~C HILE N 1 ~ 1%89 1 1 PB-214~ 0.050 1 ~ 10( 9/ 9) LN1 BF NORTHWEST 1 ~ 47( 1/ 1) 1 ~ 13( 2/

CD 68 1 47 10HILEN 1% 47- 1 ~ 47 0 ~ 98- 1 28 PB-212 NOT ESTAB 1.08( 9/ 9) LN1 BF NORTHMEST 1 ~ 60( 1/ 1) 1 16( 2/ 2) 0 '7 1 60 1 ~C NILE N 1 ~ 60- 1 60 1 ~ 15-

'6( 1 ~ 17 RA-226 0 050 1.00(

0 ~ 61 9/

1 ~ 30

9) LH1 BF NORTHWEST

.1 ~ C HILE 1 0(

1 ~ 30-1/

30

1) 1 0 '0- 2/ '1 2) 1 RA-223 NOT ESTAB G 35( 4/ 9) ATHENSr AL N

0 43(

1 1/ 1) 0 '9(

'9- 1/ 2) 28- 0 ~ 43 10 ~ 9 HILES NE 0 ~ 43- 0 43 0 0 29 RA"224 NOT ESTAB G

1 '9(

67-6/ 9) OECATURr AL 1 ~ 47(

47 1/

1%47

1) 2 VALUcS <LLO 47 8 ~ 2 MILES SSE 0 '9(

0~ 1 1 ~

BE-?. 0 160 9 VALUES <LLO 1/ 2) 0 19

~ 0 19

~

TL-208 '20 0 38( 9/ 9) LH1 BF NORTHWEST 0 53( 1/ 1) 0 '2( 2/ 2) 0 0 20- 0 '3 9) 1 ~C HILE N 0 '3" 0 53 1/

0 42"

'8(

F 0 42 2/

F 2)

AC-228 0 060 1 13( 9/ LN1 BF NORTHWEST 1 ~ 68( 1) 1 PA-234H G.60-"

'4( 1 5/

'8 9) 1~C MILE N 1 ~ 68-64(

1 ~ 68 1/ 1) 1 ~ 15-2 ~ 19(

1 ~

1/

22 2)

NCT ESTAB 2 1 '0- 3 '4 VALUES <LLO LH1 BF NORTHWEST 1 C MILE N 3

3 ~ 64- 3 '4 2 ~ 19- 2 ~ 19 2 VALUES <LLO SR 89 1 500 9 ANALYSIS PERFORHEO SR 90 11 0 '00 9 VALUES <LLO 0 0

'4(

'4- 1/

0 '4 2) 11 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 RADIOACTIVITY IN NELL HATER PCI/L - 0 ~ C37 BC/L NAME CF FACILITY EBQgbg f EBBI DOCKET NO ~ EQ=222A25QA225 LOCATION OF FACILITY LIgEEZQBE BLflEh58 RF PORTING Pc RICO TYPE ANO LO'MER LIMIT ALL CONTROL NUMB ER OF TOTAL NUMBER CF INDICATOR LOCA)IONS LQQBIIQh BJIU UIQUEKI 85UQhL BE85 ~ LOCATION) NDNROUTINE OF ANAL'YSIS DETECTION a HEAN (F) NAPE MEAN-(F) MEAN (F) REPORTED b b BEBEQBBEQ SLLQ2 B65QE QIGIhUQE 65t'IBEQIIQ5 B65QE BBBQE 5EBR!lBELEtlIX GAMHA (GELI) 26 K 40 NOT ESTAB 21 78( 1/ 13) BFN NELL 06 21 78( 1/ 13) 15 ~ 98( 2/ 13) 21

~

~ 78- 21 ~ 78 0 ~ C2 MILES N

~

21 ~ 7 8- 21 78 12 F 05-

'4( 19 '1 BI-214 NOT ESTAB 7 '3(

12-11/

14 '013) BFN NELL A6 0 ~ 02 HILES N 7 23(

0 ~ 12-11/

14 30

13) 187 14 '7" '44 13/ 13)

'213)

PB-214 NOT ESTAB CD 7 50(

'4- 7/ 13) BFN O'2 NELL A6 7 '0( 7/ 13) 186 '2( 13/

28 92-2 13 26 HILES N 2 ~ 74- 13 26 367 80 PB-212 NOT ESTAB 1 '7(

0 07 F

3/

2 '213) BFN NELL N6 0 C2 HILES N 1.C7(

0 ~ C7-3/ 13) 2 ~ 3Z 3 89(

3 '0-3/ 13) 5 '1 TL-208 03( 2/ 13) 03( 2/ 13) 0 64( 3/ 13) 0 '1-BFN WELL N6 0 '6 NOT ESTAB 0 '9-1 ~

AC-228 1

1 VALUES <LLD

'8 0 ~ CZ HILES 0 ~ ~9- 1~68 4 '9( 2/ 13)

NOT ESTAB 13 2 '7- 6 '0 TRIT IUH 330 F 000 4 VALUES <LLO 4 VALUES <LLC ANALYSIS PERFORHED

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 LOWER LIHIT ALL CONTROL NUrBER OF TOTAL NUHBER OF INDICATOR LOCATIONS LQGBIIQh HIIU UIQUEEI Bhtlght, BEIB LOCATIONS NONROUTINE OF ANALYSIS DETECTION a rEAN (F)b NAHE HEAN (F) ~ HEAN (F) b REPORTED REBEQB5jg LLI gl Bhtlgj b QIEIhHQE 659 QZBEQIIQU b BBUQE b BEPKQBEEESIE GROSS BETA 90 2 400 241-00( 46/

510

77) CHAHPICN PAPER 282 '

3 '2(

'6-BSUQE 40/ 52) F 06(

'5- 5/

'113)

TRH 2 5 10 2 3 GAHHA (GELI) 91 K-40 NOT ESTAB 17 88( 6/ 78) CHAHPION PAPER 18%62( 5/ 52) 28 73( 1/ 13) 9 '0-

~

33 '6 TRH 282 ' 9 70- 33 '6 28 '3- 28 73 BI-214 NOT ESTAB 5 '4(

14-46/ 78) 24 79 WHEELER DAHr AL TRH 274 '

6 '6( 129/ 9813) 2.85-6 23(

3 '9-9/

8 '713) 4 '8(

CD PB-214 NOT ESTAB 35-26/

19%47

78) CHAHPICN PAPER TRr 282 '

5 '7( 14/19 '752) 0%41-

~

5 '0(

1%84-6/ 13) 11 '6 PB-212 NOT cSTAB CD

'9(

0 '5-1 23/

4 '0 78) SHEFFIELDrAL TRH 254 '

ROB 2~

0%58 38( 4/ 13) 4 '0 1 '5(

0 37-6/ 13) 4 44 TL-208 - NOT ESTAB 18(

0 '8-11/ 78)

~ WHEELER OAH~ AL '7( 2/ 13) '5( 5/ 13)

'8 '3( 4/ '252) 1 1

'2

~

1 3 TRH 274 ' 1%22 0%23 2

'9( .

~ 1 AC-228 NOT ESTAB 6 7/ 78) CHAHPION PAPER 7 0 96( 1/ 13)

F 08- 17%19 TRr. 282.6 1 ~ 08- 17 ~ 19 0 '6- 0 '6 SR 89 10 F 000 12 VALUES <LLD 4 VALUES <LLO 16 ANALYSIS PERFORHED SR 90 F 000 12 VALUES <LLO .4 VALUES <LLD ANALYSIS PERFORHFD TRITIUH 330 F 000 12 VALUES <LLD 4 VALUES <LLD ANALYSIS PERFORHED

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

>6 16.7+1.3 16.4+1.1 15.9+2.6 17.1+1.5

Average, 0-2 miles I ~

(Onsite) 19.5+1.8 19.3+1.7 21,2+3.2 20.2+1.7

Average,

>2 miles (Offsite) 16.9+1.3 17.2+1.6 16.9+2.8 17.6+1.6 a

Date normalized to one quarter (2190 hours0.0253 days <br />0.608 hours <br />0.00362 weeks <br />8.33295e-4 months <br />) b All averages reported +le (68/ confidence level)

TA 8L 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 LoiiER LIMIT ALL CONTROL NUHBER OF TOTAL NUMBER OF INDICATOR LOCATIONS I QQBIIQ5 BJIU LIQllffI hh5llhL llfhH ~ LOCATIONS NCNROUTINE OF ANALYSIS DETECTION a HEAN (F) b HAKE HEAN (F) HEAN (F) b REPORTED Ef BEQB5f Q Sl LQ? BellQf b QIRIhUQf 85Q QIBfQIIQB. BBUQf B85Qf b 5f BKQBftfUIX BETA 25 F 000 3903 ~ 25 ( 1/ 1) 7 HILES NNR 3903 ~ 25( 1/ 1) 368? ~ 1 8 ( 1/ 1)

GROSS 2 3903 '5- 3903 '5 3903 25- 3903~25 3687 ~ 1 8- 3687 ~ 1 8 GAHHA (GELI)

K-40 2

NOT ESTAB 1557 ~ 05( 1/ 1) 7 PILES NNR 155? ~ C5( 1/

1557 F 05- 1557 05

1) 2257 '9(

225?a49- 2257 1/

'9 1)1) 1557%05- 1557%05 BI-214 NOT ESTAB 1 VALUES <LLO 4 ~ 96( 1/

4 ~ 96- 4 ~ 96 PB-214 NOT ESTAB 1 V ALUES <LLO 5 '3(

5e13-1/

5 ~ 13 1) 1/ 1/ 1) 0 ~ 91( 1/

PB-212 NOT ESTAB 2 2

24(

'4-

~

2 '4 1) 7 FILES NNli 2 ~ 24(

2 '4- 2~24 0 ~ 91- 0 '1 1)

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).

TABLE 17 RADIOACTIVITY IN CORN PCI/KG - 0 ~ 037 BG/KG (MET MEIGHT)

NAHE OF FACILITY BBQHHl EEBBX DOCKET NO 59=222c25Qc225 LOCATION OF FACILITY lIHESIQHE gLgggHg REPORTING PERICo 1256 TYPE ANO LONER LIMIT ALL CONTROL NUHBER OF TOTAL NUHBER OF INDICATOR LOCATIONS LQCBIIQH HIIH HIQHESI SHHUBL HE6H LOCATIONS NONROUTINE OF ANALYSIS DETECTION MEAN ($ ) NAME MEAN HE AN (F $ REPORTED BEBEQBHEQ SLLQ? BSHQE 5HC QIBECIIQH BBHQE HEBRUBCLCHI5 (F9'IGIhHCf GROSS SETA 25 000 3551%07( 1/ 1) 7 MILES NNM 3551 ~ 07( 1/ 1) 1/

'aHQd'172%74(

1) 2 3551 F 07- 3551 07 3551e07- 3551 07 2172 74- 2172.74.

GAHHA (GELI) 2 K-40 2254 39( 1/ 1) 2254 ~ 39( 1/ 1/

BI-214 NOT ESTAB NOT ESTAB 2254 '9- 2254 39 VALUES <LLO 7 HILES NNM 2254 '9- 2254 '9 1) 2094 54(

2094 3

'4-86(

2094 54 1/

1) 1)

PB-214 NOT ESTAB 1

1- VALUES <LLO F 86-0 '8(. 1/

3 '6 1) 0 '8- 0 '8 PB-212 NOT ESTAB 44( 1/ 1) 7 ILES NNM. 44( 1/ 1) VALUES <LLO 1 '4-1 ~

1 '4 P 1 ~

1 ~ 44- 1 ~ 44 1

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

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

TABLE 18 RADIOACTIVITY IN PEACHES PCI/KG - 0 ~ 037 80/KG (hET %EIGHT)

NAME OF FACILITY EBQ852 Pf BBI DOCKET. NO ~ GQ=222A2{iQc228 LOCATION OF FACILITY LIUEEIQbE TYPE AND LOWER LIMIT ALL CONTROL NUMBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LQQ8IZQb HIIU UIQUEZI 8hUQ8L 5E88 8 LOCATIONS NONROUTINE OF ANAL'YSIS DETECTION a MEAN (F) b NAME MEAN (F) MEAN (F) REPORTED QIEI85QE 85Q QIBEQIIQ5. B85QE B85QE 5E85QBEBEBIS--

PEBEQBBEQ GROSS BETA ELLQ?

25 F 000 2273 65(

B88QE 1/ 1) 4 MILES N 2273 ~ 65( . 1/

'5- '5 1) 2772 '5(

'5- 1/

'5 1)

GAMMA"(GELI) 2 2273 65- 2273 '5 2273 2273 2772 2772 2

K-40 1955 30( 1/ 1) 4 MILES 1955 ~ 30( 1/ 1) 1595 F 08( 1/ 1)

NOT ESTAB 1955 '0-C.79(

1955 1/

'0 1)

N 1955 ~ 30- 1955

'9( 1/

'0 1) 1595 ~ 08- 1595 F 08

'9( 1/ 1)

BI-214 HILES 0 5 0 '9 '9 NOT ESTAB 4 N

'0 79- 0 '9 0~ 79- 5 79- 5

'7( '7( 1/ 1) '6( 1/ 1)

'7- 1/1/9 '7 1) 4 MILES N -

PB-214 NOT ESTAB 9 9 2 9 ~ 47- =

9+47 2~ 46- 2 46 PB-212 NOT ESTAB 9

0 '8( 0 '8 1) 4 HILES N 0 '8( 1/

'8 1) 1 ~ 68( 1/

'8 1) 0 '8 0 ~ 98- 0 1 68- 1

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 RADIOACTIVITY IN PEAS PCI/KG - C 037 SC/KG (HET HEIGHT)

NAME CF FACILITY QEQE55 EEBBZ DOCKET NO~ 2Q=222c24QcZ25 LOCATION OF FACILITY Lj5ESIQHE hL62555 REPORTING PERICD TYPE AND LONER LIMIT ALL CONTROL NUHSER OF TOTAL NUMBER OF INDICATOR LCCATICNS LQQhIZQb HJIU tfIQUEKI hhHUhL 5EhB~ I LOG AT 0QS NCNRCUTINE OF ANAI.YSIS DETECTION MEAN (F)

-b NAFE HEAN ([) HEAN (g) REPORTED Ef BEQE5EQ SLLQ? QZSISHQf hUQ QlERQIIQU 855QE 5ESRQEELFUI5 GROSS SETA 2

25 F 000 6965 '6(B68QS 1/ 1) 6965 66- 6965 66 4 FILES N 6965 66(

6965 '6-EBUQE 1/

6965 '6 1) 5614 87(

561 4 ~ 87 1/

561 4 ~ S7 1)

GAHHA (GE LI) 2 K-4C NCT ESTAB 3461 '9( 1/

3461 ~ 39- 3461 +39

1) 4 FILES N 3461 ~ 39.( 1/

3461 39- 3461 39

1) ~ 3651 65(

3651 65- 3651 1/ 1)

'5 BI-214 NOT ESTAB 6 03( 1/ 1) 4 FILES N 6 C3( 1/ 1) 1 VALUES <LLD 6 03- 6 03 6 ~ C3- 6 03 PB-214 NOT ESTAB 5 '3(

'3 1/

5 03

1) 4 FILES N 5 5

~ C3(

~ C3-1/

'3 1) 1 VALUES <LLD 5

5 ~ 03- 5 03 5+C3-5 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).

