ML18029A461

Environ Radioactivity Levels,Browns Ferry Nuclear Plant, Annual Rept - 1980.

ML18029A461
Person / Time
Site:	Browns Ferry
Issue date:	12/31/1980
From:	TENNESSEE VALLEY AUTHORITY
To:
References
RH-81-5-BF2, NUDOCS 8504100206
Download: ML18029A461 (165)

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BETS-MASTER FILE REGUI ATOR Y INFORMATION DISTRIBUTION SYSTEM (RID L>V-80 ACCESSION NOR:8500100206, DOC.DATE: 80/12/31 NOTARIZED:

NO¹FACIL:50-259 Browns Ferry Nuclear Power'tations Unit 1<Tennessee 05000259 50 260 Browns Ferry Nuclear Power Station~Unit 2<Tennessee 05000260 50 296 Browns Ferry Nuclear Power Stationi Unit 3, Tennessee 05000296 AUTH BYNAME AUTHOR AfFIlIATION

• Tennessee Valley Authority REC IP~NAME RECIPIENT AFFILIATION

SUBJECT:

"Environ Radioactivity Levels<Browns Ferry f4uclear Planti Annual Rept-1980'DISTRIBUTI N CODE: IE25L COPIES RECEIVED:LTR FNCI~SIZE: o.-.'5 TITLE: Periodic Envir on Moni toring Rept (50 DKT-Annual/Semiannual/E fluent/NOTES:NMSS/FCAF 1cy, icy Nr1SS/FCAF/PM, OL:06/26/73 NMSS/FCAF 1cy, 1cy NMSS/FCAF/PM'L:06/28/74 NMSS/FCAF 1cy~'1cy NMSS/FCAF/PM, OL:07/02/76 05000?59.05000260 05000296 RECIPIENT ID CODE/NAME NRR ORB2 BC OQ INTERNAL: ACRS 11=IE'ILE Ol N.AB 09 N/DSI/R 10 RM/DDAMI/MID COPIES LTTR ENCL RFCIP IENT ID CODE/NAME AEOD NRR/DE/EEB 08 NRR/DS I/METH RGN2/DRSS/EPRPB COPIES LTTR FNCL-1 1?1 EXTERNAL: LPDR NOTES: 03 NRC PDR 02 RH-81-5-BF2 TENNESSEE VALLEY AUTHORITY.ENVIRONMENTAL RADIOACTIVITY LEVELS BROWNS FERRY NUCLEAR PLANT ANNUAL REPORT 1980.~~1'IVISION OF OCCUPATIONAL HEALTH AND SAFETY RH-81-5-BF2 ENVIRONMENTAL RADIOACTIVITY LEVELS BROWNS FERRY NUCLEAR PLANT ANNUAL REPORT 1980 Apri1 1981//~g,//>W ppP1C4~CO pg'-/~a 8504100206 801231 PDR ADQCK 05000259 R PDR CONTENTS List of Tables.List of Figures.~~~~~~~~~~~~~~~t~~~~~~~~~~~~~~~~~~~iii~~~~o iv Introduction 0~~~~~~~~~~~~~~~~~~~~~~~~1 Atmospheric Monitoring

.Terrestrial Monitoring

.Reservoir Monitoring

.~~~~~~~~~~~~~~~~~~~~~~I~~~~~~~~~~~~~~~~~~~~~~~~~~~11 21 33'uality Control.~~~~~~~~~1~~~~~~~~~~45 Data Analysis.~~~~~~~~~~~~~~~~~~~~~~45 Conclusions.

~~~~~~~~~~~I~~~~~~~~~~45 LIST OF'ABLES Table Table 1-2-Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table 6-7-8-9-10-ll-12-13-14-15-16-17-18-19-20-21-22-23-24-25-26-Table 3-Table 4-Table 5-4 le~~~~~~~~6 8 16 17 18 19 20 23 24 25 26 27 28 29 31 32 35 37 38 39 40 41 42 43 Environmental Radioactivity Sampling Schedule Atmospheric and Terrestrial Monitoring Station Locations-Browns Ferry Nuclear Plant Detection Capabilities for Environmental Samp Analysis Results Obtained in Interlaboratory Comparison Program.Maximum Permissible Concentrations for Nonoccupational Exposure Radioactivity in Air Filter.Radioactivity in Rainwater.

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

.Radioactivity in Soil Radioactivity in Well Water Radioactivity in Public Water Supply.Environmental Gamma Radiation Levels Radioactivity in Food Crops Radioactivity in Soybeans Radioactivity in Poultry Sampling Schedule-Reservoir Monitoring Radioactivity in Surface Water Radioactivity in White Crappie (Flesh).Radioactivity in Smallmouth Buffalo (Flesh)Radioactivity in Smallmouth Buffalo (Whole)Radioactivity in Sediment Radioactivity in Clam Flesh.Radioactivity in Clam Shell LIST OF FIGURES Figure 1-Tennessee Valley Region.~~~~~3 Figure 2-Atmospheric and Terrestrial Monitoring Network........13 Figure 3-Local Monitoring Stations~~~14 Figure 4-Browns Ferry Nuclear Plant Site Monitoring Stations.....15 Figure 5-Reservoir Monitoring Network.~~~~~36 ENVIRONMENTAL RADIOACTIVITY LEVELS BROWNS FERRY NUCLEAR PLANT ANNUAL REPORT 1980 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.Ho~ever, a fire in the cable trays on March 22, 1975, forced the shutdown of both reactors.Units 1 and 2 resumed.operation and Unit 3 began testing in August 1976.Unit 3 began commercial operation in January 1977.The preoperational environmental monitoring program established a baseline of data on the distribution of natural and manmade radioactivity in the environment near the plant site.However, seasonal, yearly, and random variations in the data were observed.In order to determine the potential increases in environmental radioactivity levels.caused by.the plant, comparisons were made between data for indicator stations (those near the plant)and control stations (those remote from the plant)in con)unction with comparisons with preoperational data.Staffs in the Division of Occupational Health and Safety, the-Division of'ater Resources, and Resource Services, carried out the sampling program outlined in tables 1 and 19.Sampling locations are shown in figures 2, 3, 4, and 5, 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 Muscle Shoals, Alabama and Eastern Area Radiological Laboratory (EARL)at Vonore, Tennessee.

Alpha and beta analyses were performed on Beckman Low Beta II and Beckman Wide Beta II low background proportional counters.Nuclear Data (ND)Model 100 multichannel analyzer.systems employing sodium iodide NaI(T1)detectors and ND Model 4420 systems in con]unction with Germanium Ge(Li)detection systems were used to analyze'he samples for specific gamma-emitting radionuclides.

Samples of water, vegetation, air particulates, food crops, and charcoal ('specific analysis for I)are routinely counted with NaI(T1)detection systems.If significant concentrations of radio-isotopes are identified, ox if the're is a reasonable expectation of increased radioactivity levels (such as during periods of increased fallout), these samples are counted on the Ge(Li)system.Identifi-cation 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(T1).The data obtained by Ge(Li)detectors were resolved by the ND-4420 software.The detection capabilities for environmental sample analyses given as the nomina1 lower limits of detection (LLD)are listed in Table 3.Samples processed by NaI(T1)gamma spectroscopy were analyzed for 1$specific gamma-emitting radionuclides and radionuclide combina-tions., For these analyses, radionuclide combinations such as'u and Zr-Nb are analyzed as one radionuclide.

All photopeaks found in 95 Ge(Li)spectra were identified and quantified.

Many of the isotopes identified by Ge(Li)spectral analysis are naturally occurring or naturallv produced radioisotopes, such as"Be" K Bi"Bi Pb 214 226)Pb<~Ra, etc.LLD's for the analysis of the radionuclides listed below are given in Table 3B.LLD's for additional radionuclides identified by Ge(Li)analysis were calculated for each analysis and nominal values are listed in the appropriate data tables.In the instance where an LLD has not been established, an LLD value of zero was assumed.A notation in a table of" values<LLD" for an isotope with no established LLD does not imply a value less than 0;rather it indicates that the isotope was not identified in that specific group of samples.For each sample type, only the radionuclides for which values greater than the LLD were reported are listed in the data tables.TVA's Radioanalytical Laboratories participate in the Environ-mental 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 environ-mental monitoring program.Routine sample handling and analysis pro-cedures were employed in the evaluation of these samples.Gamma spectral analyses were performed using NaI detectors.

The EARL began processing samples in May 1980.The results received during calendar year 1980 are shown in table 4.The+3o limits based on one measurement were divided by the square root of 3.to correct for triplicate determinations.

a The following radionuclides and radionuclide combinations are auantified by the ALPHA-.M least-squares computer code: 1"1'1""Ce; Cr;3 I;103~106Ru; 134Cs;137Cs Zr-Nb;58Co;"Mn'5Zn 60Co;40K;and Ba-La.

l lo"fi J/-*"i'I A L A B'A M A.I EGEND"~.,-.HARTSVILLE NUCLEAR PLANT fggjf--PHIPPS BEND NUCLEAR PLANT~-,CLIIICH RIItER BREEDER REA TOR"." h I h M I SS.G-E 0 R.-A;"'-WATTS BAR NUCLEAR PLANT-SEQUOYAH NUCLEAR PLANT.-'BELLEFONTE NUCLEAR PLANT-BROWNS FERRY NUCLEAR'PLANT YELLOW'CREEK NUCLEAR PLANT F LONSVLLS TENNESSEE VALLEY-REGlON 4'W~g W.g"~i~~-'."--(TVA NUCLEAR-Pl ANT SlTES)K E N.T U C.K Y r 5 C.*~/.)ol~~S 58%(l.v~g,~J J ASHVILL OAK IOOOS~r JACKSOIIf I I~wN P Xr~~"h")(/.MEhJ~S/CHATTANOOOAh.

~/,~,~h/c 1'I h'I j>~4 Table 1 ENVIRONMENTAL RADIOACTIVITY SAMPLINC SCHEDULE Air Charcoal Rain-Heavy Particle River Well Public Aquatic Life St tioo let ti e Filter tilter t r tello t Soil~te t ti Milk W ter Steer W t r o d Sedi eet Sordo Muscle Shoals W W M Lavrenceburg W W, M H=A RoEersville W W M M.A Athens Decatur W W M W W'M'H A H Courtland W W H Site NW-I Site N-2 Site NE-3 W W H Site NW-4 W W M Site WSW-5 W W M M A Farm B Farm Bi Farm H W Farm T Farm L Control Farms Onsite Well Wheeler Dam Elk River Tennessee River Champion Paper Co.Various Local Farms W-Weekly M-Monthly (every 4 Qeeks)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 irom Plant 1.0 Mile 0.9 Mile 1.0 Mile 1.7 Miles 2.5 Miles 13.8 Miles.10.9 Miles LM-1 BF, Northwest LM-2 BF, North LM-3 BP, Northeast LM-4 BF, Trailer Park LM-5 BF, Davis Farm PM-1 BF, Rogersville, AL PM-2 BF, Athens, AL (1.6 kilometers)

N (1.4 kilometers)

NNE (1.6 kilometers)

NE (2.7 kilometers)

NNW (4.0 kilometers)

WSW (22.2 kilometers)

NW (17.5 kilometers)

NE (13.2 kilometers)

SSE (16.9 kilometers)

WSW (51.5 kilometers)

W PM-4 BF, Courtland, AL 10.5 Miles 32.0 Miles BP, Muscle Shoals, AL (Control)BF, Lawrenceburg, TN (Control)RM-1 RM-2 40.5 Miles (65.2 kilometers)

NNW PM-3 BF, Decatur (Trinity), AL 8.2 Miles Farm S Farm B Farm H Farm T Farm Bi Farm N (Control)Farm J (Control)Farm C (Control)Farm Ca (Control)4.75 Miles (7.6 kilometers).N 7.0 Miles (11.3 kilometers)

NNW 3.75 Miles (6.0 kilometers)

N~7.0 Miles 4.5 Miles 27.0 Miles (11.3 kilometers)

ENE (7.2 kilometers)

ENE (43.4 kilometers)

NW 32.0 Miles 32.0 Miles (51.5 kilometers)

N (51.5 kilometers)

W 40.0 Miles (64.4 kilometers)

NNW Table 3 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS A.S ecific Anal ses NOMINAL LONER LIMIT OF DETECTION LLD*Air particulates

~Ci Charcoal~C1 Vegetation Fallout Mater and grain Ctl4P~Ct 1 p~CI~~dr Soil and Sediment~i~Ci~dr Pish, clam flesh, plankton, p~Ci/~dr Foods, meat, Clam shells poultry, Milk~Ci~~dr~CI/k~gt~il Total u Cross a Cross S I ill~sS SOSr 0.005 0.01 0.005 0.001 O.02 0.05 0.4 2.0 2.4 330 10 2 0.01 0.05 0.20 0.25 0.05 0.35 0.70 1.5 0.3 0.1 0.1 0.5 0.1 0.7 0.7 5.0 1.0 1.5 25 40 B 0.5 10 2*All LLD values for isotopic separations are calculated by the method developed by Pasternack and Harley as described in NASL-300.Factors such as sample sire, 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 analysed within one week of the collection date.Conversion factors: 1 pCi 3.7 x 10 Bq;1 mCi 3.7 x 10 Bq.

Table 3 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS B.Canna Anal ses NOMINAL LOWER LIMIT OF DETECTION LLD Air particulates

~Ct/o NaI*~Ce Li**Water Vegetation Soil and and milk and grain sediment~CL/L.NCL/LC~dr~CL/dr NaI~Ce Li NaI~Ce Li Nal~Ce Li Clam flesh Fish and plankton~ci/~dr~CL/d ll i~CLL N i~CLL Foods,(tomatoes potatoes, etc.)Ci/wet Clan shells NCCL/ddrr NaI~Ce Li NaI C~eLi Meat and poultry CCCL//k k'rrl: Nal Ce(lil 1 Nr 1)1 IIC C s 1Cr 1111 101~10CR 106R lSN c 117C ssZr-Nb ssz s sNb"Co ssZn coG'0R looBa-La 1008 1 aoLa 0.01 0.01 0.01 0.02 0.02 0.02 0.01 0.10 0.02 0.03 0.02 0.01 0.01 0.01 0.01 0.01 0.01 0.01 0.02 0.01 0.03 0.02 0.07 0.03 0.01 0.01 0.04 38 0.55 33 60 44 1.10 15 8.0.35 40 0.65 40 10 26 0.20 10 5 0.20 10 0.20 10 5 15 5 0.23 10 5 0.20 15 9 0.25 10=5 0.17 150 2.50 15 0.68 25 7 0.35 0.22 0.47 0.60 0.09 0.20 0.45 0.51 0.33 0.12 0.06 0.12 0.12 0.11 0.05 0.05 0.20 0.05 0.15 0.11 0.23 0.06 0.11 0.90 0.15 0.34 0.08 0.06 0.10 0.02 0.11 0.08 0.02 0.03 0.Ol 0.01 0.01 0.02 0.01 0.07 0.02 0.35 0.06 0.60 0.10 0.20 0.02 0.45 0.11 0.12 0.08 0.12 0.02 0.12 0.03 0.01 0.20 0.01 0.15 0.01 0.23 0.02 O.ll 0.01 0.90 0.15 0.07 0.02 0.35 0.56 0.07 0.74.0.48 0.08 0.15 0.07 0.07 0.08 0.17 0.08 0.30 0.10 0.35 0.60 0.20 0.45 0.12 0.12 0.12 0.20 0.15 0.23 O.ll 0.90 0.15 38 0.06 0.10 60 0.02 15 40 0.11 0.08 10 0.02 , 10 10 0.03 0.01 0.01 15 0.01 10 0.02 15 0.01 10 150 15 0.07 0.02 20 15 55 15 40 15 70 20 30-15 400 50 25 7 50 15 90 33'C 44 200 90 8 50 20 150 40 90 26 40 50 5 40 15 40 10 5 5 5 9 5*The NaI(T1)LLD values are calculated by the method developed by Pasternack and Barley as described in HASL-300 and Nucl: Instr.'ethods 91~533-40 (1971).These LLD values are expected to vary depending on che activities of the components in the samples.These figures do not represent the LLD values achievable on a given sample.Water is counted in a 3.5-L Marinelli beaker.Vegetation, fish, soil, and sediment are counted in a 1-pint container as dry veight.The average dry veight is 120 grams for vegetation and 400-500 grams for soi]sediment and fish.Meat and poultry are counted in a 1-pint container as dry veight, then corrected to vet veight using an average moisture content of 70X.Average dry veight is 250 grams.Air particulates are counted in a veil 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 vithin one veek of the collection, dace.**The Ce(Li)LLD values are calculated by the method developed by Pascernack and Harley as described in HASL-300.These LLD values are expected co vary depending on che activities of the conponencs in the samples.These figures do not represent the LLD values achievable on given samples.Water is counted in either a 0.5-L or 3'-L Marinelli beaker.Solid samples such as soil, sediment, and clan shells are counced in a 0.5-I.Marinelli beaker as dry weight.The average dry weight is 400-500 grams.Air filters and very small volume sanples are counted in pecrie dishes centered on the detector endcap.The counting syscen consists of a ND-4420 multichannel analyzer and either a 25XN 14X, 16X, or 29X Ce(Li)detector.The counting cine is normally 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.All spectral analysis is performed using the software provided with the ND-4420.assumption is made that all samples are analyzed within one week of the collection date.Conversion factor: 'pCi 3.7 x 10 Bq.

Table 4 Results Obtained in Interlaboratory Comparison Program A.Air Pilter (pCi/filter)

Gross Al ha Gross Beta Stontium-90 Cesium-137 Date EPA value (+3o)TVA AVG.WARL EARL EPA value TVA AVG.(+3o)WARL EARL EPA value TVA AVG.(+3o)WARL EARL EPA value TVA AVG.(+3@)WARL EARL 12/79 10+9 10 29+9 33 9 2 2.6 , ll 10+9 l0 3/80 Equipment malfunction at EPA 6/80 9/80 24+10 24+9 26 25 24 24 28+9 10+9 33 36 12 16 8 2 2.6 9 8 0 0<1 12+9 10+9 13 12 9 9 12/80 Results not received at this time B.Tritium in Urine (pCi/1)Date EPA VALUE (+3a)TVA AVERAGE 12/79 3/80 6/80 9/80 12/80 2060+599 2173+603 2500+610 1700+589 3150+624 2100 2300 1437 2007 1723 1693 3287 3576

.-~g a-~Table 4 (Contd)Results Obtained in Interlaboratory Comparison Pro&ram C.Radiochemical Analyses of Water (pCi/1)Gross Al ha EPA value TVA AVG.D te~33a)WIIRL EARL Gross Beta EPA value TVA AVG.~435 IIARL EARL Strontium-89 Strontium-90 Tritium Iodine-131 EPA value TVA AVG.EPA value TVA AVG.EPA value TVA AVG.EPA value TVA AVG.~33a IIARL EARL~(33a WARL EARL~33a WARL EARL~t3a IIARL EARL 11/79 12i9 14 12/79 1/80 30i14 25 2/80 3/80 13i9 12 4/80 5/80 23i9 23 20 6/80 7/80 36i16 31 19&/80 9/80 32i14 34 27 10/80 11/80 16i9 16 20 12/80 2?i9 45i9 22i9 14i9 38i9 21i9 1349 27 47 25 16 1&44 41 26 24 16 24 10i9 98 20i2.6 238 5i9 4 6 12i2.6 13 24i9 27 23 15i2.6 18 2040i599 2128 1?50i591 1920 3400i624 3363 ll 2000i598 1947 1960 53i9 44i9 2240i606 2270 2213 22i10 1210i570 1180 1223 36i9 16 3200i624 3207 3207 50 41 2J'1 19 D.Gamma-Spectral Analysis of Water (pCi/1)Chromium-51 EPA value TVA Date~33a WARL Colbalt-60 AVG.EPA value TVA AVG.MIL~(333 WARL EARL Zinc-65 Ruthenium-106 Cesium-134 Cesium-137 EPA value TVA AVG.EPA value TVA AVG.EPA value TVA AVG.EPA value TVA AVG.~a3a WARL EARL~k3a)WA)IL EARL~a3a IIARL EARL~a3a WARL EARL 2/80 101+9 93 6/80 13i9 010/80 86i9 74 lli9 ll 0 5i9 7 5 90 16i5 14 15 25i9 23i9 25i9 31 25 21 24 20 51i9 3?i9 46i9 33 loi9 16 30i9 31 36k 40 lli9 15 10 17i9 19 18 35 42 20i9 22 19 12i9 12 13 Table 4 (Contd)Results Obtained in Interlaboratory Comparison Progrbm E.Milk (pCi/1)Strontium-89 Strontium-90 EPA value TVA AVG.EPA value TVA AVG.a ee~(i3a IIARL EARL~t3a WARL EARL Iodine-131 Cesium-137 Barium-140 Potassium EPA value TVA AVG.EPA value TVA AVG.EPA value TVA AVG.EPA value TVA AVG.~33 IIARL EARL~33 a MARL EARL~33 a MARL EARL~33 a wARL EARL 1/80 10i9 ll'512.6 28 4/80 1019 10 1512.6 18 7/80 55+9 57 59 1712.6 19 18 10/80 23i9 25 25: 0 1<2 0.Oii0.2 33x9 0 igf9 0 23 0 0 18 12 40i9*39 0.0110.2 0 16001139 1577 28i9 30 0 0 11901103 1117.3519 34 35 0 0 0 15501135 1593 1533 2149 22 22 0 0<15 16201140 1447 1473 11/79 7319 3/80 7/80 94t9 11/80 819 71 113P 107P<10<10 27i2.6 13i2.6 0 F.Foods (pCi/kg, Net Weight)34P 127ill 127 2219 Sample spoiled in transit 22P 17P 5419 47 49 2719 3 3 34110 24 24 1219 27 27 ll 10 0 0 0 2260+225 2737 2730 0<15<25 2520+208 2560 2723 24 0.001 0 15111132 1372 a.Western Area Radiological Laboratory, Muscle Shoals, Alabama.b.Eastern Area Radiological Laboratory, Vonore, Tennessee.

c.Not reported to EPA.d.Low value result of deficiencies in analytical procedure..

The procedure has been revised to correct these deficiencies.

e.Specific analysis for 3 I to test the procedures used for the analysis of~I in milk.f.Results not returned by EPA.g.9Sr and Sr results reversed in report to EPA.h.Laboratory in start up mode: procedures being refined.i.Investigation of the sample and procedures produced no indication for the cause of the discrepancy.

Subsequent analyses have been satisfactory.

Belou TVA LLD.k.Analysis of these isotopes by NaI produce greater variation because of (1)the abundance of the main energy peaks (2)the broad shape of the peak, (3)relatively high background in the peak area, and (4)interference from radon peaks in the peak area.m.Values for potassium reported as mg 8X potassium per t of sample.n.Values for potassium reported as mg of potassium per kg of sample.p.Discrepancies in strontium values are believed to be due to (1)inhomogeneity of the sample ash and (2)magnification of'slight errors in weight conversions.

Efforts are being made to reduce the impacts of these variables.

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&4).Four perimeter air mbnitors 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 HV-70 particulate filter at a regu-lated flow of 3 ft/min.Zn series with, but downstream of, the particulate 3 filter is a charcoal filter used to collect iodine.Each monitor has a col-lection 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 radiati'on levels at each remote and perimeter station.Each"'of the local air monitors is fitted with a GM tube that con-tinuously scans the particulate filter.The disintegration rate of the atmospheric radioactivity is continuously recorded at each station and radio-telemetered into the plant.Air filters are collected weekly and analyzed for gross beta activ-ity.No analyses are performed until three days after sample collection.

The samples are composited monthly for analysis of specific gamma-emitting 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.With reference to table 5, which contains the maximum permissible concentrations (MPC)recommended by 10 CFR 20 for nonoccupationa1.

exposure, it is seen that the maximum beta concentration in air is 0.12 percent MPC.Rainwater is.collected monthly and a 3.5-liter'ample analyzed for specific gamma-emitting radioisotopes and tritium.The results are shown in table 7.During this period one sample was not obtained because of insufficient rainfall.The gummed acetate that is used to collect heavy particle fallout is changed monthly.During this reporting period, two samples were damaged to the extent that insufficient material remained for analysis;The samples are ashed and counted for gross beta activity.The results are given in table 8.

12 Charcoal filters are collected and analyzed for radioiodine.

The filter is counted in a single channel analyzer system.The data are shown in table 9, where the highest value reported is 0.06 percent MPC in air for I.

~)~13 Figure 2 ATMOSPHERIC AND TERRESTRIAL MONITORING NETWORK RM.2BF LAWRENCEBURG yPULASKI FAYETTEVILLE

~WILSON FLORKNCK PM-IBF WHEELER ROBE SVIL OAM FFIEL MUSCLE SHOALS RM IBF LEIGHTON TU SCUM BIA COURTLANO PM-4 F ATHENS PM-2BF BROWNS F RRY NUCLEAR PL NT OECAT PM-38F0 IO MILES HUNTSVILLE pRUSSELLVILLK HARTSKLLE 4 GUN 7 SV IL OAM 2S HALEY VILLE~CULLMAN 45 MILES RAINWATER SOIL 0-ENVIRONMENTAL MONITOIlINO STATION NOTE<THE FOLLOWING SAMPLES ARE COLLECTED FROM EACH STATION: AIR PARTICULATES RADIOIODINE HEAVY PARTJCLE FALLOUT LOCAL MONITORING STATIONS BROWNS FERRY NUCLEAR PLANT ATHENS U S HWY 72 BFN ALA.HWY 20 Legend 0 Air Monitor I Air Monitor 8 TLD Station b,.TLD Station A Automatic Well Sampler H Dairy Farm DECATUR Scale 0 I 2 3 0 5 IMiles Pi ure 4 BROWN'S FERRY NUCLEAR PLANT SITE MONITORING STATIONS I~t r/:/LMZBF LM-4BF P'i/r i LM-IBF/f5 r~~4/:/j~i rf I r gr 5 r r ATMOSPHERIC ANO TERRESTRIAL MONITORS~TLD STATIONS PLANT BOUNDRY-ROADS+WELL E WELLS (NOT BEING SAMPLED)t$vkrllrri get S WHEELER LAKE

.'16 Table 5 MAXIMUM PERMISSABLE CONCENTRATIONS FOR NONOCCUPATIONAL EXPOSURE Alpha Nonvolatile beta Tri tiUIQ 1 37Cs 103>106RII 1 44Ce 95Zr-95Nb 140Ba-140La 131I In Water~C1/1*30 3,000 3,000,000 20,000 1,0,000 10,000 60,000 20,000 300 In Air~C1 m*100 200,000 500 200 200 1,000 1,000 100 Zn'4Mn 60C"Sr 90Sr"Cr 1'3 4(58Co 1000000 100,000 30,000 3,000 300 2,000,000 9,000 90,000 2,000 1,000 300 300 30 80,000 400 2,000*1 pCi=3.7 x 10 3 Bq.

TABLE 6 RAOIOACTIlfITY IN AIR FILTER PCI/H(3)0'37 BQ/H(3)NAHE OF FACILITY hht)MBS'EBBY LOCATION OF FAC IL ITY LIMESIOUE-AL484)(4 DOCKET'NO 50m25)I*240a'K%.

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REPORTING PERIOD LRBG TYPE AND TOTAL NUNBER OF ANALYSIS EEBEOBBEO GROSS ALPHA 52 GROSS BETA 572 GAHNA (NAI)ill C5 134 I>>131 LOKER LIMIT OF DETECTION a LLLQI 0 F 005 0.010 0~010 0~010 RR 95 NB>>95 K>>40 81 214 PB 214 Pb 212 BE-V TL-208 AC 228 SR 89 SR 90 0 F 010 0~010 NOT ESTAB 0'20 0'20 NOT ESTAb 0.050 NOT ESTAB NOT ESTAB 0.005 44 0.001 44 BE 7 NOT ESTAB GAHNA t CEL I)32 RU 103 NOT ESTAB ALL INDICATOR LOCATIONS HEAN tF)b&ANGE b Oe03(466/468)0 F 01 0'2 0'lt 1/90)0,011 Oe01(10/90)0'!0~OR Oo06(BR/90)0.02-0,11 0~01(6/RT)0~Ol 0~01 Oo02(3/RT)0 F 01 0~DR 0~01(6/RT)OoOl Oe02 0'4(18/27)0~08-0~18 Oo04 (Rl/27)0'2 0'7 Oe04(14/27)0 F 02>>0')7 0 F 02(13/R7)OeOg 0'3 OoOV(13/27)0 F 05-0~11 0~Ol(5/RV)0~Ol-0~Ol 0'2(L/RT)0'2 0~OR)6 V4LUES<LLO ANALYSIS PERFORNED 16 VALUES<LLO ANALYSIS PERFORHED LH5 BF DAVIS F R~5 HILES MSM 0 F 04(Oe01>>52/52)0'2 LH2 BF NORTH 0~9 HILE NNE LNZ SF NORTH 0~9 HILE NNE LH4 BF TRAILER P LoV HILES NNM 0~01(Oo01 D'OR(0,0'1>>Oe08(Oe05>>1/9)0~01 3/9)Oo02 9/, 11)Oel0 ATHENS'L 10e9 HILES NE LH5 BF DAVIS F 2 5 HILES MSK DECATUR'L 8~2 HILES SSE LN1 BF NORTHKEST loO HILE N LH3 BF NORTHEAST 1~0 NILE NE ATHENS'L 10e9 HILES NE COURTLANOi AL 10~5 HlLES KSM LH5 BF DAVIS F 2e5 HILES KS)t COURTLANOi AL 10e5 HILES KSM LNR BF NORTH 0~9 HILE NNE 0~Ol(0'l>>Oe02(OeOR>>0'2(0'2>>0~16(0~14 0'o 05(0 F 04>>0'5(0'3>>0~03(0'3>>Doll(Dell>>O.OL(0~Ol>>Oe02(Oo02>>1/3)Oe01 1/3)Oe02 1/2)Oe02 2/2)Oy 18 2/3)0'6 R/3)Oc07 R/4)0'3 1/3)Oo ll 1/0 F 01 1/4)Oe02 LAC4ZIO(t MIIU UIGhlESI 4(t(tllAL-HE4M

--NAHE NEAN (F)b DISI4((CE 4((0 ()IEE(iIIGU R4((GE b CONTROL LOCATIONS HEAN (F)b B45GE" 0~Olt 2/52)0~01>>0~01 0.03(104/LO4)0 F 01>>0'9 Rl VALUES<LLD 0~01(2/21)Oe01>>0,02, 0~06(20/21)0'2>>0~10 5 VALUES<LLD 0 F 01(1/5)0 F 01 Oe01 Oo01(1/5)Oe 01>>0~01 Dell(3/5)0~OS>>0~1R Oe06(4/5)0 F 03>>OeOS 0 F 05]3/5)0 F 05 0'6.OeOR(2/5)0 F 02>>OeOR Oo05(3/5)0 F 05>>0'6 5 VALUES<LLD 5 VALUES<LLD 8 VALUES<LLD 8 VALUES<LLO NUNBER OF NONROUTINE REPOR~ED HEASUREHEBIS a., Nominal Lover Limit of Detection (LLD)as described in Table 3.b,"Mean and ran8e based upon detectable measurements only.Fraction of detectable measurements of specified locations is indicated in parenthesis (P).

NAME OF FACILITY BROHUS KERRY LOCATION OF FAC IL ITYLmlHKSZ09E TABLE 7 RADIOACT l VITY IN RAINHATKR PCl/L 0'37 SQ/L DOCKET NO~5Oe25Ra200c U5 ALABABAREPORTING PER100 1%SO TYPE AND TOTAL NUMBER OF ANALYSISREREORHEO GAHMA (NAI)134 1~131 BE 7 LOHER LIMIT OF DETECT ION a lLLDX le 000 NOT ESTAB 38e70(38e70 4le2l(2.60-1/ill)38'0 71/lll)101~40 ALL INDICATOR LOCATIONS MEAN (F)b RANDR3 ATMENSJ AL 10~9 MILKS NE ROGERSVILLEi AL 13~8 HILES NH 38'0(34e70~52'0(16e80a 1/13)38e70 9/ll)101e 40 LQCAZIOU HIIU UIG)(ESI A((HllAL ((EAU NAME HEAN (F)b DISIAHCK AND QXBECZIOH RA((GE'ONTROL NUHBER OF LOCATIONS NONROUTINE MEAN (F)b REPORTED RAUGKn HKASURKHEUIS 15e40(1/23)15'0.15'0 37~51(10/23)13.80-65.90 81 214 PS~214 PB 212 BE 7 NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB 330 F 000 TRITIUM 142 GAMMA (GELI)8 K%40 NOT ESTAB 7'5(76e95-21 e6(21e24 Te73(7'3%17e91()6~30 347~50(347'0<<426 F 54(332~12 1/4)76e95 2/0)22 F 00 1/0)7'3 2/6)19~51 1/6)347'0 4/117)643.26 DECATUR'L 8~2 Hl(ES SSK COURTLANDi AL 10~5 MILES HSH COURTLANDi AL 10~5 MILKS HS'H LHl SF NORTHHEST le0 HILE N ROGERSVILLEr AL 13.8 MILKS NH ATHENS'L 10~9 HILES NK 76'5(76~95'2e00(22e00~7e'73 (Te73+19e51(19~51m 347e50j 347'0e 550'8(550'8i 1/1)76~95 1/22000 1/1)7e73 1/2)19e51 1/2)347'0 1/13)550'8 2 VALUES<L(.0 15~41(2/L 2)lle77~19e05-Be67(1/2)8'7 8'7 2 VALUES<LLD 2 VALUES<LLO 25 VALUES<LLD a.Nominal Lower Limit of Detection (LLD)as described in Table 3.b.Mean and range based upon detectable measurements only.Fraction of detectable measurements of specified locations is indicated in parenthesis (F).

TABLE B RADIOACTIVITY IN HEAVY PARTICLE FALLOU'T HCl/KH(2)37000000~00 BQ/KHIR)NAME OF FACILITY BRQNUS EEBLX-LOCATION OF FACILITY LIUESIOUEAL46484 DOCKET NO'Qmtj8i?AQa.296 REPORTING PERIOb IRBQ TYPE AND TOTAL NUMBER OF ANALYSIS-EBBEOBUEO GROSS BETA 141 LOMER LIHIT OF DETECT ION a LLLOI 0.050 ALL INDICATOR L5CATIONS MBAN (F)b b w w ARRANGE ww w 0'6(115/115)0'6-F 07 LOCAZIOU WIIU UIGUESI AUUMAL UEAU~NAHE MEAN ([)OISIAhtCE ANO QZREGZIOU B4HGE LH%bF TRAILER P 0~39(13/13)1~7 HILES NNM 0~09~0~94 CONTROL LOCATIONS MEAN (~)BADGE 0'2(Rb/20)0'6 Oeb5 NUMBER OF NONROUT INE REPORTED HEASUBEHEBXS a.Nominal Lower Limit of Detection (LLD)as described in Table 3.b.Mean and range based upon detectable measurements only.Fraction of detectable measurements of specified locations is indicated in parenthesis (F).

TABLE 9 RADIOACTIVITY IN CHARCOAL F1LTERS PCI/H(3)Oo037 80/H(3)NAHE OF FACILITY;RRQKUS EERRX LOCATION OF FAC IL ITY LIHESXOHRALA84))4 POCKET NO~8Qe289a28Qa V5 REPORTIt G PERIOO 188O TYPE ANO TOTAL NUHBER OF ANALYSIS eEREOBUEO 100INE IN AIR 572 LOKER L)HIT OF OETBCT ION a.ILLOl 0+020 AiL INOICATOR LOCATIONS HkAH (F)b b RANGE 0'3(i8/468)Oe02-0 F 08 LOCAIIOU MIIU UIGUESI A((UUAL ()E48--NAHE HEAN (F)b OISIAI(CE 4((O OZRECILOU 848GE b ROGERSVILLEi AL 0'3(9/51)13oB HlLES NM 0~02~Oo06 CONTROL LOCATIONS HEAN (F)b RA((GE b 0.03(10/10~)Oe02~0'5 NUHBER OF NONROUTINE REPORTED BEASUREUEUIS a.Nominal Lower Limit of Detection (LLD)as described in Table 3., b.Mean and range based upon detectable measurements only.Fraction of detectable measurements of specified locations is indicated in parenthesis (F)~

Terrestrial Monitoxin Mi1k Milk 10-mile radius control farms.gamma-emitting in table 10.is collected from at least four of five farms within a of the plant (see figure 3), and from at least one of four Raw milk is analyzed weekly for I, and monthly for isotopes and for radiostrontium.

The result:s are shown Cow censuses were conducted in May and September 1980.It was determined that there are no dairy farms nearer the plant than the nearest farm being sampled.Ve etation Vegetation is sampled quarterly at the farms from which milk is collected and analyzed for gamma-emitting radionuclides.

Approximately 1-2 kilograms of grass is broken or cut at ground level and returned for analysis.Efforts axe made to sample vegetation that is representative of the pasturage where cattle graze.Table 11 gives the results obtained from the laboratory analyses of these samples.Soil Soil samples are collected annually near each monitoring station to provide an indication of.a long-term buildup of radioactivity in the environment.

An auger or"cookie cutter" type sampler is used to obtain samples of the top two inches (5 cm)of soil.These samples axe analyzed for gamma-emitting radionuclides and Sr and Sr.The results are given in t:able 12.Ground Water An automatic sequential-type sampling device has been installed on a well down-gradient from Browns Ferry Nuclear Plant.A composite sam-ple from this well is analyzed for gamma-emitting radionuclides monthly and composit:ed quarterly for determination of tritium.A grab sample is also taken from a control well up-gradient from the plant.The results of the analysis of well water are shown in table 13.Drinkin Wat:er Potable water supplies taken from the Tennessee River in the vicinity of Browns Ferry Nuclear Plant are sampled and analyzed for gross 22 beta and gamma-emitting"radionuclides, and composited quarterly for tritium 89 Sr, and Sr analyses.The first potable water supply downstream from the 90 plant is equipped with an automatic sampler with composite samples collected and analyzed weekly.Two additional supplies downstream and one public water supply upstream are collected by monthly grab sampling.Table 14 indicates the results from the analysis of drinking water samples.The maximum beta concentration is.0.40 percent MPC.Environmental Gamma Radiation Levels Bulb-type Victoreen Manganese-activated Calcium Floride (CaFg.Mn)thermoluminescent dosimeters (TLD's)are placed at nine stations around the plant near the site boundary and at the perimeter and remote air monitors to determine the gamma exposure rates at these locations.

The dosimeters, in energy compensating shields to correct energy dependence, are placed at approximately one meter above the ground, with three TLD's at each station.They are annealed and read with a Victoreen model 2810 TLD reader.The values are corrected for gamma response, self-irradiation, and fading, with individual gamma response calibrations and self-irradiation factors determined for each TLD.The TLD's are exchanged every 3 months.The quarterly gamma radiation levels determined from these TLD's are given in table 15, which indicates that average levels at onsite stations are approximately 2 mR/quarter higher than levels at.offsite stations.This is consistent with'evels 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.This may be attributable to natural variations in environmental radiation levels, earth moving activities onsite, the mass of concrete employed in the.construction of the plants, or other undetermined influences.

Poult and Pood Cro s Pood crops and poultry raised in the vicinity of BPN and at control.locations axe sampled as they become available during the growing season, and analyzed for gamma-emitting radionuclides.

During this sampling period samples of cabbage, corn, green beans, peaches, potatoes, tomatoes, soybeans, and poultry were collected and analyzed for specific gamma-emitting radionuclides.

No sample of soybeans was taken from a control location.'he results are given in tables 16, 17, and 18.

TABLE 10 RADIOACTIVITY IN NILK PCI/l,-Oe037 BO/L NAHE.OF FACILITYBBQM((S EERILY DOCKET NO.Sa'RSBa24O.WS LOCATION Ol FAC ILI TY'IHESIO)(E ALABAI(AREPORTING PERIOD 1BBO TYPE AND TOTAL NUHBER OP ANALYSIS BEBEOB()EO GANHA (NAI)109 CS 137'>>40 LOMER LIHIT OF DETECTION CLLOI 10~000 150 000 BI-Rli PB 214 PE 212 SR 69 SR 90 NOT ESTAB NOT ESTAB NOT ESTAB 10 F 000 118 RE 000 lib IODIHE IN HILK 0~500 460 GANHA (GELI)B K<<40 NOT ESTAB ALL INOICATOA, LOCATIONS MEAN.,(F)b b RANGE>>>>>>>>>>II~38 I 4/59)10'0 12'O 1241e93(59/59)109Re70 1404,40 0'O(4/259)Oe55 le lb 1543e00(4/4)l3OR.Oo-175R.00 Bb bit 5/4)24 62 34~45 24'2(3/4)14'4 34'7 Ib~3b(2/4)BE B)R3~95$5 VALVES<LLO ANALYSIS~ERFORHEO 4e ll(bR/45)R'e04 9'b SNITH FAAH 4 75 NILES N SHITH FARM 4e75 HILES N BROOKS FARN"'e0 MILES NN)t lle95(1 1~10>>1302'Tt 1129 e00>>0'9t 0'9>>i 2/1R)lR~80 12/1R).1404'0 3/50)lelb SNITH FARH 4e75 HILES N THRASHER FARM Te0 NILES ENE SNITH FARN 4~T5 MILES N BITTING FARH 4~5 HILES ENE 1442e00(1579 F 00>>34.45(36.i5>>34eiT t 36e47>>23e95t 23e95 Rl.R)1705 F 00 1/3de45 1/R)96 F 47 1/2)23e95 BAOOKS FARN Te0 HILES NNM 5ei3(12/12)3e34>>9'B LQCAIIOI()(IIU BIG'HESZ At(t(L)AL t)E48--NANE'EAN (P)b OISIAI(CE At(O t)IBECIIOU BAI(GEb CONTROL LOCATION/MEAN (F)BAI(GEb 10'0(1/50)10 F 60>>10eb0 1229e93(50/50)1087~50 1371~00.Oe54(2/201)De50>>Oe41 i 147be50(2/2)1450e00<<1503e00 20e04(2/2)17eb2>>22eR5 15~Bl(Rl 2)15'4>>lbe57 2 VALUES<LLD 53 VALUES CLLD 5'1(43/53)2'4>>9eb9 MUNBER OP NONROUT I NE REPORTED BEASUBEBEHIS-a.Nominal Lover Limit of Detection-(ILD) ss described in Table 3.b.Mean and range based upon detectable measurements only.Fraction of detectable measurements of specified locations is indicated in parenthesis (F).