TABLE 20 RADIOACTIVITY IN POTATOES PCI/KC - 0 ~ 037 BC/KG (NET HEIGHT)

NAME OF FACILITY ag{}55$ EcEEI DOCKET NO. NQ-222A25QA225 LOCATION OF FACILITY L j5EEIQ5E BLBEB5B RcPORTING PERIOD JgpB TYPE ANO LO'NER LIMIT ALL CONTROL NUMBER OF TOTAL NUHBER OF INDICATOR LOCATIONS LQQAIIQ5 HII5 5IQUESI 455QBL 5EB5~ LOCATIONS NONROUTINE OF ANALYSIS DETECTIONa MEAN (g) b TAHE MEAN (j) HEAN (g) REPORTED EEEEQ85EQ Il LQ 1 BB5QE QIEIB5QE A5Q QIEEQIIQ5 BB5QE EB5QE

'0( 1/

5EBkllEELE5IE GROSS BETA 25 OOOO 7312.07( 1/ 1) 7 rILEs NNv 7312.c7( 1/ 1) 6571 1) 2 7312 F 07 7312 F 07 7312 ~ 07" 7312 07 6571 ~ 60- 6571 ~ 60 GAHHA (GcLI) 2 K-40 NOT ESTAB 3287o97( 1/ 1) 7 rILEs NNM- 3287 ~ 97( 1/ 1) 3924 ~ 85( 1/ 1)

'/

3287o97" 3287.97 3287o97- 3287 ~ 97 3924.85- 3924 F 85 BI-214 NOT ESTAB 2 '3(

2.73-1/

2m 73

1) 7 NILE 5 NNN 2 ~ 73(

2 '3- 1/

2 '3 1) 3.29(

3 '9" 1/ 1) 3 '9 1)

PB-214 ESTAB 78( 1/ 1) 7 rILES NNN Oo78( 1/ 1) 12 44(

0 '8" NOT CD 0.78- 0+78 0 F 78 12 44- 12 ~ 44 PS-212 83( 1/ 1) rILES 0 '3( 1/ 1) VALUES <LLD 0 '3-NCT ESTAB CD 7 NNM 1 Ce83- 0.83 0 ~ 83-

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 RADIOACTIVITY IN POULTRY PCI/KG - 0 ~ 037 BQ/KG (lrET NEIGI T)

NAME OF FACILITY EBQBUX EEBBZ DOCKET NO ~ XQ=222c28QA225 LOCATION OF FACILITY LIVE/IDEE T'YPE ANO LONER LIHIT ALL CONTROL NUHBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LQG8IIQh 'dLIU UZQUESI 8hUD8I. UE88 LOCATIO!jS NON ROUTINE OF ANALYSIS DETECTION MEAN ($ ) NAME HEAN (FT HEAN REPORTED 5E 85l!BEBEUIB gF)'8SQ.

DIE I85QE 85K D! BEQIIQH B88QE Bf BEDEWED GROSS BETA SOLD?

25 F 000 5016.47(

B8BQE 1/ 1) PAGE FARH 5016 ~ 47( 1/ 1) 4902 '4(

'4- 1/

'4 1) 2 5016 '7 5016 '7 8 ~ 75 HILES E 5016 ~ 47- 5016 ~ 47 4902 4902 GAHHA (GELI) 2 1/ 2511 ~ 67( 1/ 1) 2317% 20( 1/ 1)

K-40 NOT ESTAB 2511 67(

2511 ~ 67- 2511 1/

'7 1)1) PAGE FARH 8 75 HILES E 2511 67- 2511 ~ 67 12 '2( 1/ 1) 231? 20- 2317 ~ 20 8 ~ 41( 1/ 1)

BI-214 NOT ESTAB 12 62( PAGE FARH 12 ~ 62- 12 '2 8 75 MILES E 12 ~ 62-

'1( 12 ~ 62 1/

8 "41=

90(

8 ~ 41 1/ 1) 1/ 1)

'1 1)

PB-214 NOT ESTAB 8 61( PAGc FARH 8 8~

8 ~ 61- 8 ~ 61 8%75 HILES E 8%61 8 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).

TA8LE 22 RACIOACTIVITY IN TOMATCES PCI/KG - 0 ~ 037 SQ/KG (MET MEIGl'T)

NAME CF FACILITY BQUUg EEBBI OOCKET. NO fQ 222AZCQc2R4 LOCATION OF FACILITY LIUEBIQUE Sl SESUS RcPORJING PERICO $ gE$

TYPE ANO LONER LIMIT ALL CONTROL iVUMBER OF TOTAL NUMBER CF INGICATOR LCCATIONS LQCSIIQU HIIU UIQUESI ShUUSL UESU~ NONROUT INE OF ANALYSIS OET ECTION MEAN (F) NAME MEAN (F) MEAN (F) REPORTED BEBEQBUEQ ILLQ? BSUQE b QIEXSUCcE SUB DIBEQIIQU BSUQE BSUQE UESEll BEUEUIE GROSS SETA 25 000 1617 91( 1/ 1) 7 FILES NNM 1617 91( 1/ 1) 3007 ~ 66( 1/ 1) 2 161? 91" 1617 ~ 91 1617 91- 1617 91 3007 66- 300'7 ~ 66 GAMMA (GELI) 2 K-40 NOT ESTA8 2161.25( 1/

2161.25- 2161 ~ 25

1) 7 rILES NNM 2161 25(

2161 '5- 1/

2161 '5 1) 2552 '2( 1/

2652 92- 2652%92 1)

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 4J cl ANNuu AVERAGE Cl '0 Q

JJ JJ 6ROSS BETA ACTIVITY O CC Preoperational Operational CJ Phase Phase I N HRI M>e 1976 1977 1978 1979 1988 1981 1982 1983 1981

41 Olrect Radlatlon Levels Ilalts BN Nuclear Plant 22 Ii Il e One i te I

~'

1 le I 0

I l,a tt

~

I I I o.'

Ott stteo I

o-+

! i! I i j I o~ I 16 I I I

I lj I'2 e 1 ~

'e I

'e w I I' 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 ensile L

e 0 O.g e~%

0 18 I

e i 'e-o

~..e-o y'"~

.0" e I Oftstto o o~ e o

16 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 Water Samples River/river mile phytoplankton fauna Sediment Fish (collected monthly)

Tennessee 277.9 K Tennessee 285.2 Tennessee 288..7 X X Tennessee 291.7 Tennessee 293.5 Tennessee 293.7 X (discharge area)

Tennessee 305.0 (Control)

Tennessee 307:5 X X (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. h.

TABLE .24 RACIOACTIVITY IN SURFACE LATER TOTAL PCI/L - 0 ~ 037 EQ/L hAHE CF FACILI Y inQnb~ Q "RRAikQA2o>

LOCAT

CN OF FACILITY L3ME)IQbE REFORTI.iu FERICO 19~4 TYPE ANO LOwER LIHIT ALL CONT RCL .'iUro R CF TOTAL NUHBER CF INCICATOR LCCATIOtiS LQSAIIQh tt3IU LIQiifkI >h'dQAi "f85 LOCATIONS tiCti ROUT I NE OF ANALYSIS OETECTIOh a YcAN (F) b NAYE rEAN (F)sS YcAN ([)b REPORTED 2EEEQEQEQ I Li..? 4 JQs QISIoNQf ~bi QIB=QI3Qb "ASQE E659E "-821!" f t'-hIS GROSS ALPHA 2.C00 E VALUES <LLC 1 VALLES <LLC ANALYSIS PERFORr.EO GROSS BETA 1

2 '00 3 '2( 27/ 39) TRY 3 31(

Ze54-8/ 13) 3 '2(

2~43-d0/

12a06 26) 65 Zo54- 5e18 4o25 GAHHA (GELI) 6c K 4C NCT =STAB 21.09( 5/ 39) TRY 285 ' 23 '5(

23.C5-1/ 13) 23 43(

'4- 2/ 26) 27.12 ED 59-, 38.69 23.05 19 BI-214 5.56( 14/ 39) 293 ' 8 ~ 39( 5/ 13) o 57( 15/ 26)

NCT cSTAB 61- 1S 71 TRY BFh CISCHARGc 2.18- 18 71 0 'Z-

~

26 '726)

PB-214 NCT ESTA3 CD 3.06( 7/ 39) TRY Z93 F 7 3 '5( 4/ 13)

'4 3) 6 71( 14/

C.01- -~ 14 BFN DISCHARGE 0 72-

~ 7 0 ~ 59- 18 ~ 1C PB-212

~ lc

,'tCT c ST,AB 1'1 ( 20/ 3.9) TRY- 285 2 F 64( 5/. 2.64( r 7/ 26)

C ~ 10- 4 ~ 52 0.99- 4. 52 1

0 'd- 5 '5 VALUES <LLG SR d9 10 ~ 000 12 VALUES <LLO 8 ZC ANALYSIS PERFORt'EO SR 9E 2 CGO 12 VALUcS <LLC 8 VALUES <LLC 2C ANALYSIS PERFORHEO TRIT IUH 330 . COO 387 92( 2/ 12) . TRY 293 ' 416 ~ 31( 1/ 4) 8 VALUES <LLD 2C 359 53" 416 31 416 ~ 31- 416 31

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)..

TABL E 25 RADIOACTIVITY Ih NHITE GRAF F I E (FLESn)

PCI/O C ~ 037 BC/0 (CRY 4 EIGI T) hANE CF FACILITY f ggQ)lbA" j3$ I NO ~ cQ 2+2A REPORTING FERICC RQCRXa--------

LOCATICN OF FACILITY LgQ $ $ Q>f BLAfn58 TYPE ANO LONER LINIT ALL CONTROL )LI'5ER GF TOTAL NVABER CF IN"ICATOR LCCATIONS LQCRXTQh l(kent t?QLl=cI khhQAL-L= LOCATIONS Y~i ROUT Ihf Y.EAN (F)b

'( YEAN (F) NEAN (F)

OF ANALYSIS OETECTIOh a NAYc REPCATE" PEBfQ3"=EQ SI I QR oANnc Si QO b QckIhdQcc bhQ Q13ccQIIQh 8ABQ 4cb EBhQE r~faccQB'YfbT$

)) 2/

GROSS BETA 6

0.100 Zge19(

21 'C-4/

33 ~ 50

4) wNEELER RES TRY 275-349 29 25 ~ 1>>-

2/

~ 9o ZZ.B9(

20 '6- 37 '3 2)

GAHHA (GELI)

CS-1 3? 0.020 C C9( 3/ 4) NILSON RESERVCIR 0~ 11( 1/ 2) C~ 09( 2/ 2)

C.CE- 0 11 TRY 259-27c 11 C 11 0.07" C 11 K-4C NCT ESTAB 15 3C( 4/ 4) 'NNEELER RES 16m

~

14( 2/ 2) 14 '9( 2/

~

2) 12.8C- 1? 51 TRIP 275-649 14.77- 1?s51 11o72- 16.85 BI-214 0 ~ CZO C.C4( 1/ 4) NFEELER Rcg C+C4( 1/" 2) 0 02( 1/ 2)

C.04- 0.04 TRY Z?c- 0 c4 ~ 04 C.02- C ~ 02 PB-214 NCT "STAB CD 17( 2/ 4) ILSON REScMVCIR C. 8( 1/ 2) .0.03( 1/ 2)

CD 05" 0.28 TRY 259"275, C 28- C ~ 28 0.03- 0 03 1/ 1/ 2)

PB-212 NCT ESTAB C C~

01(

01-1/

0 01

4) NYEcLcR RES TRY 275-349 G.C1 (

0 ~ C1 0 '1 2) O.OC(

0.00- 0 ~ OC SR 89- 0 '00 2 VALUES <LLD 1 VALVES <LLC ANALYSIS P ERFORYEO SR 9C 0 ~ 100 2 VALUES <LLO 1 VALUES <LLC ANALYSIS PERFORHEO

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$ OGCKET HO. ~G=ii2ci(tGAi24 LOCATICh OF FACILIT'Y f,qLr~c$ Jg~u REFORTI!tG FcRI u ]$ ~s~

TYPE ANO LO~ER LIP IT ALL COhTRCL NLt'BER OF TOTAL KU,'tBER CF IACICATCR LCCATICttS LQ{;AITQh H1t) hatt'dt;5I AhtiUBL "RhU~ LCCATICttS hChRCI.'T IhE OF ANALYSIS CETECT Ch PEAtt (c) VcAh (g) PGRTcG REBFQRCKQ LI l 0 1 8hhct- fiT516bki Bbk Q~ Bf;CIIQb RAbki u=tt'MS'""gIS GROSS BcTA 0 2c.56(

'2- 4/ 4) WHEELER RE< 32 'B(

'r- 2/ 2) 20>>42( 2/ 2)

GANESA (GcLI) 12 39 '8 TRODI 275-345 25 39 'd 19 F 86- 2G ~ 98 CS-157 OoC23 C ~ 05( 3/ 4) trHccL R RCS Q. 6( 2/ 2) 0.05( 1/ 2)

CD G4- G.C7 TRY. 275-349 C C4- 0 07 0.05- C.06 K-40 DICT ESTAB 12 96( 4/ 4) 'WHEELER RE< 15 44( 2/ 2) 12. 11( 2/ 2)

BI-Z14 0.020 2.8 6" 1b.33 2/

TRY 275-349 12 ~ 55- 15.33 9 '4" 14 BE C ~ C4( 4) 4'ILSOtt REScRVCIR 0 ~ C5( 1/ 2) 2 VALUES <LLC C.04.- G.G5 TRR 259"275 0 ~ C5- 0.05 PB-214 NOT FSTAB CD G4( 3/ 4) ttILSOtt RESERVOIR GsC5( 1/ 2) F 02( 2/ 2)

C.GZ- 0.7o TRF.'59-275 0 ~ C6" 0.0o 0.01- G ~ 03 P3 212 ttCT ESTAB C'o 01 ( 1/ HHEELER RES 0 C1( 1/ 2) 0 '01( 2/ 2)

C.G1- G.G1 TRr 275-349 0.01 0 F 00- 0.01 SR 89 0.5GG 3.VALUES <LLC 1 VALLES.<LLC 4 A'tALYSIS PERFORREO SR 9C 0.100 VALUcS <LLO 1 VALUES <LLC 4 AttALYSIS P ERFORHEO

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

b..'tean and:ange based upon detectable "easurements only. 'Fraction'of'detectable s ecified measuremen nt s .at spec e oca ons is;-indicated locations s;- in parentheses (F).

TABL= 27 R'DIGACTIVITY IN SYALLYOUT. Bl.FFALC ('iJMGLE)

PCI/O - C.C37 BC/G ('RY ~EIGYT) tiAME CF FACILITY c3lig"'$ OCChET NO ~ >Q-agog,7ggg,P>>"

LOCATION OF F'CILITY gIg" $ Iggc "CARn5A REFORTItiG PERICD TYPc AND LOii R L Y IT ALL CONTRCL Nl "" =R C.