TABLE ll RADIOACTIVITY IN VEGETATION NAME OF FACILITY BRQldUS KERRY LOCATION OF FACILITY LIUESIOUE PCI/G>>0'37 BQ/G (ORY HEIGHT)DOCKET NO~SQmRSRg.26Qa 29 REPORTING PERIOD LRBQ TYPE AND TOTAL NUMBER OF ANALYSIS BFREORUEQ GROSS BETA 36 GAMMA (GELI)36 CE 144 BA 140 LA 140 RU 103 CS 13'7 ZR 95 NB 95 K>>40 81<<214 PB 214 PB 212 BE 7 TL>>208 AC-228 LOHER L)HIT OF DETECTION a CLLQI 0.200 0~220 0~340 0 F 080 0'00 0'60 0.110 0~050 NOT ESTAB 0.100 NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB Oe40(2/Ro).Oe36 Oe44 20 VALUES (LLO Oe 10(Oe la-0,38(Oe21 Ool)t 0 F 07 Oe44(Oe22<<0 F 54(0~27 12'4(Le37 0~28(0~11 Oe23(0 F 08 Ool5t Ooob 7e69(0~81 Oe07(Oe03 0'4(Oe 14<<1/Ro)0~10 5/Ro)0'5 6/2D)0~17 5/20)Oe96 5/20)1ooo 20/20)27ebo 17/20)0 F 53 LB/20)0~41 15/20)o,33 20/20)R9e 11 6/20)Oe12 10/20)0~57 AiL INDICATOR LOCATIONS MEAN (F)b b BOUGE>>~>>23'6(20/20)7e54-50'2 LOONEY FARM 5~75 HILES ENE 0'4(0 F 44>>1/4)0'4 THRASHER FARH 7'HILES ENE LOONEY FARH 5,75 HILKS ENE LOONEY FARM 5'5 HILKS ENE LOONEY FARH 5'5 HILES ENE LOONEY FARH 5'5 HILKS ENE THRASHER FARH 7'HILES ENE LOONEY FARH 5o75 HILKS ENE LOONEY FARM 5o75 HILKS ENE LOONEY FARH 5~75 MILES ENE BITTlNG FARH 4~5 HILES ENE LOONEY FARH 5.75 MILKS ENE LOONEY FARH 5~75 MILES ENE Oolo(0~10>>Oe65t'Oe65>>0~lb(0,16 Oe96(Oo96>>l coo(looo>>17e77(be51>>0~34(Oe ll>>Oe26(Ool2>>Oo23(Oe13>>10'lt Oe 81>>-OeoBt Oe03 Oe54(oe50>>1/4)0~10 1/4)oeb5 1/4)Oolb 1/4)0~96 1/4)Leoo 4/4)27ebo 4/4)Oe53 3/4)Oo34 2/4)0 F 33 4/4)29'l 2/Oe12 3/4)Oo57 LOCOIIOU MIIU>>UIGUESIOUUUOL UEOU NAHE MEAN (F)b QISIOUCE 4UQ QIRECIIOU ROUGEb THRASHER FARM 31~14(4/4)7~0 HILES ENK 16 36 40~68 0~38'(Oo25, Oo59(oe59>>0'2(0.42.o.35'(0~24.0~12(Oe08>>Oe48(Oe27>>0'9(Oo31>>9e29(3,12 Oe29(Oe 10 Oe24(Oo12>>oo 13(0 F 07>>9e43(2e13>>Oeob(Oe04>>0~25(oe12>>2/16)0~50 1/16)Oe59 1/16)Oe42 4/16)Oe50 6/Lb)0,16 4/16)Oeb8 4/16)0~84 15/16)22'9 12/16)Oo49 13/lb)0'7 12/16)0~R4 16/16)26'7 8/16)Oolo 7/16)0~34.CONTROL LOCATIONS HEAN (F)b ROUGKb------

18~57t 16/16)5e47>>44'2 NUHBER OF NONROUTINE REPORTED UEASUREUEUIS a.Nominal Lover Limit of Detection (LLD)as described in Table 3.b.Mean and range based upon detectable measurements only.Fraction of detectable measurements of specified locations is indicated in parenthesis (P).

TABLE 12 RADIOACTIVITY IN SOIL PCI/G~0~037 SQ/G lORY HEIGHT)N4ME OF F4CILITY BRQL(US EERBY-DOCKET ND SOm2%Ra26Qa286 LOCATION OF FAClLITYLIBESID9E 4L4B454REPORTING PERIOD 1RSQ TYPE AND TOTAL NUHBER OF ANALYSIS EEREQeZEO GAHMA (GEL I)ll CS-137 K~CO Sl 214 SI 212 PB 21C PS~212 RA-226 RA 213 TL 208 AC~228 Sg 89 SR 90 LONER LIMIT OF DETCCT I()N a CLLQl0'20 0..250 0'50 0~100~0.050 NQT ESTAB 0.050 NQT ESTAB 0'20 0.060 1 o 500 Oo300 ALL, INDICATOR LOCATIONS MEAN (F)b R4NQEP~0~41(9/9)0.18-0.86 5o82(9/9)3e49 8~QC le04(9/9)Qe65 1~39 Qe77(9/9)Qe50 0'7 1o10(9/9)0,73 1~43 le24(9/9)Q~71 le56 1.04(9/Qo65 1~39 0'9(6/9)0.28-0,48 Oe42(9/.9)0'6-0'2 1.21(9/Qo77.le51 9 VALuES<LLO ANALY51$PERFORMED.9 VALUES<LL,D ANAL.YSIS PERFQRHEO ATHENSa AL 10~9 HILES NE LH1 SF NQRTHMEST 1~0 HILE N LH2 SF NORTH 0~9 MILE NNE LHC SF TRAILER P 1~7 HILES NNM LH2 SF NORTH 0,9 MILE NNE PECATURi AL 4~2 MILES SSE LH2 BF NORTH 0~9 HILE NNE LH2 SF NORTH 0~9 MILE NNE PECATURe AL.()~2 MILES SSE LHl SF NQRTMMEST 1~0 HILE N Qe86(0.86-8'4(8~Ohe 1 e39(1~39~Qe97(0'7~le43(le43-le56(1~56~lo39(1~39~0,48(0.48-Qe52(Qe52 le51(1 e 51~.1/1)Oe86 1/1)Be04 1/1)le39 1/1)Qe97 1/1)leh3 1/1)le%6 1/1)1~39 1/1)Qe48 1/1)Qy52 1/1)le51 LOCAIIO(()t(IXU UIGL(EST 48(LUAL L(EAU<-NAME MEAN (F)QISIAUCE AUQ OIRECZIQ((RA((GE CONTROL LOCATIONS HEAN (F)b BA((GEb 0'0(Qo45~4e51(4e19 0~91(Oe82~Oe78(0'7~0'9(0 F 89~le02(1 e00a Oe91(Qo82 2 VALUE 2/2)De75 2/2)4e83 2/2)le01 2/2)Oe78 2/2)lo09 2/2)le04 2/2)1~01 S<LLD Oe39(2/2)oo37>>Oehl'loll(2/2)F 04>>lel8 2 VALUES<LLD 2 VALUES<LLD NUHBER 0F NQNRQUTINE REPORTED L(EASUREL(EUZS a.Nominal Loeeer Limit of Detection LLD)as described in Table 3.b.Mean and range based upon detectable measurements only.Fraction of detectable measurements of specified locations is indicated in parenthesis (F).

TABLE RADIOACTIVITY IN MELL MATER PC I/L 0~037 b0/L DOCKET NO~5()n25'Ra26Qa2M REPORTING PERIOD 1950 LOCATION OP FACILITY LIMESTONE-<<

---4L46454 TYPE ANO LOMER LIMIT.ALL TOTAL~UMBER OF INDiCATOR LOCATIONS LQCAZXOu X1ZU UZO)(ESZ 4((((uaL ((E4N OF ANALYSIS DETECTIONa HEAN (F)b NAME MEAN (/)b GAMMA (NAI)PEBEORMEO LLLQl RAMOEP OISXAHCE 4MQ QIBECZlQU R4((GE 22 ll VALuES<LLD ANALYSIS PERFORMED GAMMA (GELI)K~40 NOT ESTAB 67e32(bb~53e 13,63 (13'3+12g51(12651 2/.2)bbsll 1/2)13sb5 1/2)12e51 BFN MELL'b 0'2 HlLES.M BFN MELL Nb 0~02 HlLES M BFN'MELL Nb 0~02 HlLES M 67o32(2/2)bb~53 68~11 13163 (1/2)l3.63-13, 63 12.5I(1/2)12o5i 12e51 2 VALUEs<LLD NOT ESTAB NOT ESTAB NOT ESTAB 330 F 000 8 81 214 P B-214 PB~212 TRIT IUM 4 VALuES<LLD ANAiYSIS PERFQRHED CONTROL LOCATloNS MEAN (F)EAHGE~-----11 VALUES<LLD 69'0(1/2)69'0~b9e70'6'4(1/2)lb.04-16.04 11~53 (1/2)11.53-11.53 13~35(1/2)13'5~13e35 4 VAI.UES<LLD NUHBER OF NONROUTINE REPORTED MEASUREMEBIS-a.Nominal Lover Limit of Detection (LLD)as described in Table 3.b.Mean and range based upon detectable measurements only.Fraction of detectable measurements of specified locations is indicated in parenthesis (F).

NAHE OF FACILITY.BROWSES EEBRX LOCATION OF FAC IL ITY LIHESIO)(E TABLE 14 RADIOACTIVITY IN PUBLIC MATER SUPPLY PCI/L-0.037 80/L FT NQ.SQ 2 4L48454 REPORTING PERIOD 1QBQ TYPE AND'TOTAL NUHBER DF ANALYS IS EEBEOBHED GROSS BETA 91 GAHHA (NAI)84 LOMER LIHIT OF DETECTION a CLLQI 2 F 400 AiL IND ICA'TOR LOCATIONS HEAN (F)b 84NGl----b 3'9(46/78)Re41-llo99 72 VaLuES<LLD ANALYSIS PERFORHED LQCAZIO(t MIZU UIGUESZ 4((((VAL ME48 NAHE HEAN (F)b DISIAI(CE 4UD QIBECIIOU B4((GE b MHEELER DAHi AL 5'3(4/13)TRH 274'Ro49>>Ill 99 CONTROL LOCATIONS HEAN (F)b--84htGE b 3'5(3/13)Re49>>3IBO 12 VALUES<<LLO NUHBER 0F NONROUTINE REPORTED HEASUBEHEUTS--

81-214 PB 214 P 8-212 SR$9 SR 90 TRITIUH NOT ESTAB NOT ESTAB NOT ESTAB 10 F 000 2 F 000 330 F 000 16 lb lb GAHHA (GELI)7 K>>40 NOT ESTAB 76~44(2/4)j4.65-78.22 19 F 88(3/6)9 I 09 26~20 2lsb>(2/6)lhe84 24e35 15.03(2/6)10sbl.19e43$2 VALUES<LLD ANALYSIS PERFORHED g2 VaLuES<LLD ANALYSIS PERFORHED 343~R9(1/1R)343eR9 343'o29 CHAHPION PAPER TRH 282 F 6 MHEELER DAHi AL TRH R74~9 CHAHPION PAPER TRH 282.6 CHAHPION PAPER TRH RBR F 6 78'2(78 F 22>>26'0(26 20 24I35(R4~35>>19g43(19~43>>1/3)78's 22 1/26>20 1/3)24'5 1/3)19 I 43 SHEFFIELDwAL ROB 343e29(1/4)TRH 254'343'9>>343e29 102 80(1/1)102a80>>102e80 9~15(1/1)9o 15 9~15 13'3(1/1)13e33>>13'3 1 VALUES<LLD 4 VALUES<LLO 4 V~~UES<LLO 4 VALUES<<LLD a.Nominal Lover Limit of Detection (LLD)as described in Table 3.b.Hean and range based upon detectable measurements only.Fraction of detectable measurements of specified locations is indicated in parenthesis (F).

28 Table 15 ENVIRONMENTAL GAMMA RADIATION LEVELS uarter Location Environmental Gamma Radiation Levels l~i January-April 1980 On-Site (8)b Maximum Minimum Average c 10.6 7.3 9.4+2.3 23.1 15.9 20.7+5.0 May-July 1980 July-September 1980 Off-Site (7)Maximum Minimum Average On-Site (8)Maximum Minimum Average Off-Site (7)Maximum Minimum Average On-Site (9)Maximum Minimum Average 12.5 27.4 6.9 15.2 8.6+3.7 18.9+8.2 10.0 21.9 7.4 16.3 9.0+2.0 19.8+4.4 ll.1 24.3 6.8 14.9 8.1+2.8 17.8+6.1 10.3 22.6 7.9 17.3 9.5+1.8 20.9+4.0 Off-Site (7)Maximum Minimum Average 11.0 7.3 8.5+2.5 24.2 16.0 18.6+5.5 October-December 1980 On-Site (9)Maximum Minimum Average Off-Site (7)Maximum Minimum Average ll.5 25.1 7.8 17.2 10.0 i 2.3 21.9+5.0 12.0 26.3 7.4 16.3 8.7+3.1 19.1+6.8 Data normalized to one quarter (2190 hours0.0253 days <br />0.608 hours <br />0.00362 weeks <br />8.33295e-4 months <br />)Number of stations (normally three TLD's at each station)All averages reported+2a (95%confidence level)

TABLE 16 RADIOACTXVXTT IH POOD CROPS PCI/KG 0 037 BO/KG (NET WEIGHT)DOCKET NOo SOa25%8260a296 ALA()4))4----REPORTING PERIOD PRO()CONTROL LOCATIONS HEAN (Fg>RA)(GE b NAHE OF FAClLITY,BBQVUS EERIY---LOCATIDN OP FACILITY LlHESIOBE TYPE ANO LOWER LIHIT.ALL TOTAL NUMBER OF INO1CATDR LOCATIONS LQC4ILQU XLIU UIQ))ESI 4((HL)4L ()E48 DF ANALYSIS OETRCTIONa HEAN (F)b NAHE HEAN (F)~EEREOB))EQ CLLQL RA((GEE)QISI4((CE AUQ QLSECI1QU 84)IGE RADIOACTIVITY IN CABBAGE NUHBER OF NONROUT INE REPORTED BEASUBEBEBIS-GROSS BETA 25'000 2 GAHHA (GELI)2 K>>40 NDT ESTAB PB 212 NDT ESTAB 44i3o59(1/1)4413.59-4413.59$NITH FARH 4413ef9(1/1)4.75 HILES N 4413~5'9>>4413~59 4338~21 t, 1/1)4338.21 4338.21 1748~00(1/1)SNITH FARH 1748,00-1748.00 4.75 HILES N'lb~52(L/1)$HITH FARN lbef2 Lbe52 4e75 HILE$N 1748.00(1/L)1646,00(1/1)1748 F 00>>1748'o00 1646 F 00 1646 F 00 16'2(L/1)L VALUES<LLD lbe52>>Lbe52 GROSS BETA 2 GAHHA (GEL I)2 K>>40 NOT ESTAB 2440 F 00(1/1)1'?58'0t L/1)2440 F 00>>2440e00 1758e00>>1758 F 00 2440e00(1/1)SNITH FARN 2440 F 00 2440~Ob 4o75 HlLES N RAOlOACTLVITY IN CORN 25~000 3f%5~84(1/1)SHITH FARN%535 e44(1/1)3247e77(1/1)3535ol4 3f35~84 4'5 HILES N 3535~84>>3535 F 84 3247'7>>3247e77 25 F 000 GROSS BETA 2 GAHHA (GELI)2 K>>40 NOT ESTAB PB 212 NOT ESTAB 4817e18 (1/1)4817.18 4817~LB 2916,00(1/1)2916.00-2914e00 ll e 17(1/11 T.L~17-lie 17 SHITH FARH 4o75 HILES'N SHITH FARH 4o75 HILES~N 29lbe00(1/1)2916~00>>29lbe00 ll~17(1/1)llo17>>lie l7 RADIOACTIVITY Ig GREEt(BEANS SNITH FARH 4817e18(L/1)4o75 HILES N 4817~18>>4817~18 4638eb3(1/1)4638e63>>4638~63 2310.00(1/1)2310~00>>2310~00 10'8(1/1)10'8>>10'8 a.Nominal Lower Limit of Detection (LLD)as described in Table 3.b.Mean and range based upon detectable measurements only.Fraction of detectable measurements of specified locations is indicated in parenthesis (F).

TABLE l6 (Cqntd)RADIOACTIVITY IN FOOD CROPS PCI/KG-O.037 Sa/KG (MET HEIGHT)DOCKET NO~Spm25o)a250a296 REPORTING PERIOD 12()O NAHE OF FACILITY BBP)(BS EEBBY LOCATION OP FAC IL ITY LIHESIOHE--ALAaA(IA-.-------TYPE ANO LONER LIMIT ALL TOTAL NUHSER OF INDICATOR LOCATIONS LOCAIIOU)(II)j UIGQESI 4((UL)AL ()EAU~-OF ANALYSIS DETECTION MEAN (F)b NAME HEAN tF)EEBEOBIIEO LLLQL RANGES--OISIAUCE AUD OIBECIIOh BA((GE CONTROL NUMBER OF LOCATIONS NONROUT INE MEAN tF)b REPORTED BAI(GEb LEASUBEIIEUIS GROSS SRTA 2 GAMMA (GELI)2 K~40 NOT ESTAB 2183 e00(1/1)2183~Oo 2183~00 SHITH FARH 2183~00(ll 1)'1SBS~00(1/1)4~75 MILES N 2183~00+2143~00 1888~00~1888~00 RADIOACTIVITY IN PEACHES 25~000 5690~34(1/1)SMITH FARH 5490~34(1/1)4935~15(1/1)5490~34 5490~34 4~75 MILES N 5490~34'490e34 6935oL5~6935~15.RA010ACTIVITY IN POTATOES GROSS BETA 2 GAHHA (GELI)'K 40 25 F 000 NOT ESTAB 7789'5(1/1)7789e95 7749 F 95 4121 o 00 (1/1)4121~00 4121~00 HARGROVE FARH 3~75 HILES N HARGROVE FARM 3~75 HILES N 7789'5(1/1)7789'5~7749o95 4121e00(L/1)412Lo00~412le00 8228~30('/1)'228~30~822bo30 34S3 F 00(1/1)3483o00~3443 F 00 25 F 000 GROSS SETA 2 GAHHA (GELI)2 K 40 NOT EST~8 2485.0Ot ll 1)2485,00-2445.00 SMITH FARM 2485~00(ll 1)2456e00(I/1)4~75 MILES N 2485e00~244%~00 2456~00~2456~00 RAOIOACTlVITY IN TOHATOES 4876o55(1/1)SHITH FARH 4874~55(ll 1)4844~24(1/1)4876'5~487bo55 4'5 HILES N 4S74~55r 4876o55 4844'4+4844'4 a.Nominal Lower Limit of Detection (LLD)as described in Table 3.b.Hean and range based upon detectable measurements only.Fraction of detectable measurements of specified locations is indicated in parenthesis (F).

TABLE RAOlOACTIVITY IN SOYBEANS PCI/G-0.037 80/G (ORY MElGHT)NAHK OF FACILITY'BQQUS KELLY---QOCKET NOSQa2%Ra264a LOCATION OF FACILITY LmIUESIOUE ALAS4U4 REPORTING PER100 1914 TYPC AND TOTAL NUMBER OF ANALYSIS eEBEOBUEQ GROSS BETA l GAHMA (GELI)1 Kecj,O 8 I-2]b PB-214 LOMER LIHIT OF DETECT ION a CLLQl 0'00 NOT ESTAB NOT ESTAB NOT ESTAB 17e07(I7~07 0'b(0'b 0'6(0'6 1/1)17'07 1/1)0'6 1/1)0'6 AiL INDICATOR LOCATIONS HEAN (F)b b BANGS 40.89(1/1)40'9-60~89 HARGROVE FARH 3'5 HILES N HARGROVE FARH 3o75 HILES N HARGROVE FARH 3~75 HlLES N 17e07(17e07~0'6(0'6~0'6(0'6~1/1)17o07 1/1)0 F 06 1/1)0,06 LOC4IIOU llIIUUIGUESZ 4UULl4L U84U->--'AME HEAN ($)QISIAUCE 4UQ-QIBECIIQU-----EAUGE HARGROVE FARH%O S&9(1/1)3.75 MILES N 60.89-40.89 CONTROL LOCATION)HEAN ([)RAUGE NUHBER OF NONROUTINE REPORTEQ UEASUBEUEUZS-a.Nominal Lower Limit of Detection (LLD)as described in Table 3.b.Mean and range based upon detectable measurements only.Fraction of detectable measurements of specified locations is indicated in parenthesis (P).

tkAME OF FACILITY SROMUS EERRY TABLE 18 RADlOACTIVITY IN POULTRY PCI/KG-0~057 BQ/KG Ii)ET itEIGHT)DOCKET NO~SOmZSQcZlhOa&5

---

REPORTING PERIOD IRSO TYPE AND TOTAL tJUMBER OF ANALYSIS REREORI)ED GROSS BETA 2 GAHMA (GELI)2 CS 157 K>>40 Bl 214 PS-214 TL-208 LOMER LIHIT'F DETECTION a ILLO>25e000 15~000 NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB ALL INDICATOR LOCA/IONS HEAN IF)BAUGEJ-----

45i4.98(1/1)4514.98-4514.98 iBe96(1/1)i8.96-18.96 1950e00(1/1)1980 F 00 1950e00 1 VALUES<LLD VALUES<LLD 20eDII 1/1)20.01-20.01 SMITH FARH 4~75 HILES N SHITH FARH 4~75 MILES N 18e96(1/1)1$e'94>>18~'96 1950e00(1/1)1950 F 00>>1950 F 00 SHITH FARH 4.75 MILES N 20 F 01(20 F 01>>1/1)20e01 LOCAZIOV)IIZU UIGVESZ aNUUAL.I)EAII~

NAHE HEAN IF)OISZAUCE ANO OIRECZIOU B4IIGEb SHITH FARM 4514e98(1/1)4~75 MILES N 4514~98>>45'14~98 CONTROL LOCAT ION)HEAN ([)RANGE 2496'9(1/1)2496'9>>.2496'9 1 VAI.UES<LLD 2152~00 I 1/1)2152 F 00>>2152e00 19'6(1/1)19e76>>19e76 11.81(1/1)lle81>>lle81 1 VALUES<LLD NUMBER OF NONROUTINE REPORTED I)EASUREHEHIS a.Nominal Lover Limit of Detection (LLD)as described in Table 3.b.Hean and range based upon detectable measurements only.Praction of detectable measurements of specified locations is indicated in parenthesis (P).

33 R'eservoir Monitorin Samples are collected from the Tennessee River as detailed in table 19.Samples collected for radiological analysis include plankton from three of these cross sections and bottom fauna and sediment from four cross sections.'The locations of these cross sections are shown on the accompanying map (figure 5)and conform to sediment ranges established and surveyed by the Data Services Branch, TVA.Parer Water samples are collected automatically by sequential type sampling devices at three cross sections and composite samples analyzed monthly for gamma-emItting radionuclides.

Further composites are made quarterly for strontium and tritium analyses.In addition to these required samples, grab samples were also collected monthly from the vicinity of the plant discharge to the Tennessee River, and at a point on the Elk River, and analyzed for gross beta, gamma-emitting radionuclides, and strontium.

Results are displayed in table 20.Fish Radiological monitoring for fish is accomplished by analysis of composite samples of adult fish taken from each of three contiguous reser-voirs-Wilson, Wheeler, and Guntersville.

No permanent sampling stations have been established within each reservoir; this reflects the movement of fish species within reservoirs as determined by TVA data from the Browns Ferry Nuclear Plant preoperational monitoring program.Two species, white crappie and smallmouth buffalo, are collected representing both commercial and game species.Sufficient fish are collected in each reservoir to yield 250 to 300 grams oven-dry weight for analytical purposes.All samples are collected semiannually and analyzed for gamma-emitting radionuclides.

The composite samples contain approximately the same quantity of flesh from each fish.For each composite a subsample of material is drawn.for counting.Results are given in tables 21, 22, and 23.Plankton As indicated in table 19, net plankton (all phytoplankton and 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 eo nd Sr content.During this reporting period, all samples contained in-sufficient volume of material for gross beta, strontium, or gamma analyses.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 19.Results are shown in table 24.Bottom Fauna The flesh and shells of Asiatic clams collected semiannually from the cross sections at four stations (table 19)are analyzed for gamma-emitting radionuclides.

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

A 50-gram (wet weight)sample provides sufficient activity for counting.During this reporting period, one sample of clam flesh contained insufficient volume for analysis.Results are given in tables 25 anl 26.

Table 19 SAMPLING SCHEDULE-RESERVOIR MONITORING Biolo ical sam les collected semiannuall River/river mile Zooplankton, chlorophyll, h to lankton Benthic fauna Sediment Fish Water samples collected monthl Tennessee 277.9 Tennessee 285.2 Tennessee 288.7 Tennessee 291.7 Tennessee 293.5 X X Tennessee 293.7 (discharge area)Tennessee 305.0 Tennessee 307.5 Elk 20.5 X a.Gill net and/or electroshocker will be used for collection.

from Guntersville, Wheeler, and Wilson Reservoirs.

b.Automatic sampler.c.Grab sample.Samples of fish are collected 36 Figure 5-R ESERVOI R MONITORING NETWORK Elk River WHEELER DAM mile 274.90 mi)e 277.98 Rogersville 0 mile 282.6 mile 29l.76 Athens~mile 285.2 B.F.NUCLEAR PLANT S Champion Paper Co.Courtland le 288.78 mile 293.50 mile 295.70 0 Decatur mite 305.0 mile 307.52~-Automatic Sam ter Scale of Miles NAHE OF FAC IL 1TY BRO)t(IS EERRY LOCATION OP FAC IL I TYLIIIESIOIIE TABLE 20.RADlOACTIVITY IN SURFACE MATER TOTAL PC1/L 0'37 80/L DOCKET NO~SQm2%%a26Qa~

4L4B4II4 REPORTING PER100 19BQ Bl 214 PB>>214 PB 212 SR 89 38 SR 90 38 TRlT IUH 20 NOT ESTAB NOT ESTAB NOT ESTAB 10~000 RE 000 330e000 TYPE AND LONER LIHIT TOTAL NUMBER OF OF ANALYSIS DETECTlON a EEREORIIEQ ILLQI GROSS BETA F 400 26 GAHHA (NAI)(50 GAHHA (DELI~)15 K 40 NOT ESTAB ALL INDICATOR LOCATIONS HEAN IF)b w w BANGEw b 3e48(6/13)Re47-6'3 26 VALUES<LLD ANALYSlS PERFORHED 92'0(6/13)53e90-156eRD 23.3o(9/13)Te75-39~ll I8.04(~11.96-24.02 16e5o(5/13)8.04-24,93 21 VALUES<LLD ANALYS1$PERFORHED$1 V4LUES<LLD ANALYS1S PERFORHED 460e44(2/1R)431~76 489e12 TRH 293'8FN 01SCHARGE TRH 293'BFN 01SCHARGE TRH R93~7 BFN 01SCHARG'E TRH 285'106e54{64'4>>24e50{12e74>>19e91(19e91>>18 62(12e09>>4/4)156 F 20 3/6)30'3 1/6)19e91 4/5)R4e93 TRH 285'489elR{1/4)489~12>>489~12 LOCAIIOu MIIU)IIGIIESX NIIUAL.))%48 NAME HEAN (F)b QISIAI{CE AUQ QIREGIIOII

--RAIIGE TRH R93~7 3 88(6/13)BFN 01SCHARGE 2'7>>ee63 CONTROI.LOCAT10NS HEAN (F)b RA(I GE b 4e2R(10/13)2'4>>12'5 24 VALUES<LLD R VALUES<LLD 13'9{1/2)13'9 13'9 2 VALUES<LI.D 2 VALUES<LLD 17 VALUES<LLD 17 VALUES<LLD 599.3R{1/8)599'2 599e32.NUHBER OF NONROUTINE REPORTED IIEASUREIIEIIIS a.Nominal Lover Limit of Detection (LLD)as described in Table 3.b.Mean and range based upon detectable measurements only.Fraction of detectable measurements of specified locations is indicated in parenthesis P.

TABLE 21 RAO(OACTlVlTY lN XH(TE CRAPPlE (FLESH)PCl/G 0~037 SQ/G lORY XElGHT)NAHE OF FAClL1TY ()ROWUS EERRYOOCKET NO~5Om259626Oa29~

LOCAT(ON OF FAC 1LlTY LIUESIOUE-

-ALA()AUAREPORTING PER100 l((nQ TYPE ANO TOTAL NUMBER OF ANALYS1S REREORUEQ GROSS BETA 6 GAHHA (GELl)6 CS 137 K>>40 81 214 PS 214 PS 212 LOWER L1HIT OF OETECT lONa CLLQI 0~100 0 020 NOT ESTAB.0~020 NOT ESTAB NOT ESTAB 0~10(0 F 08 15 ll(13~40 0~05(0 F 05 0~OS(ooob Oo03(0)03 4/4)0~11 4/4)16,84 2/4)0'6 3/4)=o, ll 1/4)og03 ALL 1NDICATOR LOCAT10NS HEAN (F)b aANQEb 33 F 49(4/4)28o97 3be75)(lLSON RESERVO(R TRH 259"275 XHECLER RES TRH 275"349 WHEE(.ER RES TRH 275"349 X1LSON RESERV01R TRH 259-275 XlLSON RESERVOlR TRH 259 275 0~10(oa09>>15'2(13 F 40>>o.'ob(0 F 06>>0 F 08(0(06>>oe03(O.O3-2/2)Oell 2/2)1beb4 1/2)ooob 2/2)OIll 1/2)Oe 03 LQCAIIOU MIIU UIQUESI AUUU4L UEAU NAHE HEAN (F)b QISIAUCE-AUQ QIRECIIQU RAUGEbWHEELER RES 35I32(2/2)TRH 275"349.33 F 89>>3be75 CONTROL LOCAT)ONS MEAN (F)ILAUGE b 4be19(2/2)43e78 48obl 0~Oi ('/2)0~08>>-0~10 17'5(2/2)lbebo 18~10 oeob(1/2)o,ob-o.oe 0 F 05(1/2)Oe05oo05 2 VALUES CLL0 NUHSER OF NONROUTlNE REPORTED UEASUREUEUZS a.Nominal Lower Limit of Detection (LLD)as described in Table 3.b.Mean and range based upon detectable measurements only.Fraction of detectable measurements of specified locations is indicated in parenthesis (F).

TABLE 22 RADlOACTlVITY lN SMALLHOUTH BUFFALO (FLlSH)PCl/G~0~037 8()/G tORY ME'(GHT)NAHE OF FACILITY BRONZES EERRY LOCATION OF FACILITYLSHESZOBE-ALABAMA DOCKET NO', 5Qm25Ra2bQ<395 REPORTING PERIOD lRBO TYPE AND TOTAL NUMBER OF ANALYSIS REREOBBED GROSS BETA b GAMMA (GELI)b CS 137 K%40 8 l-214 PB 214 PB 212 LONER LIMIT OF DETECTION a iLLQ1 0~100 0~020 NOT ESTAB 0~020 NOT ESTAB NOT ESTAB 0~04(0 F 03 11.7o(gobb 0'7(Oo04-0~07(0 F 06 0~01(0~Oi-3/4)0~05 4/4)13'3 3/4)0~09 2/4)0 F 08 1/4)o,ol ALL INDICATOR LOCATIONS HEAN (F)b b BABQE gb.30(4/4)20~4B 31~03 MHEELER RES TRH 275 349 MHEELER RES TRH 275 349 MILSON RESERVOIR TRH 259-275 MILSON RESERVOIR TRH 259-275 MILSON RESERVOIR TRM 259-275 0~05(0~05r 12e82(12~41~0~08(0~07~0 F 08(0 F 08~0~01(os Ole 1/2)OI 05 2/2)13e23 2/2)0~09 1/2)0 F 08 1/2)0~01 LOCATION)tuM UZGUESZ ANNUAL IRAN>NAHE MEAN (F)OISIAMCE AHQ QlREQILOU RAtlGSb MHEELER RES 30~91(2/2)TRH 275-349 30~78~31~03 0~05(0 F 04~15~39(15IOB~0~14(0,14 oslo(0~10 0 F 07(0'4m 2/2)oo05 2/2)15eb9 1/28 0~14 1/2)0010 2/2)oo09 CONTROL LOCATIONS MEAN (F)b ,-RAUGEb 31~17 (2/2)29e93~32'2 NUMBER OF NONROUTINE REPORTED MEASUREHENS a.Nominal Lover Limit of Detection (LLD)as described in Table 3.b.Mean and range based upon detectable measurements only.Fraction of detectable measurements of specified locations is indicated in parenthesis (P).

TAB).E 23 RADIOACTIVITY IN SHALLHOUTH BUFFALO (WHOLE)PCI/O>>0~037 BQ/G (ORY WEIGHT)DOCKET NO~5Om259a26OaMS-------

REPORTING PERIOD lQR()DECONTROL LOCATIONS MEAN{F)B48(lE b 13'5{2/2)11~1lr 15~99 NUHBER OF NONROUT INE REPORTED BEASURE)IENIS WILSON RESERVOIR TRH 259"275 WHEELER RES TAH 275-3h9 WHEELER RES TRH 275-3h9 WHEELER RES TRH 275-3h9 Qe{}3(3/h)0 02 Qe03 7'3(h/h)be2i" Pe67 0~11{3/h)0~08 0~16 Dell(3/h)Qe05-.0'1 h VALUES<LI.O 0'20 NOT ESTAB 0'3(1/2)0 F 03>>0'3 Bo38{2/2)7e95>>8 F 81 0 F 07{1/2)0~07, 0~07 0'3{1/2)Oe03 Oo03 0'3(1/2)Oo03>>0'3 0 VALUES<LLD 1/2)Qeoa., 2/2)Pe67 1/2)Qe lb 1/2)0~21 0.03(Q~Q3>>Bo81(7e95>>0~16(Qolb>>Oo21(Qe21>>K>>40 BI 21h PB 21h PB 212 0~020 NDT ESTAB NOT ESTAB 0.500 2 0'00 2 SR 89 2 VALUES<LLD ANALYSIS PEAFORHED 0'2(2/2)0~11-0~13'WHECLER RES TRH 275-3h9 SR 90 0'2(2/2)0, 1 lr Oe 13 NAHE OF FACILITY,BRgeuS EERRY LOCATION OP FACILITY LLHKSIOUE ALABAIIA TYPE AND LOWER LIHIT ALL TOTAL NUHBER.OF INDICATOR LOCATIONS LOCAILOu){CIU UIGHEKI N({UAL (IEO((OF ANALYSIS OETljCTION a HEAN{F)NAHE MEAN (F)~REREORUEO CLLD1ROUGE-DISIauCE A({D DCBEGXlOUBAUGE b GROSS BETA 0~100 15~81()/h)WHEELER RES 19o ll(2/2)6 lQ 86-20'2 TRH 275-3h9 17'0>>20'2 GAMMA{GELI)6 CS 137 a.Nominal Lower Limit of Detection (LLD)as described in Table 3.b.Mean and range based upon detectable measurements only.Praction of detectable measurements of specified locations is indicated in parenthesis (P).

TABLE 24 RAOIOACTIVITY IN SEDIMENT PCI/G 0~Q37 80/G (DRY WEIGHT)NAHE OF FACILITY RRQWUS KERRY DOCKET NO~50s25Ra20Oa~

OCATIDN OF FACILITYLtt(ES10UE ALARAU4REPORTING PERIOD LRRO TYPE AND TOTAL NUHBER QF ANALYSIS REREOBUEO GAHHA (GELI)8 C0-60 CS-137 X>>40 Bl 214 Bl 212 PB 2L4 PS 212 RA 226 RA 223 BK 7 TL 208 AC 228 SR&9 SR 90 0'10 0'20 NDT ESTAB 0~020 0 100 NDT KSTAB NOT ESTAB NOT ESTAB NDT ESTAB NOT ESTAb 0'20 0.060 LE 500 0'00 5/4)0~14 6/6)2'0 0/0)R5e71 0/0)2'7 6/0)1~60 0/6)2'3 0/0)R,e&9 4/0)2'7 3/0)De&0 l/0)OeR2 6/0)0'0 6/6)2~78 ES<LLO ERFORHED 2/6)Qe32 Q.LQ t Oo00>>1~32(0'4 15~79 (SobQ 1.33(Do23" Lo05(~Oe51 1.58(0'9 1~82t 0~79-1.50t Oobb Oebbt 0'0 Qe22(0'2 0.5&t 0 F 27 1~77(0 AD&2 6 VAI.U ANALYSIS P 0'2(0'2 LOWER LIHIT ALL OF INDICATOR LOCATIONS DETECTION a HEAN (F)b XLL'OX RANG@.TRM 293'BFN DISCHARGE TRM 277~98 TRH 2&&~78 TRM 277'8 TRM 28'&TRM RBB~78 TRH 2SB~78 TRH 288'8 TRH 284 78 TRH R93o7 SFN DISCHARGE TRH RBSo78 TRH 288 F 78 Q~10(0 F 00>>2'&t 2'0>>ROAN 09(Lhehb>>Leb3(le45>>lo24(Oe87>>le9lt le28>>2o24(Le89>>le&0(1~23>>0'5(0'0>>Oe2R(Oe22>>Oo71(0'R>>2~21(1~64>>2/R)0~14 2/2)2'0 2/R)R5e71 2/2)1~&5 2/2)le00 2I 2)2'3 2/2)2o59 2/2)2~3'7 2/2)0 AD&0 1/2)Qe 22 2/2)Qe90 2/2)2e7&TRH 293'SFN DISCHARGE Oe32t 1/2)0'R>>Qe3R LOC4ZIOU)ttIU UIGUESX 4UUUAL UE4U.NAHE MEAN tg)b OISIAUCE AUO t)LRECZIOU R4UGE CONTRDL LOCATIONS MEAN t i')b RAUGEb Qe07(0'07>>0'5(Doll>>la 67t 10.03>>Le25t lelQ Qe97t 0 F 84>>le32(leL&>>lohb(le 29 1~25t lel0>>0.56(0'0 2 VAI.UE 1/2)0'7 2/2)Qe99 2/2)Lbe71 2/2)1ehl 2/2)lel0 2/2)lo47 2/2)leb3 2/2)le41 1/2)Oe5b S<L(,D 0'0(2/2)0'4>>0'0 1.56(2/2)1~28 1~S4 2 VALUES<LLD 2 VALUES<LLD NUHBER Of NDNROUTINE REPORTED UEASUREUEUIS-a.Nominal Lower Limit of Detection (LLD)as described in Table 3.b.Mean and range based upon detectable measurements onl.Fr parenthesis (F).n y.raction of detectable measurements of specified locations is indicated in TABLE RADIOACTIVITY IN CLAH FLESH PCI/G-0~037 BQ/G (DRY HEIGHT)TRH 288,78 21>>40(21'0.2'1t 1>>34~2>>33(1>>30>>2'4(1>>07$~16(1,16-I 3/5)32'6 4/5)3'4 3/5)4>>93 5/5)F 78 1/5)0'8 1'$(10~03 2'6(1>>24 3~41(1>>54-1>>52(0>>47 0'8(0'8 1/')21 F 40 2/2)3>>67 2/2)3~%7 2/2)4~22 1/2)1>>16 32'6(32>>36>>2>>39t 1'4m 4'3(h>>93~1>>75(F 75~0>>58(0'8~1/2)32'6 2/2)3'4 1/2)4>>93 1/1)1>>75 1/2)0>>58 TRH 293'BFN 01SCHARGE TRH 288'8 NOT ESTAB'OT ESTAB NOT ESTAB NOT ESTAB BI 214 P 8-214 PB 212 TL 208 TRH 277'8 TRH 293>>7 SFN'1SCHARGE NAME OF FACILITY.BRObtNS EERRY DOCKET NO 50s25Ba260 395 LOCATI OF A ILITY LIHESXOUE'LABAMAREPORTING PERIOD 1RBO TYPE AND LOMER LIHIT ALL CONTROL TOTAL NUMBER OF INDICATOR LOCATIONS LOCAXION BXZU OXGVESZ N((()AL BEAN-LOCATIONS OF ANALYSIS DET(FACT ION a HSAN (F)b NAHE HEAN (F)+HEAN (s)b REREORBEO CLLOl---------RANGE-----

OISIAUCE-ANO OlBECI1ON RANGE-BAI(GE GAHHA (GELI)7 K~40 NOT ESTAB NUHSER OF NONROUTINE REPORTED BEASUBEHENIS-a.Hominal Lover Limit of Detection (LLD)as described in Table 3.Mean and range based upon detectable measurements only.Fraction of detectable measurements of specified locations is indicated in parenthesis (F).

TABLE 26 RA010ACTIVITY IN CLAN SHELL PCI/G-0.037 80/G (ORY MElGHT)DOCKET HDe 5Qs>>25Ra2lhQcÃk-REPORTIHG PERIOD IMQ CONTROL NUHSER OF LOCAT1DNS HONROUT INE)b HEAN (F,)b REPORTED RAI{GE==.I(EASUREIIEBZS

.NAHE OF FAC1LITY SRQ)(NS EERRY LOCAT1DN DF FACILIT'Y Lit)ESIO){E

---

'-At.45454 TYPE AND LOMER LIHIT.ALL TOTAL NUH8ER OF INDICATOR LOCATIONS LOCAXIOB MIIII BIG){ESI Attt(t)AL gl48 OF ANALYSIS OETfCTIONa HEAN (F)b NAHE MEAN (F (IEREORt{EO ILLQ)RANGE b OISZA({CE ANQ QIRECZlat{

R4(IGEh GAHHA (GELI)8 ll 2)0905 2/2)4e96 2/2)Oo79 1/2)Oe31 2/?)Oebb 2/2)Oe47 2/2)0'9 2I 2)Oe 15 2/2)Oe58 CS 137 K>>40 81 214 81>>212 PS 214 PS 212 RA>>224 TL 208 AC-228 Oo04(2/6)Oo02 0'5 le78(6/4)0 F 43>>, 4~96 0.39(6/4)Oe lb Oe79 Oe28(2/IS)0~25 0~31 0'9{6/4)0,14 0'8 Oe29{4/4)0, ll-0.47 Oe39{6/4)Oe 18 Oe79 Oe lo{4/6)0~05 0~15 0~$6{3/6)Oe32.0 F 58 6 VALUES<LLO ANALYS1S PFRFORHEO 3~1 1 (4/6)1~97-F 08 0'20 NOT ESTAS 0+050 0 F 100 0'50 NDT ESTAS 0 F 050 0'20 0,060 F 000 1 000 TRH 293'SFN DISCHARGE TRH 277'8 0'5{0'5>>3'9(0'3>>Oe48(0,18>>0~31(Oe31>>Oebl(0~14>>0'4(0'e 40>>Oe48{Oelb>>0~14(Oe13>>Oe53{0'8>>TRH 277'8 TRH 293'SFN 01SCHARGE TRH 277o98 TRH 293'8FN DISCHARGE TRH 277'8 TRH 293'SFN DISCHARGE TRH 293o7 SFN 01SCHARGE SR 89 SR 90 TRH 288e78 3'0(3 ll>>2l 2)4e08 1/2}0'3 2/2)1~12 2/2)Oo51 1/2)0 F 45 2/2)0'9 2/2)0'5 2/2)0'1 2/2)Oel7 2)Oe50<LLO Oe03(0 F 03>>1~Ob(le05>>Oe44(0~3'7>>0~45(0'5>>0'3{Oe 36.0'4(0~16>>Oe44{Oe37 0'2(0 F 07>>Oe39{Oo28>>2 VALUES 4.35(2/2)3'4>>4'5 a.Nominal Lover Limit of Detection (LLD)aa described in Table 3.b.Mean and ranbe based upon detectable measurements only.Praction of detectable measurements of s ecified lo i i i d arenthe i (Pj pec e ocat ons s n icated in W j.

45 ualit Control A qu'ality 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 the Browns Perry Nuclear Plant are forwarded to these laboratories for analysis, and results are exchanged for comparison.

Data Anal sis Data measured at the control stations for each medium were aver-aged for each sampling period.In order to describe the distribution of control station data, a mean, standard deviation, and 3-sigma value were calculated.

We can expect, with 99 percent confidence, 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 can say, with 99 per-cent confidence, that the indicator data were not significantly affected by the nuclear plant.If the data do not fall within the Ximits, we will perfoxm further analyses to determine if the difference is attributable to the nuclear pl'ant.Conclusions A vast ma)ority of the indicator station data was found to be within the distribution defined by the control station data.The ALPHA-M least squares computer program identified concentrations slightly exceedin the limits of the control station data for a small number of radionuclides excee ng in samples from indicator stations.Many of these values may be discounted because the error reported by the ALPHA-M program was greater than the cal-culated concentration.

The remaining isolated elevated concentrations may be the'result of fallout, fluctuations in the existing environment com-puter program artifacts, or analytical errors.The same type of isolated high values occurred in the control station data and may be attributed to the same sources.Increased levels of radioactivity were observed in milk, rain-water,'air particulates, heavy particle fallout, vegetation, and in atmos-pheric radioiodine in October, November, and December following the atmo-spheric nuclear weapons testing conducted by the Republic of China in mid-October.

This increase was seen in control stations as wall as indicator stations, and was widely reported in the eastern portion of the United State@.Levels: of I in milk as high as 1.2 pCi/1 were observed.The primary radioisotopes identified in the atmospheric media were SZr, Nb, 214Bi,'nd 103Ru 46 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 occur-ring radionuclide potassium-40, 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 that there were no significant increases in environmental radioactivity attributable to the operation of Browns Ferry Nuclear Plant.

ENVIRONMENTAL RADIOACTIVITY LEVELS BROWNS FERRY NUCLEAR PLANT ANNUAL REPORT-1981 TVA/OMS/OHS-82 7 April 1982 CONTENTS I,ist of Tables 1.21 List of Figures.~~~~1V Introduction

.Atmospheric Monitoring Terrestrial Monitoring Reservoir Monitoring Quality Control.Data Analysis.Conclusions'.