CF INCICATCR LCCATICiVS LQCRIIGh 'JJIId tiatt~caI chUUkL Llchtt~ LOCATIONS NCNRCL1 INE TOTAL NUMBER OF ANALYSIS CETECTICNa McAN (F) tJAYc MEAN (F) YEAiV (F) RcPC" TEG oitti9B"'9 CLt ~2 865(th

.b O':IBDCJ; hh'C QIB=CI'JJ5 Shfik= A,,

hCE b EAKllc=p=hIS GROSS ScETA 0 ~ 109 ZC ~ 52( 4/ I) NILSON RESERVCIR 23 ~ co( 2/ 2) 15+90( 2/ 2) 6 13.60- 33.71 TRt'59-275 13.c9- 33 ~ 71 15 ASS- 16+25 GAMMA (GELI)

CS-1 37 0.929 C 04( 2/ 4) NILSOtJ RcScRVCIR 0 ~ C4( 2/ 2) G.02( 1/ 2)

CD C3- 0 G4 TRJ Zc9-2?c 9 C3" 9.04 0 Go- G ~ OZ X-4C VCT ESTAB 56( 4/ 4) NILSON RcSERVCIR 9.65( 2/ 2) 7 ~ 61( 2/ 2)

ED 7 '7- 10.79 TRt'59-275 E c1 0 ~ (4(

10 79 1/ 2) 7 ~ 61-0.05(

?o62 1/ 2) bl-214 0.920 C ~ 03( 2/ 4) WILSON RESERVCIR C.GZ- G. 4 TRJ'59-275 0 ~ C4- 0 ~ 04 0 ~ CS" C ~ 95 PS-214 NCT cSTAB C.94( 2/ 4) HHEELER RES G.C5( 1/ 2) 0,04( 1/ 2)

CD G3" Go05 TRY 275-349 G.CS" GROS 0 ~ 94- 0 ~ 94 PS-212 NCT ESTAB C 01( 1/ 4) 'iJYEELER RcS G.C1( 1/ 2) Ge01( 1/ 2)

C C1 0 01 TRJ'?5-349 G.C1" 9 01 0.01- Ce01 RA-223 tJCT ESTAB C.26( 1/ 4) NI<SON RESERVCIR 0.26( 1/ 2) 2 VALDES <LLC C ~ 26- 0.2o TRY 259-275 0 ~ 20 0 ~ 2o 0 ~ 069 C.Gd( 1/ 4) NILSON RESERVCIR O.Co( 1/ 2) 2 VALUcS <Lt C AC-228 C.GB- 0 08 TRY 259-2?5 G.CB- G.GS 0.590 2 VALtJES <LLG 1 VAI.LcS <Li C SR 89 ANALYSIS PERFORMED SR 9C G~ 190 2 VALUES <LLO G~ 23( 1/ 1) 0.23- CD 23

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

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

TABLE 28 RADIOACTIVITY IN SEC IHEhT PCI/G - 0 ~ Gc7 BQ/G (ORY ttEIGHT) hAHE OF FAcILIT Y igggb$ iin3$ OCCKET .'tC. 5~>-i2ociRQc2zR LOCATICh OF FACILITY j,j vc$ 'Igni REPG<TIttG P RI-w 1225 TYPc AttO LOwER LIMIT ALL CONTRCL Nt!rBER OF TOTAL NUHBER CF IhOIC "TGR LOCA/IGNS LQLAIAQh 'd?ItI BIttliiZ Ahi984 L'ih~i LCCATIOhS t>GKRCLiTINc OF AtiALYSIS "ETECT Ot HEAti (F ) NAH 8 HcAN (F) 8 t'E A tt (F) RcPGRTcO 2iECQEhi2 KI.L-.? >> Uaaw GliIhttli 65K OIBifiI95 Alki Ngc riAkllRi"iBIR-GAHHA (GcLI CO-60 G. C10 C.31 ( v/ o) TRr 277 98 C.82( 1/ 2) 0.02 ( 1/ 2)

CS-134c 0.0c 0 C 27-C.14(

0+36 2/ c) TRY 293.7 0 v2-0.1.7(

0 1/

'2 2) 0.02-2 C.02 VALUES <LLC 1C- 0 17 BFh OISCHARGc 0 17- 0 ~ 17 CS-137 O.CZG C

C ~ 90(

C.78-

"/ 6)

'2 o)

TRr 277 '8 G 95(

G 78-

.2/

12

2) 0.48(

0.30-2/

Ce65 2) 277 '8 1

K-4C tCT c STAB 14 '2(

11.78-1 6/

1o 82 TRr 15 54(

14 ~ co-2/

16 82

2) 1G 7~

64(

91-2/

13.38 2)

BI-214 G.C20 1.37( 6/ o) TRr 277.98 1 ~ 49( 2/ 2) 1o11( 2/ 2)

BI-212 0.105

'CD 94-01(

1.62<

4/ 6) TRr 277 '8 1 ~ 44-2.C6(

1 2/

'4 2) 1 ~

1 ~

01-45(

1 2/

'1 2)

PB-214 NCT FSTAB 1 86-1.55(

2 6/

'6 5) TRr 2BB.?E 2.Co-1.64(

2 2/

05 2) 1 ~ 3o" 1.25(

1 ~ 5 2/ 2) 1.21- 1.65 1 ~ c1 1 ~ 68 1 ~ 16- 1 ~ 34 PB-212 NCT ESTAB 1.49( 6/ o) TRP 277.98 1 ~ 60( 2/ 2) 1 ~ 21( 2/ 2)

'A-226 NCT ESTAB 1.33" 1.52(

1 2/

'1 o) TRH 277 '8 1 ~ 38-1 ~ c4(

1 ~

1/

81 2) 1 ~ 18-1.11(

1 ~

2/

24 2) 1.51- 1.54 1 ~ c4- 1 54 1. 01- 1 ~ 21 RA-224 NCT ESTAB 1.69( 1/ o) TRH 293 F 7 1 ~ 69( 1/ 2) 1 ~ 28( 1/ 2) 1.69- 1 69 BF h DISCHARGE 1 ~ 69" 1 ~ 69 1 ~ 28- 1 ~ 28 TL-203 0.020 C.53( 6/ o) TRr 277.98 0 ~ 56( 2/ 2) 0.41( 2/ 2)

C.33" 0 61 0 c2 0.61 0 ~ 38- CD 44 AC-228 G.CoG '0(

'7- 6/ 5) TRr 27? ~ 98 73( 2/ 2) 22( -2/ 2)

PA"234H 1

1 3.4C(

1,94 1/ o) TRr 27'8 1

1 '2

'0( 1 ~

1/

94 1

1 ~

'2 15- 1 ~ 28 SR 89 NCT ESTAB 1 500 40-VALUcS <t.LO 3.4C 3

3.40- 3 '0 Z) VALLES 2 VALLCS <LLC

<LLC Att>>LYSIS PERFORHEO SR 9C 0 'G0 VALUES <LLC 2 VALI.ES <LLC ANALYSIS PERFORt'cO

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 134 Cs are also conparable with levels reported in sanples fron the Tennessee River in preoperational nonitoring prograns conducted, by TVA at other sites.

TABL" 29 RACIPACTIVITY Ih CLAM FLESI, FCI/C - C.057 BC/G (CRY 'r =IGFT) hAME CF FACILITY cg('tbbg PcgtII HO.~ cw cr 422ts~icaaR or,r LOCATION OF FACILITY jAHgggggP -nLksk "t" RcFORTIHG R=RICO TYPE Ati'0 LCQE R LIMIT Al L COHTRCL 4Ly"cR TOTAL NUMBER A c INDICATOR LCCAbTICNS LGHIIQh 81IV LIuOESI hhbU8L 5R Ah LCCATIOHS NOhRO'.NE PF ANALYSIS O=TECT.ON MEAN (F) HAy E vc AN < RT.C

(~) ,MEAN ($ ) REP P~cRC23"k2 fLLik sachs ~ a:-1IAbCi 65K aiR:f,I198 ds h GAMMA (GcLI) 5 t(-4C HOT ESTA3 3 VDLUcS <LLC 2.06( 2/ 2) 1.55- 2 '27 BI-214 NCT ESTAB 2.47(

1 '6- 3/

3 'G

3) TRy 277 ~ 9E 3 3

'0(

~ 6G-1/

3 '0 1) 1 ~ 52( 2/

2

~

'2 2)

PB"214 NOT ESTAB 2.33( 3/ 3) TRM 277. 9E 2e75( 1/ 1) 0.85 ( 2/ 2)

PB-212 1 '8- 2+75 2 ~ 75- 2 ~ 72 G~ 63- 1 ~ 07 NOT cSTAB C.26( 1/ 3) TRy 2cE. 7E 0.26( 1/ 1) C.15 ( 1/ 2)

TL-20S C ~ 26- 0 'o C.26- 0 ~ 26. C ~ 15- C ~ 15 NCT =STAB 3 VALVES <LLO C.07( 2/ 2) 0 ~ 03- C ~ 1G AC-22S NOT STAB VALVES <LLG 1 ~ 59( 1/ 2) 1 ~ 39" 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).

TABL c 30 RAD 0 CTIVITY Itt CLAt'HELL CI/O 0~ 7 C/G (ORT Vt IGMT)

IC h CF F>>CIL IT I $ 3/'Ah/ c 2 >I OOCt(ET NO ~ 'AC=2>2c2(t2A2c~

LQ C A T 0 F F A C I L I T Y g I <l g $ I Q g>

TYPc ANJ LIH-T ALL CONTROL NUVBER TOTAL NUMBER CF INDIC ATOR LCCAbTIC4S L908IIQh nIId =Itt~CSI khdQBi COG- L~c8tt LCCATI0>4S NCKRCUTINE OF AtiALYSIS ETECTION V At" (F) B'AV 8 VEAh (FT HcAN gFP RcPCRTc~

BRBf935'2 Bcbkvcb 'uIRI85Cs Eh'IBRCII2h BAb~: s u A Vl 5fka'liBf"aNIS GATV>> (GELI) 7 K-4C NCT,=STAB C.OG( 1/ r 5) TRv 2=c ~ 78 C.CO( 1/ 2) C.13( 1/ 2)

BI-214 C.CO- i 3/

~ iu C. 0.00 G ~ 13- C ~ 13 O.C50 C ~ 22( 5) TRV 29' C.IO< 2/  ?) C.15( 2/ 2)

PB-214 G.C7- 0 ~ 42 3Fh C I S C t'. A 2 G E

'8 0~1 7 3 42 0 '6- Co23 0+C50 C.28( 5/ 5) TRV 277 0 5i( 1/ 1) 0.18( 2/ 2)

G ~ 08- C ~ 5C e '0- G ~ 50 0.06- C.29 PB-212 hCT ESTAB 0.06( 3/ 5) TRV 28c.78 O.C6< 2/ 2) 0.02( 1/ 2)

C4- 0~I 7 GeC4- 0 ~ 07 Oe02-RA-226 0.050 C ~

C.er<

C. C7-1/. 5) 0 ~ 07 TRV .288 '8 0 ~ C7(

C C7-1/

0 F 07

2) 0 G

'6(

06-1/

CD 0.06 02 2)

AC-228 Ooeae C.G7( 1/ 5) TRV 288 78 O.C7( 1/ 2) 0.07( 1/ 2)

C.C7- 0.07 Oo C7- 0 07 0.07- C"07 SR 89 5 ~ cee 6 24( 1/ 5) TRV 293 ' 6.24(" 1/ 2) YALLES <LLG'

'4 2)

~ 2 6.24- 6 F 24 bFh c>>

SR 9C 1 ~ COO 1.14(

1.01-4/

1 c4

5) TRV 288 'c DISCHARGE 0~

1.23(

1 ~ c1-6 2/

1 '4 1 ~

16(

16-1/

1'16 2)

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 53 R ESERVOI R MONITORING NETV/ORK Etk River WHEELER DAM mile 274.90 mile 277.98 Rogersville 0

mile 29l.76 Athens mite 282.6 0

~mile 285.2 B.F. NUCLEAR PLANT 8

Champion Paper Co.

ile 288.78 mile 293.50 mite 305.0

,0 Co'ur tland mile 295.T0 Decatur mile 307.52 Scale of Miles

~ - Automatic Sam ler 0

Eigure 12 ANNUaL AveRase Cl Preoperational Operational Bess Hva AcTtvm o

o co Phase Phase th MFacE ltaieR lio mo JJ CJ th e kl Rows FeRRv NUcL'eaR P~

Le C/'

o o V

4J

'o c 0 Average:

Q Preoperational'hase T

l 1 968 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 RADIOACTIVITY LEVELS BROMNS FERRY NUCLEAR PLANT ANNUAL REPORT - 1985 TVA/NUC SVS/RH

TENNESSEE VALLEY AUTHORITY 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 iii List of Figures. iv Introduction . l Atmospheric Monitoring . ll Terrestrial Monitoring . ~ ~ ~ 23 Reservoir Monitoring . 43 equality Control. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 57 Data Analysis. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 57 Conclusions. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 58

LIST OF TABLES Table 1 Environmental Radioactivity Sampling Schedu le Table 2 Atmospheric and Terrestrial Monitoring Stat I.on Locations - Browns Ferry Nuclear Plant .

Table Detection Capabilities for Environmental Sam pie Analysis Table Results Obtained in Interlaboratory Compari so Program Table Maximum Permissible Concentrations for Nonoccupational Exposure . ~ ~ 13 Table 6 Radioactivity in Air Filter . ~ ~ 14 Table 7 Radioactivity in Rainwater ~ ~ 15 Table 8 Radioactivity in Heavy Particle Fallout . ~ ~ ~ ~ 16 Table 9 Radioactivity in Charcoal Filters ~ ~ 17 Table 10 Radioactivity in Milk . 26 ll

~ ~

Table Radioactivity in Vegetation . ~ ~ 27 Table 12 Radioactivity in Soil . ~ ~ 28 Table 13 Radioactivity in Well Water . ~ ~ 29 Table 14 Radioactivity in Public Water Supply ~ ~ 30 Table 15 Environmental Gamma Radiation Levels ~ ~ 31 Table 16 Radioactivity in Cabbage ~ ~ 32 Table 17 Radioactivity in Corn . ~ ~ 33 Table 18 Radioactivity in Green Beans ~ ~ ~ ~

Table 19 Radioactivity in Apples ~ ~ ~ ~ 35 t Table 20 Radioactivity in Potatoes ~ ~ 36 Table 21 Radioactivity in Beef . ~ ~ 37 Table 22 Radioactivity in Tomatoes ~ ~ 38 Table 23 Sampling Schedule - Reservoir Monitoring ~ ~ 45 Table 24 Radioactivity in Surface Water ~ ~ 46 Table 25 Radioactivity in White Crappie (Flesh) ~ ~ 47 Table 26 Radioactivity in Smallmouth Buffalo (Flesh) ~ ~ 48 Table 27 Radioactivity in Smallmouth Buffalo (Whole) 49 Table 28 Radioactivity in Sediment . 50 Table 29 Radioactivity in Plankton . ~ ~ 51 Table 30 Radioactivity in Clam Flesh . ~ ~ 52 Table 31 Radioactivity in Clam Shell . ~ ~ 53

LIST OF FIGURES Figure 1 - Tennessee Valley Region . 9 Figure 2 - Atmospheric and Terrestrial Monitoring Network l8 Figure 3 - Local Monitoring Stations l9 Figure 4 - TLD Locations, BFN 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 7 - Direct Radiation Levels, BFN 40 Figure 8 - Direct Radiation Levels, BFN (4-quarter Moving Average) 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 RADIOACTIVITY LEVELS 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.