~~~~~~11 23 41 53 53 53 P l 1 a~

LIST OF TABLES Table 3-Table 4-Table 5" Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table 6-7 8-9~10-ll-12'-13-14-15-16-17-18-19" 20-21-22" 23" 24-25" 26-Table 1-Table.2'-Environmental Radioactivity Sampling Schedule Atmospheric and Terrestrial Monitoring Station Locations-Browns Ferry Nuclear Plant Detection Capabilities for Environmental Sample Analysis Results Obtained in Interlaboratory Comparison Program.Maximum Permissible Concentrations for Nonoccupational Exposure Radioactivity in Air Filter.Radioactivity in Rainwater.

Radioactivity in Heavy Particle Fallout.Radioactivity in Charcoal Filters Radioactivity in Milk Radioactivitj'n Vegetation Radioactivity in Soil Radioactivity in Well Water Radioactivity in Public Water Supply.Environmental Gamma Radiation Levels Radioactivity in Food Crops Radioactivity in Soybeans Radioactivity in Poultry Sampling Schedule-Reservoir Monitoring Radioactivity in Surface Water Radioactivity in White Crappie (Flesh.Radioactivity in Smallmouth Buffalo (Flesh)Radioactivity in Smallmouth Buffalo (Whole)Radioactivity in Sediment Radioactivity in Clam Flesh.Radioactivity in Clam Shell~~~~~~~~~~~~4~~5 6 8 13 14 15 16 17 26 27 28 29 30 31 32 35 36 43 44 45 46 47 48 49 50\

LIST OP FIGURES Figure l-Tennessee Valley Region.Figure 2-Atmospheric and Terrestrial Monitoring Network.Figure 3-Local Monitoring Stations 3 l8 19 Figure 4 Figure 5 TLD Locations, BFN Annual Average Gross Beta Activity in Air Filters, Browns Ferry Nuclear Fiant 20 21 Figure, 6-Annual Average Gross Beta Activity in Drinking Water, Browns Perry Nuclear Plant Figure 7-Direct Radiation Levels, BFN 38 Figure 8-Direct Radiation Levels, BFN (4-Quarter Moving Average)38 Figure 9-Direct Radiation Levels, WBN 39 Figure 10-Direct Radiation Ievels, WBN (4-Quarter Moving Average)Figure 11-Reservoir Monitoring Network Figure 12-Annual Average Gross Beta Activity in Surface Water 51 52 1r~I ttq ENVIRONMENTAL RADIOACTIVITY LEVELS BROWNS FERRY NUCLEAR PLANT ANNUAL REPORT 1981 Introduction The Browns Ferry Nuclear Plant (BFN), operated by the Tennessee Valley Authority, is located on a site owned by TVA containing 840 acres of land in Limestone County, Alabama, bounded on the west and south by Wheeler Reservoir (see figure 1).The site is 10 miles southwest of Athens, Alabama, and 10 miles northwest of Decatur, Alabama.The plant consists of three boiling water reactors;each unit is rated at 3,293 MWt and 1,098 MWe.Unit 1 achieved criticality on August 17, 1973, and began commercial operation on August 1, 1974.Unit 2 began commercial operation on March 1, 1975.However, a fire in the cable'rays on March 22, 1975, for'ced the shutdown of both reactors.Units 1 and 2 resumed operation and Unit 3 began testing in August 1976.Unit 3 began commercial operation in January 1977.The preoperational environmental monitoring program established a baseline of data on the distribution of natural and manmade radioactivity in the environment near the plant site.However, seasonal, yearly, and random variations in the data were observed.In order to detexmine the potential increases in environmental radioactivity levels caused by the plant, com-parisons were made between data for indicator stations (those near the plant)and control stations (those remote from the plant)in conjunction with com-parisons with preoperational data.Staffs in the Division of Occupational Health and Safety and the Office of Natural Resources carried out the sampling program outlined in tables 1 and 19.Sampling locations are shown in figures 2, 3, 4, a'nd 11, and table 2 describes the locations of the atmospheric and terrestrial'onitor-ing stations.All the radiochemical and instrumental analyses were conducted in TVA's Western Area Radiological Laboratory (WARL)located at Muscle Shoals, Alabama, and Eastern Area Radiological Laboratory (EARL)at Vonore, Tennessee.

Alpha and beta analyses were performed on Beckman Low Beta II and Beckman Wide Beta II low background proportional counters.Nuclear Data (ND)Model 100 multichannel analyzer systems employing sodium iodide NaI(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(Tl)detection systems.If significant concentrations of radioisotopes are identified, or, if there is a reasonable expectation of increased radioactivity levels (such as during periods of increased fallout), these samples are counted on the Ge(Li)system.Identification of gamma-emitting radionuclides in all other types of samples is routinely performed by analysis on the Ge(Ii)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(T1).The data obtained by Ge(Li)detectors were resolved by the ND4420 software.The detection capabilities for environmental sample analyses given as the nominal lower limits of detection (LLD)are listed in table 3.Samples processed by NaI(T1)gamma spectroscopy were analyzed for 13 specific gamma-emitting radionuclides and radionuclide combinations

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

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

Many of the isotopes identified by Ge(Li)spectral analysis are naturally occurring or naturally produced radioisotopes, such as 7Be, 4oK, Bi'i,.Pb, Pb, Ra, etc.LLDs for the analysis of the radio-nuclides listed below are given in table 3B.LLDs for additional radio-nuclides identified by Ge(Li)analysis were calculated for each analysis and nominal values are listed in the appropriate data tables.In the instance where an LLD has not been established, an LLD value of zero was assumed.A notation in a table of" values<LLD" for an isotope with no established LLD does not imply a value less than 0;rather it indicates that the isotope was not identified in that specific group of samples.For each sample type, only the radionuclides for which values greater than the LLD were reported are listed-in the data tables.TVA's Radioanalytical Laboratories partioipate in the Environmental Radioactivity Laboratory Intercomparison Studies Program conducted by EPA-Las Vegas.This program provides periodic cross-check samples of th'e type and radionuclide composition normally analyzed in an environmental monitoring program.Routine sample handling and analysis procedures were employed in theevaluation of these samples.The EARL began processing samples in May 1980.The results received during calendar year 1981 are shown in table 4.The+36 limits based on one measurement were divided by the square root of 3 to correct for triplicate determinations.

a The following radionuclides and radionuclide combinations are quantified by the ALPHA"M least-squares computer code: 141'l44Ce; Cr;I;'u;~Cs'Cs,.Zr-Nb'o;+Mn;Zn;oCo;OK;and OBa-La.

1)(" OAOVCAH/\.(,+N~JACKSON+///MEMPHIS I M I S S.LOOISVILLE I N D..t-TENNESSEE VALLEY REGION 4 (TVA NUCLEAR PLANT SITES)4, W V A BOWLING CREEN RP S C A R (~SHOALS/o t~//I A L A rB A M A LEGEND-HARTSVILLE NUCLEAR PLANT/gal-PHIPPS BEND NUCLEAR PLANT 78%V-CLINCH RIVER BREEDER REACTOR G EORG I A~-WATTS BAR NUCLEAR PLANT XE-SEQUOYAH NUCLEAR PLANT'-BELLEFONTE NUCLEAR PLANT 9E5[-BROWNS FERRY NUCLEAR PLANT~-YELLOW CREEK NUCLEAR PLANT'r~K E-N T U C K Y r l.I'/1 SvOR\j rr/)NASHVILL OAK RIOGE+Ei g N~-N E S S E~""'-N rc A R.\///r (xr 7 (SON J jl I J~/)/+HUNTSVILLE 1 1 J MOSCLE lg/~

Table 1 ENVIRONMENTAL RADIOACTIVITY SAMPLING SCHEDULE'ir Charcoal Rain-Heavy Particle River Mell Public Aquatic Life station rotation Filter kilter ater tello t soil~lla aration Milk water Mater rater'nd dedi ent Foods Muscle Shoals W Lawrenceburg W Rogersville M Athens M M Decatur M M Courtland W Site NM-l W Site N-2 M M M M Site NE-3 M M Site NM-4 Site WSW-5 W Farm B Farm Bi/Farm P Farm H Parm T Farm L Control Farms Onsite Well Wheeler Dam Elk River Tennessee River Champion Paper Co.Various Local Farms M-Weekly M-Monthly (every 4'eeks)Q-Quarterly S-Semiannually A-Annually Table 2 Atmospheric and Terrestrial Monitoring Station Locations Browns Ferry Nuclear Plant Sam le'Station LM-1 BF, Northwest IM-2 BF, North LM-3 BF, Northeast LM-4 BF, Trailer Park LM-5 BF, Davis Farm PM-j.BF, Rogersville, AL PM-2 BF, Athens, AL Approximate Distance and Direction from Plant 1.0 Mile (1.6 kilometers)

.'0.9 Mile (1.4 kilometers)

NNE 1.0 Mile (1.4 kilometers)

.ENE 1.7 Miles (2.7 kilometers)

NNW 2.5 Miles (4.0 kilometers)

WSW 13.8 Miles (22.2 kilometers)

NW 10.9 Miles (17.5 kilometers)

NE PM-3 BF, Decatur (Trinity), AL 8.2 Miles (13.2 kilometers)

SSE PM-4 BF, Courtland, AL 10.5 Miles (16.9 kilometers)

WSW RM-1 BF, Muscle Shoals, AL (Control)RM-2 BF, Lawrenceburg, TN (Control)I Farm S Farm B Farm H Farm T Farm Bi (Out of business 7/20/82)Farm P (Sampling, begun 8/3/82)Farm N (Control)Farm J (Control)Farm C (Control)Farm Ca (Control)32.0 Miles 40.5 Miles 4.75 Miles 7.0 Miles 3.75 Miles 7.0 Miles 4.5 Miles 8.8 Miles 27.0 Miles 40.0 Miles 32.0 Miles 32.0 Miles.(51.5 kilometers)

W (65.2 kilometers)

NNW (7.6 kilometers)

N (11.3 kilometers)

NNW (6.0 kilometers)

N (11.3 kilometers)

ENE (7.2 kilometers)

ENE (14.1 kilometers)

E (43.4 kilometers)

NW (64.4 kilometers)

NNW (51.5 kilometers)

N (51.5 kilometers)

W Table 3 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS A.S ecific Anal ses HOMINAL LOWER LIMIT OF DETECTION LLD*Air Particulates

~cr Charcoal~cr/Fallout Water mCi/km p Ci/1 Vegetation Soil and and grain Sediment~CE/~d~C//~dr Fish, clam flesh, plankton,~C1/dr Foods, meat, Clam shells poultry, Milk~cr/d dc//k~dc dcr/1 Total a Cross c3 Gross B 3331 SSS 44sr 0.005 0.01 0.005 0.001 0.02 0.4 2.0 0.05 2.4 330 10 2 0.01 0.05 0.20 0.25 0.05 0.35 0.70 1.5 0.3 0.1 0.1 0.5 0.1 0.7 0.7 5.0 1.0 1.5 25 40 8 0.5 10 2*All LLD values for isotopic separat.ions are calculated by the method developed by Pasternack a y n k and Harle 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 Mithin one s/eek of the collection date.Conversion factors: 1 pCi~3.7 x 10 Bq;1 mCi~3.7 x 10 Bq.

Table 3 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS B.Canna Anal ses NOMINAL LOWER LIMIT OF DETECTION LLD Vegetation and grain~Ci/dr Air parciculates

~c/Io Water and milk~ci/I Soil and sedinenc~cz/dr~NaI*~Ce Li**Nal~Ce Li Nal~Ge Li NaI~Ce Li)Clan flesh Fish and plankton deci/d d~ci/'d it I~ce Li M I~ce La Foods,(tomatoes potatoes, etc.)Ci/vet Clan shells Cccal/a acr NaI~Ge Li NaI C~eLi Meat and poultry Naf Ge(Li>1/d l~1 dr dr Ce C$1Cr 1111 141d 146R 1 46Ru 1 ldrC 13$C Zl-Nb$529"Nb'4Co Mn 6$Zn Co'4K Ba-La 164Ba 0.03 0.02 0.07 0.03 0.01 0.01 0.04 0.03 0.01 0.02 0.01 0.01 0.01 0.01 0.01 0.02 0.01 0.02 0.01 0.02 0.01 0.01 0.01 0.10 0.02 0.02 0.01 60 15 40 10 10 10 15 10 15 10 150 15 33 44 8 40 26 5 10 5 5 5 9 5 25 7 0.55 0.22 1.10 0.47 0.35 0.09 0.65 0.51 0.20 0.33 0.20 0.06'.20 0.11 0.05 0.23 0.05 0.20 0.05 0.25 O.ll 0.17 0.06 2.50 0.68 0.34 0.08 0.35 0.06 0.60 0.10 0.20 0.02 0.45 0.11 0.12 0.08 0.12 0.02 0.12 0.03 0.01 0.20 0.01 0.15 0.01 0.23 0.02 O.ll 0.01 0.90 0.15 0.07 0.02 0.35 0.06 0.60 0.10 0.20 0.02 0.45 0.11 0.12 0.08 0.12 0.02 0.12 0.03 0.01 0.20 0.01 0.15 0.01 0.23 0.02 0.11 0.01 0.90 0.15 0.07 0.02 0.35 0.56 0.07 0.74 0.48 0.08 0.15 0.07 0.07 0.08 0.17 0.08 0.30 0.10 0.35 0.06 0.60 0.10 0.20 0.02 0.45 0.11 0.12 0.08 0.12 0.02 0.12 0.03 0.01 0.20 0.01 0.15 0.01 0.23 0.02 0.11 0.01 0.90 0.15 0.07 0.02 38 60 15 40 10 10 10 15 10 15 10 150 15 20 15 55 15 40 15 70 20 30~15 400 50 25 7 50 15'!90'3 4C 44 200 90 8 50 20 150 40 90 26 40 50 5 40 15 40 10 5 5 5 9 5+The NaI(T1)LLD.values are calculated by the method developed by Pasternack and Harley as described fn HASL-300 and Nucl.Instr.Methods 91, 533-40 (1971).These LLD values are expected to vary depending on the activities of the conponents in the samples.These figures do not represent the LLD values achievable on a given sample.Water is counted in a 3.5-L Marfnelli beaker.Vegetation, fish, soil, and sedfment are counted in a 1-pint container as dry veight.The average dry veight is 120 grans for.vegetation"and 400-500 grams for soil sedfnent and f fsh.Meac and poultry are counted in a 1-pint container as dry vefght, then corrected to vet veight using an average moisture content of 70X.Average dly weight is 250 grams.Air particulates are counted in a veil crystal.The counting system consists of a multichannel analyzer and either a 4" x 4" solid ol 4" x 5" veil NaI(T1)crystal.The counting time fs 4000 seconds.All calculations are performed by the least-squares conputer progran ALPHA-M.The assumption is made that all samples are analyzed vithin one week of the collect fon date.<<The Ge(Lf)LLD values are calculated by the method developed by Pasternack and Hal'ley as described in HASL-300.These LLD values are expected co vary depending on che activities of the components in the samples.These figures do not represent the LLD values achievable on given samples.Water.is counced in either a 0.5-L or 3.5-L Marinelli beaker.Solid sanples such as soil, sediment, and clan shells are counted in a 0.5-L Marfnelli beaker as dry weight.The average dry weight is 400-500 grams.Afr filters and very small volume sanples are counted fn pectic dishes centered on the detector endcap.The counting system consists of a ND-4420 multichannel analyzer and either a 25X, 14X, 16X, or 29X Ge(f,f)detector.The counting tine is normally 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.All spectral analysis is performed using the software provided with the ND-4420.assumption is made that all samples are analyzed within one week of the collection date.Conversion factor(1 pCi~3.7 x 10 Bq.

Table 4 Results Obtained in Interlaboratory Comparison Program A.Air Filter (pCi/filter)

Gross Al ha Gross Beta Strontium-90 Cesium-137 Date EPA value (+3a).TVA AVG.WARL EARL EPA value TVA AVG.(+3a)WARL EARL EPA value (+3a)TVA AVG.MARL'EARL EPA value (+3a)TVA AVG.WARL EARL 12/80 3/81 6/81 9/81 21+9 30+13 28+12 25+11 22 23 31 31 29 32 26 25 19+9 50+9 54+9 51+9 24 26 55 49 62 59 61 54 18+2.6 19+2.6 16+2.6 2<2 18 15 19 23 16 19 19+9 14+9 16+9 19+9 20 22 15 14 17 18 21 20 B.Tritium in Urine (pCi/L)Date 3/81 6/81 9/81 11/81 EPA Value (+3a).810+549 1600+585 2050+599 2700+615 TVA AVERAGE WARL EARL 713 390 1637 1830 2103 2573 2623 a.Western Area Radiological Laboratory, Muscle Shoals, Alabama b.Eastern Area Radiological Laboratory, Vonore, Tennessee c.Efficiency curves were checked and known spikes were run.Everything found was within acceptable limits.We are awaiting the next cross-check for further investigation.

d.Results were mailed to EPA but not reported by them.e to obtain another sample, from EPA and reanalyze Table 4 (Contd)Results Obtained in Interlaboratory Conparison Progran ED Nilk (pCi/L)Strontiu3a

-89 EPA value TYA AVG.IM~(.33 I:AEL EAIIL 1/81 0<10<10 4/81 25 9 28 7/81 ,25t9 23 30 10/81 23t9 25 28 EPA value (a3a)20s5.2 11a2.6 17s2.6 18a2.6 TVA AVG.WARL EARL 21 20 13 14 16 17 16 Strontiun-90 EPA value 26a17 26t10 ,01+52s10 TVA AVG.'MARL EARL 24 21" 21 29<15<15 49 47 Iodine-131 EPA value 43t16 22 9 31t9 25'9 TVA AVG.'MARL EARL 40 41 21 24 32 32 27 27 Cesiun-137 EPA value (a3o)TVA AVG.WARL EARL<25<15<15<15<15<15 Bariun-140 Potassiun EPA value TVA WARL 1490 1453 1513 1674 1623 1620 1620 1500 1550 232 1559 135 1600t139 1530 133.Cobalt-60 AVG.EPA value TVA AVG.EARL~3a)MARL EARL F.Foods (pCi/kg, Wet Weight)0 3/81 47+9 42 44 7/81 44a9 53 51 11/81 38t9 49 54 29a2.8 31a2.8 23 2.6 38P ZI P 31 32 25 22 119t21 82i14 None 126 80 121 106 53t9 45~9 33i9 56 55 43 54 29 35 0 0 0<15<15<25<25<15<25 2640t229 2640t229 2730t237 2857 2917 2870 3437 q 0 9 25 k.Values for potassiun are reported, as ng/liter of sanple.n.Results were narginally out of linits.Efficiency curves were checked with no conclusive findings.Subsequent results have been satisfactory.

n.Only two results were sent.to EP*.Results were not included in their analysis.o.Values for potassiun are reported as ng/kg sa~le.p.Investigation of this problen was initiated bur.no satisfactory conclusions have been reached.We suspect difficulties arising (ron sanple inhos3ogeniety.

An incorrect weight was obtained in the gama analvsis of this sanple.Further analysis destroyed the sanple so that the correct weight could not be deternined.

Invesrigarion was conducted.

No satisfactory explanation was found.Other cross-checks on this isotope in different nedia are satisfactory.

Table 4 (Contd)Results Obtained in Interlaboratory Comparison Program C.Radiochemical Analyses of Water (pCi/L)Gross EPA value Date (+3u)Alpha Gross Beta Strontium-89 Strontium-90 Tritium TVA AVG.EPA value TVA AVG.EPA value TVA AVG.EPA value TVA AVG.EPA value TVA AVG.WARL EARL~(+3a)WARL EARL (+3o)WARL EARL (f 3o)WARL EARL (f 3a)WARL EARL TVA AVG.WARL EARL EPA value~(-3o f Iodine-131 1/81 9+9 2/81 3/81 25+10 4/81 5/81 2L+9 6/81 7/81 22t 10 8/81 9/81 33+14 10/81 11/81 2li9 12/81 10 9 44r9 49 49 16+9 11 14 34%3.1 388 28 23 15i 25f9 26 29 21 14 14+9 14 16 20 29 22 15i9 i 18 28t9 21 13 23+9 15 18 29 26 23+9 26 23 18 24 lla2.6 11 10 36+9 40 33 22f2.6 21 22 2210+603 2263 2197 27003615 2717 2807 76+13 65 56~1760L591 1917 1753 27104615 2467 2723 30+10 32 28 1950f 596 1990 1947 26303613 2623 2713 73a13 79 73 D.Gamma-Spectral Analysis of Water (pCi/L)Chromium-51 EPA value TVA AVG.Eal~RI)WARL EARL EPA value~3I)TVA AVG.WARL EARL Cobalt-60 Zinc-65 EPA value TVA AVG.~33 IIARL EARL EPA value~EW TVA AVG.WARL EARL Ruthenium-106 Cesium-134 EPA value TVA AVG.~(-+3l WAIIL EARL EPA value~RW TVA'AVG.WARL EARL Cesium-137 2/81 6/81 10/81 0 0 34+9<60<60 25i9<60<60 17+9<60<60 22i9 25 25 18 17 25 22 85f9 0 24a9 84 83<15<15 26 21 0 15+9 0<40<40<40<40<40<40 36+9 39 21+9 23 21+9 21 35.21 24 4i9 31+9 32+9 6 10 27 30 35 32 f.Specific analysis for'to test the procedures used for the analysis of milk.g.Investigations cLf the analytical procedure were conducted and new efficiency curves were determined.

Results have been satisfactory since that time.h.New efficiency curves were determined subsequent to this analysis.Subsequent results were satisfactory.

i.Excess humidity in counting room and a change in the amount of solid introduced into the sample by EPA are suspected in the difficulty with this sample type.Steps have been taken to correct or compensate for these items.Results are possibly due to an incorrect chemical form of the precipitate counted in this procedure.

Investigations continue.

Atmos heric Monitorin~The atmospheric monitoring network is divided into three groups.Four, local-air monitors are located on or adjacent to the plant site in the general areas of greatest wind frequency.

One additional station is located at the point of maximum predicted offsite concentration of radionuclides based on preoperational meteorological data (see figures 3 and 4).Four per'imeter air monitors are located at distances out to lO miles from the plant, and two ,remote air monitors are located at distances out to 45 miles.These monitoring stations are shown in figure 2.The remote monitors are used as control or baseline stations.At each monitor, air is continuously pulled through a Hollingsworth and Voss LB5211 glass fiber filter at a regulated flow of 3 fts/min.In series with, but downstream of, the particulate filter is a charcoal filter used to collect iodine.Each monitor has a collection tray and storage.container to obtain rainwater on a continuous basis and a hori-zontal platform that is covered with gummed acetate to catch and hold heavy particle fallout.Thermoluminescent dosimeters are used to record gamma radiation levels at each remote and perimeter station.Each of the local air monitors is fitted with a GM tube that con-tinuously scans the particulate filter.The disintegration rate of the atmospheric radioactivity is continuously recorded at each station and radio-telemetered into the plant.Air filters are collected weekly and analyzed for gross beta activ-ity.No analyses are performed until three days after sample collection.

The samples are composited monthly for analysis of specific gamma-emitting radio-nuclides and quarterly for Sr and oSr analysis.The results are combined for each station to obtain an annual average.During this reporting period, three samples were not obtained because of equipment malfunction.

These data are presented in table 6.The'nnual averages of the gross beta activity in the air particulate filters at the indicator stations (local and perimeter monitors)and at the control stations (remote monitors)for the years 1968-1981 are presented in figure 5.Increased levels due to fallout from atmospheric nuclear weapons testing are evident, especially in 1969, 1970, 1971, 1977, 1978, and 1981.These patterns are consistent with data from monitoring programs conducted by TVA at nonoperating nuclear power plant construction sites.Table 5 presents the maximum permissible concentrations (MPC)recommended by 10 CFR 20 for nonoccupational exposure.Rainwater is collected monthly and a 3.5-liter sample analyzed for specific gamma-emitting radioisotopes and tritium.The results are shown in table 7.The gummed acetate that is used to collect heavy particle fallout is changed monthly.The samples are ashed and counted for gross beta activity.The results are given in table 8.

12 Charcoal filters are collected and analyzed for radioiodine.

The filter is counted in a single channel analyzer system.The results are shown in table 9.During this reporting period, two samples were not taken because of equipment malfunction.

13 Table 5 HAXIHUN PERNISS IBLE CONCENTRATIONS FOR NONOCCUPATIONAL EXPOSURE Alpha Nonvolatile beta Tritium 1 37CS 103~106Ru 144(e 9szr-"Nb'40Ba-140La 131Z 6SZn 54Nn 60Co 89Si"Sr 51Cr 1 34CS 58Co In Water~Ci/1*30 3,000.3,000,000 20,000 10,000 10;000 60,000 20,000 300.100,000 100,000 30,000 3,000 300 2,000,000 9,000 90,000 MPC In Air~C1/m+100 200,000 500 200 200 1,000 1,000, 100 2,000 1,000 300 300 30 80,000 400 2;000*1 pCi~3.7 x 10 Bq.

TABLE 6 RADIOACTIVITY IN AIR FILTER PCI/N(3)" 00637 BG/N (3)TYPE A TOTAL NU ,OF ANALY Pf Rf QR~N GROSS ALPHA 52 GROSS BETA 569 GAHNA (NAI)49 CE 141s144 0~010 Ge 08(0~01 456/465)6038 8/39)0 F 06 5/39)0~06 20/39)0013 6/39)0~62 35/39)0~21 0003D 0~05(0~03 0005(0~05-0~C6(0~01-0~02(0~Ol 6~D9(0~01-RU 1'03s 106 ZR-95st(B-95 1-131 BE-7 00C40 O.O10 F 010 NDT E'STAB NANE OF FACILITY Qf~ot~4~ERRY LOCATION OF FAC'ILITY LIHESTO~N ND LOYER L IHI T ALL HBEP.OF, ItJLI GATOR LOCATIONS SIS DETECTION a HEAN qF)b~Lt Q)R ANt(L 00005 ALA AHA DOCKET NO~50 25~9'EPORTING PERIGG~I9 LN4 BF TRAILER P I e 7 HI LES NNV 0 F 09(0001 50/52)DN36 CONTROI.LGCATIGINS HEAN (F)b R ANGf b 0001(3/52)0 F 01-Oeol 0'8(103/104)0001-CD 39 LN3 BF NORTHEAST 1~0 HILE ENE Lt(3 BF NORTHEAST 1~0 NILE ENE ATHENS'L 16 9 NILES NE DECATURs AL 8 2 HILES SSE ATHENSs AL 1009 NILES NE 0 F 06(0006 0 F 06(0~06-0.13(0~13-0 F 02(0~62-0~12(0 F 67 ll 4)0006 1/4)0~06 1/3)0~13 1/5)0 F 02 3/3)0 021 0 04(4/10)0003-0~07 6005(" 2/10)0~05-0'5 0~06(5/10)0002-CD 13 10 VALUES (LLD 0~10(10/16)0 F 05-0'3 i GER~IN lfIIH~HHEEE RMHiiRj NEIN NUHBER OF NONRDUT INE REPORTED~NIRUII II Nil GANNA (GELI)94 CE-141 CE-144 RU 103-ZR 95 NB-95 K-40.BI-214 BI"212 PB-214 PB 212 BE-7 TL 208 SR 89 SR 90 0~016 0 C2C NOT ESTAB 0~016 Deolo NOT, ESTAB De 020 NOT ESTAB 0'2D NOT ESTAB 0~OS('OT ESTAB 0~DOS 00001 0~01(0~01-0~C4(0002-6061(0 F 00 D~03(Dool-0~05(0061-0012(6006 D~04(0~02-0~04(0~04-G~04(0~02-0 F 01(0~60-0068(0~05-0 F 01(0 F 00 0~Gl(0~01-O.OD(8/78)0~62 16/78)0~67 38/78)0 03 34/78), 0~06 40'/78)0~15 58/78)0~30 44/78)0'9 1/78)0 F 04 28I 78)0 F 08 35/78)0~03 41/78)0~47 14/78)0 F 01 18/36)0~01 7/36)EE ATHENSs AL 1009 H.ILES NE ROGERSVILLEs

'AL 13~8 t'.ILES NV LNl BF NORTHVEST 1~0 NIILE N RDGERSVILLEs AL 13~8 HILES tJV DECATURs AL 8~2 HI LES SSE LH2 BF NORTH 0~9 H I LE tJNE DECATURs AL 8 2 HILES SSE DECATURs AL=8~Z HILES SSE DECATURs AL 8~2 NI LES SSE LN3 BF NORTHEAST 1~0 HILE ENE DECATURs AL 8 Z HILES SSE LH4 BF TRAILER P le7 HILES NNQ LH5 BF DAVIS F 2~5 H ILES VSV ROGERSVJLILE's AL PNILES NV D~02(6~62--*0~05(0~04-O.02(0~01-0~04(0~02-0~07(0~03-0~16(0~12 0~D5(0~02-0'4(0~04-.6~05(0~03-0'2(0~02-0~16(0~05-0 F 01(0~01-0 F 01(0~0$'-0~DD(0~00-ll 10)D~02 2/16)0~07 4/8)0'3 5/16)0~66 4/')D012 3/6)0~18 6/8)0'9 1/8)0 F 04 3/')De D7 1/9)0'2 5/8)6~47~2/7)0 F 01 2/4)0,0 01 1I 4')0 F 00 0~03(0~02-0 F 01(0'Do 0~07(0 DS-6~01(0001-0 F 01(0~Dl-0"e'00(0~00 6/16)6~07 7/16)0~02 9/16)0~10 3/16)0 F 01 4/8)D 0'01 3'/'8)C 00'16 VALUES R.'LLD 0012 (3/'16)0002-0~30 0 F 01(7/16)0 F 01-0 F 02 0~02(8/16), 0001 0~C3 DRAGS(" 8/16)0002 0'9 C013(13/16)0~ll-0'6 0~04(7/16)0 03-0~08.16 VALUES'(LLD'9 RADIOACTIVITY Itl RAIN!JATER PCI/L-0'37 BO/L NAt,E OF FACILITY RROV~NFERRY LOCATIOtl OF FAC)LITY L IH~STO~tl ALABAMA REPORTI toG PERIOD 9 TYPE AND TOTAL NUMBER OF ANALYSIS P~FRFOR'!EO GAMMA (NAI)97 CC-141 144 RU-103'06 LO4ER LIMIT OF DETECT ION a (LLD)38~OGO 40~ODO I-131 BE-7 15 000 ,'JOT ESTAB ZR-95~'JB-95 10 DOG 77 VALUES<LLO 48'0(48~20-15 F 02(10e10-22~10(22~10-51 F 80(7~30-I/77)48'O 19/77)25~10 1/77)22~1D 49/77)133'0 ALL I JJOICATOP LOCATIOtJS MEAN (F)RANGr h DCCATUR~AL 8 2 MILES SSC LH4 BF TRAILER P lo7 MILES Nt(M LHS BF DAVIS F 2'MILES JJSM LHS BF DAVIS F 2e5 MILES)JSM 48~20(48~20-20'0(15~60-22 F 10(22~10-67 F 88(39~70-1/8)48'0 3/8)25 F 10 1/6)22 10 4/6)115'0 CONTROL LOCATIONS MEAN (F)b RANG b 43'0(I/20)43'0-43'0 20 VAl.UES<LLD 19e63(3/20)10'0-35 F 10 2C VALUES<LLD 56~86(14/20)14 F 00-108'0 NUMBER OF NONROUTINE REPGR TED JJ8-95 K-40 BI-214 Pi)-214 PB-212 Oc 7 TRITIUM So000 NOT CSTAB NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB 330 F 000 143 9e63(2/40)8~93-10'2 81'7(21/40)32 F 71-125 F 00 22'9(25/40)11'2-48'8 17o15(12/40)F 41-29'7 14'2(8/40)8'9-18 F 09 49'5(3/40)43'8-54'6 117 VALUES<LLO ANALYSIS P ERFORHED GAMMA (GCL I)46 ZR-95 10~ODO 40 VALUES<LLD LH5 BF DAVIS F 2~5 MILES)JSll LH3 OF tJORTMEAST 1~0 HILE Ct'E LM3 BF NORTHEAST 1~0 MILE ENE LH3 BF NORTHEAST 1 D MILE ENE COURTLAtJDt AL 10~5 MILES MSM LH5 BF DAVIS F 2o 5 HILES MS M 10'2(10~32-125 F 00(125o00-29~43(16~24-28'8(28~38-18.09(18~09-49'5(43~28-1/7)).0~32 I"/6).12S~00 4/6)48'8 1/6)28'8 1/3)18~09 3/7).54~06 10'2(1/6)1De12-10'2 13e82(I/6)13o82-13'2 58'9(2/6)54'9-61'8 40 21(3/6)23'9-70'1 11'6(2/6)8'5-14'6 6 VALUES<LLD 105 F 00(1/6).105 F 00-105 00 26 VALUES<LLD a.)toninal Lower Linit of Detection (LLD)as described in Table 3.b.Mean and ran8e based upon detectable neasureaents only.Fraction of detectable aeasurements of specified locations is indicated in parentheses (F).c.Identified as fallout.

TABLE B RADIOACTIVITY IN HEAVY PARTICLE FALLODT HCI/KH(2)-37GCOOCO~GO BG/KH(2)NAHE, GF FACILITY SRO'MNS FLURRY LOCATION OF FACILITY LIHESTONE/LABAH/DOCKET h0~~~~0296 REPORTING PER IOD~981 TY~E ANO TCTAL)JUHBER OF 1',JALYS IS GROSS BETA 143 LOMER L I HIT OF OETECTIONa

~(L Q)0'50 ALL IhOICATOR LOCATiORS HEAN Ig)b RANG/1~09<117/117)0~08-3~73 NAHE HEAN (F)b LH4 BF TRAILER P I~354 13/13)1~7 HILES)JNM 0'6-3'3 CONTROL LGCATIONS HEAN IF)b~RAN b 1+04 I 26/26)0+12-2'9 NUHBER OF NONROUTINE REPORTED a.IIominal Lover Limit of Detection (LLD)as described in Table 3.b.Hean and range based upon detectable measurements only.Fraction of detectable measurements of specified locations is indicated in parentheses (F).

TABLE 9 RADIOACTIVITY IN CHARCOAL FILTERS PCI/Y (3)-0~037 BQ/H(3)NAHE OF FAC ILI TY~Fi Vt-'Q FLURRY LOCATION OF FACILITY LIH~STONQ ALABAMA DOCKET NO~50-259'~60 296 REPORTING FERIOD 198/TYPE AND TOTAL WUHBER OF ANALYSIS PQRF~ORH 0 IODINE IN AIR 570 LOi(ER L IHIT OF BETE CT IONa (QQ)0'20 ALL INDICATOR LOCATIONS MEAN ([)b RANG~0 03(62/466)0'2-0'9~OCC T~IGtl M TH~Hg~HJ ilhN~~AH NAME HEAN (g)b ((I ST~ANC~AN" A I P~rCT I ON RANGE COURTLANDt AL 0'6(2/50)I 0~5>ILES'a S)0.02-0.09 CONTROL LOCATIONS 0~02(13/104)0+02-0'%NUHBER OF NONROUT INE REPORTrD~H~ASUR HEN T S a.Nominal Lover Limit of Detection (LLD)as described in Table 3.b.Mean and range based upon detectable measurements only.Fraction of detectable measurements of specified locations is indicated in parentheses (P).

18 Figure 2.ATMOSPHERIC AND TERRESTRIAL MONITORING NETWORK RM.2BF LAWRENCEBURO yPULASKI FAYETTEVILLE gy WILSON FLORENCE OAM PM-IBF WHEELER ROBE SVIL OAM FFIEL MUSCLE SHOALS RM-IBF LEIGHTON TUSCUMBIA COURTLANO PM-4 F ATHENS PM-2BF BROWNS FERRY NUCLEAR PL NT OECAT PM-3BFO IO MILES HUNTSVILLE pRUSSELLVILLE UNT SV IL HARTSELLE OAM 25 HALEYVILLE CULLMAN 45 MILES RAINWATER SOIL Q-ENVIRONMENTAL MONITORING STATION NOTE: THE FOLLOWING SAMPLES ARE COLLECTED FROM EACH STATION: AIR PARTICULATES RADIOIODINE HEAVY PARTjCLE FALLOUT Figure 3 LOCAL MONITORING STATIONS', BROWNS FERRY NUCLEAR PLANT ATHENS U S HWY 72 BFN ALA.HWY 20 LegendAir Monitor Automatic Well Sampler H Dairy Farm DECATUR Scale 0 I 2 8 0 5 Miles 20 Figure 4 J J~J'1 TLD Locations ('~)~I r I>>j'('r t h)1 t I.n~I I)'v)l;I))I h,'<<<<<<$l.,r)l t'(ht(".ht,', ,'tlt1 t rt",j'ij(', r").$.')I'., Igp 1,)+I)a(J<<t)t>>O'I xt I r'I I w>)$(j 4,th I'l tl trl>>I<<I)n,,~t,(j al/<<I IW n Er t),'l!', n 7 tI';I t'I~'O.I!Ihg I)$.1<<I~,roh(t I')I I~>>~A't'<<al I r~>>f l>>~<>'I W".'jt S 4<<~IA I<<I, I)I~,~t t.a I, 1)I I I<<gsk'r I 2 , I r ,()))I'KR<<J"'1'pi""O))I (I/)'~<<~I I.)(.Y5~: I I W I I)<<Tl r<<PI~0\ISI<<SE<<$~$0 V I Figure 5.30.25 Preoperational Phase Operational Phase AWUAL AVERAGE.6ROSS 8ETA ACTIVITY IN AIR FILTERS HROWS FERRY NUCLEAR PLANT.20.15 0'o co 4J 0~v IJ 4J N+v 4J CC 0 0 4J c 0 w O Average: Preonerational Phase.10.05 I 68?969 1970 ,1971 19 1972 1973 19730 1971 1975 1976 1977 1978 1979 1980 1981 23 Terrestrial Monitorin'Milk Milk is collected from at least four of five farms within a 10-mile radius of the plant (see figure 3), and from at least one of four control farms.Raw milk is analyzed weekly for I, and monthly for gamma-emitting isotopes and for radiostrontium.

The results are shown in table 10.Cow censuses were conducted in May and September 1981.It was determined that there are no dairy farms nearer the plant than the nearest farm being sampled.During this period however, one of the dairy farms being sampled (farm B, table 2)went out of business and all.cows were sold.Another dairy farm (farm P)was added to the monitoring program on August 3, 1981.V~e etation Vegetation is sampled quarterly at the farms from which milk is-collected'and analyzed for gamma-emitting radionuclides.

Approximately 1-2 kilograms of grass is broken or cut at ground level and returned for analysis.Efforts are made to sample vegetation that is representative of the pasturage where cattle graze.Table ll gives the results obtained from the laboratory analyses of these samples.Soil Soil samples are collected annually near each monitoring station to provide an indication of a long-term buildup of radioactivity in the environ-ment.An auger or"cookie cutter" type sampler is used to obtain samples of the top two inches (5 cm)of soil.These samples are analyzed for gamma-.emitting radionuclides, Sr, and oSr.The results are given in table 12.Ground Water An automatic sequential-type sampling device has been installed on a well downgradient from BFN.A composite sample from this well is analyzed for gamma-emitting radionuclides monthly and composited quarterly for determination of tritium.A grab sample is also taken from a control well upgradient from the plant.The results of the analysis of well water are shown in table 13.Drinkin Water Potable water supplies taken from the Tennessee River in the vicinity of BFN are sampled and analyzed for gross beta and gamma-emitting radionuclides, and composited quarterly for tritium, Sr, and oSr analyses.The first potable water supply downstream from the plant is equipped with an automatic sampler with samples collected and analyzed weekly.The sampler is located on the water intake structure and takes the sample from the river as the raw water is drawn into the water treatment facility.Two additional supplies 24 downstream and one public water supply upstream are sampled by taking monthly grab samples of treated water at user points.Table 14 indicates the results from the analysis of drinking water samples.During this reporting period, six of the weekly samples were not taken because of the malfunction of automatic sampling equipment.

Figure 6 shows the trends in gross beta activity in drinking water from 1968 through 1981.The annual average level from the raw water samples tends to run slightly hi'gher than the average for treated water samples;however, the levels are consistent with the activities reported in surface water samples taken upstream from BFN (figure 12)and in samples taken from the Tennessee River in preoperational monitoring programs conducted by TVA at other sites.Environmental Gamma Radiation Levels Bulb-type Victoreen manganese-activated calcium fluoride (Ca~F: Mn)thermoluminescent dosimeters (TLDs)are placed at sixteen stations around the plant near the site boundary, at the perimeter and remote air monitors, and at nineteen additional stations out of approximately five miles from the site to determine the gamma exposure rates at these locations.

The dosimeters, in energy compensating shields to correct energy dependence, are placed at approxi-mately one meter above the ground, with three TLDs at, each station.They are annealed and read with a Victoreen model 2810 TLD reader.The values are corrected for gamma response, self-irradiation, and fading, with individual gamma response calibrations and self-irradiation factors determined for each TLD.The TLDs are exchanged every three months.The quarterly gamma radiation levels determined from these TLDs are given in table 15, which indicates that average levels at onsite stations are approximately 2-4 mR/quarter higher than levels at offsite stations.This is consistent with levels reported at TVA's nonoperating nuclear power plant construction sites where the average radiation levels onsite are generally 2-6 mR/quarter higher than levels offsite.The causes of these differences have not been completely isolated;however, it is postulated that the differences are probably attributable to combinations of influences, such as natural variations in environmental radiation levels, earth moving activities onsite, the mass of concrete employed in the con-struction of the plant, and other undetermined influences.

Figure 7 compares plots of the data from the onsite or site boundary stations with those from the offsite stations over the period from 1976 through 1981.To reduce the variations present in the data sets, a four-quarter moving average was constructed for each set.Figure 8 presents a trend'lot of the direct radiation levels as defined by the moving averages.The data follow the same general trend as the raw data, but the curves are smoothed considerably.

Prior to 1976 measurements were made with less sensitive dosimeters, and consequently the levels reported in the preoperational phase of the moni-toring program are 1-2 times the levels reported herein.Those data are not included in this report.Therefore, for comparison purposes, figures 9 and 10 depict the environmental gamma radiation levels measured during the 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 Poultr and Pood Cro s Pood crops and poultry raised in the vicinity of BFN and at control locations are sampled as they become available during the growing season, and analyzed'for gamma-emitting radionuclides.

During this sampling period, samples of cabbage, corn, green beans, peaches, potatoes, turnip greens, tomatoes, soybeans, and poultry were collected and analyzed for specific gamma-emitting radionuclides.

No sample of soybeans or cabbage'as taken from-a control location.The results are given in tables 16, 17, and 18.

TYPE AND TOTAL NUHBER OF ANALYSIS P~RF g R H~O GAHHA (NAI)107 CS-137 LO'MER LIH IT OF OETECTIO~II 10 F 000 15D~ODD DH500 IODIN'E IN HILK 454 GAHHA (GELI)6 CS-137 5~000'tOT ESTAB RIOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB 10 F 000 2 000 K-40 81-214 PB-214 PB-212 TL-258 SR 89 SR 90 113 113 ALL INDICATOR LOCATIONS HEAIN (F)b AWOr'3 63(3/55)Ill 70-16 F 00 1246'1(55/55)1049'0-1569'0 253 VALUES<LLD ANALYSIS PER FORHCO 8'0(3/6)7~54-15 16 15DD F 50(6/6)1287 F 00-1845HDD 20 63(5/6)7 39-30 43 18'5(3/6)14'9-2D~63 14H88(3/6)9HS3-20'63(2/*6)2'8-F 48 61 VALUES<LLD ANA(.YSIS PERFORHED 3'5(61/61)F 01-F 19 NAHE OF FACILITY DHARMA(S FLURRY LOCATION OF FAC ILITY~Lill ATONE RADIOACTIVITY Ik HILK PCI/L-DH037 BG/L DOCKET t(O~50-25~92~60

~96 RCPORTIttG PERIOD 19&1 ALABAHA CONTROL LOCATION/HCAN (IF)RAN LOCATIQN III TH HIO~HT ANNUAL E HAN NAHE HEAN ()PAGE FARH 8~75 t'.ILES E THRASHER FARY 7~0 HILES ENE SHITH FARH 4~75 HILES N THRASHER FARH 7 0 HILES ENE SHITH FARH 4~75 HILES N BROOKS FARM 7~0 HILES NNM SHITH FARH 4~75 HIl CS N PAGE FARH 8~75 HILES E SHITH FAR)t 4 75 HILES N 10'6(ID+16-1845'D(1845~00 30 F 43(30H43 20'3(20-63-20~96(2D~96-6H48(6H48-4~74(3H12-1/1)10'6 1/1)1845 F 00 1/1)30 F 43 1/1)2D~63 1/1)2DH96 1/1)6'8 13/13)8 19 52 VALUES<LLO 4'3(40/52)2'6-7'6 13'3(3/4)10'0(1/52)11H70-16 F 00 10'0-10'G 1308'1(12/12)1232'5(52/52)1127 20-1569 20 , 1037H20 1391'0 201 VALUES<LLC NU)E DER OF-toONROUTINE REPORTED~V.A yRQ~HNTS a.Nominal Lover Limit of Detection (LLD)as described in Table 3.b.Hean and range based upon detectable measurements only.Fraction of detectable measurements of specified locations is indicated fn parentheses (F).

TABLE ll NAME OF FACILITY SROVNS FERRY LOCA'TION QF FAC ILITY~IMESTOtlE RADIOACTIVITY IN VEGETATION PCI/G 00037 BO/G (DRY VEIGKT)ALABAMA DOCKCT NO~50-259 260 REPORTING PERIOD~~98 TYPE ANO TOTAL NUNBCR OF ANALYSIS~FR F 0 R R-0 GROSS BETA 36 GAMNA (GCL I)38 LO'VCR LI HIT OF DETECT IONa CLLO)0~200 ALL INDICATOR LOCATIONS HEAN (F)b 26'3(20/.20)7070-48082 LO ATIOII VT TK KIGKEST ANtiUA MEAN NAME HCAN (F)b SITTING FARM 35~32(2/2)4~5 MILES ENE 31 88-38 75 CONTROL LOCATIONS HEAN CF)b R~NI+b 26'2(16/16)10007-45'4 NUNSER OF NONROUT INE REPORTED CE-141 CE-144 op.-144 RU-103 RU-106 CS-137 00200 00270 NOT ESTAB 5 200 0 510 00060 0 110 0005G'COT'ESTAB 0 050 NOT ESTAB 0'00 NOT ESTAB NOT ESTAB NOT STAB NOT CSTAB NOT E'STAB NOT ESTAB 2R-95 NB-95 K-40'lN-54 II I-214 BI-212 PB-214 oS 212 RA-226 BE-7 TL-208 AC-228 NOT ESTA B t mit of De sed upon a.Nominal Lover Li b.Mean and range ba THRASHER FARM 700 IIILES ENE LOONEY FARM 5075 MILES CNE LOONEY FARM 5 75 MILES EtlE LOONEY FARM 5~75 HILCS ENE THRASHER FARM-7~0 MILES.CNE BITTIilG FARM 4~5 MILES ENE SITTING FAR)I 4~5 MILES ENE BITTING FARM 4~5 HILES ENC BROOKS FARM 700 HILES tRICV THRASHER FARH 7~0 HILES Ct(E SITTING FARM 4~5 MILES ENE SITTING FARI'~5 H ILES ENE LH1 BF tlORTHVEST le0 NILE N SITTING FARH 4eS MILES ENE LH1 SF NORTHVEST 1~0 NILE N BROOKS FARM 700 MILES NNV LOONEY FARM 5075 MILES ENE LHI SF NORTHVEST 1~0 NILE LN1 BF NORTHVEST 1~0 HILE N able 3.Fraction of detectable 5/21)2e92 1?I 21)5~49 3/21)4e61 6/21)2014=2/21)1 05.4 14/21)0'2 10/21)4~46 18/21)10~28 21/21)25098 21)0~10 1/71)0.02 9/21)0'2 1/21)0'3 19/21)0041 20/21)0~72 3/21)0~14 21/21)15063 16/21)0~29 18/21)0~48 1~93(1021-1.56(0023-3'0(1~43-F 25(0 22-1~28(1001-0016(0007 1'6(0~17-2'4(0006-10~40(2000-0 F 08(0~06-F 02(0~02-0035(0~14-0'3(0033-0020(0~Sl-y 1818(0~03-0'9(0~06-5'5(1012-0 F 08(0~00-0023(0007-(LU))as d ection escribed in T detectable measurements only..2'2(2~92-2060C 0~41-4061 (4061-1053(1 53-1~54(1054-0032(0032 3e95(3~95-4038(0~39-17086(2~88-0~10(0~10-0~02(0~02-0~49(0~49-0~33(0~33-0 27(0016-0'2(0~72-0014(0~14-7017(1~12-0029(0~29-0'6(0~36-1/4)2'2 2/4)4'0 1/4)4'1 1/4)1053 1/4)1054 1/2)0032 1/2)3095 2/2)8036-4/4)22 F 06 1/4)0'0 1/2)0 02 1/2)0'9 1/I)~0033 2/2)0038 1/1)0072 1/4)0'4 4/,4)13061 1/1)0'9 1/1)0 36 1 93(4/17)1016-2'6 1'9C 13/17)0~30-5'5 2'1(1/17)2'1-2'1 1~39(4/17)1010-1~65 1~ll(2/17)0'9-1034 0'1(7/17)0'6 0~40 1~90(8/17)0'0-4'1 2065(13/17)0 F 06-9'6 11'TC 17/17)2'3-28'5 0~10(4/17)0 F 08-0'2 17 VALUES<LLO 0'0(10/1?)0011-0'064 17 VALUES<LLD, 0'1(0010-0017(0~'04-0 F 07(0~03-5 96(2~29-0~05(0~01-F 17(0~02-12/17)0~50 14/17)0'3 2/17)F 11 17/17)14'0 9/17)0'6 14 I 17)0~52 is indicated in paientlieses (p).measurements of specified locations TABLE 12 RADIOACTIVITY IN SOIL PCI/G-0'37 BD/G (DRY INEIGHT)NAHE OF FACILITY QRGV)JS FERRY LOC A TI ON OF F AC (L I T Y L I YES TONr ALAnAYA DOCKET tJO~50 259~26~0296 REPORTING PERIOD~19 I TYPE AtJD TOTAL NUl'BE4 OF ANALYSIS PERFORMED GAYHA (GELI)11 LOVER LIMIT OF DETECT ION (L D)ALL I'NDI CATDR LOCA TI OIJS YEAN (()RANGE NAYs HEAN ([)C~ISTRMC~RMII CIR I:TICII~RRNR CotJTROL LOCAT IGNIS MEAN (f)RANGE NUMBER OF NONROUTINE REPORTED~RISC~RIM MTS CE-141 CC-144 RU-1D3 CS-137 Zo-95 NOT ESTAB 0~030 ti'8-95 K-40 BI-214 BI-212 Pf'.-214 PB-212 RA-226 RA-223 I)E-7 TL-208 AC-228 PA-234M 0~050 0'50 0'50 DE 020 NOT ESTAB SR 89 11 SR 90 11 Lower ranoe a.Ito b.Mea minal n and 0'30 0006(1/o)0'6-0~06 0'60 0013(4/9)0 F 08-0~24 0002(4/9)0032-3'3 0'20 De55(9/9)0~10-F 82 0-06(8/0 F 04 Dell 0~010 0014(9/9)0006-0'5 0'50 5042(9/9)'090-F 13 1 01(9/9)C~51-1~40 00100 0 66(9/9)0029-0086 1 08(9/9)0 F 58-F 46 NOT ESTAP 1~08(9/9)0059-1~43 1~16(9/9)De51-2'3 NOT ESTAB 36(4/9>0'9 0~46 0 F 160 0'4(>>2/9)0'1-0~26 0'8(9/9)0~18-0 F 48 0~060 1 12(9/9)0'2-1~46 3'50(1/'9)3050-3050 I~500 9 VALUES<LLD AYAI.YSIS PERFORMED De300 9 VALUES<LLD ANALYSIS PERFORHED Limit of Detection (LLD)as described in based upon detectable measurements only LH2 BF NOPT4 C 9 MILE NNC ROGERS VILLC~AL 13~8 MILES NV LH1 BF NORTHVEST 100 MILE tJ ROGERSVII.LCC 13~8 MILES tJV POGERSVILLEt AL 13 8 MILES WV ROGERS VILLE'L 1308 MILES NV LHR BF TRAILER P 107 KILCS tJNV LH2 BF NORTH 009 HI LE NtJE DECATUR'L 8~2 MILES SSC LH2 BF NOPTH 0 9 MILE NtJE DECATUR'L 8't(ILES SSE ATHCNSc AL 10'YIILCS NE LKc BF TRAILEP P 1~7 MILE;S JJNV LHz BF NORTHEAST 1~0 HILC FNE LH1 BF NORTHVEST 1~0 t(I LE ti DECATUR'I.

8~2 HILES SSE LK2 BF NORTH 0~9 HI LF Nt(E o.oe(0~Ce-0~24(0~24-0~03(0~63-1~82(1082-0~11(0~11-0~35(0 035-R 7 13(7~13-F 40(1~40-O086(0~86-1~46(1046-F 43(1~43-F 43(2~43-0 F 46(0046-0~26(0~26-0 F 48(0~48-I~46(1~46-F 50(3~50-I/1)0~36 I/I)0~24 1/1>0003 1/1)I~82 1/1)F 11 1/I)-:0 35 1/I)7'3 1/1)F 40 1/1)0 F 86 1/1)I~46 1/I)1043 1/I)2'1/I>0~46 1/1)0'6 1/I)o.48 1/1)1~46 I/1>3'0 2 VALUCS<LLD 0~10(2/2)0008-0~12 0'3(2/2)0~02-0'3 0'6(2/2)0~64-1028 0'B(2/2)G~04-0 12 0'R(2/2)0~09-0019 4'7(2/2)4097-4098 D090(2/2)0~78-F 02 0'6(2/2)0034-0~58 0092(2/2)0081-1~04 0'4(2/')0'6-1~03 0'0(2/2)0~78-F 02 2 VALUES<LLD 0'5(2/2)0019-0~30 0'3(2/2)0031-0~36 DE 97(2/2)0'0-1~05 4'9(I/2)4'9-4'9 2 VALUES<LLD 2 VALUFS<I.LD Table 3.Fraction of detectabl e measurements of specified locations is indicated in parentheses (p).

TABLE 13 NAME.OF F"CILITY BROl'NS FERRY LOCATION OF FACILITY I lr~STOgr RADIOACTIVITY IN QELL)I'ATER PCI/L-ON037 BQ/L DOCKET NON~l~~oa26~0 AL/BAHA REPORTING PERIOD~>~I YPE ANO TOTAL NUMBER OF ANALYSIS GAMMA (NAI)I CS LOVER LIMIT OF OETECTIONa ALL INDICATOR LOCATIONS XE/N (F)b RANGE b 12 VALUES<LLO ANALYSIS PERFORMED~LO IITION HITH HIOH'SI LLI'U'L MCRII R(A ROE MEAN (F)b~ISTANC II;I OIRgCTIOR~R4N R CON TROI LOCATIONS MEAN ()b R~IN 7 VALUES<LLD NUNBER OF NONROUT INE REPORTED ASUR~~HTS GAMMA (GEL I)7 K-40 NOT ESTAB 1 VALUES<LLD BI-214 NOT ESTAB VALUES<LLD PB-214 NOT ESTAB 1 VALUES<LLD PB-212, NOT ESTAB 1 VALUES<LLD TRITIUM 330LN 00 0 4 VALUES<LLD 8 ANALYSIS PERFORNED 99 F 84(3/6)86~85-115'0 28 F 00(1/6)28 F 00-28'G 12'9(2/6)7~42-17'6 6 F 48(1/6)6'8 6N48 4 VALUES<LLO a.Nominal Lover Limit of Detection (Lu))as described in Table 3.b.Mean and range based upon detectable measurements only.Praction of detectable measurements of specified locations is indicated in parentheses (p).

TABLE, I4 RAO IOACTI V IT Y I ti PUBL IC)JAT ER SUPPLY PCI/L 0~C37 BQ/L TYPE.AND TOTAL NUMBER OF ANALYSIS P f R~FR~MF GROSS BETA 85 GAHHA (tJAI)70 LO)RER L IH IT OF DETECT I 0'J a (Q~L)2'00 ALL INDICATOR LOCATIOtJS IJEAN (F)b P,AN~Gb 3%96(61/72)2%46-14 F 70 61 VALUES<LLO ANALYSIS PERFORMED NAHE OF FACILITY PROM)JS F/RRY LOCATION OF FACILITY QIH~SYON~r DOCKET NO~-2<9 60 296 REPORTING PERIOD~~8 CONTROL LOCAT I OQS HEAN (F)-~R4 EO 3%20(11/13)2 50-4 08 ALABAMA 9 VALUES<LLO QQQATIOh NITH HIGHEST At(NUAL MEAN tJAHE HEAN (F)b O~ISTANC ANO STRICTION RIINOEO CHAMPION PAPER 4~11C 44/46)TRJ'82'2 46>>14~70 NUMBER OF NONROUTI WE REPORTED~HAS~R~EN TS B I-214 PB-214 PB-212 TL-208 SR 89 SR 90 TRIT IUH NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB 10%000 16 2 F 000 16 330 000 16 GAHHA CGBLI)15 K 40 JJOT ESTAB 74 F 11(2/11)72'9-75 F 73 24%80(8/11)12 F 00-43 F 03 15%03(4/11)llew lb 23'3 11%90(1/11)11%90-11%90 11 VALUES<LLD 12 VALUES<LLO ANALYSIS PFRFORHEO 3'5(1/12)3%25-3'5 369%21(1/12)369'1-369'1 CHAMP IOtJ PAPER TRH 282'SHEFF I E LD~AL ROB TRH 254 3 CHAHPIOtJ PAPER TRH 282'SHEFF IELDi AL ROB TRJ'.254%3 74 F 11(72~49-28%91(28%91-16'3(12 52-11'0(11%90-~2/8)7S~73 I/1)28'1 3/8)23'3 1/..1)11%90 SHEFFIELO+AL ROB 3'5(, 1/.4)TRH 254%3 3'5-3%25 CHAHPION PAPER 369~21('/--4)TRK 282 6 369 21-369'1 101%00(I/4)101 F 00 101 F 00'17%78(2/4)13 60-21%95 15'2(2/lS%68-15'5 16 18(21 4)13%13-19'2-5 F 84(I/4)5%84-5'4 4 VALUES<LLO 4 VALUES<LLD 376 F 59(1/4)376 F 59-376'9 a.Nominal Lower Limit of Detection (LLD)as described in Table 3.b.Mean and range based upon detectable measurements only.Fraction of detectable measurements of specified locations is indicated in parentheses (F).

31 Table 15 ENVIRONMENTAL GAMMA RADIATION LEVELS Average External Gamma Radiation Levels at Various Distances from Browns Ferry Nuclear Plant for Each Quarter-1981 mR/Quarter Distance miles Avera e External Gamma Radiation Levels b 4th uarter 3rd uarter 0-1 1"2 2-4 4-6>6 18.8+1.2 21.7+2.0 17.1+1.2 17.3+2.2 16~5+1.",2 15.6+1.8 16.6+1.1 17.0+1.6 16.5+2.2 16.8+2.7 21.0+1.6 16.7+3.2 16.2+3.3 17.1+2.2 20.0+1.5 20.0+5.0 16.5+1.7 16.6+1~3 15.9+3.5 16.6+2.3 Average, 0-2 miles (Onsite)18.4+1'20.6+2.8 19.9+2.7 20.1+2.1 Average,>2 miles (Offsite)16.5+1.5 16.7+2.0 16.6+2.8 16.6+1.7 a.Data normalized to one quarter (2190 hours0.0253 days <br />0.608 hours <br />0.00362 weeks <br />8.33295e-4 months <br />).b.All.averages reported+la (68 percent confidence level).