Table l ENVIRONMENTAL RADIOACTIVITY SA.'PLIVO SCNEDL'LE Station Location Muscle Shoals Air FllcFllcCharcoal

'W Rain- Heavy Particle M

t F ll M

c 5 A

kl V~eel M

Milk I; t lb< I: c d 5 df r River 'Well Public Aquatic Life d

Lawrenceburg W M M A M Rogersvilie 'W M M A M Athens M M A M Decatur W M M A Courtland W M M A M Site 1 (N) W M M A M Site 2 (NNE) W M M A M Site 3 (ENE) W "M Site 4 (NNW) W

' M Site 5 (WSW) W M M Farm B M Farm Bn+ M W Farm ~ 'W Farm L W Farm E Farm W Control Farms M 'W Onsite Well Wheeler Dam Elk River Tennessee River S Champion Paper Co.

Various Local Farms W - Weekly M - Monthly (every 4 weeks) - Quarterly S - Semiannually A - Annually

• Sampling commenced November 1985 Q

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 LM-1 BF, North 1.0 Mile (1.6 kilometers) N LM-2 BF, North-Northeast 0.9. Mile (1.4 kilometers) NNE LM-3 BF, East-Northeast 1.0 Mile (1.4 kilometers) ENE LM-4 BF, North-Northwest 1.7 Miles (2.7 kilometers) NNW LM-5 BF, West-Southwest 2.5 Miles (4.0 kilometers) WSW PM-1 BF, Rogersville, AL 13.8 Miles (22.2 kilometers) NW PM-2'F, Athens, AL 10.9 Miles (17.5 kilometers) NE PM-3 BF, Decatur (Trinity), AL 8.2 Miles (13.2 kilometers) SSE PM-4 BF, Couri.land, AL 10.5 Miles, (16.9 kilometers) WSW RM-1 BF, Muscle Shoals, AQ 32.0 Miles (51.5 kilometers) W (Control)

RM-2 BF) 'awrenceburg, TN 40.5 Miles (65.2 kilometers) NNW (Control)

Farm Bn>> 4.75 Miles (7.6 kilometers) N Farm B 7.0 Miles (11.3 kilometers) NW Farm L 5.0 Miles (7.0 kilometers)

Farm P-'- 8.8 Miles (14.1 kilometers) E Farm E 6.1 Miles ( 9.8 kilometers) NE Farm W 6.9 Miles (11.0 kilometers) NE Farm N:(Control) 27.0 Miles (43.4 kilometers) NW Farm J (Control) $ 0.0 Miles (64.$ kilometers) NNW I

Farm C (Control) 32.0 Miles (51.5 kilometers) N Farm Ca (Control) 32.0 Miles (51.5 kilometers) W Farm Cb (Control) 22.5 Miles (36.2 kilometers) E Farm M (Control) 22.5 Miles (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)*

Fish, Air Vegetation Soil and Clam Flesh, Foods, Heat,

~cl/

'harcoal Particulates pCI/m'a1 lout mCI/Km Water

~CI/I and Grain yp~CI/ i, Dry Sediment i>C i/cC,~Dr Plankton,

/

DCCi/ D Clam

~CI/

Shells Dr Poultry,

~Ci/K WDC Hiik

.DCi/1 Gross a 0.005 2 0.05 0-35 0.1 0.7 Gross 8 0.01 0.05 2 0.20 0.70 0.1 0.7 25 H-3 330 I- i31 0.01 0.5 Sr-89 0.005 10 0.25 1.5 0.5 5.0 40 10 Sr-90 0.001 2 0.05 0. 15 0.1 1.0 8 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 3.7 x 10 Bq; I mCi ~ 3.7 x 10 Bq.

DD

Table 3 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS B. Galena Anal ses NOHINAL LOWER LIHIT OF DETECTION (LLD)

Air Water Vegetation Soll and Clam flesh Foods, (tomatoes Heat and particu)ates and milk and grain sediment Fish and plankton Clam shells potatoes, etc.) poul try Ci/ dr pCi/< dr Ci/ dr pCi/ , d Ci/ d Ci/K , wet pCi/K wet Ge LI *

~Ct/I Ge Li MGe L~i ~Ge L~I ~Ge L~i Ge Li ~oGee~LI Ge Li Ge Li 0.22 o.o6 o.o6 0.35 o.o6 33 40 Ce-144 0.02 33 o.47 0.10 -0. 10 o.56 0. 10 44 90 Cr-51 0.03 44 20 1-131 0.01 8 0.09 0.02 0.02 0.07 0. 02 8 Ru-106 0.03 30 0.51 0.11 0.11 o.74 0. 11 4o 90 0.33 o.o8 0.07 o.48 o:o8 26 4o Cs-134 0.0] 5 Cs-137 0.01 5 o.o6 0.02 0.02 o.o8 0.02 5 15 Zr-95 0.01 10 0.11 0.03 0.03 0.15 0.03 Io 20 Nb-95 0.01 5 0.05 0.01 0.01 0.07 0.01 5 15 Co-58 0.01 5 0.05 0.01 0.01 0.07 O.DI 5 15 Hn-54 0.01 5 0.05 0.01 0.01 o.o8 0.01 5 15 0.11 0.02 0.02 0.17 0.02 9 20 Zn-65 0.01 9 Co-60 0.01 5 o.o6 0.01 0.01 0.08 0.01 5 15 Fe-59 5 0.10 o.34 0.07 0.07 0. 30 0.07 25 50 Ba-140 0.02 25 La-140 0.01 7 o.o8 0.02 0.02 0.10 0.02 7 15 These LLD values are

+ The Ge(Li) LLD values are calculated by the method deve)oped by Pasternack and Har'ley as described in HASL-300. the LLD values achievable expected to vary depending on the activities of the components in the samples. These figures do not represent 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 andmultichannel very smal I volume analyzer samples are counted in petri dishes centered on the detector endcap. The counting system consists of a ND-6700 and germanium detector having an efficiency of 20 percent. The counting time is normally 4-15 hours. Al I spectral analyses are performed collect'ion date.

using the software program HYPERHET. -2 The assumption is made that all samples are analyzed within one week of the Conversion factor: I pCi ~ 3.7 x 10 Bq.

Table 4 RESULTS OBTAINED IN INTERLABCFZ..C:PY COMPARISON PROGRAM A. Air Filter (pCi/Filter)

Gross Alpha Gross Beta Strontium-90 Cesium-137 EPA value EPA va I ue TVA EPA value TVA EPA value TVA Date (+3a) (+3~) ~Av . (+3a) ~Av . ~(A v) ~Av .

l 1/84 15+9 15 52+9 61 21+3 21 10+9 10 3/85 10+9 ]1 3 +9 40 15+3 16 6+9 6 8/85 13+9 12 44+9 45 18+3 16 8+9 9 B. Tritium in Urine (pCI/R)

Date EPA value (+3a) TVA AvcV.v 4/85 3056+622 2687 7/85 2444+610 2280 C. Radiochemical Analysis of Water (pCI/g)

Gross Alpha Gross Beta Strontium-89 Stronium-90 Tri tium Iodine-131 EPA value TVA EPA value TVA EPA value TVA EPA value TVA EPA value TVA EPA value TVA Date ~(+3 ) ~Av . (+3o) ~Av . (+3e) AvcV. (+3a) ~Av . (+3o) ~Av . (+3<) ~Av ~

4/84 23+9 22b 26+3 26 1/85 5+9 15+9 19 3+9 10 30+3 29 2/85 3796+634 3817 3/85 6+9 15+9 17 4/85 355"+630 3347 7.5+1.4 7.3 4/85 72+9 69 10+9 9d 15+3 16 5/85 12+9 9 11+9 14 39+9 49 15+3 13 6/85 2416+608 2257 7/85 11+9 12 8+9 8/85 4480+776 4127 33 +10 29 9/85 8+9 8+9 12 20+9 26 7+3 5 10/85 1974+598 1880

Table 4 (Continued)

RESULTS OBTAINED IN INTERLABORATORY COMPARISON PROGRAM (Continued)

D. Gamma-Spectral Analysis of Water- (pCI/!I,)

Chromium-51 Cobalt-60 Zinc-65 Ruthenium-106 Cesium-1 Cesium-137 EPA value TVA EPA value TVA EPA vali.'e TVA EPA" value TVA EPA value TVA Date (+3(r) ~Av . (+3cr) Avcv. (+3(r) Avcv. (=3(r) ~Av . (+3(r) Avcv. (+3cr) ~Av .

4/84 3N:9 30 3L<:9 27 26+9 27 2/85 48z9 45 20-'9 20 55+5 53 9 40b 35-+9 32 25+9 25 15'9 16 15+9 15 12+ 9 13 4/85'/85 4ir+9 14 9 14 47+9 48 62='9 53 35+9 34 20+ 9 19 40b 10/85 21+ 9 40 20 9 21 19<-9 20 20 9 25 20+9 18 20+9 20 E. P'ood (pCi,/Kg., Mob Weight)

Strontium-89 Strontium"90 I od inc-131 Cesium-137 Potassium 40 EPA value TVA EPA value TVA EPA value TVA Date (+3(r) ~Av . (+ 3cr ) Avg. (+3cr) Avg. (+3ci) Aver. ~(e a ~AV .

1/85 34+9 37 37 35+10 33 29+9 28 1 '.82+208 1270 7/85 33+9 34 34f 35+10 36 29+9 31 1514+132 1567 F. Milk (pCi/R,r Strontium-89 Strontium-90 Iodine-131 Cesium-137 Potassium-40 EPA value TVA EPA value TVA EPA value TVA EPA value TVA Date (+3(r) Avcv. (+3cr) ~Av . (+3(r) Avg. (+3o) P.vg. (+-3(r) ~Av .

3/85 9+1.6 11h e 6/85 11+9 13 11+3 11 11+10 ll 11+9 12 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.

LOIHSYLLC A'

g 1.: TENNESSEE VALLEY REGION Ci\ ~

'~T (TVA NUCLEAR PLANT SITES)

W V I L L.

i fr

~

K E N T U C K Y Lt l.

C BOWUHG GRCCH 7

~,M

..J

~ '

\

~ ~ ~

r I I

~/ o~

I- ~

5 ~I v~~ i

~ - I I l5HNL< OAK IHOGCp I

I+ T ~

N N E S S E~l N rC A R.

I A

,r I rI (X/

)

I I

IvCQHHS

\ /p o t

I CHAT TlHOOG l~ ~

'WI

'l~

BLH

~HVHTSVILLC J I I' C A R SW IS lg I LEGENO r> / o M I S S.

I A L A B A fg M A GEORG I A

~-

XS

-WATTS BAR NUCLEAR PLANT

-SEOUOYAH NUCLEAR PLANT BELLEFONTE NUCLEAR PLANT

.-. BROWNS FERRY NUCLEAR PLANT I

I

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 In Water In Air

~Ci/I+ ~Ci/m

• Alpha 30 Nonvolatile beta 3,000 100 Tritium 3,000,000 200,000 1 37Cs 20,000 500 103~ 106R 10,000 200 144(e 10,000 200 "Zr-96Nb 60,000 1,000 1 0Ba 140La 20,000 1,000 131Z 300 100 65Z 100,000 2,000

'4Mn 100,000 1,000 "Co 30,000 300 09S 3,000 300 90Sr 300 30 "Cr 2,000,000 80,000 "4C 9,000 400 6sG 90,000 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 DOCKET NO- 59=252/?69c?oR LOCATION OF FACILITY l,?UESI9UE 8l.858U8 REPORTING PERIOD TYPE AND LONE R L I HIT ALL CONTROL NUMBER OF OTAL NUHBER OF INDICATOR LOCATIONS l 998II9U HINDU UIGUEDI 8UUll8l. UE8U LOCATIONS NONROUTINE IF ANALYSIS DETECTION HEAN (F) NAHE MEAN (F) cAN (F) REPORTco PERFORHEO (LLO) RANGE DISTANCE ANO DIRECTION RANGE RANGE EASUREHckTS cE UQIE 1 KEE U9IE ? GEE U9EE 2 5EE h9IE 2

!OSS ALPHA 5 'OE-03 6.73E-03( 1/ 52) 52 6 '3E 6.738-03

'4E-02( 449/ 462) 2 '9E"02( 103/ l v)

IOSS BETA 566 1.0GE-02 1 1.00E-02 - 4 '3E-02 OECATURr AL 8~2 NILES SSE 2.13E-02 (

1.18E-02 - 50/ 52) 3.o9E"02 1 ~ 10E-02 - 3.64E-02 IHNA (GELI) 145

'-40 NOT ESTAB 1 '1c-02( 43/ 117) LH1 SF 40RTHWEST 2 CZE-02( 7/ 13) 8 'SE-03( 11/ 26)

C.COc-O3 - 3.53E-OZ 1 ~ 0 NILE N 9 90c-03 3 ~ 26E-02 1 '0c 1.C38-02 II-21 4 2.00E-02 2.42E-02( 2/ 117) LH3 BF NORTHEAST 2.68E-02( 1/ 13) 26 VALUES <LLD zi16E 2!68E-02 1 ~ 0 MILE ENE 2 '8E-02 2 '8E-02 SI-21 2 NOT ESTAB '7E-02( 1/ 117) LH3 BF NORTHEAST 1 47E-02( 1/ 13) 25 VALUES <LLD 1

1.47E-02 - 1.47E-02 1 ~ 0 NILE ENE 1 '7E 02 1 47E-02

~8-?14 2.00E-02 2 '2E-02( 2/ 117) LH3 BF NORTHEAST 3.0BE-02( 1/ 13) VALUcS <I I 0 2 36E-02 - 3 OBE-02 1 0 NILE ENE 3 OBE-02 3.088-02

}8-212 NOT ESTAB 3 ' 6E-04( 19/ 117) LN3 BF NORTHEAST 5 00 -04( 1/ 13) 3.00E-04( 3/

'0c 26) 1.00E 1.00E-03 1 ~ 0 HILE ENE 5 ~ OOE"04 5.00E-OC 2 ~ OOE-04 5 0 lE-7 5 'OE-02 8 '9E-02( 94/ 117) DECATURr AL 1 02E-01( 1/ 15) 1 '1E-01( 22/ 26) 5 60E-02 - 1 '5E-01 8 ~ 2 NII.ES SSE 5 '6E-02 1 ~ 34E-01 o.31E-O2 - 1.438-01

'oc-04( 1/ 13) Doc 04( 2/ 26) rL-208 NOT ESTAB 1 1 ~ Ooc-04 - 2 5/ 117)

'OE-04 RGGERSVILLEr AL 13 ~ 8 HILES NN 2 OOE"04(

2.00E-04 F 008-04 F 008 7 ~ OOE-04

'2E-05( 1/ 2/

- 12/

AC-228 NOT ESTAB 2 117) ATHENSr AL 5 OOE-03( 15) 9.5CE-OC( 26) 7.00c 04 7 '0E-03 1'0 e 9 NILE S NE 5.00E-03 5.00E-03 9 'OE-OC - 1 'GE-G3 5 ~ OOE-03 36 VALVES <LLD S VALVES <I.LD 44 ANALYSIS PERFORHED R 90 1 'OE-03 36 VALUES <LLD VALU"S <'O 44 ANALYSIS PERFORMED 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) ~

TABLE 7 RADIOACTIVITY IN RAINWATER PCI/L - 0 ~ 037 80/L NAHE OF FACILITY kjfQtt55 LOCATION OF FACILITY ff BBI DOCKET ttO. $ Q252c25Q4230 REPORTING PERIOD 12'>

LIMDIQUf TYPE ANO LOWER LIMIT ALL CONTROL NUHSE'R OF TOTAL NUHBER OF INDICATOR LOCATIONS L.Qgbr?Qtt )tIIO UK(tUfDI BUUQbl. t)fSU LOCATIONS NONROVTINE OF ANALYSIS DETECTION ttEAN (F) NAHE MEAN (F) MEAN (F) REPORTED PERFORMED (LLD) RANGE DISTANCE ANO DIRECTION RAtt E RANGE EASURcMENTS off HQIf 1 5f f UQIf 2 Xff LtQIf 2 off bQIf 2 GAMMA (GELI) 13o K"40 NOT cSTAS 20.64< ATHENSr AL 35.62( 2/ 12) 2 18(. 2/ 24) 4.02 - 65.94 10 9 MILES NE 5 '0

'3(

65.94

~

0.59 3 ~ 6'7 8 I-21 4 NOT FSTAB 5 '2( 59/ 112) LH5 BF OA VIS F 9 o/ 13) 6.60( 2/ 24) 0 '5 1

0.36 - 29+58 2 ~ 5 HILE5 XS)t 29.38 0.04 20e32 PB 214 NOT ESTAB 5 '4( 35/ 112) LH5 BF OA VIS F 9 '0( 3/ 13) 5.58( 4/ 24)

'4 0.33 - Z1 F 05 2 ~ 5 HILES XSW 1 ~ 58 21.05 Oo 51 7 PB-?12 1o70( 29/ 11?) LH5 BF OA VIS F 2.83( 4/ 13) 2 39( 7/ 24)

NOT ESTAB 0 '1 58 12< 24/ 112) 6.05 2 ~ 5 MILc5 XS LM1 SF NORTHWEST 0 '3 78.56( 6/

o.05 13)

~

0 ~ 05 54.56(

5o97 8/ 24)

NOT ESTAB

'o 37 '2 7

24.G9 - 197 1 ~ 0 MILE N 197.75 z1 AD ?2 106.55 TRITIUM 530.00 112 VALVES <LLD 24 VALVcS <LLD 136 ANALYSIS PERFORMED 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) ~

TABLE 8 RADIOACTIVITY IN HEAVY PARTICLE FALLOUT HCI/KH('2) - 3/000000 00 BQ/KH(2)

NAHE OF FACILITY ggQUU$ DOCl(ET NO ~ 29=2>2c?CQcR2k LOCATION OF FACIlITY .gjUgggQUP REPORTING PERIOD TYPE AND LONER LIHIT ALL CONTROL NUHBER OF fOTAL NUHBER OF INDICATOR LOCATIONS LQC4IIQU UZIU UKQUEKI SUUQBL UEBU LOCATIONS NONROUTIitE

)F ANALYSIS DETECTION HCAN (F) RANE HEAN (F) HEAN (F) REPORTED PERFORHEO (LLO) RANGE DISTANCc ANO OIRcCTION RANGE RANGE HEASURE"ENTS GEE UQIf 1 ZcE UQIt; 2 APE UQ..E 2 RF~c UQIR 2-tOSS BETA 0.05 0 16( 10S/ 117) LP4 BF TRAILER P 0,31( 13/ 13) 0 ~ 11 ( 25/ 26) 143 0.06 - O.SS 1 ~ 7 'HILES NNM Dodo Oe88 0.05 - 0.20 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) ~

TABLE 9 RADIOACTIVITY IN CHARCOAL FILTERS PCI/M(3) - 0 ~ 037 8Q/M(3)

NAHF OF FACILITY $ QQWQk EEggy DOCt(ET NO ~ NQ:252c25QA?25 LOCATION OF I F ACIL T Y i. I5 c5IQHE REPORTING PERZOO 1$ ES TYPE ANO LOitER LIMIT ALL CONT ROL NUMBcR OF TOTAL NUMBER OF INDICATOR LOCATIONS i.QQ81IQ5 BIIU >?ltd)EKI 85598!. t)E64 LOCAT IOtlS NONROUT INE OF AiNALYSIS DETECTION MEAN (F) NAHE HEAtl (c) MEAN (F) REPORTED PERcORMED (LLO) RAtlGE DISTANCE AND DIRECTION RAilGE RAtlGE MEASUREMcNTS cc gQIE SEE UQIE 2 SEE UQIE 2 5EE BQIE 2 IODINE-131 566 0.01 1

0 '2( -

0.01 6S/ 452) 0.13*

LF1 BF NORTH)tEST 1 ~ 0 MILE N 0+02(

0 ~ 01 - 12/ 52) 0.13+

0.01(

0 ~ 01 " 15/ 0.02 104)

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 PM-I BF WHEELER ROBE SVILL FLORENCE OAM ATHENS PM-2BF FFIEL MUSCLE SHOALS BROWNS FERRY HUNTSVILLE RM-I BF NUCLEAR PL NT LEIGHTON TUSCUMBIA COURTLANO PM-4 F OECAT PM-3BF0 10 MILES pRUSSELLVILLE GUNT SV IL HARTSELLE OAM HALEY VILLE

~CULLMAN 45 MILES Q-ENVIRONLKNTAL MONITORING STATIN NOTE: THE FOLLOWING SAMPLES ARE COLLECTED FROM EACH STATION:

AIR PARTICULATES RAINWATER RADIOIODINE SOIL HEAVY PART]CLE FALLOUT

LOCAL MONITORING STATIONS 19,"

BROWNS FERRY NUCLEAR PLANT ATHENS US HWY 72 BFN ALA. HWY 20 Legend 0 Air Monitor DECATUR-AUtomatic Well Sampler N Dairy Farm Other Firm" Scale 0 I 2 3 . 4 6 Miles

20 Figure 4 t>>~,t << .$

.~

V,+

II I ~

r

=

i

~ .

4! II

'PQ g ~ ~ ~ ~ t

\

TLD Locations I 'g'-- '1 P~"

~

~

8FN I

r I

sr JC p Ssp dJ /Q ; 'I I

Cp C ) tlt r~ I t t ~

~r C,'.

ti IW

)

/

tlI Ir I C p 7 t 1 !I t j

~ CC

~ .

t I ~ I It

'Y

',t  !

'Q '.7

'r r

'I 2 tC'>> r ~

<<I w

~ ~

I gw-yF~i' Il <> , L~~",

"-'I t tt .ir i

C I ,t,"

4 ~

I r'I I J )1 v-<<.

IwI C >>tt

~ t c, r

~ I<<

Ey I' ~I

~ i r 1

rr

'I t);

<<I II I Q

~

4

Figure 5 Wmu AVaeeE

.30 6ROSS 8ETA ACTIVITY IN AIR FILTERS BRANS FERRY Nrem Preoperational Phase I Operational Phase Pusan'20 25 e

n o

Il 0 o

1J IJ C

4J tC 4

V n

.15 Ave~ra e: Preo~erational Phase

.10

.05 1968 19 69 19 70 1 971 1972 1973P 19730 1974 1975 1976 1977 1978 1979 1980 1981 1 82 1983 I.984 I n85

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.

this reporting period, three samples were inadvertently 'uring 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 RADIOACTIVITY IN MILK PCI/L - 0 ~ 037 BQ/L NAME OF FACILITY gg{}UUQ LOCATION OF FACILITY LIUE/IQUE P fggI DOCKET NO ~ -29=222A2(lQc22{i REPORTING PERIOD TYPE ANO LONER LIHIT ALL CONTROL NUMBER OF TOTAL NUHBER OF INDICATOR LOCATIONS L9C8IIOU hIIU UIfiUEH 8UUll8L UE8U LOCA1'IOHS NONROUTINE OF ANALYSIS DETECTION MEAN (F) NAHE HEAN (F) MEAN (F) REPORTED PERFORMED (LLO) RANGE DISTANCE AND DIRECTION RAilGE RAHGc HEASUREHENTS Sff kff UQIE OD IN E-1 31 434 0 '0 UNTIE 1 156 VALUES <LLD ANALYSIS PERFORHED 2 SEE UOLTE 2 SEE UQIE 2 278 VALUES <LLO AHHA (GELI) 108 cs.-13r F 00 8 F 41( 6/ 39) PAGE FARH 8 41( 6/ 11) 8 F 59( 2/ 59)

K-40 NOT ESTAB 6 29 1193 '9(

39/

9 '8 59) 8 ~ 75 HILES E LOONEY FARH 6

1264 '3(

'9 13/

9 98 15) 5 84 1297 44(

69/

11 '4 69) 768 95 - 1686.67 5 ~ 75 MILES ENE 1058 '4 1435 68 781.33 - 1925 '4 BI-214 NOT ESTAB 7 ~ 41 ( 31/ 39) SMITH/BENNETT FA 9 98( 2/ 2) 6.93( 38/ 69)

PS-214 NOT ESTAB 0 '9 -

7.85(

35 13/ 39)

'8 4 ~ 75 MILES N LOONEY FARH 8.41 10 02( 4/

11 '5 13) 0 '2 -

7 '8(

21 27/ 69)

'7 1 '6 - 26 '5 5 ~ 75 MILES ENE 1 36 26 95 0 '4 - 29 05 F

P8-212 NOT ESTAB 2.00( 8/ 39) LOONEY FARH F 00( 1/ 13) '1.98( 12/ 69)

TL-208 HOT- ESTAB 0.39 -

1.35(

3 6/ 39)

'0 5%75 MILES ENE PAGE FARH 2 F 00 25( 2/

3.00 11) 0.56 0 '7(

- 6.27 13/ 69)

AC-228 NOT ESTAB Oe12 =

8.52( 3/

3 '3.

39) 8.75 HILES PAGE'ARM E 0 '7 10+23( 2/

3.63 11) 0.01 -

5.20(

2.r8 9/ 69)

R 89 10 F 00 5 F 08 -

39 VALOES <LLO 13 '6 8 75 HILES E 7.21 13 '6 0 '2 -

68 VALVES <LLO 11 '6 107 ANALTSIS PERFORHEO R 90 F 00 3 '0(

'5 - 38/ 39) SHITH/BENNETT FA 4 ~ 12( 2/ 2) 3 70( 56/ 68) 107 2 5 44 4 ~ 75 NILES N 3 77 - 4 '8 F 00 - 6 '1 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 NO ~ 29=222c2kQc22(i LOCATION OF FACILITY ling EIQ5f aiaaaLB REPORTING PERIOD $ PB$

TYPE AND LOWER LIMIT ALL CONTROL NUMBER OF TOTAL NUMBER OF INDICATOR LOCATIONS l QCGIZQU liIIU UIQi)EEI 685M8l ilfilU LOCATIONS NONROUT INE OF ANALYSIS DETECTION MEAN (F) NAME MEAN (F) HEAN (F) REPORTED PERFORHED (LLO) RANGE DISTANCE ANO DIRECTION RANGE RANGE HEASUREHENTS SEE UQIE 1 EE BQIc 2 Kff BQIE 2 SEE HQIE 2 IODINE-131 NOT ESTAB 0 00( 85/ 183) DECATURr AL 0 01( 6/ 12) 0 00( 10/ 25) 208 0.00 - 0 ~ 02 8 2 MILES SSE 0.00 - 0 02 0+00 - 0+01 GAMMA (GELI) 226 C0-60 0 ~ 49(

- 1/ 185) 0.49( 1/ 13) 0 ~ Oe LM1 BF NORTHWEST 41 VALUES <LLD (Note 3)

CS-137 0 ~ 06 0.49 0 '3( 14/

0 ~ 49 85) 1 ~ 0 HILE PAGE FARH N 0 '9 0~27( 1/

0 49

11) 0 12( 3/ 41) 1 K-40 NOT ESTAB 0 '7 -

15 56( 182/

1 0 '7 185) 8 ~ 75 MILES PAGE FARM E 0 ~ 27 25.86( 11/

0 ~ 27 11) 0 ~ 06 15 87(

40/

0 ~ 15 41)

BI-214 0 ~ 10 F 04 "

0 '2( 43 '1 93/ 185) 8 ~ 75 MILES E PAGE FARH 5 '6 0:39( 4/

43 '1 11) 1 43 -

~

0.20( 14/

40 34 41) 0 '0 0 '8(

0 F 60 2/ 185) 8 ~ 75 MILES E 0 ~ 13

0. 50(- 1/

0 '0 11) 0 '1 -

VALUES <LLD 0.46 BI 212 NOT ESTAB PAGE FARM 41 0 27 - 0 50 8 ~ 75 MILES E 0 '0 12/

0.50 0.12(

PB-214 NOT ESTAB 0.16( 167/ 185) o.oo - o.ee EVANS FARH 6 ~ 1 HILE5 HE 0 21(

0 F 06 13) 0 42 0 ~ 01 - 33/ 41) 0 ~ 40 PS-212 NOT ESTAB 0.07( 126/ 185) EVANS FARM 0 '3( 9/ 13)

'0 0 ~ 04(

'1 - 18/ 41) 0 00 - 0 ~ 43 6 ~ 1 MILES NE 0 01 0 0 0 11 BE-7 NOT ESTAB '3( - 184/ 25185) SMITH/BENNETT FA 10 28( 5/ 5) 7 '4( 41/ 41) 7 0.61 '2 4 ~ 75 HILES N 6 ~ 47 6/

15.56 0097 -

02( 11/

18 '5 TL-208 NOT ESTAB 0 ~ 04 ( 78/ 1 85) EVANS FARM 0 07( 13) 0 41) 0 ~ 00 - 0 ~ 14 6 ~ 1 MILES NE 0.01 0.11 0 F 00 - 0.05 AC"228 NOT ESTAB 0.20( 73/ 185) PAGE FARM 0 29( 2/ 11) 0 ~ 16( 12/ 41) 89 0 '5 0 F 02 -

57 VALUES <LI.O 0 ~ 79 8~ 75 MILES E 0 '3 0 ~ 45 0 '5 "

8 VALUES <LLO 0 ~ 30 SR 65 ANALYSIS PERFORMED SR 90 0 ~ 05 0 20( 53/ 57) ROGERSVILLEi AL 0 35( 4/ 4) 0+21( 8/ 8) 65 0 ~ 06 - 0+56 13 ~ 8 MILES NW 0.16 - 0.56 0 09 " 0.41 NOTE 1 ~ HOMINAL LOWER LIMIT OF DETECTION (Ll.O) AS DESCRIBED IN TABLE 3 ~