.TAPLE 16 RADIOACTIVITY IN FOOD.CROPS NAHE OF F/CILITY/Roar>S FLURRY LOCATION OF FACELESS~IN STONE PCI/KG 0~037 BQ/KG (MET I(EIGHT)AI ABAHA SOCKET NO~3~5.I"A'-TOG REPOPTIIRG PER IOD~PQ TYPE A)ID LOVER LIHI T ALL TCTAL NUMBER OF INDICATOR LOCATIONS OF AN ALYS IS DETECT IONa WEAN (F)trRFORV (LLO)RANGE LOCATTOII I'ITN NIGIIEST ANNIIIL MEAN'I A I!E V E AN (F~)CONTROL LOCATIONbs HEAN (P RAN E NUMBER OF NONROUTINE REPORTED~NEAR~AGENTS RADIOACTIVITY IN CABBAGE, GROSS (OETA 25 F 000 o I-'R14 PB-212'iOT EST AB NOT ESTAB 1 GAHwA (GELI)1 K 40 NOT ESTAB 1873 F 00(1873~00-13 F 40(13~40-15'5(15~75-1/1)1873 F 00 1/1)13 40 1/1)15 F 75 4286 86(1/1)4286'6-4286'6)IILES N MILES N HILLS N 4 H ILES tA 1873M OC(1873M 00-13~40(13~40-15'5(15N75-1/1)1873 F 00 1/I)13N40 1/1)15'5 4286'6('/1)')286N86-4286'6 RADIOACTIVITY IN CORN GROSS BETA 2 GAHVA (GELI)2 K 40 25 F 000 NOT ESTAB 4163'2(1/1)4163'2-4163 F 82 LH2 BF NORTH 0~9 NILE t(tiE 1964 F 00(1/1)LH2 BF'NORTH 1964 F 00-1964 F 00" 09ILE tiNE 4163~82(1/1)4163'2-4163'2 1964 F 00(I/1)1964 F 00-1964N00 399S~66(1/1)3995'6-3995'6 1932 F 00(1/1)1932 F 00-1932 F 00 RADIOACTIVITY Iti GREEN BEANS GROSS BETA 2 GAHHA (GELI)25 F 000 4874'3(1/1)4874'3-4874'3 2 H ILES NNM 4874'3(1/1)4874 F 83-4874'3 3251'4(1/1)-3251'4-3251'4 K-40 BI-214 PB-212 NOT FSTAB~NOT ESTAB NOT ESTAB N 2132 F 00(1/1)2132'C-2132 F 00 1 VALUES (LLD 6~89(1/1)6~89-6~89 2 I'L E S NNii 2 HILES NN)i 6~89(5~89-1/))6.89 2132 F 00(1/1)2132'C-2132 F 00 1682 F 00(1682~00-20.50(20~SG-29 58(29~58-1/1)1682 F 00 1/1)20 F 50 1/1)29 F 58 a.Nominal Lower Limit of Detection (LLD)as described in Table 3.b.Mean and range based'pon detectable measurements only.Fraction of detectable measurements of specified locations is indicated in parentheses (F).

NAH'F FACILITY BROVNS FERRY LOCATION OF FAC ILI TY~H~Tg1ti(, TABLE 16 (Contd)RADIOACTIVITY 1'OOD CROPS PCI/KG-0~037 EO/KG (NET VEIGHT)ALAQAHA REPORTI)MG PERIOD)o81 TYPE AND LONER LIHIT ALL TOTAL NUHBER OF INDICATOR LOCATIONS OF ANIALYSIS DETECTION<<EAN (F)b LOCAT TOM MATH HIGH~S~TA'UUAQ M~AM NAKE'EAN ($)ISTANCE AND OIR CTI ON PANGE CONTROL LOCATION)HEAN (f)RANGE NUHBER OF NONROUT INE REPORTED HEASUREPENTS RADIOACTIVITY IN PEACHES GROSS BETA 2 GAHHA (GELI)2 K-4 0 BI-214 PB-212 25 F 000 NOT ESTAB NOT ESTAB NOT ESTAB 1697M 00 t 1697~00-22'3(22~43-19'3(19~53-1/1)1697'O 1/1)22~43 1/1)19'3 3127'3(1/3127'3-3127'3 SHITH FARH 4~75)'.ILES K SHITH FARH 4~75 HILLIS SKITM FARM 4~75 MILES SMITH FAR>>4~75 H ILES 1697 F 00(1697~00-22'3(22~43-19'3(19~53-1/1)1597MOG I/1)22'3 1/I)19'3 3127 13(1/1)3127'3-31?7'3 2970~49(1/1)2970'9-2970'9 1252 F 00(1/1)125?F 00-125?~OG VALUES<LLD 1 VALUES<LLD RADIOACTIVITY IN POTATOES BI-214 PB-212 NOT ESTAB NOT ESTAB GROSS BETA 25 F 000 2 GAHHA (GEL I)2 K-40 NOT ESTAB 3201'O(3?01MO"-15~62(15~62-13'2(13~62-1/1)3201 F 00 1/1)15'2 1/I)13'2 H ILES NNL'H ILES NN I 2 HILES NNM 7112~16(I/I)2 MILES NNN 7112+16-7112 F 16 3201 F 00(3?01 00-15'2(15~62-13'2(13 62-1/1)3201 F 00 1/1)15'2 1/1)13'2 3473 F 00(1/1)3473 F 00-3473 F 00 1 VALUES<LLD 1 VALUES<LLD 7112~16(I/1)7721H34(1/1)-7112~16-7112HI6-7721~34-7721M34 a.Nominal Lower Limit of Detection (LLD)as described in Table 3.b.Mean and range based upon detectable measurements only.Praction of detectable measurements of specified locations is indicated in parentheses (P).

NANC GF FACILITY BRO'wtJS FERRY LOCATIOH OF FACILITY~~I~OOL TABLE 16 (Contd)RPDIOACTIVITY IM POOD CROPS PCI/KG-0 037 80/KG (MET MCIGIIT)DOCKET toO~50-259~260'96 6A A ABACA REPORTING PERIOD 19RI TYPE AND LOQER LIHIT ALL TOTAL NUNBER OF IHOICATOR LOCATTOHS LOCATIOH IIITH HIGH ST REROLL~HAH OF ANALYSIS DETECTION a NEAN (F)b.I;AIIS IICAO IRIS CONTROL LOCATIONS HEAN ([)RANGE NUHBER OF NONROUT INE REPORTED H SUR H TS RADIOACTIVITY IN TOHATOES GROSS BETA 2 GANNA (GCLI)2 K 4G PB-212 NOT ESTAB NOT ESTAB 2513'0(1/1)2513 F 00-2513 F 00 11'5(I/I)ii+15-, llH15 BROOKS FAFI.7~0 NILES NNI BROOKS FARtl 7a0 NILE S NNls 2513 F 00(1/1)2513oQO-2513 F 00 11 F15(I/1)11H15-llew 15 2381 F 00(1/1)2381 F 00-2381 F 00 1 VALUES CLLO 25 000 5130 21(I/1)BROOKS FARM 5130'1(1/1)5669 17(1/1)5130~21-5130.21-7~0 MILES NN)t 5130~21-5130~21 5669~17-5669~17 RADIOACTIVITY IN TURNIP GREENS GROSS BETA 2 GAHHA (GELI)2 K-40 BI-214 PD-214 PB-212 BE-7 25a000 NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB 2262 F 00(2262~00-22'3(22~93-13'3(13~53-11'2(11~42-194'0(194~40-1/1)2262 F 00 1/I)?2'3 1/1)13H53 1/1)11~42 1/1)194'0 4 N ILES N NILES tt 4 NILCS N ANILCS N HILES N 5500 16(1/1)4 MILES N 5500 F 16-5500~16 2?62 00(1/ll 2262 00 2262 F 00 22'3(1/1)'2'3-22'3 13'3(1/1)13'3-13'3 11'2(1/I)lle42-llew 42 194H40(1/I)194 F 40-194'0 2980HGG(1/1)2980 00-2980 00 37'4(1/I)37'4-37'4 1 VALUES o:LLO 26H21(I/I)26'1-26+21 1 VALUES<LLO 5500'6(1/1)5969e01(I/1)5500'6-5500'6 5969~01-5969H01 a.)Ioafnal Lower LfrTft of Detectfon (LLD)as described in Table 3.b.Mean and range based upon detectable sTeasurenents only.Fraction of detectable neasurements of specified locations is indicated in parentheses (p),~

TABLE 17 NAME OF FACILITY BROVNS FERRY LOCATION OF FlCILI'IY~III STONE RADIOACTIVITY IN SOYBE ANS PCI/G-6~037 80/G (CRY VEIGHT)~AARA)(A DOCKET NO~50-259 260 296 R POllT INC PERIOD~IS BI-214 PB-214 BE-7 AC-228 hOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB TYPE ANO LOVER LIMIT TOTAL NUt(BER OF OF ANALYSIS DETECTION a PER~FRM D ILLOI GROSS BETA 0~200 2 GAMMA CGELI)2 K-40 NOT ESTAB 15'4(14070-0'3(0003-0'5(0'4 0020(~0.20-0011 (0~11 2/2)16077 1/2)0'3 2/2)0'6 1/2)0'0 I/2)0'1 ALL It)DICATOR LOCATIONS=29'0-29'5 LM2 BF NORTH 0'MilLE NNE 29'3(29040-2/2)2o065 LM2 BF hORTH 009 MILE NNE Lt(2 BF hORTH 009 MILE NNE LiM2 BF NORTH 009 MILE NNE LM2 BF NORTH 0 9 MILE NNE LM2 BF NORTH 009 MILE iNNE 15074(14070-0403(0~03-0'5(0~04-0'0('0~20-F 11(0011 2/2)16'7 1/2)0~03 2/?)0 F 06 1/2)0'0 1/2)0411~LO IITIDH NITH H1DHfST AIMDAL MEAN NAIIE IIEIIN IF ID ISTA.MC ARD R TION~RA COt(TROL LOCAT I.ONS MEAN (F)b RA G b NUMBER OF NONROUTINE REPORTED~MASU~RM~N TS a.Nominal Lower Limit of Detection (LLD)as described in Table 3.b.)(can and range based upon detectable measurements only.Fraction of detectable measurements of specified locations is indicated in parentheses (F).~'P TALLE 18 RADIOACTIVITY It>POULTRY PCI/t(G-OH037 BO/KG (t'ET MEIGMT)Nht(E OF FACILITY BROMNS FERRY LOCATION OF FACILITY LINESTOtlE

~ALII'AHA REPORT ING PER IOD~98 TYPE AtoO TOTAL t;Uo(BER OF ANALYSIS~PR P 0 R I'.I GROSS BETA 2 GA)(t(A (GELI)2 K 40 8 I-214 o8-214 PB-212 NOT ESTAB NOT.ESTAB NOT ESTAB NOT ESTAB 2412H 00 (1/1)2412H00-2412 F 05 I VALUES<LLD 1 VALUES<LLD I VALUES<LLD LOMER LIMIT ALL OF INDICATOR LOCATIONS OETEC T ION a YEAN (F)b (LLO)RAN~25 000 4972~66(I/I)49T2~66-4972~66.Lt(5 BF DAVIS F 2 o5 MILES MS)t 2412~00(1/I l 2412 F 00-2412 F 00~ICATION III TH HIGH RT ANHUA~LII AR NAME t(EAtt (F)b LNS BF DAVIS F 4972~66(I/I)-2H5 MILES)tS)R 4972~66-4972'6 2137 F 00(2137 F 00 19~56(19~56-18 38(18~38-10'6(10 86-1/1)2137 F 00 I/I)19~56 1/I)18'8 1/1)10 86 CONTROL LOCATIONS ttEAN (F)b, A b 6458'6(1/I)6458'6-6458'6 NUNBER OF NONROUTINE REPORTED TS a.Nominal Lmrer Limit of Detection (LLD)as.described in Table 3.b.Mean end range based upon detectable measurements only.Fraction of detectable measurements of specified locations is indicated TA in parentheses'(F).

=.

Figure 6 tO 0 0 v<<0 4J Ql C LI 5e Ch 0 4J 0 jj 0 0 0 Q Preoperational Phase Operational Phase<<5 ,?L ANNIAL AVERAGE 6ROSS BETA kl'IVITY I N ERI%1%MATER SUPPLIES HROW%FERRY itLLEAR RAhT Average: Preoperational Phase<<k-<<L IL LL II jL.<<I-I j-,j I<<'I t.4'.19 8 19 9 19 0 1 1 19 2 19 3P 19 30 1 4 1 5 19 6 1 7-19 8 1 9 19 0 1 1 38 Figure 7 0 tr ec 1 Rod I at Ion Levels Browns ferry Nuclear Plant 22 I O C.g 18 C7 6 Onsi te I I't i o I'l/!o'I~Of fsi te 9 il t t 1 1 I t i'1 p r", I'~O 12 1976 1977 1978 1979 1988 1 981 Figure 8 22 Otrect Rodiation Levels Browns ferry Nuclear Plant I-Quarter Hovtng Average Q C.o 18 8 l7 6 16 Onsite p" r'o.A'P/0 Offstte 1976 1977 1978 1979 , 1988 1981 Figure 9 39 Otr ect Radtot ion Levels Mat ts Bar Nucleor Plant C.h C.0 18 Ct Ct: C Onstte Offsi tee 9"w I (/I/I Fi I't I I I p../l 12 1978 1977 1978 1979'1988 1981 Figure 10 2%22 Oirect Radiation Levels Motts Bor Nucleor Plant'I-Quarter Moving Average 0 t.0 18 a e Onstte/b.m.~/~~.W Offstte 12)978 1977 1978'979 1988 1981 41 Reservoir Monitorin Samples are collected from the Tennessee River as detailed in table 19.Samples collected for radiological analysis include plankton from three of these cross sections and bottom fauna and sediment from four cross sections.The locations of these cross sections are shown on the accompanying map (figure ll)and conform to sediment ranges established and surveyed by TVA.Water Water samples'are collected automatically by sequential type sampling devices at three cross sections and composite samples analyzed monthly for gamma-emitting radionuclides.

Further composites are made quarterly for strontium and tritium analyses.Xn addition to these required samples, grab samples were also collected monthly from the vicinity of the plant discharge to the Tennessee River, and at a point on the Elk River, and analyzed for gross beta, gamma-emitting radionuclides, and strontium.

Results are displayed in table 20.Figure 12 presents a plot of the gross beta activity in surface water from 1968 through 1981.No gross beta measurements were made in surface water samples in 1978.The levels reported are consistent with gross beta levels measured in surEace water samples taken from the Tennessee River in preoperational monitoring programs conducted by TVA at other sites.Fish Radiological monitoring for fish is accomplished by analysis of composite samples of adult fish taken from each of three contiguous

'reser-voirs--Wilson, Wheeler, and Guntersville.

No permanent, sampling stations have been established within each reservoir; this reElects the movement of fish species within reservoirs as determined by TVA data from the BFN preoperational monitoring program.Two species, white crappie and smallmouth buffalo, are collected representing both commercial and game species.Sufficient fish are collected in each reservoir to yield 250 to 300 grams oven-dry weight for analytical purposes.All samples are collected semiannually and analyzed for gamma-emitting radionuclides.

The composite samples contain approximately the same quantity of flesh from each fish.For each composite a subsample of material is drawn for counting..

Results are given in tables 21,, 22, and 23.Plankton As indicated in table 19, net plankton (all phytoplankton and zoo-plankton caught with a 100 p mesh net)is collected for radiological analyses at each of three stations by vertical tows with a 1/2-metei 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, all samples containe'd 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 19.Results are shown in table 24.Bottom Fauna The flesh and shells of Asiatic clams collected semiannually from the cross sections at four stations (table 19)are analyzed for gamma-emitting radionuclides.

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

A 50-gram (wet weight)sample provides sufficient activity for counting.During this reporting period, one sample of clam flesh contained insufficient volume for analysis.Results are given in tables 25 and 26.

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

)River/river mile Zooplankton, chlorophyll, Benthic phytoplankton fauna Sediment Pish (co8ecfe8 mlnNly)Tennessee 277.9 Tennessee 285'X Tennessee 288.7 X Tennessee 291.7 Tennessee 293.5 Tennessee 293.7 (discharge area)K Tennessee 305.0 (Control)Tennessee 307.5 (Control)X X Elk 20.5 (Control)a.Gill net and/or electroshocker will be used for collection.

from Guntersville, Wheeler, and Wilson-Reservoirs.

b.Automatic sampler.c.Grab sample.Samples of fish are collected TABt.E 20 RA310ACTIVITY It,'URFACE"ATER TOTAL PCI/L-0'37 BQ/L NAHE OF FACILITY BR))ONS FERRY LOCATION OF FACILITY~~HQ~Ottg DOCKET KO~55-259 2~65 296 REoORT It(G PERIOD~1 T YPE A'iD TOTAL t(UHBER OF ANALYSIS PER F~OE(H 0 GROSS BETA 32 GAHHA (NAI)45 LOMER LIHIT OF DCTCCTIONa (LLD)2'00 ALL INDICATOR LOCATIONS HEAR (F)b R ANGE b 3'3(14/17)2'3-F 16 27 VALVES (LLD ANALYSIS PERFORHE.D LOCATIOt'I TH HIGHEST ANNUAL HQAN NAHL HEAN 4[)b 0 IS I A NCE At'P QI RECT I Oti RANGE TRH 293'3'6(2/2)3'0-4'2 CONTROL LOCATIONS HEAN (F)RANGEb 5'7(12/15)2'9-9'8 18 VALUES (LLD NUHBER OF NONROUTINE REPORTED~ll RSOR IIERT.BI-214 PB-214 PB-212 SR 89 SR 90 TR IT IUH NOT ESTAB NOT ESTAB NOT ESTAB 10 F 000 2 F 000 330 F 000 GAHHA (GELI)20 K-4 0 NOT ESTAB 105'0(5/12)51 F 52-159'0 15'9(5/12)4'6-23'7 26 F 00(1/12)26 F 00-26 F 00 15525(3/12)12'3-17'2 20 VALVES (LLD ANAL YS IS P ERFO RHEO 2'1(1/20)2'1" F 81 372511(2/12)364 F 86 379'5 TRH 293'BFN DISCHARGE TRH 285'TRH 293'BFti DISCHARGE TRu 285~2 TRH 293'BFIN D I SCHARGC TRH 293'139 45 (119 10-18'0(18~14-26 F 00(26500-17 F 62(17~62-2/3)159 F 80 2/3)19 F 06 1/3)26 00 1/3)17'2 2 F 81(1/12)2 81-2'1 379535(1/4)379~35-379'5 96'3(2/8)74 F 85-118'0 31'4(6/8)5500-83~65-27'4(4/8)10'4-55'9.13 F 83(3/8)8'2-22'1 16 VALUES (LLD F 07(1/16)2507-2'7 8 VALUES (LLD I a.Hominal Lower Limit of Detection (LLD)as described in Table 3.b.Yuan and range based upon detectable measurements only.Fraction of detectable ueasureuents of specified locations is indicated in parentheses (F).

T>BLE 21 RADIOACTIVITY I)G'HITE CRAPPIE (FLESH)PCI/G-0~037 BO/G ('DRY MEIGHT)NAME OF F AC ILI TY QRRM~NjERRY LOCATION OF FACILITY LIYESTONE DOCKET NO~50-25%~0 R PORTING PERIOD 19IRI TYPE AND TOTAL NUMBER OF ANALYSIS GROSS BETA ES GAHHA (GEL I)6 CS-137 K-40 BI-214 PB-214 PB-212 LOMER L I HIT OF DETECT ION a CLLD)Oo1 00 0'20 NOT ESTAB 0'20 NOT ESTAB NOT ESTAB ON12(0'9 14'5(12~72-0~07(0005-Oo0?(-0~06-0'2(0~02-4/4)0~14 4/4)-15~63 2/4)0'9 2/4)0 F 07 1/4)0'2 ALL INDICATOR LOCATIONS PEAN (F)b RANGE b 35N 18(4/4)33~04-37~16 MILSON RESERVOIR TRH 259-27c MILSON RESERVOIR TRH 259-275 MHEELER RES TRH 275-349 MILSON RESERVOIR TRH 259-275 MHEELER RES TRH 275'-349 0~13(0~13-15 20(1,4~77-0'9(0~09-0 F 07(0~07-0'2C 0 02-2/2)0'3 2/2)15'3 1/2)0~09 1/2)0+0-7 1/2)Oo02 DOCRTIGP~III IN N NEST~N~iNU D~NRN NAPE HEAN CF)b MILSON RESERVOIR 35'6(2/2)TRY 259-275 34'8-35a54 CONTROL LOCATIONS HEAN (F)R~N~b 34 F 87(2/2)33~03-36 72 F 14(2/2)0'9-F 18 17 F 50(2/2)15'9 19'1 0 F 06(1/2)0'6-ON06 2 VALUES (LLD 0~02(1/2)0~02-0~02 NUHBER OF NONROUTINE REPORTED~SIDDUR~NUTS a.Nominal Lover Limit of Detection (LLD)as described in Table 3.b.Ncaa and range based upon detectable measureaeats only.Fraction of detectable neasureaeats of specified locations is indicated in parentheses (F).

TA)LE 22 RADIO~C~IVITY IN SHALLHOUTH BUFFALO (FLESH)PCI/G-0~037 BO/G (IORY'dC IGHT)NAKE OF FiECILITY BPOMNS FLURRY LOCATION OF FACILITY LIHESTONC ALABAHA REPORT 1RG PERTOO~OGI TYPE ANO T OT Ai.NUK DER OF ANALYSIS~PFORII 0 GROSS aCta 6 GA~H4 (GELI)6 LOMER LI HI T ALL OF I'GDI CATOR LOCATIONS DETECTION HiEAN (F)b (LLO)R AN GCb 0~100 23>>07(4/4)19>>04-27>>20 DISTANCE ANO DIR CTION RANGLb QHECLEF RES 25'7(2/2)TRil 275-34o 24>>74-27'0 CONTROL LOCATIONS HEAR (F)b~RAGG 22 40(2/2)20 12-24'8 NUHBER OF NOiVROUTINE REPORTED~HASQ~RH NTS CS-137 K-40 8 I-214 PB-214 PB-212 TL-2Iii8 SP 89 SR 90 0>>920 NOT ESTAB 0'20 NOT ESTAB NOT ESTAB 0'20 0'00 0 F 100 0'5(4/4)0.04-0.06 9~64(4/4)7'6-11'6 0'6(3/4)0'5-0 F 08 0.06(2/0'5-0'7 0'4(1/4)0'4-0 F 04 0'2(1/4)0~02-0'2 1 VALVES<LLD ANALYSIS PERFORHED 1 VALUES<LLD ANALYSIS PERFORHED VHCELEP RES TRH 275-349 MHCELER RES TRH 275-349 LfILSON EEESERVOIR TRH 259-2?5@HEELER RES TRH 275-349 MHEELER RES TRH 275-349 iGHEELCR RCS TRK 275 349 0 F 05(0 04-11~03(10>>49-0>>08(0.~08-0~07(0~07-0'4(0~04-0>>02(0>>02-2/2)0 F 06 2/2)llew 56 1/2)0'8 1/2)0'7 1/2)0 F 04 I/2)0 F 02 0 F 08(2/2)0'7-0 F 08 8'2(2/2)F 00-10'4 F 14(1/2)0~14-0'4 0'9(1/2)0'9-0'9 2 VALUES<LLD 2 VALUES<LLD 0 VALUES<LLD'0 VALUES,<LLD a.Honinal Lower LimEit of Detection (LLD)as described in Table 3.b.Mean and range based upon detectable aeasurecEents only.Fraction of detectable rEeasurements of specified locations is indicated in parentheses (F).

TABLE RADIOACTIVITY IN SHALLVOUTH BUFFALO (MHOLE)PCI/G-GD 037 BC/G (DRY ME IGHT)NAME OF FACILITY BROMt)S FLURRY LOCATION OF FACILITY L~HESTOt(E ALA~AHA DOCKET KD 5~5-259"55 E9ET REPORTING PER I OD~aal TYPE AND TOTAL tJUHBER OF ANALYSIS~PIIF R~GROSS BETA 6 GAHHA (GELT)6 CS-137 K-40 BI-214 PB-214 PB-212 SR 89 SR 90 LOMER LIHIT OF DETECT IONa 0~100 0~020-NOT ESTAB 0'20 NOT ESTAB NOT ESTAB'0~500 0~100 ALL INDICATOR LOCATIONS HEAN (F)b RANGEb 19'2(4/4)18 F 57-19'5 0~03C 2/4)Oa03-0'3 8008(4/4)~6'3-9'1 0~06C 4/4)0'4-0+08 0'7(3/4)0504-0~12 0~03(2/4)0 03-0 F 03 1 VALUES<L'LD ANALYSIS PERFORMED 1 VALUES<LLO ANALYSIS PERFORHED MHEELER RES TRH 275-349 MKEELER RES TRH 275-349 MILSOt9 RESERVOIR TRH 259-275 MILSON RESERVOIR TRH 259-275 MHEELER RES TRH 275-349 0%03(0~03-8'0(7~50-0.06(0 04-0'2(0~12-0 03(0+03 1/2)0003 2/2)8'9 2/2)0 F 08 1/2)0512 I/2)0'3 NAME MEAN (F)o MHEELER RES 19'6(2/2)TRH 275-349 18957-19'5 CONTROL LOCATIONS HEAN (g)RANGE 20'4(2/2)14 97-26 91 0'4(1/2)0 F 04-0'4 7'8C 2/2)5910-9 67 0'6C 2/2)0'3-0 08 0'8(1/2)0 F 08-0~08 0'3(2/2)0 F 03 0'4 G VALUES<LLD 0 VALUES<LLD NUMBER OF NONROL'TINE REPORTED QQAQ~R~M)(TS a.)tominal Lover Limit of Detection (LLD)as described in Table 3.b.Mean and range based upon detectable measurements only.Fraction of detectable measurements of specified locations is indicated in parentheses (F).

TABLE NAHE OF FACILITY BRO)tNS FERRY LOCATION OF FACILITY LIHf STO~N RADIOACTIVITY IN SEOIHENT PCI/G-0'37 BO/G (DRY)(EIGHT)ALABAHA DOCKET t'0>>50-25~9 260+9$REPORT IttG PE'RIOO 1981 ALL It(0 I GATOR LOCATIONS MEAN (F)b~RR'TYPE At(0 TOTAL NUHBER OF ANALYSIS PQ~FgH jQ GAHHA (GEL I)8 CO-60c NUHBER OF NONROUTINE REPORTED~ASgf+~HN T S LOVER LIHIT OF OETECTIONa

~())CONTROL LOCATION)OCATION MITH HIGHEST ANhUAL HEAN NAHE HEAR (j)b IIRRRRR~C RR PIRQC7704~RRRR 0>>14 (5/6)0'7-0~21 0>>13(1/6)0~13-0'3 1~70(6/6)0 83-2'5 6 VALUES<LLD 0~20(0'9 0 13(F 13 2>>24(2'3 0~010 0 F 080 0'20 0~030 0~010 TRH 293 F 7 BFN DISCHARGE TRHR 293'BFN DISCHARGE TRH 277'8 2/2)0~21 1/2)0>>13 2/2)2'5 2 VALUES<LLO 2 VALUES<LLD CS-134 CS-137c ZR-95 NB-95 2/2)O>>31 1/2)0>>07 1/2)0'2 2/2)15 861/2)0'3 2/2)1~96 2/2)1~36 2/2)2'9 2/2)F 18 2/2)le96 2/2)0'7 2/21 0~78 2/2)2>>68 S<LLD 0'7(0~23-0>>07(0>>07 F 12(0>>12 6 VALUES<LLD 2/2)16>>42 1/2)0'6 2/2)1~53 1/2)1~33 2/2)1~71 2/2)2 F 05 2/2)1'3 1/2)0 F 50 2/2)0067 2/2)1~94 ESTAB 13>>64-0~03(0~03-1>>79(le61 1>>15(0~93-1~86(l>>64-2 F 00(1>>82 1~79(1>>61 0>>75(0>>62 0'3(0>>68-2'2(1>>95-2 VALVE TRH 293 7 BFN DISCHARGE TRH 277'8 81-214 BI-212 P B-214 NOT ESTAB RA-226 NOT ESTAB RA-223 NOT 0'20 AC-228 0'2(1/2)0 52-0~52 locations is indicated in parentheses.(P).

to the distribution reported<<the C~>>4 R h K>>40 NOT 14'0(6/6)TRH 288'8 15'5(-14'5(II 11~42-16~42".15~07-HN-54 0'10 0'5(2/6)0 F 06(0'4-0'6 0'6 0>>020 1'5(6/61 1'4(1~11-1>>53 1~35-0 100 1 06(5/6)TRH 288'8 l>>33(0>>68-1~33 1~33-ESTAB 1'0(6/6)TRH 277'8 1'8(1~18-1~71 1~66 PB-212 NOT 1~86(6/6)TRH 288'8 F 01(1~57-F 05 1~98-ESTAB 1 35(6/6)TRH 277'8 1~44(1~ll-1~53 1~35 0 49(2/6)TRH 293'0~50(0>>47-0'0 BFN DISCHARGE 0 F 50 TL-208)~57(6/6)TRH 277 98 0'5(0~44-0'7 0~62-0'60 1.72(6/6)TRH 277.98 1~89(le35-1>>94 1~83-SR P9 1~533 6 VALVES<LLO 8 ANALYSIS PERFORt".EO SR-90 0~300 6 VALUES<LLD a.Nominal Lowek Limit of Detection (LLD)as described in Table 3.b.Mean and range based upon detectable measurements only.Praction of detectable measurements of specified nd 3 Cs'etween indicator'and control locations'reported herein is comparable TABLE 25 RADIOACTIVITY IN CLAN FLESH PCI/G-0'37 BC/G'tORY VEIGHT)NAME OF FACILITY FROWNS FERRY LOCATION OF FACILITY L~IM STOL(ALABAMA OGCKET NO~5+~59 gggx?Si REPORT ING PERIOD)981 TYPE AND TOTAL hUHBER OF ANALYSIS GAMMA (GELI)7 LOVER LIHIT OF DETECT IOti~(Q,Q)ALL INDICATOR LOCATIOt)S ME N (F)b RANGFb LOCATION VI TM HIGHEST AtthUAL HEAN NAME MEAN (F)o CONTROL LOCATI Ot(S HEAN (F)b RAt'Gfb t UHBER OF tiONROUTINE REPORTED YQ~AS~RH N S K-40 BI-214~8-214 PB-212 TL-208 NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB 8~97(6~49-4~2.7 (lo70-4s59(I~10-12(I~02-0.40(Oo40-4/5)12'5 5/5)7~05 5/5)9~05 3/5)1~17 1/5)Os40 TRH 288'8 TRH 277'8 TRH 277'8 TRP 288~78 TRM 288'8 9 32(6 4o F 40(6~40-9e 05(9~05-1'7(1 17-0'0(0~40-2/2)12'5 1/1)6'0 1/1)F 05 I/2)i+17 1/2)0~40 17 F 11(1/2)17'1.17'l 2 72(2/2)2'2-3'2 4 71(2/2)l.F 80-7'3 0'0(I/2)0'0-0'0 2 VALUES<LLD a.Noninal Lower Linit of Detection (LLD)as described in Table 3.b.Mean and range based upon detectable neasurenents only.Fraction of detectable neasurenents of specified locations is indicated in parentheses (F).