NOTE: 2 ~ HEAN AND RANGE BASED UPON DETECTABLE MEASUREHENTS ONLY ~ FRACTION OF DETECTABLE HEASUREHENTS AT SPECIFIEO LOCATIONS IS INDICATEO IN PAREhTMESCS (F) ~

Note: 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)

NAME OF FACILITY ggQgQ$

LOCATION OF FACILITY LIQEEIQgf ffgg7gggfggg 'EPORTINGDOCKET NO ~ NQ 2$ gc25Qc2$ $

PERIOD TYPE AND LOIIE R L IMIT CONTROL NUMBER OF TOTAL NUHBER OF LQQGIIQS HIIU UIQUESI BHUllhl. Ufhu LDCATIDNS NONROUTINE OF ANALYSIS DCTECTION NAHE HEAN (F) MEAN (F) REPORTED PERFORHED (LLO) DISTANCE AND DIRECTION RANGE RANG( MEASUREMENTS AHMA (GELI)

EEE 5QIE I GEE 8QIE 2 Ef f hQIE 2 11 CS-1 37 '2 0.46( 9/

'39)9) 43( 1/ 0+38( 2/

K-40 0

0 '5 0.02-5 '8( 9/

1 LH5 BF OA VIS F 2.S MILES LH1 BF NORTHWEST WSM 1

1 ~ 43 7 ~ 24( 1/

1) 1a43 1) 0.20-4.D3( 2/

0 '72)2)

BI-214 0 F 05 2 89-

'8(

~

9/

7 '49) 1+0 MILE LM2 SF NORTH N 7 24 43( 1/

7 24 1) 3~

0 17

'0( 2/

4 '92) 1 0 63-

~ 1 43 0 ' MILE NNE 1 ~

1 43 1 '~ 0.87- 0 '4 BI-212 Oe10 1 '1( 9/ 9) -LI'.2 SF NORTH 55( 1/ 1) 0 91( 2/ 2)

PB-214 0 F 05 0 62-

~

1o17( 9/

1 ~ 55 9) 0 ~ 9 MILE NNE LM1 BF NORTHNEST 1

1 '5 48( 1/

1 '5 1) 089-0.96( 2/

0 '42)

PS-212 NOT ESTAB 0 67-04( 9/

1 '89) 1 ~ 0 MILE N OECATURr AL 1 ~

1 ~

'5( 48 1/

1 '8 1) 0~ 88-0.8S( 2/

1 04 2)

RA-226 0 F 05 1 ~

0 52-

~

F 08( 9/

1 .35 9) 8.2 HILES SSE Lr2 SF NORTH 1

1 '5 43( 1/

1e35 1) 0~ 83-0.90( 2/

0.87 2)

RA-224 0.63-1.11( 7/

1 '39) 0 ~ 9 MILE NNE 1 ~

1 43 47( 1/

1 43 0.87 0.87( 2/

0.94 LH3 BF NORTHEAST 1)

'32)2)

NOT ESTAB SE-7 0 ~ 16 0 '2 0 '1( 2/

F 47 9) 1 ~ 0 MIl.E ENE DECATURr AL 1 ~

0 1 '7 24(. 1/

ie47 1)

Oo80-0 22( 1/

0 TH"227 NOT ESTAB 0 ~ 18 9 VALUES <LLD 0 24 8 ~ 2 MILES SSE 0 ~ 24 0 '4 0.22 0 11( 1/

0 '2 2) 0 ~ 11 0.11 TL-208 Oa02 0 36( 9/ 9) DECATURr AL 0 ~ 47( 1/ 1) 0 28( 2/ 2)

AC-228 0.06 0 ~ 19 06( 9/

0 ~ 47 9) 8~2 HILES SSE OECATURr AL 0 47 38( 1/

0.47 1) 0 '7 0.85( 2/

0.29 2) 1 ~

0 '5 4/ '89) 2.18(

1 8 2 MILES SSE 1 ~

1 2.74(

'8 1o38 0.83 0 F 87 PA-234M NOT ESTAB ROGERSVILLEr AL 1/ 1) 2.59( 2/ 2)

R 89 1 ~ 50 1 '3 9 VALUES <LLD 2 '4 13.8 r.ILEs Nv 2 '4 2 '4 1.44 2 VALUES <LLO 3.33 ANALYSIS PER FORMED 0 ~ 24( 4/ 0.28( 1/

R 90 0 ~ 15 0~ 20- 0 '89) LMS BF 2.5 MILES DAVIS NSV F

0 ~ 28 1) 0 ~ 28 2 VALUES <LLO 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) ~

TABLE 13 RADIOACTIVITY IN NELL kATER PCI/L 0 ~ 037 BO/L NAHE OF FACILITY EBQHUR Ef ESI DOC<ET NO ~ 59=212c259c225 LOCATION OF FACIlITY IIUEKIQUE 8I8E8U8 REPORTING PERIOD 1252 TYPE ANO LONER LIHIT ALL CONTROL NUHBER OF TOTAL NUHBER OF INDICATOR LOCATIONS IQI8ITQU UIIU UIQUERI 8UU98I UE8U LOCATIONS NON ROUTINE OF ANALYSIS DETECTION HEAN (F) NAHE MEAN (F) HEAN (F) REPORTED PERFORHEO (LLD) RANGE DISTANCE ANO DIRECTION RANGc RANGE HEASUREMENTS SEE UQIE 1 Kff UQIE 2 SEE UQIE ? Kff UQTE 2 GAHHA (GEL!)

25 K-40 NOT ESTAB 8

'292(

- 1/ 13) BFN kELL N6 8 92( 1/ 13)

'2 4 '7( - 2/ 1Z) 8

~

'6( 8 'Z 0 ~ 02 HILES k 8.92 12/

8 1+06 175 '2(

8.09 BI-214 NOT ESTAB 9 1 %3 - 12/ 17 22

13) BFN MELL N6 0 ~ 02 HILES .X 9 36(

1 ~ 43 13) 17 'Z 40 '7 -

12/

680 12)

'5 PB-214 NOT ESTAB 12 08( 9/ 13) BFN MELL P6 12 08( 9/ 13) 177 10( 12/ 12) 2 '7 - 18 '7 '4 682 '2 F

0 ~ 02 HILES W 2 ~ 97 18 ~ 27 43 PB-212 NOT ESTAB F 80( 4/ 13) 4 '4 BFN NELL P6 F 80( 4/ 13) 3 '7( 3/ 12)

'6 0 '1 - 0 OZ HILES 0 71 4 54 1.63 - 6 TL-208 NOT ESTAB 13 VALUES <LLO 0.33( 2/ 12) 0 '8 " 0 '8 AC-228 NOT ESTAB 7 7

'9(

'9 - 1/

7 1S)

'9 BFN MELL P6 0 ~ 02 HIlES 7 ~ 09(

7 09 - 1/ 13) 7 '9 12 VALUcS <LLD TRITIUH S30.00 4 VALUES <LLD 4 VALUES <LLO ANALYSIS PERFORHEO 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 l.PCATIPN OF FACILITY ff BBX DOCKET NO ~

---

REPORTING PERIODgggf 2Q=222C25QA22k--------

gggfggggf 8L85858 TYPc AND LOVER LIMIT ALL CONTROL NUMBER OF TOTAL NUHBER OF ANALYSIS OF DETECTION INDICATOR l.OCATIONS HEAN (F)

LQQhIIQU III'IQBffI NAHE hUUQhl UfBU McAN (F)

LOCATIONS HEAN (F)

NONROUTINE REPORTED PERFORMED (LLD) RANGE DISTANCE ANO DIRECTION RANGE RANGE MEASUREMENTS off HQIf 1 off UQIf 2 off UQIR 2 off HQIf 2 ROSS BETA

'02 F 00 3 '3(

2.05 -

55/ 76) 6.58 3%38(

2.08 -

40/ 50) 6.58 2 '3(

2.04 -

22/ 26) 5+62 AHMA (GELI) 102 14.82( 3/ 1/

K-40 NOT ESTAB 2 '2 - 12/ 42 76)

'6 WHEELER DAHr AL TRH 274 '

23 ~ 86 (

11 ~ 40-13) 42 16 0 ~ 47(

0 '7 = 0 26)

'7 BI-214 NOT ESTAB 5.45( 39/ 76) NHEELER DAHr Al 7.39( 7/ 13) 9 22( 12/ 26) 0 '7 - 19.73 TRH 274 ' 1 s51 14.32 0.13 - 47o47 PB-214 NOT ESTAB 4 86( 24/ 76) SHEFFIELDr AL ROB 7 29( 3/ 13) 5.62( 7/ 26) 0.38 " 17 '9 TRH 254 ' 0 '6 17 79 0 47- 18 90 PB-212 NOT ESTAB 1.76( 15/ 76)

'8 HHEELER OAHr AL 4 10( 1/ 13) '9(

~

0 '9 -

6/ 26)

TL-208 NOT ESTAB 0 '1 -

1 02( 12/ 76) 8 TRH 274 '

CHAMPION PAPER 1

~

4e10-05( 8/

4 '0 50) 1 26 VALUES <LLD 2~72 AC-228 NOT ESTAB 0 F 00 5 '6(

- 2 38 9/ 76)

TRM 282 '

SHEFFIELDrAL ROB

~

Oe00 49(

/

2 '8

13) 8 '8( - 4/ 26) 11 '9

~ 1 Oe13 - TRM 254 ' 9.49- 9 ~ 49 0.93 27.49 R 89 10 00 12 VALUES <LLD 8 VALUES <LLD 20 ANALYSIS PERFORHED iR 90 F 00 12 VALUES <LLO 8 VALUES <LLD 20 ANALYSIS PERFORHED

'RITIUH 330 F 00 12. VALUES <LLD 333e48( 1/ 8) 20 333 '8 333.48 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 Avera e External Gamma Radiation Ievels b miles 4th uarter 0-,1 18.0 + 2.5 19.4 + 0.8 21.8 + 3.7 21.0 + 2.1 1-2 16.2 + 2.6 17.7 + 1.8 17.9 + 3.8 18.1 + 2.4 2-4 15.1 + 1.4 15.9 + 1.5 16.1 + 3.0 18.2 + 2.7 4-6 14.8 + 1.3 16.1 + 1.7 16.5 + 3.2 17,6 + 2.2

>6 14.4 + 1.3 15.8 + 1.5 '5.2 + 2.4 17.4 + 1.9

Average, 0-2 miles (Onsite) 17.6 + 2.5 18.9 + 1.3 20.8 + 4.0 20.3 + 2.4

Average,

>2 miles (Offsite) 14.8 + 1 ~ 3 15.9 + 1.5 16.0 + 2.9 17.6 + 2;2

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

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

TABLE 16 RADIOACTIVITY IN CABBAGE PCI/KG- = 0 ~ 037 BO/KG (MET MEIGHT)

NAHE OF F AGILITY QBQBUK EtBBI DOCKET NO ~ $ Q-2$ gg2$ QA2$ $

LOCATION OF FACILITY Qggf5IQgf =

SaaaSBS REPORTING PERIOD ],Pgg TYPE ANO LONER LIMIT ALI. CONTROL NUMBER OF OTAL NUMBER OF INDICATOR LOCATIONS LQQ8IIQU liIIU tfIQUfKI hBUQhl. UfBB LOCATIONS NONROUTINE

>F ANALYSIS DETECTION HcAN (F) NAME MEAN (F) MEAN (F) RcPORTED PERFORHEO (LLO) RANGE DISTANCE AND DIRECTION RANGE RANGE ASVREHcNT SETA Rff 5QIf 25.00 I ff 3764.15(

gQIf 2 1/ 1)

Bff 3764 ~ 15(

UQl= 2 1/ 1)

Sff hQIh 2 3440 ~ 65 ( 1/ 1)

OSS 2 3764 15 - 3764.15 3764 ~ 15 - 3754.15 3440.55 - 3440.55 iHMA (GELI) 2

-40 NOT ESTAB 1652.54( 1/ 1) PAGE FARH 1652.54( 1/ 1) 1569.45( 1/ 1) 1652 ~ 64 - 1652 ~ 04 8.75 MILES E 1552 ~ 64 - 1652 ~ 54 1569 ~ 45 - 156? ~ 45 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)

NAME OF FACILITY EEQVS> riaar OOCKET tlO 5{}=222c2{tQA22fi LOCATION OF FACILITY {,IUEKIQUE SLSQhhh RcPORTItlG PERIOO 12/i

,TYPc ANO LOitER LIMIT ALL CONTROL NUMBER OF TOTAL NUMSER OF INOICATOR LOCATIONS LQQ4XIQB hII5 UiltUEKI AQttQS{. 5EA5 t.OCATIONS tlONROUTINE OF ANALYSIS OETECT ION MEAN (F) NAME MEAN (F) ~- MEAN (F) RcPORTEO PcRFORHEO (LLO) RAtlGE OISTANCE ANO DIRECTION RANGE RANGc MEASUREMENTS SEE 5QIE 1 hiE 8QIE 2 UQ1% 2 KEc 5QEE 2 GROSS SETA 2

25.00 4152.57(

4152 ~ 67 - 1/

4152.67

1) 7 HILES NN'N 4152

%RE 4152 67(

'7 1/ 1) 4152.67 3807 3807

'4(

'4 - 1/ 1) 3807.94 GAMv4 (GELI) 2 K-40 1/

NOT ESTAB 2518 ~ S6(

2518 '6 2518 1)

'6 7 MILES NNu 2518 86(

2518.86 - 1/2518.86

1) 2153+31(

2153 ~ 31 - 1/ 1) 2163.31 1/

- 1/ 10.58 P8-214 NOT ESTAB 10 ~ SS( 1) 7 MILES NNN 10 58( 1) VALUES <LLO 10 '8 10 '8 'o 1

- . 10 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)

NAME OF FACILITY gggggr'l ff gfJ DOCKET NO 19=222ckkGA220--------

LOCATION OF FACILITY l LUffIQuf - 6l 6N58 REPORTING PERIOD 1252-TYPE AND LOWER LIMIT ALL CONTROL NUMBER OF

'OTAL NUMBER OF INDICATOR LOCATIONS L9liAIIQ8 HII~ ~Il'lUfkI SuHQEL UfhH LOCATIONS NONROUTINE IF ANALYSIS DETECTION MEAN (F) NAME MEAN (F) l EAtr (F) REPORTED PERFORMCO (LLO) RANGE 'DISTANCC AND DIRECTION RANGE RANGE MCASUREMENTS Rff UQjf 1 5f f UQIf 2 5f f 59] f 2 off hQIf 2 3823 47(

- 1/ 1) 3823.47( 1/ 1/

l'OSS BETA 25 F 00 7 MILES NNW 1) 5150 ~ 78( 1) 2 3823.47 3823 '7 3823 '7 - 3823 ~ 47 5150 ~ 78 - c150.78 IMMA (GELI) 2

-.40 1659 47( 1/ 1) 1659 47(

- 1/1659 1) 2003 r 71( 1/

NOT ESTAB 7 MILES NNW 1)

SI" 214 1659 '7 - 1659.47 1659 '7 '7 2003.71 2003 ~ 71 NOT ESTAB VALUES <LLD 5 ~ 70( 1/

'01)1) 1 3 70- 3

'B-214 NOT ESTAB 1 VALUES <LLD 2 ~ 14( 1/

2.14 2 ~ 14 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 OoCKET NO ~ XQ=222A2OQA22O LOCATION OF FACILITY LIQEJIQllE - hLBEMS RcPORTING PERIOO TYPc ANO LONER LIMIT AI.L CONTROL NUMBER OF TOTAL NVHBER OF INDICATOR LOCATIONS l,QQhILQll XIII VIQdEDI 83Ullhl. llEhki LOCATIONS NONROVTINE OF ANALYSIS Oc TECTI ON MEAN (F) NAHE MEAN (F) MEAN (F) REPORTEO PERFORHEO (LLO) RANG" DISTANCE ANO DIRECTION RANGE RANGE MEASUREMENTS SEE 8QIE I GEE SQIE 1695 ~ 72( 1/

2 1)

SEE 5QIE 2 1695e72( 1/ 1)

KEE UQIE 2 1618 ~ 79( 1/ 1)

GROSS BETA 25 F 00 PAGE FARH 2 1695.72 - 1695e72 8.75 MILES E 1695.72 - 1695.72 1618e79 - 1618.79 GAHMA (GcLI) 2 K-40 1080.23( 1/ 1) 1080 ~ 23( 1/ 862.72( 1/

BI-214 NOT ESTAB NOT 'STAB 1080+23 1

- 1080.23 VALUES <LLO PAGE FARH 8.75 HILES E 1080.23 - 1) 1080.23 862. 72 8o47(

862 1/

'21)1) 8.47 8.47 3.62( 1/

PB-214 AC-228 NOT ESTAB NOT ESTAB 1

1 VALUES <LLO VALUES <LLO 3.62 2 70( 1/

3 '21)1) 2I70- 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 LOCATION OF FACILITYLIUE5IQUE ffgg7 DOCKET NO ~ $ Q:7$

REPORTING PERIOD oc7$ {}c2$$

BLBftBUB TYPE ANO LONER LIHIT ALL CONTROL NUHBER OF l'OTAL NUHBER OF INDICATOR LOCATIONS LQQBXIQU UIIU UIQUEDI BUUQBL UEBU LOCATIONS NONROUTINE

)F ANALYSIS DETECTION MEAN (F) NAHc HEAN (F) HEAtl (F) cPORTED PERFORHEO (LLD) RAtlGE DISTANCc AND DIRECTION RANGC RANGE HCASUREHENTS Zff UQZE 1 Xff UQIE 2 Gff MA+

UQ~ c 7 off UQIE lOSS BETA 25.00 6048 '6(

'6 1/

'61) PAGE FARH e048.46(

- 1/6048.46

1) 6564 '8( 2 1/ 1) 2 6048 6048 8 ~ 75 HILLS c 6048.4e 6564.38 - 6564.38 NHA (GELI) 2

'-40 1/

- 1/3408.85 NOT ESTAB 3408 F 85( 1) PAGE FARH 3408.85( . 1) 3694 e1 ( 1/ 1) 3408 ~ 85 - 3408 ~ 85 E 75 MILES s S408.85 3694.61 - 3694.61 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)

FACILITY hggg55 EEEBZ OF LOCATION OF FACILITY LIPEEI9UE BlBEB~B DOCKET NO ~ 19=22242694226 REPORTING PERIOD TYPE ANO LONER LIMIT ALL CONTROL NUMBER OF TOTAL NUMBER OF INDICATOR LOCATIONS MEAN (F)

L99BII98 III'IQUEXI BBUllBl HEBE LOCATIONS NONROUTINE OF ANALYSIS PETcCTION NAHE HEAN <F) MEAN (F) REPORTcD PERFORMED (LLO) RANGE DISTANCE AiVO DIRECTION RANGE RANGc HEASUREHENTS 5EE 59IE 1 Xff 59IE 2 REE 89IE 2 EEE UNTIE 2 GROSS BETA 25 ~ 00 4397.55( 1/ 1) LOONEY FARM 4397 55( 1/ 1) 3768.67( 1/ 1)

GAHHA (GELI) 2 4397s55 - 4397.55 5 ~ 75 NIL iS ENE 4397 e 55 4397 ~ 55 3768 '7 '3768 ~ 57 2

K-40 NOT ESTAB 1838 1838

'2(

'2 1/

1838 '21)1) LOONcY FARH

'5 1838 ~ 92(

- 1/1838.92

1) 1384 '5( 1/ 1) 5 MILES ENE 1838 92 1384.55 1384 ~ 55 0 '0( 1/

- 1/ Oo10 PB-214 NOT ESTAB LOONEY FARM 0 ~ 10( 1) 1.21( 1/ 1) 0.10 0.10 5 ~ 75 H ILES ENE 0 ~ 10 1e21 1 ~ 21 0.33( 1/

- 1/ 0.33 PB-212 NOT cSTAB 1) LOONEY FARH 0 33( 1) O.rr< 1/

0 '3 0.33 5 ~ 75 MILES ENE 0 '3 Oo 77 0.77 1 )

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)

TYPE ANO NAHE OF LOCATION OF FACILITY l, LONER LIMIT f

FACILITY gQllg>

jgf$ IQgf ALL Sl.kf ffgfI 855 DOCKET NO ~ 19=?22c?6Qc225 REPORTING PERIOD 1$ fjg CONTROL NUMBER OF TOTAL NUMBER OF INDICATOR LOCATIONS l.QCBIIQB hIIU tlIGUESI BHHQBL BEAU LOCATIONS NONROUTINE

)F ANALYSIS DETECTION MEAN (F) NAHE HEAN (F) HcAN (F) REPORTED PERFORMED (LLD) RANGc DISTANCE ANO OIRcCTION RANGE RANGE MEASUREMENTS hf f UQIE 1 ff BQIE 1/2 4228 '7(

Rff 5Q:f 2 off 3786.61(

BQIE 2 ROSS BETA 2

25.00 4228 87 " 4228.87

1) 7 MILES NNM 4228 ~ 87(

4228.87 1/

- 4228.871) 3786.61 - 1/ .

3786.61 1)

AHHA (GE LI) 2 K-40 NOT ESTAB 21 03 ~ 35 ( 1/ 1) 7 HILES NNN 2103.35( 1/ 1) 2103'9 ( 1/ 1) 2103 ~ 35 " 2103.35 2103.35 2103m 35 2103.69 2103.69 BI-21 4 6.31( 1/ 1) 7 MILES NNN 6.31( 1/ 1) 8.97( 1/ 1)

NOT ESTAB 6.31 6 ~ 31 6 ~ 31 6. 31 8 ~ 97'- 8 '71)

PB-214 NOT ESTAB 2 2

'0(

'0 1/

2 '01) 7 HILES NNN 2 20(

'2 ~ 20 1/ 1) 2.20 3 ~ 10(

3 ~ 10 1/

3o10 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 C ANNIAL AVERAGE 0 'P o

IJ C

4J Preoperational Operational 6ROSS 8ElA kTIVIIY 0 Phase Phase IN HRI N<1% MATER SUPPLIES tlJ C

~ BOWN FERRY NuCLEAR fLANT O CO C

0 rr rl CA 4J Ch o

IJ ev 0

V '4 4l

'P C p Q Average: Preooerational phase 11 I

, 1 g1:i

.WiI 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 Fl ure 7 24.

+h <to Direot Radiation Levele D OFFono Browne For ry Nuolear Plant 20.

1976 1977 1978 1979 1980. 1981 1982. 1983. 1984 1985. 1986.

24. Figure 8

+ Onomato Direot Radiation Levele D OFFoce Browne Ferry Nyolear Plant

22. 4-Quarter Moving hverago 14.

12.

1976. 1977. 1978. 1979. 1980. 1981. 1982. 1983. 1984. 1985. 1986.

bl FlguFe 9 26.

Direot Radiation Levels Watts Bar Nuolear Plant 24.

Onelto p OFFeite 22.

16 14.

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

Figure l0 26.

,Direot Radiation Levele Wat te Bar Nuol ear Plant

24. 4-Quarter Moving Average Oneite p OFFeite 22.

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 7

gamma activity and 89 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, Benthic Water Samples River/river mile phytoplankton fauna Sediment Fish (collected monthly)

Tennessee 277.9 X Tennessee 285.2 Tennessee 288 ' K, Tennessee 291.7 X Tennessee 293.5 Tennessee 293.7 X (discharge area)

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 LOWER L IH IT ALL CONTROL NUMBER OF TOTAL NUMBER pc INDICATOR LOCATIONS L994II98 hIIU-UIQUEKI 6859hL 5E65 LOCATIONS NONROUTINE OF ANALYSIS DETECTION MEAN (F) NAHc HEAN (F) MEAN (F) REPORTED PERFORMED (l.LD) RANGE DISTANCE AND DIRECTION RAtlGE RANGE PlEASUREHENTS BEE 89IE 1 SEE UQIE 2 GEE UNTIE 2 5EE NQIE 2

ROSS ALPHA F 00 0 VALUES <LLD 1 VALUES <LLO 1 AtlALYSIS PERFORHED (ROSS BFTA Ze00 3 ~ 13( 35/ 39) TRH 293 ' 3.27(

- 12/ 13) F 24( 22/ 26) iAMHA (GELI) 65 2 ~ 13 - 4o37 2 '7 4.31 2 07 - 5o49 65 K 40 NOT ESTAB 11 ~

11e52 52 (

- 1/ 11.52

39) TRH BF tl 293.7 DISCHARGE 11.52(

11 '2 1/ 13) 11 52 27.D4(

20.68 3/ 26) 39.53 BI "214 NOT ESTAB 7.02( 11/ 39) TRM 285 ' 9.47( 5/ 13) 10.56( 17/ 26) 0.34 - 23.29 0 '4 22 '3 0 13 44 F 09 PB-214 NOT ESTAB F 08(

- 6/ 39) TRH 293 ' 4 66( 3/ 13) 7 29( 15/ 26)

PB-212 NOT ESTAB 0.'78

'4( 6 6/ 39)

'0 BFN DISCHARGE TRH 285 ' 3 2 07 47( 1/

6. 30 13)

De47-57( 10/

18 90 26) 0 '2 '7 '9 1 1 3 5.47 5 ~ 47 0 3 ~ 11 AC-228 15 F 00 39 VALUcS <LLD 27.49( 1/ 26) 27e49 27.49 iR 89 10 F 00 12 VALUES <LLD 8 VALUES <LLO 20 ANALYSIS PERFORMED iR 90 F 00 12 VAl.UES <LLD 8 VALUES <LLO 20 ANALYSIS PERFORMED tRITIUM 330 F 00 334 '1( -

334.51 1/ 12) 554 ~ 51 TRH 285 ' 334 51(

354.51 - 1/ 4) 333 48( 1/

333.48 8) 20 554 ~ 51 333 ~ 48 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 OOCKET NO ~ 2Q=252c2(tQc225 LOCATION OF FACILITY LIUESIQUE hLSEMB REPORTING PERIOO TYPE AHO LOWER LIHIT ALL CONTROL HUHBCR OF TOTAl. NUHSER OF INOICATOR LOCATIONS I QtihIIQU liIIU UIQUEGI 8UUMhl UEhU LOCATIONS NONROUTINE OF ANALYSIS OETECTION HEAN (F) 'h AHE HEAN (c) HEAK (F) REPORTEO PERFORHEO (LLO) RANGE OISTANCE ANO OIRECTION RANGE RANGE'EE HEASURcHENTS UQIE 1 SEE UQIE 2 SEE UQIE 2 UQIE 2 BcTA SEE 0 ~ 10 32 66(

- 4/ 37.75

4) 32 '7( 2/ 2) 29.20( 2/ 2)

GROSS 6 27.58 27.58 - 37.75 28 '7 29o75 GAHHA (GELI) 6 0.08( 4/

CS-137 0.02 0 '6 0 4)

'1 WILSON RESERVOIR TRH 0 09(

0 F 07 - 2/ 0,11 Oe09(

Os09 2/ 2) 0 ~ 10 4/ 2/ 2/

259-275'ILSON K-40 HOT ESTAB 14 03( 4) RESERVOIR 14~25( 2) 15 ~ 15( 2)

'2 10 F

'1 16 '1 TRH 259-275 13 '8 - 14 '2 14 ~ 59 0 ~ 02( 1/

15 ~ 71 BI-214 0 4 VALUES <LLO 2) 0 F 02 0 02 PB 214 NOT ESTAB 0 ~ 02( 1/ 4) 0.02 WHEELER RCS TRH 275-549 0 '2(

0.02 - 1/ 2) 0 01( 1/ 2) 0,02 0.02 0.01 0 ~ 01 PB-212 NOT ESTAS 0 F 00( 1/ 4) WHEELER RcS 0 00( 1/ 2) 2 VALUES <LLO 0 ~ OG- 0 F00 TRH 275-349 0.00 - 0 00 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 RADIOACTIVITY IN SHALLHOUTH BUFFALO (FLESH)

PCI/G - 0 037 SQ/G (DRY WEIGHT)

NAME OF FACILITY gllQguggf ggI DOC<ET NO ~ 20=222c20Qc220 LOCATION OF FACILITY g jgfQTQllf REPORTING PERIOD TYPE AND LOWER LIHIT ALL CONTROL, NUHBER OF TOTAL NUMBER OF INDICATOR LOCATIONS l QQIIIQB dIIB UIQUESI BUUllhL BEST LOCATIONS NON ROUTINE OF ANALYSIS DETECTION MEAN (F) NAHE MEAN (F) HEAN (F) REPORTED PERFORHED (LLD) RANGE DISTANCE AND DIRECTION RANGE RANGE HEASURCMENTS Rf f HQIE 1 BEE 5QIE 2 Sff 5QIE 2 Kff HQIE GROSS SETA 0 ~ 10 19 33( 4/ 4) WHEELER RES 20 ~ 16(

- 2/ 2) 20 '6(

'9 "

2 2/

'22)

SAMHA (GELI) 6 16 '2 - 20 '8 TRH 275-349 20+07 20 '5 18 21 6

CS-137 0 '2 Oa03(

'3 - 2/ 4) 0 03 WILSON RESERVOIR TRM 259-275 0 ~ 03(

0.03 - 1/ 2)

'3 0+03(

- 1/ 2) 0 F 03 0 0 0 ~ 03 K-40 NOT ESTAB 9 95(

8.65 - 4/ 11 4) 90 WHEELER RES TRH 275-349 10 '4(

9.37 ".