TABLE 26 NAHE.OF F AC ILI I Y PROVNS FURR~LOCATION OF FACILITY LIMESTONE RADIOACTIVITY IN CLAM SHELL PCI/G-0~037 Bf/G (DRY):EI G)IT)ALABAHA DOCKET NO~~P$~9~0t7~RrPORTING PERIOD 1981 TYPE ANO TOTAL NUHBER OF ANAL YS IS GA""A (GELI)8 LOI'ER LIMIT ALL OF INDICATOR LOCATIONS DETECTION MEAN (F)b (LLD)RANGL LOCATION MITH HIGHEST ANNUA~HEAr'AME HE,AN (F)b DISTANCE AN~DIRECTION RANGP CONTROL LOCATIONS MEAN CF)RANGEb NUHBER OF NONROUTINE REPORTED K-4 0 81-214 91-212 PB-214 PB-212 RA-226 TL-208 AC-228 SR 89 SR 90 NOT ESTAB 0'50 0 F 100 0'50 NOT ESTAB 0'50 0'20 0'60 5 F 000 1 F 000 1~15(0~19-0 F 48(0~11-0'0(0%20-0'6(0~09-0'9(0~09-0'8(0 I?-0~08(0~05-0'1(0.28-6 VALU ANALYSIS P I~99(1~28-6/6)3'2 6/6)1%57 1/6)0~20 6/6)1~05 5/6)0%90 6/6)1~57 4/6)F 11 3/6)0'3 ES<LLD ERFORHED 6/6)2~70 TRH 277'8 TRH 2T7~98 TRH 293'BFN=DISCHARGE TRH 277'8 TRH 2T7~98 TRH 277'8 s TRH 293'BFN DISCHARGE TRH 288'8 TRH 293'BFN DISCHARGE 2'6(0~99-0'2(0%27-0'0(0%20-0~63(0%21 0~49(0%09-0 92(0~27-.0~10(0%09-0.32(0~32-2/2)92 2/2)1 57 1/2)0'0 2/2)1 05 2/2)-0.90 2/2)1~57 2/2)0~11 1/2)0'2 2%49(2/2)2'7-2 F 70 1~13(2/2)0%86-1~41 0%46(2/2)0'0-0 52 2 VALVES<LLD 0'6(2/2)0'2-0%50 0'5(2/2)0'7 0'4 0'6(2/2)0 F 40-0'2 0%13(2/2)F 11-0~14*o 0%53(1/2)0'3-0%53 2 VALUES<LLD 2'2(2/2)2'1 2'3 a.Nominal Lower Limit of Detection (LLD)as described in Table 3.b.Mean and range based upon detectable measurements only.Fraction of detectable measurements of specified locations is indicated in parentheses (F).

Figure 11 R ESERVOI R MONITORING NETWORK 51 Etk River N WHEELER DAIVl mile 274.90 rnite 277.98 Rogersville 0 rnite 282.6 mile 29l.76 Athens I-mi(e 285.2 B.F.NUCLEAR PLANT II Champion Paper Co.0 Cour tland ite28878 mite 293.50 mile 293.70 0 Decatur mile 305.0 mile 307.52 e-Automatic Sam ter Scale of Miles Figure l2 C o cl C kJ o 4J ll th 4 tf, o o 0 Q l Il'o 0 Q Preoperaclonal Phase 1 Operational Phase Oem AVERAGE 6ROSS IIETA ACTIVlTY 1N SURFACE HATER IRONS FERRY NUCLEAR PLANT Average: Preoperational Phase 1968 1969 1970 1971 1972 1973P 19730 1974 1975 1976 1977 1 78 1979 1980 1 81 53 ualit Control A quality control program has been established with the Alabama Department of Public Health Environmental Health Administration Laboratory and the Eastern Environmental Radiation Facility, Environmental Protection Agency, Montgomery, Alabama.Samples of air, water, milk, and vegetation collected around BFN are forwarded to these laboratories for analysis, and results are exchanged for comparison.

Data Anal sis 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 f'all within the limits, we will perform further analyses to determine if the difference is attributable to the nuclear plant.Conclusions A vast majority of the indicator station data was found to be within the distribution.

defined by the control station data.The data analysis software identified concentrations slightly exceeding the limits of the control station data for a small number of radionuclides in samples from indicator stations.Many of these values may be discounted because the error reported by the analysis program was greater than the calculated concentration.

The remaining isolated elevated concentrations may be the.result of fallout, fluctuations in the existing environment, computer program artifacts, or analytical errors.The same type of isolated high values occurred in the control station data and may be attributed to the same sources.Increased levels of radioactivity were observed in rainwater, air particulates, heavy particle fallout, and in vegetation in the winter and spring following the atmospheric nuclear weapons testing conducted by the Republic of China in mid-October 1980.This increase was seen in control stations as well as indicator stations.The primary radioisotopes identified in the atmospheric media were, Zr,~.Nb, I, Bi, and Ru.Dose estimates were made from concentrations of radioactivity found in samples of environmental media.Media sampled include, but are not limited to, air, milk, meat, vegetation, drinking water, and fish.Doses estimated for persons at the indicator locations were essentially identical to those determined for persons at control locations.

Greater than 99 percent of those doses were contributed by the naturally occurring radionuclide potassium-40, 54 and by strontium-90 and cesium-137 which are long-lived radioisotopes found in fallout from nuclear weapon testing.'t is concluded from the above analysis of the data and from the trend plots presented earlier that there were no measurable increases in environmental radioactivity attributable to the operation of BFN.

TENNESSEE VALLEY AUTHORITY MUSCLE SHOALS.ALABAMA 35660 River Oaks Building.i'~S May 5, 1982 U.S.Nuclear Regulatory Commission c/o Regional Administrator Region II Attention:

A.L.Cunningham Suite 3100, 101 Marietta Street Atlanta, GA 30303/~$9~C~~r~A.C)(3 C>The enclosed report No.TVA/OMS/OHS-82/7"Environmental Radioactivity Levels-Browns Ferry Nuclear Plant-Annual Report-1981," is furnished for your information and use.Very truly yours, R, B.Maxw ll, Chief Radiological Hygiene Branch Enclosure An Equal Opportunity Employer P l TENNESSEE VALLEY AUTHORITY CHATTANOOGA.

TENNESSEE 37401 400 Chestnut Street Tower II April 30, 1982 U.S.Nuclear Regulatory Commission Region II ATTN: James P.O'Reilly, Regional Administrator 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303

Dear Mr.O'Reilly:

Enclosed is a copy of the following report prepared by the Tennessee Valley Authority pertaining to environmental monitoring at the Browns Ferry Nuclear Plant: Environmental Radioactivity Levels, Browns Fet ry Nuclear Plant, Annual Report 1981 This monitoring program is specifically responsive to the recommendations and requests of the United States Fish and Wildlife Service.We understand that the Office of Nuclear Reactor Regulation will transmit five copies of the report to the Secretary of the Interior.Very truly yours, TENNESSEE VALLEY AUTHORITY L.M.Mi ls, Manager Nuclear Licensing Enclosure cc: Director of Nuclear Reactor Regulation (

Enclosure:

20)Attention:

Mr.Darrell G.Eisenhut, Director Division of Licensing U.S.Nuolear Regulatory'ommission Washington, DC 20555 Go>+~~~+&8 1(t An Equal Opportunity Employer-

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r.g~~J":,o r.~talvN QAg~'F'P.6)p~>;f~>fl/~9>l<<K fAlli~~+~~J~~"PQ","" no~~ri'd"~'" E ll-i RH-81-5-BF2 ENVIRONMENTAL RADIOACTIVITY LEVELS BROWNS FERRY NUCLEAR PLANT ANNUAL REPORT 1980 April 1981 OPr1CV~COrV El-F93 850O100voe SO>aalu PDR ADOCK 05000259 R PDR CONTENTS List of Tables.~~~~0 ili List of Figures.~~~~~o iv Introduction

~~~1 Atmospheric Monitoring

.Terrestrial Monitoring

.Reservoir Monitoring

" Quality Control.Data Analysis.~~~~~~~~~~~~~~~~~11 21 33 45 45 Conclusions.

~~~~~~~~~~~~~45

LIST OF TABLES Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table 6-7-8-9-10-11-12-13-14-.15-16-17-18-19-20-21-22-23-24-25-26-Table 3-Table 4-Table 5-le~ion pie so Environmental Radioactivity Sampling Schedu Atmospheric and Terrestrial Monitoring Stat Locations-Browns Ferry Nuclear Plant Detection Capabilities for Environmental Sam Analysis Results Obtained in Interlaboratory Compari Program.Maximum Permissible Concentrations for Nonoccupational Exposure Radioactivity in Air Filter.Radioactivity in Rainwater.

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

.Radioactivity in Soil.Radioactivity in Well Water.Radioactivity in Public Water Supply.Environmental Gamma Radiation Levels Radioactivity in Food Crops Radioactivity in Soybeans Radioactivity in Poultry Sampling Schedule-Reservoir Monitoring Radioactivity in Surface Water'adioactivity in White Crappie (Flesh).Radioactivity in Smallmouth Buffalo (Flesh)Radioactivity in Smallmouth Buffalo (Whole)Radioactivity in Sediment Radioactivity in Clam Flesh Radioactivity in Clam Shell'.~~~~4 5 6 8 16 17 18 19 20 23 24 25 26 27 28 29 31 32 35 37 38 39 40 41 42 43 LIST OF FIGURES Figure 1-Tennessee Valley Region.~~3 Figure 2-Atmospheric and Terrestrial Monitoring Network.13 Figure 3-Local Monitoring Stations~~~~14 Figure 4-Browns Ferry Nuclear Plant Site Monitoring Stations.....15 Figure 5-Reservoir Monitoring Network.36

ENVIRONMENTAL RADIOACTIVITY LEVELS BROWNS FERRY NUCLEAR PLANT ANNUAL REPORT 1980 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 Decatux, Alabama.The plant consists of three boiling water reactors;each unit is rated at 3,293 MWt and 1,098 MWe.Unit 1 achieved criticality on August 17, 1973, and began commercial operation on August 1, 1974.Unit 2 began commercial operation on March 1, 1975.However, a fire in the cable trays on March 22, 1975, forced the shutdown of both reactors.Units 1 and 2 resumed operation and Unit 3 began testing in August 1976.Unit 3 began commercial operation in January 1977.The preoperational environmental monitoring program established a baseline of data on the distribution of natural and manmade radioactivity in the environment near the plant site.However, seasonal, yearly, and random variations in the data were observed.In order to determine the potential increases in environmental radioactivity levels caused by the plant, comparisons were made between data for indicator stations (those near the plant)and control stations (those remote from the plant)in con)unction with comparisons with preoperational data.Staffs in the Division of Occupational Health and Safety, the.-=--Division of'Water Resources, and Resource Services, carried out the sampling program outlined in tables 1 and 19.Sampling locations are shown in figures 2, 3, 4, and 5, 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 Muscle Shoals, Alabama and Eastern Area'adiological 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 con)unction with Germanium Ge(Li)detection systems were used to analyze'he samples for-specific gamma-emitting radionuclides.

Samples of water, vegetation, air particulates, food crops, and charcoal ('specific analysis for I)are routinely counted with NaI(Tl)'detection systems.If significant concentrations of radio-isotopes are identified, or if the're is a reasonable expectation of increased radioactivity levels (such as during periods of increased" fallout), these samples are counted on the Ge(Li)system".Identifi-cation 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(T1).The data obtained by Ge(Li)detectors were resolved by the ND-4420 software.The detection capabilities for environmental sample analyses given as the nominal lower limits of detection (LLD)are listed in Table 3.Samples processed by NaX(T1)"gamma spectroscopy were analyzed for 13 specific gamma-emitting radionuclides and radionuclide combina-a tions.For these analyses, radionuclide combinations such as'u and Zr-Nb are analyzed as one radionuclide.

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

Many of the isotopes identified by Ge(Li)spectral analysis are naturally occurring or naturallv produced radioisotopes, such as Be" K Bi 4Bi Pb 214 226 t't t Pb<Ra, etc.LLD's for the analysis of the radionuclides listed below are given in Table 3B.LLD's for additional radionuclides identified by Ge(Li)analysis were calculated for each analysis and nominal values are listed in the appropriate data tables.In the instance where an LLD has not been established, an LLD value of zero was assumed.A notation in a table of" values<LLD" for an isotope with no established LLD does not imply a value less than 0;rather it indicates that the isotope was not identified in that specific group of samples.For each sample type, only the radionuclides for which values greater than the LLD were reported are listed in the data tables.TVA's Radioanalytical Laboratories participate in the Environ-mental 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 environ-mental monitoring program.Routine sample handling and analysis pro-cedures were employed in the evaluation of these samples.Gamma spectral analyses were performed using NaI detectors.

The EARL began processing samples in May 1980.The results received during calendar year 1980 are-shown in table 4.The+3@limits based on one measurement were divided by the square root of 3 to correct for triplicate determinations.

a The following radionuclides and radionuclide combinations are quantified by the ALPHA-M least-squares computer code: "'4Ce;Cr;I;103 106Ru;134Cs;"Cs;Zr-Nb;58Co;"Mn.65Zn..60Co;

" K;and 140Ba-La.

MEVPIRS//.\l CN\)~~~g PAOUCAH/M O.'.(,.5'+~@V~JACKSON+f LOUISVLLE I N D.EVANSVILLE TENNESSEE VALLEY REGlON 4 (TVA NUCLEAR LAN IT S L" W V A 80wUNG GREEN S C A R VOwENSSORO r'K E N T-U C K Y r (~M r..J r}I SPUR}PSN/}fM~~y/l f NASHVILL OAK RIOGEr I N g N E S S E~}/r I~le N (xz~(l 7->r t/8-I CHATTANOOGA~

~'Wr}I 8LN~+HUNTSVILLE f n J J f MUSCLE lg/M I SS.(SHOALS I N/(~r~I A L A 8 A M A G EORG I A LEGEND-HARTSVILLE NUCLEAR PLANT~-PHIPPS BEND NUCLEAR PLANT YiRRP-CLINCH RIVER BREEDER REACTOR-WATTS BAR NUCLEAR PLANT-SEQUOYAH NUCLEAR PLANT-BELLEFONTE NUCLEAR PLANT-BROWNS FERRY NUCLEAR PLANT-YELLOW CREEK NUCLEAR PLANT

~Table 1 ENVIRONMENTAL RADIOACTIVITY SAMPLING SCHEDULE Air Charcoal Rain-Heavy Particle River Well Public Aquatic Life dtatioa ioaaei ritter ritter ater Parle t soil~vetatf o Milk w ter rater rater aad aedia ot Foods Muscle Shoals W M M A Lawrenceburg W Roger sville W Athens Decatur M M,-A M M A M M A M M A Courtland W Site NW-1 Site N-2 Site NE-3 Site NW-4 W Site WSW-5 W Perm B Perm Bi M A M A M.A M M A Farm H Farm T Farm L Control Farms Onsite Well Wheeler Dam Elk River Tennessee River Champion Paper Co.Various Local Farms S A W-Weekly M-Monthly (every 4'eeks)~rterlya..-'S-Semiannually A-Annually e

Table 2 Sam le Station Atmospheric and Terrestrial Monitoring Station Locations Browns Ferry Nuclear Plant Approximate Distance and Direction from Plant LM-1 BF, Northwest LM-2 BF, North LM-3 BF, Northeast LM-4 LM-5 BF, Trailer Park BF, Davis Farm PM-1 BF, Rogersville, AL PM-2 BF, Athens, AL 1.0 Mile 0.9 Mile.1.0 Mile 1.7 Miles 2.5 Miles 13.8 Miles 10.9 Miles (1.6 kilometers)

N (1.4 kilometers)

NNE (1.6 kilometers)

NE (2.7 kilometers)

NNW (4.0 kilometers)

WSW (22.2 kilometers)

NW (17.5 kilometers)

NE PM-3 BF, Decatur (Trinity), AL 8.2 Miles (13.2 kilometers)

SSE RM-2 BF, Muscle Shoals, AL (Control)BF, Lawrenceburg, TN (Control)Farm S PM-4 BF, Courtland, AL 10.5 Miles 32.0 Miles (16.9 kilometers)

WSW (51.5 kilometers)

W 4.75 Miles (7.6 kilometers)

N 40.5 Miles (65.2 kilometers)

NNW Farm B 7.0 Miles (11.3 kilometers)

NNW Farm H Farm T Farm Bi Farm N (Control)Farm J (Control)Farm C (Control)Farm Ca (Control)3.75 Miles (6.0 kilometers)

N 7.0 Miles 4.5 Miles (11.3 kilometers)

ENE (7.2 kilometers)

ENE 27.0 Miles-, (43.4 kilometers)

NW 32.0 Miles, (51.5 kilometers)

N 32.0'iles (51.5 kilometers)

W 40.0 Miles (64.4 kilometers)

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

~C/Charcoal~C//Vegetation Fallout Water and grain 0//k~ci I:~C//d Soil and Sediment~c//.ar Pish, clam flesh, plankton,~Ci/~dr Foods, neat, Clan shells poultry, Milk~Ci/<<~dr pC1/k~gg~il Total a Gross o Cross 8 4H 444I"Sr 44S 0.005 0.01 0.005 0.001 0.02 0.05 0.4 2.0 2.4 330 10 2 0.01 0.05 0.20 0.25 0.05 0.35 0.70 1.5 0.3 0.1 0.1 0.5 0.1 0.7 0.7 5.0 1.0 1.5 25 40 8 0.5 10 2*All LLD values for isotopic separations are calculated by the method developed by Pasternack and Harley as described in HASL-300.Factors such as sample site, decay time, chemical yield, and counting efficiency nay vary for a given sample;these variations may change the LLD value for che given sample.The assunption is nade that all samples are analysed within one veek of che collection date.Conversion factors: 1 pCi~3.7 x 10 Bq;1 nCi~3.7 x 10 Bq.

Table 3 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS B.Canna Anal ses NOMINAL LOWER LIMIT OF DETECTION LLD Air particulates CL/o NaI*~Ce Li**Water Vegetation and milk and grain-~Ct/1.r~Ctl d NaI~Ge Li local~Ge Li Soil and sediment NCCL//de re NaI~Ge Li Clam flesh Fish and plankton N~CL/~ar~CL/dr Far~Ge LL Nar~Ge Lr Clan shells~CLI dr NaI~Ce Li Foodsk(tomatoes potatoes, etc.)Ci/vet Nal-C~eLi Meat and poultry~Ct/k Nal Ge(Li>1 6 1 N 1 Na s C e 166C 3 1Cr 1311 103~106R 106R 136Cs 1 33C"Zr-hq"Zr"Nb"Co 63zn 60C K Ba-La 1008 160La 0.03 G.02 0.07 0.03 0.01 0.01 0.04 0.03 0.01 0.02 0.01 0.01 0.01 0.01 0.01, 0.02 0.01 0.02 0.01 0.02 0.01 0.01 0.01 0.10 0.02 0.02 0.01 38 0.55 60 15 40 33 44 8 l.10 0.35 0.65 40 10 26 10 5 10 0.20 0.20 0.20 10 5 15 5 0.23 10 5 0.20 15 9 0.25 10.5 0.17 150 2.50 15 0.68 25 7 0.34 0.08 0.35 0.22 0.06 0.47 0.60 0.10 0.09 0.20 0.02 0.45 0.51 O.ll 0.33 0.12 0.08 0.06 0.12 0.02 0.12 0.03 0.01 0.20 0.01 0.15 0.01 0.23 0.02 0.11 0.01 0.90 0.15 0.07 0.02 0.35 0.06 0.60 0.10 0.20 0.02 0.45 O.ll 0.12 0.08 0.12 0.02 0.12 0.03 0.01 0.20 0.01 0.15 0.01 0.23 0.02 O.ll 0.01 0.90 0.15 0.07 0.02 0.35 0.56 0.07 0.74 0.48 0.08 0.15 0.07 0.07 0.08 0.17 0.08 0.30 0.10 0.20 0.15 0.23 0.11 0.90 0.15 0.03 0.Ol 0.01 0.01 0.02 0.01 0.07 0.02 0.35 0.06 0.60 0.10 0.20 0.02 0.45 0.11 0.12 0.08 0.12 0.02 0.12 38 60 15 40 10 10 10 15 10 15 10 150 15 90 33'4 200 8 50 150 40 26 40 5 40 40'10 5 5 55 5 40 9 70 5 30 400 50.25 7 4C 90 20 90 NO 15 20 15 15 15 20 15 50 15*The Nal(Tl)LLD values are calculated by the method developed by Pasternack and-Harley as described in HASL-300 and Nucl.Instr, Methods 91, 533-40 (1971)~These LLD values ate expected to vary depending on the activities of the components in the samples.These figures do not represent the LLD values achievable on a given'sample.

Water is counted in a 3.5-L Marinelli beaker.Vegetation, fish, soil, and sediment are counted in a 1-pint container as dty weight.The average dry veight is 120 grams for vegetation and 400-500 grams fot soil sediment and fish.Meat and poultry are counted in a 1-pint container as dry weight, then corrected to vet weight using an average moisture content of 70'.Average dry weight is 250 grams.Air particulates are counted in a veil crystal.The counting systen consists of a multichannel analyzer and either a 4" x 4" solid ot 4" x 5" well NaI(T1)crystal.The counting time is 4000 seconds.All calculations are petforned by the least-squares computer program ALPHA-M.The assumption is made that all samples are analyzed within one week of the collection.

date.+*The Ge(t,i)LLD values are calculated by the method developed by Pasternack and Harley as described in HASL-300.These LLD values ate expected to vary depending on the activities of the components in the samples.These figures do not represent the LLD values achievable on given samples.water is counted in either a 0.5-L or 3.5-L Matinelli beaker.Solid samples such as soil, sediment, and clam shells are counted in a 0,5-L Marinelli beaker as dry weight.The average dry weight is 400-500 grams.Air filters and very small volume samples are counted in pattie dishes centered on the detector cndcap.The counting system consists of a hq3-4420 nultichannel analyzer and either a 25ZN 14Z, 16K, ot 292 Ce(Li)detector.The counting tine is normally 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.All sPectral analysis is Performed using the software Provided with the ND-4420.The assumption is made that all samples ate analyzed vithin one veek-of the collection date.Conversion factor: 1 pCi 3.7 x 10 Bq.

Table 4 Results Obtained in Interlaboratory Comparison Program A.Air Fil.ter (pCi/filter)

Date 12/79 Gross Al ha EPA value TVA AVG.(+3o)WARL EARL 10+9 10 Gross Beta EPA value TVA AVG.(+3o)WARL EARL 29+9 33 Stontium-90 EPA value TVA AVG.(+3a)WARL EARL 9+2.6 ll Cesium-137 EPA value TVA AVG.(+3o)WARL EARL 10+9 10 3/80-Equipment malfunction at EPA 6/80 9/80 24+10 24+9 26 25 24 24 28+9 10+9 33 36 12 16 0 0 (1 8'+26 9 8 12+9-10+9 13 12 9 9 12/80 Results not received at this time B.Tritium.in Urine (pCi/1)Date 12/79 3/80 6/80 9/80 12/80 EPA VALUE (+3a)2060+599 2173+603 2500+610 1700+589 3150+624 TVA AVERAGE WARL EARL 2100 2300 1437 2007 1723 1693 3287 3576 Table 4 (Contd}Results Obtained in Interlaboratory Comparison Program C.Radiochemical Analyses of Water (pCi/1}Gross Al ha EPA value TVA AVG.Date (a3a)WARL EARL Gross Beta EPA value TVA AVG.(i3a)WARL EARL Strontium-89 Strontium-90 Tritium Todine-131 EPA value TVA AVG.EPA value TVA AVG.EPA value TVA AVG.EPA value TVA AVG.~3a wARL EARL (33a)wARL EARL~(e3a wARL EARL~33a wARL EARL 11/79 12+9 14 12/79 1/80 3M14 25 2/80 3/80 13i9 12 4/80 5/80 23t9 23 20 6/80 7/80 36il6 31 19 8/80 9/80 32+14 34 27 10/80 11/80 1619 16 20 12/80 27i9 45+9 22i9 14+9 38i9 2&9 13f9 27 47 25 16 18 44 41 26 24 16 24 10+9 98 20+2.6 238 2040+599 2128 1750f591 1920 5+9 24j9 27 23 1542.6 18 16 1210+570 1180 1223 3200+624 3207 3207 2240+606 2270 2213 3400j624 3363 4 6 12i2.6 13 11 2000i598 1947 1960 53x9 50 44i9 41 36R9 33 26" 22+10 21 19 Chromium-51 EPA value TVA Date~(A3a wARL Colbalt-60 D.AVG.EPA value TVA AVG.EARL (+3o)WARL EARL Gamma-Spectral Analysis of Water (pCi/1)Zinc-65 Ruthenium-106 Cesium-134 Cesium-137 EPA value TVA AVG.EPA value TVA AVG.EPA value TVA AVG.EPA value TVA AVG.~3a IIARL EARL~(A3a WARL EARL~e3a WARL EARL~3a WARL EARL 2/80 10li9 93 6/80 13i9 Op 10/80 86i9 74 11+9 ll 0 519 7 5>>90 16f5 14 15 25+9 23+9 25+9 31 51+9 33 1019 16 30+9 31 25 21 37+9 36k 40 11+9 15 10 1719 19 18 24 20 46i9 35 42 20+9 22 19 1219 12 13 Table 4 (Contd)Results Obtained in Interlaboratory Comparison Program E.Milk (pCi/1)Strontium-89 EPA value TVA AVG.Deca~33a WARL EARL Strontium-90 EPA value TVA AVG.~3tf WARL EARL Iodine-131 Cesium-137 Barium-140 Potassium EPA value TVA AVG.EPA value TVA AVG.EPA value TVA AVG.EPA value TVA AVG.~33a WARL EARL~33a WARL EARL~3a llARL EARL~3a llARL EARL 1/80 1019 4/80 10i9 7/80 55i9 10/80 23i9 ll 10 57 59 25 25 25+2.6 15f2.6 17+2.6 0 28 18 19 18 1<2 0.0140.2 33+9 0 lg f 9 0 23i 0 18 0 12 40+9 39 2819 30 35t9 34 21+9 22 0.01%0.2 0 35 0 22 0 0 0 0 0 0<15 16001139 1577 11901103 1117 1550j135 1593 1533 1620+140 1447 1473 F.Foods (pCi/kg, Wet Weight)11/79 73+9 3/80 7/80 94i9 11/80 gi9 71 113P 107P<10<10 2712.6 13+2.6 0 34 127i ll 127 Sample spoiled in transit 22 17P 54+9 47 49 3 3 34ilo 24 24 22i9 24 0.001 0 1511+132 1372 2719 27 27 0 0 0 2260+225 2737 2730 12+9 11 10 0<15<25'5204208 2560 2723 a.Western Area Radiological Laboratory, Muscle Shoals, Alabama.b.Eastern Area Radiological Laboratory, Vonore, Tennessee.

c.Not reported to EPA.d.Low value result of deficiencies in analytical procedure..

The procedure has been revised to correct these deficiencies.

e.Specific analysis for I to test the procedures used for the analysis of I in milk.f.Results not returned by EPA.g.Sr and Sr results reversed in report to EPA.h.Laboratory in start up mode: procedures being refined.i.Investigation of the sample and procedures produced no indication for the cause of the discrepancy.

Subsequent analyses have been satisfactory.

Below TVA LLD.k.Analysis of these isotopes by NaI produce greater variation because of (1)the abundance of the main energy peaks (2)the broad shape of the peak, (3)relatively high background in the peak area, and (4)interference from radon peaks in the peak area.m.Values for potassium reported as mg 6X'otassium per t of sample.n.Values for potassium reported as mg of potassium per kg of sample.p isc pane s in atro t um~~l~~s are believed to be due to (I)inhomogeneity of.the~ample ash and (2)magnificatio~

of'sli h n we g t conversions.

Efforts are being made to reduce the impacts of these variables.

8 Atmos heric Monitorin The atmospheric monitoring network is divided into three groups.Pour local air monitors are located on or ad)acent 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 6 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 HV-70 particulate filter at a regu-lated flow of 3 ft/min.In series with, but downstream of, the particulate 3 filter is a charcoal filter used to collect iodine.Each monitor has a col-lection 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 con-tinuously scans the particulate filter.The disintegration rate of the atmospheric radioactivity is continuously recorded at each station and radio-telemetere'd into the plant.Air filters are collected weekly and analyzed for gross beta activ-ity.No analyses are performed until three days after sample collection.

The samples are composited monthl~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.With reference to table 5, which contains the maximum permissible concentrations (MPC)recommended by 10 CPR 20 for nonoccupational exposure, it is seen that the maximum beta concentration in air is 0.12 percent MPC.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 period one sample was not obtained because of, insufficient rainfall, The gummed acetate that is used to collect heavy particle fallout is'changed monthly.During this reporting period, two samples were damaged to the extent that insufficient material remained for analysis.The samples are ashed and counted for gross beta activity.The results are given in table 8.

12 Charcoal filters are collected and analyzed for radioiodine.

The filter is counted in a single channel analyzer system.The data are shown in table 9, where the highest value reported is 0.06 percent MPC in air for 131I.