2/ 2) 11.90 9.20(

7 49 - 2/

1oe90 2)

SI-214 0 ~ 02 4 VALUES <LLD 0 F 07( 2/ 2) 0.04 - 0.10 PB-214 NOT ESTAB 0 ~ 04( 1/ 4) WILSON RCSERVOIR 004 ( 1/ 2) 0 06( 2/ 2) 0 '400( - 0 04 TRH 259-275 0.04

'1(

- 0 ~ 04 0.04 " 0.08 2/ 1/

- 1/

PB-212 NOT ESTAB 0 4) WHEELER RES 0 2) 0 F 00( 2)

SR 89 0 '0 000-2 VALUES <LLO 001 TRH 275-649 0 '1 0.01 o.oc 0 VALUES <LLD o oo ANALYSIS PERFORHED SR 90 0 ~ 10 VALUES <LLO 0 VALUES <LLO ANALYSIS PERFORHED NOTE: 1 ~ NOMINAL LOWER LIMIT OF DETECTION (LLD) AS DESCRIBED IN TABLE 3 ~

NOTE: 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 OOCKET NO ~ 5Q=222c2BQA22B LOCATION OF FACILITY l,jl)EJIQUE 8! Bl!Br58 REPORTING. r ERIOO 12!i>

TYPE ANO LONER LIMIT ALL CONTROL NUHBER OF TOTAL NUHBER OF INOICATOR LOCATIONS l QGBI?QU lrIIU UIQtlfKI BHUQBt. tlfBh LOCATIONS NONROUT INE OF ANALYSIS 0 ET ECT ION HEAN (F ) NAHE MEAN (F) HEAN (F) REPORTEO PERFORHCO (LLO) RANGE OISTANCE ANO OIRECTION RANGE RArrGE HcASUREHENTS GROSS BETA 5 r. 5QIG 1 0 ~ 10 if'9(

17 f UQIE 4/

2

4) MHEELER RES 17 SEE

'S( - VQIE 2 2/ 2)

SEE lrQIE 2 19 '9( - 2/ 2) 5 14+48 - 20.02 TRH 275-349 1'7 35 18 52 17.54 21.64 GAMMA (GcLI) 6 CS-137 0. 02 0 ~ 03( 2/ 4) NILSON RESERVOIR 0 F 05( 2/ 2) 2 VALUES <LLO 0 '208( 0.03 TRH 259-275 0 '2

'9( 2/

0 03

'4( 2/ 2)

K-40 4/ 4) rrHEELER RES 7 2) 11 NOT cSTAB 7F 6 '5 8 F 00 TRH 275-349 6 '7 8 00 7~ 37- 14 70 BI-214 0 '2 0.04(

0 '4 1/

0.04

4) rrHEELER RES TRM '275-34'9 0.04(

0.04 1/ 2) 0+04 0~04(

0+04-1/

0 '42) 0 '3( 4/ 0 F 03( 2/ 2) 2 VALUES <LLO PB-214 NOT ESTAB 0 '1

'1( 3/

0 '44)4) 'HHEELER RES TRH 275-349 WILSON RESERVOIR 0 '3 0 '1( 1/.

0.04

2) 2 VALUES <LLO PB-212 0 NOT ESTAB 0 F 00 0 '1 TRH 259-275 0 '1 0 01 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 DOCKET NO eJQ"252C26QC226-LOCATION OF FACILITY l.IHEGIQHE-- - BLJlQMdl- REPORTING PERIOD gggeJ TYPE AND LOJJER LIMIT ALL CONTROL NUMBER OF TOTAL NUHBER OF INDICATOR LOCATIONS LQQBI?QU llIIU UIQllESI ht/U!lhl. UESU LOCATIONS NONROUTINE OF ANALYSIS OET ECTION HEAN (F) NAHE HEAN (F) MEAN (F) REPORTED PERFORHEO (LLD) RANGE DISTANCE ANO DIRECTION RANGE RANGE HEASUREHENTS REf HQZE 2 BEE UQIR 2 li'ee,e e KEf. 5QIE 2 r AMMA (GELI) 14 CO"60 0 ~ 01 0 15( 9/ 10) TRM 293 ' 0~ 21( 3/ 3) 0.03( 2/ 4)

CS-134 Oe08 0 '2 0 '1(

5/

0 '3 10)

BFN DISCHARGE TRM 293 '

0.17 0 12( 3/

Oe23 3) 0.02 -

4 VALUES <LLD 0.03 0 08 - 0 '8 BFN DISCHARGE 0 F 08 0 ~ 18 CS-13? 0.02 F

0.79(

0 F 04 - 10/ 10)

'7 TRH 288 '8 1 ~ 08(

0 ~ 59 2/ 2) 27 0 ~ 30(

0~ 1 7 4/

0.51 4)

'5( - 10/ 16e?2 288 '8 1 1 ~

K-40 NOT ESTAB 13 10) TRM 16e23( 2/ 2) 13 ~ 00( 4/ 4)

ZN-65 0 '2 7.92 0 '4( 2/ 10) TRM 293 '

15 0

'3

'7( 1/

16.72 3) 11.76 4 VALUES <LLO 13 '9 Oe02 " Oe07 BFN DISCHARGE 0 F 07 0 0?

BI-214 0 '2 '2( 10/ 10) '8 '1( 2/ 4/

BI-21 2 0 ~ 10 0 '6 1

'9( 1 10/ 10)

'1 TRH 288 TRM 28S.O 1

1 '9 59( 1/

2) 1e82 1) 1 12(

0.98

'5( 4/

1 '24)4)

PB-214 NOT ESTAB 0 '8 -

1

'2( 1 10/ 10)

'7 TRM 25'8 1 ~

1 '9

'6( 2/

1.'39 2) 1 1.05 1 19( 4/

1. 4?

4) 0 '0 '9 '3 1 1

" 1e99 01 40 PB"212 NOT ESTAB 1.44(

0 43 - 10/

1 1

10)

'6 TRM 288 '8 1 1.75(

'0 2/ 2) 96 1 ~

1 2?(

1?

4/

1 ~

'64)4)

RA-226 NOT ESTAB 1 '2( - 6/ 10) TRH 28' 1

1.34( 1/

1 ~

1) 1 ~

1

'509( 3/

1 RA-224 NOT ESTAB 0.36

'0( 5/

1.34

10) TRM 285 '

1 e34 86( 1/

1 '4 1) 0 1.50( 2/

1 22 4)

BE 7 NOT ESTAB 1

0.35 -

0~ 18( 2/

1.86

10) TRH 292e7 1

'6 0 '0(

1 1/

F 86 1) 1.48 27.( 3/

1 51 4) 0 '0 Oe TL-208 0 '2 0.16 0 '0(

10/

Oe20

10) TRH 288 '8 0 '5( 2/

0 '0 2) 0 17 0 '4( 4/

0 46 4) 0 '5 - Oed8 0 '3 Oe6S 0 '232( 0.47 AC-228 0 ~ 06 '4( 10/ 10) TRH 288 '8 79( 2/ 2) 4/ 4) 0 '4 - '2 '7 1 1 1 ~

2 1 1e91 1 15 41 PA 234M NOT ESTAB 2 '4(

2.18 -

2/

2 10)

'1 TRH 291 ~ 76 2 '1(

2 91.

1/ 1) 2 ~ 91 3

~

4.27(

'6 2/

1 ~

4*~

4) 87 SR 89 1 '0 6 VALUES ANALYSIS PCRFORMEO

<LLO

~

2 VALUES <LLO SR 90 0 ~ 15 0 0

'5(

'8 - 4/

0 '56) TRH 277 'b 0 ~ 41(

0.36 Oe 2) 45 0.34(

0.34-1/

0.34 2)

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) ~

TABLE 29 RADIOACTIVITY IN PLANKTON (SAHPLE 1)

PCI/G - 0 ~ 037 BQ/G (DRY HEIGHT)

NAHE OF FACILITY QUQUU$ Efgpg DOCKET NO ~ 29=212c20Qc225 LOCATION OF FACILITY LJUE/IQUE REPORTING PERIOD 1Pgg TYPE AND LOIIER LIMIT ALL CONTROL NUHBER OF TOTAL NUHBER OF INDICATOR LOCATIONS LQfiBIIQU UIIU UIQUEGI BUUQBL UEBU LOCATIONS NONROUT INE OF ANALYSIS DETECTION HE'AN (F) NAHE HEAN (F) MEAN (F) REPORTCD PERFORMED (LLD) RANGE DISTANCE ANO DIRECTION RANGE RANGE MEASUREMENTS off UQIE 1 Xff UQIf 2 off UQIE 2 Kff UQIE 2 GROSS BETA 1

NOT ESTAB SEE NOTE 3 34 71(

34 '1 - 1/ 34 '11)

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.

TABLE 30 RADIOACTIVITY IN CLAH FLESH PCI/G - 0 ~ 037 80/G (ORY WEIGHT)

NAME OF FACILITY QgQggg jfpagI DOCi(ET NO ~ RQ=Z22c26Qc22D LOCATION OF FACILZTY L,IgggIQg aiaa8~8 REPORTING PERIOD gggf TYPE AND LONER LIHIT ALL CONTROl. NURSER OF TOTAL NUHBER OF INDICATOR LOCATIONS LQQ&IIQ8 hIIU UIQUEKI hllUQBI UEEU LOCATIONS NONROUTINE OF ANALYSIS DETECTION MEAN (F) NAHE HEAN (F) HEAN (F) REPORTED PERFORMED (LLO) RANGE DISTANCE AND DIRECTION RANGE 'RANGE MEASUREMENT

)AHHA (GELI) 5EE BQIf 1 $ ff UQIE 2 Gf c gQIh 2 SfE UQIS 2 12 CO-60 0 '8 0.16 016-( 1/ 8) 0 ~ 16 TRH 293 '

BFN DISCHARGE 0.16(

0.16 1/ 3) 0 ~ 16 4 VALUES <LLD z-40 NOT ESTAB F 0 '900( 5/ 8) 12 F 43 TRH 288 '8 12 43(

12 '3 1/

12 1)

'3 2 '2( -

0.90 4/

5.49 4)

ZN-65 0 ~ 17 '9( 4/ 8) TRH 293 ' 53( 2/ 3) 4 VALUES <LLO (Note 3) 1

'4 1 1 0.64- 81 BFN DISCHARGE 81 BI-214 NOT ESTAB 2 '0(

0 33-8/

1 ~

7 '28)8) TRM 288 '8 4 1

90(

90 1/

1 ~

4 1)

'0 1.45(

2~-

4/

'64)4)

PB-214 NOT ESTAB 2 '1(

~

0 30-8/

6 '6 TRM 277 '8 2

.4 2

~

96(

'6 1/ 1) 2 ~ 96 0

1 ~ 40(

0 ~ 12 4/

4 4 ~ 98.

PB-212 NOT ESTAB

~

Oo10(

0 04 5/

0 8)

'18) TRM 277 '8 0 21(

0 21 1/ 1) 0 21 0~ 20(

0 ~ 11 3/

0 '54)4)

TL-208 NOT ESTAB 0 ~ 03(

0 '2 3/

0 F 05 TRH 291.76 0.05(

0 '5 1'/ 1) 0 05 0

0~

'2(

02-1/

0 02 AC-228 NOT. ESTAB 0 16( 2/ 8) TRM 293 ' 0.16( 2/ 3) 0 ~ 14( 1/ 4) 0 15- 0 17 BFN DISCHARGE 0 15 0 ~ 17 0 ~ 14 0 14 NOTE: 1 ~ NOMINAL LOMER LIHZT OF DETECTION (LLD) AS DESCRIBED IN TABLE 3 ~

NOTE: 2 ~ HEAN AND RANGE BASED UPON DETECTABLE HEASUREMENTS ONLY ~ FRACTION OF DETECTABLE MEASUREM NTS AT SPECIFIED LOCATIONS IS INOICATEO IN PARENTHESES (F) ~

NOTE: 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.

TABLE 31 RADIOACTIVITY IN CLAH SMELL PCI/G - 0 ~ 037 BQ/G (DRY WEIGHT)

NAME OF FACILITY QBQ855 EREBUS DOCKET NO ~ 09=222cgkQc225 LOCATION OF FaCILITY I IIEKIQBE

~ 8LBQBlh REPORTING PERIOD TYPE ANO LONER LIMIT ALL CONTROL NUHBER OF TOTAL NUMBER OF INDICATOR LOCATIONS I.QQ8IIQH hIXU UTQUENI 85HQBL UfaU LocaTIo~s NONROUTINE OF ANALYSIS DETECTION HEAN (F) NAME MEAN (F) MEAN (F) REPORTED PERFORHEO (LLD) RANGE DISTANCE tND DIRECTION RANGE RANGE MEASUREMENTS GEE UQI 1 SEE UQIE 2 SEE 5QIZ ? ICE HQIi 2 GAMMA (GELI) i 12 CO-CIO 0 '1 001 0.01 -

( 1/ 8) TRH 293.7 0 01( 1/ 3) 4 VALUES <LLO 0.01 BFN DISCHARGE

'8 0 ~ 01 0 '1

'93)-

K-40 NOT ESTAB 0 13(

0 01 - 6/ 0 TRH 277 0 ~ 22(

Oe 22 1/ 1) 0 F 22 0 '9 3/2/ 0 '04)4) 0 ~ 14(

BI-214 0 F 05 0 '6( - 6/ 8) TRM 288 '8 0.25( 1/ 1) 0.19 (

BI-212 Oe10 0

0

'9

'2( 1/

0 '8

8) TRM 292 '

0 ~ 25 0.12( 1/

0 ~ 25

1) 4 0 '9 VALUES <LLO 0.35 0 '2 - 0 '2 0 ~ 12 0 ~ 12 PB-214 0 F 05 0 17(

- 7/ 0 '4

8) TRH 288 '8 0 '7( 1/ 1) 0.17(

'9 3/ 4)

PB-212 NOT STAB 0 ~ 0?

0 '6(

001 -

8/

016

8) TRM 288 '8 0 ~ Z7 0 ~ 16(

0 ~ 16 1/

0 ~ 27 1) 0 ~ 16 0

0 OZ(

0 '1

~ 3/

0.32 4) 0.04 Ra-226 0 F 05 0 ~ 11( 2/ 8) TRH 293.7 0 ~ 12( 1/ 3) VALUES <LLO TL-208 0.02 0 ~ 10 0 ~ 05(

3/

0.12 8)

BFN TRH 288.78 DISCHARGE 0 ~ 12 0.08( 1/

0 '2

1) 4 VALUES <LLO 0.02 - 0 ~ 08 0 ~ DB O.oe AC-228 0 '6 0 ~ 20(

0 '7 - 7/ 0 '08) TRM 258 '8 0+40(

0 '0 1/ 1) 0.40 0

0 '113(

- 3/ Oo14 4)

SR 89 5. 00 4 VALUES <LLD 2 VALUES <LLD ANALYSIS PERFORHEO SR 90 F 00 F 09(

- 1/ 4) TRH 293 ' 1 09(

- 1/ 2) 1.02( 1/ 2) 1.09 1.09 BFN DISCHARGE 1 ~ 09 1 ~ 09 1 ~ 02 1.02 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) ~

Figure 11

.g4 R ESERVOIR MONITORING NETWORK N

Elk River WHEELER DAM mile 274.90 rnite 277.98 Rogersville 0

mite 29).76 Athens mite 282.6 0

~mile 285.2 B.F. NUCLEAR PLANT S

Champion Paper Co.

ite 28878 0 rnite 293.50 mile 305.0 Cour tland mile 293.70 0

Decatur mite'307.52 Scale of Miles

- Automatic Sam ter 0

Figure 12 ANMNL AVERAGE 6ROSS HETA ACTIVITY m

n Preoperational Operational 0 Phase Phase IN SURFACE )IATER 4l o 4l lJ 1hOWS FERRV i%CLEAR Pusan CA C IJ Ls CC o

IJ 0

o Jl C

C 0 Average:

w V 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.