13 Figure 2 ATMOSPHERIC AND TERRESTRIAL h(lONITORING NETWORK RM.28F LAWRENCEBURG yPULASKI FAYETTEVILLE

~WILSON FLORENCE PM-IBF WHEELER ROGE SVIL OAM ATHENS PM-28F FFIEL MUSCLE SHOALS RM-I BF LEIGHTON TUSCUMSIA It COURTLANO PM-4 F pRUSSELLVILLE BROWNS FERRY NUCLEAR PL NT OECAT PM-38FD IO MILES HARTSELLE HUNTSVILLE IL GUN T SV OAM 2S HALEYVILLE CULLMAN r 45 MILES RAINWATER SOIL O-ENVIRONMENTAL MONITORING STATION NOTE: THE FOLLOWING SAMPLES ARE COLLECTED FROM EACH STATION: AIR PARTICULATES RADIOIODINE HEAVY PARTICLE FALLOUT LOCAL MONITORING STATIONS BROWNS FERRY NUCLEAR PLANT ATHENS Qa U S HWY 72 BFN ALA.HWY 20 0 O Legend Air Monitor Air Monitor 8 TLD Station N DECATUR b,:TLD Station h Automatic Well Sampler H Dairy Farm 0 Scale I 2 3 4 5 Miles Picture 4 BROWN'S FERRY NUCLEAR PLANT SITE MONITORING STATIONS I/~.e e I:~e/LM4BF LM-4BF~X LM-IBF<~.',~~a 4~/I5 e ooI e ee 5\r ATMOSPHERIC AND TERRESTRIAL MONITORS~TLD STATIONS--PLANT BOUNDRY ROADS+WELL ZL WELLS (NOT BEING SAMPLED)qcccct B Neet/j's.~etcctecccletctel Tceee/a e ce WHEELER LAKE

.'16 Table 5 MAXIMUM PERMISSABLE CONCENTRATIONS FOR NONOCCUPATIONAL EXPOSURE Alpha Nonvolatile beta Tritium 137CS 10 3 s 106RU 144Ce 95zr-95Nb 140Ba 140L 131I 65Z s4Mn Co 89Sr"Sr 51C 134CS s0G In Water~Ci./1*30 3,000 e 3,000,000 20,000 10,000 100000 60,000 20,000 300 100,000 100,000 30,000 3,000 300 2,000,000 9,000 90,000 MPC In Air~Ci/m'*100.200,000 500 200 200 1,000 1,000 100 2,000 1,000 300 300 30 80,000 400 2,000*1 pCi=3.7 z 10 3 Bq.

TABI.E 6 RADIOACTIVITY IN AIR FILTER PC I/H(3)Os037 BQ/H(3)NAHE OF F AC IL I TY~RRDM(IS E ERR Y LOCATION OF FACILITY LIHESlOHE--ALAB4))4 DOCKET NDo 5DeeRBR*26Dc2%.

REPORTING PERIOD 198D TYPE ANO TOTAL NUHBER OF ANALYSIS EEREORBED GROSS ALPHA 52 GROSS BETA 572 GAHHA (NAI)1ll CS>>134 I>>131 BE 7 LOWER LIHIT OF DETECTION a ILLDI 0+005 0~010 0~010 0 010 NOT ESTAB LR 95 NB>>95 0~010 0'10 NOT ESTAB 0'20-Os020 NOT ESTAB X 40 8 l>>214 PB 214 PB 212 BE<<T TL>>208 AC 228 , Os050 NOT ESTAB NOT ESTAB 0.005 0~001 SR'9 44 SR 90 44 GAHHA (GEL I)32 RU>>103 NOT ESTAB ALL INDICATOR LOCATIONS HEAN (F)b 84NGE b 0 F 03(466/468)0 F 01>>0~1R 0~0 I (1/90)0 F 01'~01 0~01(10/90)0 F 01 0~OR 0'6(BR/90)Os 02 0~ll 0~01(6/RT)0 F 01-0'1 0 F 02(3/RT)0~OI-0~OR 0 F 01(6/RT)-Os01 O,OR*0~14(18/27)0 F 08 0'8 Os04(21/RT)0 F 02" 0~OT Oo04(14/27)OoOZ>>Oo07 0 F 02(13/27)0 F 00 0'3-0'7(13/RT)0 F 05 0~ll OsOI (5/27)0 F 01 0~Ol 0 F 02(1/27)0 F 02 0'2 q6 ViLVES<I.LD'ANALYSiS PERFORHEO 36 VALUES<LLO ANACYSIS PERFORHEO LH5 BF DAVIS F 2~5 HILES WSK 0'4(Oe01 52/52)Oe12 LH2 BF NORTH 0~9 HILE NNE LH2 BF NORTH 0~9 HILE NNE LH4 BF TRAILER P le7 HILES NNK Oo01(0~Ol>>0~OR(0,01>>0 F 08(0 F 05>>1/9)0~01 Sl 9)0'2'9/1 1)Oe 10 ATHENS'L 10e9 HILES NE LH5 BF DAVIS F 2,5 HILES WS'K DECATUR'L 8~2 HILES SSE LH1 BF NDRTHKEST loO HILE N LH3 BF NORTHEAST 1~0 NILE NE ATHENS'L 10'HILES NE COURTLANOi AI.10~5 HILES MSM.LH5 BF DAVIS F 2~5 HILES MS'K COURTLANDi AL 10'HILES WSM LH2 BF NORTH 0'NILE NNE 0~01(Oo01>>OeOR(0~OR>>Oe02(O,OR>>Oe 16(Oo 14>>Oe05(Oo04>>0 F 05(0~OS>>0~OS(OeOS>>0~ll(Oe ll>>0~Ol(0~Ol>>0'2(0'2>>1/3)0 F 01 1/3)Oe02 1/2)Oe02 2/2)Oe18 2/3)Oe06 2/3)Oe07 Rl 4)OeOS 1/3)Oe ll 1/4)'e01 ll 4)Os02 LDCAIID(I-KIIU UIGUESI NhlQAL IIE48 NAHE HEAN (F)b DISZAIICE 4ND DIREDIIDII R4uGE b CONTROL LOC AT IONS HEAN (F)b R4t(GE b 0~01(2/52)Os01>>0~01 0 F 03(104/104)0 F 01>>0'9 Rl VALUES<LLO 0~01(2/21)0~Ol>>0~02 0~06(20/21)0'2>>0'0 5 VAI.UES<LLO 0.01(1/5)0~01 0~01 0~Ol(1/5)Oo 01>>0~Ol 0~ll (3/5)0e08 0~12 0 F 06(4/5)Os03>>0 F 08 0 F 05(3/5)0 F 05.Oe06.0'2(2/5)OoOR>>0'2 Oo05(3/5)0'5 0 F 06 5 VALUES<LLO 5 VALVES<LLD 8 VALVES<LLD 8 VALUES<LLO NUHBER OF NONROUT INE REPORTED BEASUREHEBZS a..Hominal Lover Limit of Detection (LLD)as described in Table 3.b." Mean and range based upon detectable measurements only.Praction of detectable measurements of specified locations is indicated in parenthesis (P).

TABLE 7 RADIOACTIVITY IN RAINWATER PCI/L-0e037 8()/L NAHE OF FACiLITY BBOWUS EEBLY-DOCKET NO~NaZSRa26Qa Q9 LOCATION OF FAC IL ITY il)(ESIO9E

---4L484((4REPORT ING PERIOD 198O TYPE AND TOTA(NUHBER OF ANALYSISREBEOBHEQ GAHHA (NAI)134 1~131 BE 7 LOWER LIHIT OF DETECT ION a ILLQJ.15~000 NOT ESTAB AiL INDICATOR LOCATIONS HEAN (F)b B4NGRJ----

38.70(1/ill)ATHENS'L 3S~70 38~70 10~9 HILES NE 41e21(71/111)ROGERSVILLEi AL 2~60 101 e 40 13~8 HI LES NK 38s70(1/13)38e70~38e70 52.50(9/ll)16 F 80~-101'0 LOCAZIOI(WIZEN UIGIIESZ 4((MAL.IIE4N NAHE HEAN (f)b QISX4(1CE 4((Q QIBECZIOU 84((GEo---CONTROL NUHBER OF LOCATIONS NONROU TINE SEAN (F)REPORTED 845GEo" 8EASUBEHEBIS 15e40(1/23)15e40~15s40 37 e51(10/23)13.80-65.90 81 214 PS~2%4 PB 212 BE 7 TRIT IUH 142 NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB 330 F 000 GAHHA (GELI)8 K~40 NOT ESTAB 76'5(76'5 21e62(21~24 7eTa(7'3%17.9i()6e30 347~50(347'0" 426'4(3$2e 12 1/6)76e95 2/6)R2 F 00 1/6)7~73 2/6)19~51 1/6)347'0 6/117)643'6 DECATURs AL 8~2 HILES SSE COURTLANOs AL 10 5 HILES WSW COVRTLANQs AL 10e5 HILES WSW LH1 BF NORTHWEST 1~0 HILE N ROGERSVILLEi AL 13~8 HILES NK ATHENS@AL 10~9 HI LES NE 76'5(76s95~22 F 00(22'0m 7s73(7e73>'9e51(19'la 347s50(347e50e 550e98(550'8i 1/1)T6e95 1/1)22e00 1/1)7e73 I,/2)19~51 1/2)347e50 1/13)550e'98 2 VALUES<LLD 15e41(2/2)1 l,e 77~-19~05'e67(1/2)8'7~8'7 2 VALVES<LLD 2 VALUES<LLD 25 VALUES<LLD a.Nominal Lover Limit of Detection (LLD)as described in Table 3.b.Mean and range based upon detectable measurements only.Praction of detectable measurements of specified locations is indicated in parenthesis (P).

TABLE 8 RADIOACTIVITY IN HEAVY PARTICLE FALLOUT HCI/KH(2)37000000i00 BQ/KH(2)NAME OF FACILITY BBQNUS EEBBY----'DOCKET ND Ns2$%a25Qa296.LOCATION OF FAC I L ITY LuIHESZOHE ALABAIIAREPORTING PERIOO IQBQ TYPE AND TOTAL NUMBER OF ANALYSIS EEBEOBHEO GROSS BETA 141 LONER LIHIT OF DETECT ION a CLLQl 0.050 ALL INDICATOR LOCATIONS MEAN (F)b RANQE-Oo26(115/11$)0'6*F 07 LOCAIIOU MIZU UIOHESX AUhlUAL 5EAhl-~--NAME MEAN ([)QISZAHCE ANQ QIBE(:rIObl BA((QE LH4 BF TRAILER P 0~39(13/13)1~7 MILES NNN 0~09~Oe94 CONTROL NUHBER OF LOCA T logS NONROUTINE MEAN (f)REPORTED BAHGE BEASUBEHEBXS-0~22(26/26)0 F 06 0'5 a.Nominal Lower Liuit of Detection (LLD)as described in Table 3.b.Mean and range based upon detectable neasureuents only.Fraction of detectable neasurenents of specified locations is indicated in parenthesis (P).

TABLE 9 RADIOACTIVITY IN CHARCOAL FILTERS PCI/H(3)Oe037 80/H(3)NAME OF FACILITY'ROW((S EERRY-POCKET NO SDn25Ra24Da V5" LOCATiON OF FAC ILiTV iIHESZOhla ALAB454REPORT It G PERi00 19RD TYPE AND TOTAL NUHBER OF ANALYSIS EEREORHED IODINE IN AIR 572 LOWER LIHIT OF DETECTION a CLLD}0.020 ALL INDICATOR LOCATIONS HEAN (F)b b RANGE Oe03(48/468)0'2-0 F 08 LOCAZIOI(MllU UIGUESI N(IU4L UE48--NAHE HEAN (F)b DISIAIICE 48D DIRECIIOU R4((GE b ROGERSVILLEi AL 0~03(9/51)13~8 HILES NM 0~02 Oe06 CONTROL LOCATIONS HEAN (F)BABGEb Oo03(10/104)0~OR>>0'5 NUHBER OF NONROUTINE REPORTED BEASUREHEBIS a.Nominal Lower Limit of Detection (LLD)as described in Table 3.b.Mean and range based upon detectable measurements only.Fraction of detectable measurements of specified locations is indicated in parenthesis (P).

Terrestrial Monitorin Milk Milk 10-mile radius control farms.gamma-emitting in table 10.is collected from at least four of five farms within a of the plant (see figure 3), and from at least one of four Raw milk is analyzed weekly for I, and monthly for isotopes and for radiostrontium.

The results are shown Cow censuses were conducted in May and September 1980.Xt was determined that there are no dairy farms nearer the plant than the nearest farm being sampled.Ve etation Vegetation is sampled quarterly at the farms from which milk is collected and analyzed for gamma-emitting radionuclides.

Approximately 1-2 kilograms of grass is broken or cut at ground level and returned for analysis.Efforts are made to sample vegetation that is representative of the pasturage where cattle graze.Table 11 gives the results obtained from the laboratory analyses of these samples.Soil Soil samples are collected annually near each monitoring station to provide an indication of a'ong-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'and Sr and Sr.The results are given in table 12.'round Water An automatic sequential-type sampling device has been installed on a well down-gradient from Browns Ferry Nuclear*Plant.

A composite sam-ple 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 up-gradient from the plant.The results of the analysis of well water are shown in table 13.Potable water supplies taken from the Tennessee River in the vicinity of Browns Ferry Nuclear Plant are sampled and analyzed for gross 4*

22 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'ith an automatic sampler with composite samples collected and analyzed'eekly.

Two additional supplies downstream and one public~ater supply upstream are collected'y monthly grab sampling.Table 14 indicates the results from the analysis of drinking water samples.The maximum beta concentration is 0.40 percent MPC.'S Environmental Gamma Radiation'Levels Bulb'-type Victoreen Manganese-activated Calcium Floride (CaFg.Mn)thermoluminescent dosimeters (TLD's)are placed at nine stations around the plant near the'ite boundary and at the perimeter and remote air monitors to determine the gamma exposure rates at these locations.

The dosimeters, in energy compensating shields to correct energy dependence, are placed at approximately one meter above the ground, with three TLD's 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 individualgamma response calibrations and self-irradiation factors determined for each TLD.=The'LD's are exchanged every 3 months.The quarterly gamma radiation'levels determined from"these TLD's are given in table 15, which indicates that average levels at.onsite stations are approximately 2 mR/quarter'igher 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.This may be attributable to natural variations in environmental radiation, levels, earth moving activities onsite, the mass of concrete employed in the.construction'of the plants, or'other undetermined influences.

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

-During this sampling period samples'f cabbage, corn, green beans, peaches, potatoes, tomatoes',-so'ybeans, and'poultry were collected and analyzed for specific gamma-emitting radionuclides.-

No sample of soybeans was taken from a control location.'The results are given'n tables 16, 17, and 18.

TABL'E lo RADIOACTIVITY IN XILK PCI/L Oe037 84/L NAME.OF f AC ILITYBRQbt(IS EERRY DOCKET NOD SQsRHa26Oa29$

LOCATION Of FAC IL ITY LIIIESIQI(E 4L464II4---REPORTING PERIOD 1984 TYPE AND TOTAL NUHBER'f ANAI.YSIS REBEQ85EQ GANHA (NAI)-109'CS 137'ONER LIMIT OF DETECTION a I,LLQl10 000 81-214 P 8!214 Pb 212*SR 89 SR 90 (NOT ESTAB.NOT ESTAB NOT ESTAB 10o000 118 2 F 000 118 K>>40.-150 F 000 IODINE IN NII.K'Oo500 460 GAHHA (GEL I)8 K>>40 NOT ESTAB-le 38(4/)59)x0.5o-12.80.1261'3(59/59)109'0<<, 1406e40.0 F 80(6/259).Oe55 le 18 SHITH FARM 4o75 HILES N SNITH FARH-'4e75'ILES N BROOKS FARH'e0 MILES NN)(llo95(11~10>>1302 F 87(1129~00>>Oe89(Oeb9>>2/1R)12 F 80 12/1R).140be40 3/50)le 18 15<3 F 00(.6/6)1302oOo" 175'0 88e84(5/')24 ddt 3'5 ,24'2(3/6)le 34 36e47 id'8.(2/6)-..8 F 81>>, 23~95 65.V4LUES CLLO ANAiYSIS PERFORMED 4e ll (62/65)2e04 9e08 SNITH FARM 4e75 NILES N THRASHER FARM Too MILES ENE SNITH FARM 4e75 MILES N 8 ITTING FARH 4eS HILES ENE BROOKS FARH 7'e0 MILES NNM 1642e00(1579 F 00>>3'5(3be45>>3be47(36e47>>R3~95(23e95>>2/R)1705e00 1/1)36 F 45 1/.2)$6~47 1/2)23~95 5 43(12/12)3e36>>F 04 ALL INDICATOR LOCATIONS LQCAIIQH MIIU UIGI(ESI NBLIAL 5E48 MEAN.(F)b--NAHE HEAN (P)b 84NGE b QISIAI(CE AUQ ()1RECIIQM

-84hlGEb CONTROL I.QCAT ION/, MEAN (F)'a((GER 10.60(1/50)-10.60-10.60 1229.93(50/50)1087~SO 1371~00.Oe56(2/201)Oo50>>Oebl 1476'0(2/2)1450 F 00>>1503 F 00 RO~04(2/R)17'2>>22eRS.15.81(z/=z)~15~04>>16~57 2 VALUES<LLD 5$VALUES elLLD 5'1(43/53)RE 06>>9e89-NUHBER OF NQNROUT INE REPORTED IIEASUREIIEBIS C+','a.Noadnal Lower Liait of Detection-(LLD) as described in Table 3.b., Mean and range based upon'detectable.measurecients only.Praction of-detectable measurenents of specified locations is indicated in parenthesis'-(P).

~

TABLE 11"RADIOACTIVITY IN VEGETATlON PCI/G>>0~037 BQ/G (DRY MEIGHT)NAHE OF FAC IL I TY~RRQMUS KERRY DOCKET NQ~SQ?Hg.26Qa 296 LOCATION OF FACILITY LIUESIOUE--

---OLORO5OREPORTING PERIOD 19SQ TYPE AND TOTAL NUMBER OF At(ALYSIS-SFREORUEO GROSS BETA 36 GAHMA (GELI)36 CE 144 BA-140 LA-140 RU-103 CS 137 ZR 95 NB 95 K>>40 Bl 214 PS 214 PB 212 BE-7 TL 208 AC-228 COMER LIHIT OF DETECTION a CLLQX 0'00 0'20 0~3o0 0 F 080 0'00 0.060 0'10 0.050 NDT ESTAB 0 F 100 NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB 0'0(2/20)Oe36.0'4 20 VALUES<LLD 0~10(0~10 0'8(0'1 0~11(Oe07-0.44t Oe22 0'4(0~27-12'4t le 37-0'$(Dell OoR3(Oo08 Oe15(Oe06 7ob9(0~81 Oo07(0 F 03 0'4(Oe14 1/20)0~10 5/20)Oeb5 6/20)Oo 17 5/20)Oe96 5/20)le00 20/20)27e60 17/RO)Oe53 18/20)De41 15/20)0'3 20/20)29e ll 6/20)0'2 10/20)0'7 ALL INDICATOR LOCATIONS MEAN (F)-ROUGE b 23o56(20/20)7o54 50'2 LOONEY FARM F 75 HILES ENE 0.44(1/4)0 F 44>>0'4 THRASHER FARM 7'MILES ENK LOONEY FARH 5o75 MILES ENE LOONEY FARM 5~75 HILES ENE LOONEY FARH 5o75 MILES ENE LOONEY FARM 5o75 HILES ENE THRASHER FARH 7'HILES ENE LOONEY FARM 5'5 MILES ENE LOONEY FARH 5o75 HILES ENE LOONEY FARH 5~75.MlLES ENE SITTING FARH 4~5 MlLES ENE'OONEY FARH 5'5 HILES ENE I.OONEY FARH 5~75 MILES ENE 0'0(0~10>>Oob5t 0.65>>0~16(0.16 0'6(0'6>>le00t le 00>>17e77(be51>>0'4(Oe 1 lr Oe26(Oe12>>Oo23(Oe13>>10e31(Oe81>>Oe08(Oo03>>Oo54(0'0>>1/4).0'0 1/4)Oe65 1/4)Oe 16 1/4)0'6 1/4)1~00 4/27'0 4/4)Oo53 3/4)Oo34 R/4)Oe33 4/4)29e ll 2/4)0~12 3/4)0'7 LOCOIIOU MIIU UIGHESI AUUUOL HEAU---NAME HEAN (F)b OISIOUC.E OUQ QIRECIIOU ROUGE THRASHER FARM 31~14(4/o)7'MILES ENE 16,36 40'8 Oo38(Oe25.0'9(Oe59 Oe42(Oe42>>0,35(0'4>>0~12(0~08>>Oe48(0'7>>0'9(Oe319'9(F 12 0'9(Oe10>>0.24(De 12, Ool3(0 F 07>>9'3(2o 13, 0'6(oo04 Oo25t Oo12>>2/16)Oe50 1/lb)Oe59 1/16)0'2 4/16)Oe50 6/16)Oe lb 4/lb)Oeb8 4/16)0.84 15/16)22'9 12/16)Oe49 13/16)Oe47'2/16)0'4 16/16)2beR7 8/16)Oe10 7/16)0~34.CONTROL LOCATIONS HEAN (F)b RAUGEb 18.57(lb/16)5o47 44o02 NUHBER OF NONROUT INE REPORTED UEASUREUEUZS a.Nominal Lover Limit of Detection (LLD)as described in Table 3.Mean and range based upon detectable neasurenents only.Fraction of detectable measurements of specified locations is indicated in parenthesis (F).

NAME OF FACILITYRRQNt(S KERR)(LOCATION OF FAC IL I TY LIHKSIO((K TABLE I2 RADIOACTIVITY IN SOIL PCI/G>>0~037 BQ/G tORY MEIGHT)DOCKET NO~KQaRRRa26Qa~

REPORTING PERIOD 1RRQ TYPE AND TOTAL NUHBER OF ANALYSIS REBEORHEQ GAHHA (GEL I)ll CS 137 K>>40 B l>>214 BI 212 PB 214 PB>>212 RA-226 RA 223 TL 208 AC 228 SR 89 11 SR 90 ll LOMER LIHIT OF DETECTION a CLLQl 0'20 0.250 Os050 0~100 0.050 NOT ESTAB 0'50 NOT ESTAB 0'20 0.-060 1~500 Os300 ALL INDICATOR LOCATIONS HEAN (F)b BANQE3~Oe4lt 9/9)0~18-De86 5'2(9/9)3e49-8'4 le04(9/9)0'5 1~39 0'7t 9/9)0'0 0'7 1.10t 9/9)0,73-1~43 leR4(9/9)Oe71 1~56 1 e04 (9/9)0'5>>=1~39 0'9(6/9)0 F 28 0'8 0'2(9/9)0'6 0'2 le22(9/9)Oe77.le51.9 VALUES<LLO ANALYSIS PERFORHED 9 VALUES<LLD ANACYSIS PERFORHED ATHENS'L 10e9 MILES NE LHl BF NORTHWEST le0 HILE N LH2 BF NORTH 0~9 NILE NNE LH4 BF TRAILER P 1~7 H ILES NN)(LH2 BF NORTH 0~9 NILE NNE DECATUR'L 8~2 HILES SSE LH2 BF NORTH Oe9 HILE NNE LH2 BF NORTH 0~9 NILE NNE DECATUR'L 8~2 HILES SSE LHl BF NORTHWEST le0 HILE N De86(.De86>>8'4(Be04>>1~39(ls39>>Oe97(0'7>>le43(1,43 1e56(1.56 1~39(1~39>>0'8(0 F 48>>0'R(Oe5R le5),(le 51>>'/1)0'6 1/1)8 F 04 1/1)lo39 1/1)De 97 1/1)le 43 1/1)le56 1/1)le 39 1/1)0'8 1/1)Oe52 1/1)1e51 LQCAZIQI(MCTV VZQUESZ au((UAL t(Eau<NAHE MEAN (F)QlSIAI(CE AUQ QIRE(iZIOtt RA((GE CONTROL LOCATIONS HEAN (F)b RA((GEb 0.60(2/2)Oe45>>Oe75 4.51(2/2)4e)9 4e83 Oe91(2/2)0'2>>F 01 0 F 78(2/2)Oe77 De78 Oe99(2/2)0 F 89 F 09 1'R(2/2)1~00>>F 04.0~91(2/2)Oe82>>le01 R VALUES<Ll.D 0'9(2/2)De37>>0'1 loll(2/2)1<<04>>le18 2 VALUES<LLD 2 VALUES<LI.D NUHBKR OF NONROUT INE REPORTED t)KASURE((EhlZS a.Nominal Lower Limit of Detection (LLD)as described in Table 3..b.Mean and range based upon detectable.

measurements only.Fraction of detectable measurements of specified locations is indicated in parenthesis (P).

NAME OF FAC ILITY BRQMUS KERRY LOCATION QP FACILITY LIHESIOUE TABLE 13 RADIOACTIVITY IN MELL MATER PCI/L-0.037 80/L DOCKET NO.SQn252c26Qc2M REPORTING PKRIOD 198Q TYPE AND TOTAI.NUHBER OF ANALYSIS PEREORBEQ GAHHA (NAI)22 iOHER LIHIT OF DETECTIONa ZLLQX ALL INDICATOR LOCATIONS I'IEAN (F)b R4HQEI w w w 11 VhLUES<LLD ANAiYSIS PERFORHED CONTRDL LOC4XIOU-MIIU hII(3)1ESI 4WMAL ()E48, I.OCAT IDNS NAHE HEAN (P)b HEAN (F)b QISI4HCE 4((Q QIRECIIOU RAt(GE~-RAGE'1 VALUES<LLD.NUHBER OF NONROUT INE REPORTED ((EASUREBEhlIS 81 214 PB-214 PS~212 TR IT IUH NOT ESTAB NOT ESTAB NOT ESTAB 330 F 000 GAHHA t GEL I), 4 K 40 NOT ESTAB 67.32(2/.2)66.53-68.11$3~63(1/2)13,63 13'3 12.5lt 1/2)i2 5i<<12 51 2 VALUES<LLD VALUES<LLD ANALYSIS PERFORHED BFN MELL¹6 0.02 HILES M BFN HELL¹6 0~02 HILES W BFN HELL¹6 0'2 HILES M 67'2(bbo53r 13a63(13~63>>12e51(12~51~2/.2)68ell 1/2)13~63 1/2)12 F 51 68.70(1/2)69i70<<69'e70'bi04(1/2)16'4~16 F 04 11~53 (1/2)11 53~ll 53 13.35(1/, 2)13'5~13+35 4 VALUES<L(.0 a.Nominal Lower Limit of Detection (LLD)as described in Table 3.b.Mean and range based upon detectable measurements only.Fraction of detectable measurements of specified locations is indicated lri parenthesis (P).

TABLE 14 RADIOACTIVITY IN PUBLIC MATER SUPPLY PCI/L 0~037 BQ/L NAHE OF FACILITY BROMhlS EERRY-DOCKET NO 5Rn2$Ra26QaMS LOCATION OF FAC IL ITY LIHESIOUE'L464I)4REPORTING PERIOD 1MQ TYPE AND TOTAI NUHBER OF ANALYSIS REREORIIEQ GROSS BETA 91 GAHHA (NAI)84 LONER LIMIT OF DETECTION a LLLQ1F 400 ALL INDICATOR LOCATIONS BAN (F)b-8486%--b 3.69(46/78)2~41~ll~99 72 VALUES<LLD ANACYSIS PERFORMED LOC4IIOU-MIXU UI(1)1ESZ 4((OVAL WE48--NAHE MEAN (F)b QISIAUCE 4UQ RIRECIIOU R4(IGE MHEEI.ER OAHi AL 5'3(4/13)TRM 274'2'9>>11'9 CONTROL LOCATIONS MEAN (F)bR4(IGE b Se05(3/13)2 F 49~3e80 12 VALUES<LI.D NUHBER OF NONROUTINE REPORTED IIEASUREHEHZS BI 214 P 8~214 PB 212 SR 89 16 SR 90 16 TRITIUM 16 NOT EST~8 NOT ESTAB NOT ESTAB 10~000 F 000 330 F 000 GAHHA (GEL I)7 K~40 NOT ESTAB 76e44(2/6)74e65 78'2 19 F 88(3/6)9e09-26 F 20 21e6 1 (2/6)i8.86 24,35$5e03(2/6)i0,6i-...19.4S 1Z VALUES<LLD ANALYSIS PERFORHED$2 VALUES<LLD ANALYSIS PERFORMED 34S.29(1/12)343e29-343 F 29 CHAMPION PAPER TRH 282eb llHEELER OAHi AL TRH 274'CHAMPION PAPER TRH 282 F 6 CHAHPION PAPER TRH 282'78'2(78e22~26'0(26 F 20~24'5(Zhe35~19e43(19'3~1/3)78'e 22 1/3)Z6~20 1/3)24'5 1/3)19e 43 SMEFFIELOiAL ROB 343e29(1/4)TRH 254'343'9~343e29 102 F 80(1/1)102 F 80~102 F 80 9~15(1/1)9e15 9~15 13'3(1/1)13'3>>13'3 1 VALUES<LLD 4 VALUES<LLD 4 VALUES<LLD 4 VALUES<LLD a.Nominal Lower Limit of Detection (LLD)as described in Table 3.b.Mean and range based upon detectable measurements only.Fraction of detectable measurements of specified locations is indicated in parenthesis (p).

28 Table 15 ENVIRONMENTAL GAMMA RADIATION LEVELS uarter January-April 1980 Location On-Site (8)-b.Maximum, Minimum Average c Environmental Gamma Radiation Levels I~i 10.6 23.1 7.3 15.9 9.4+2.3 20.7+5.0 Off-Site (7)Maximum Minimum Average 12.5 6.9 8.6+3.7 27.4 15.2 18.9+8.2 May-July 1980 On-Site (8)Maximum Minimum Average 10.0, 21.9 7.4 16.3 9.0+2.0 19.8+4.4 July-September 1980 October-December 1980 Off-Site (7)Maximum Minimum Average On-Site (9)Maximum Minimum Average Off-Site (7).Maximum Minimum Average On-Site (9)Maximum Minimum Average ll.1 6.8 8.1+2.8 10.3 7.9 9.5+1.8 11.0.'~3 8.5'+2.5 11.5 7.8 10.0 x 2.3 24.3 14.9 17.8+6.1 22.6 17.3 20.9+4.0'24.2 16.0 18.6+5.5 25.1 17.2 21.9+5.0 Off-Site (7)Maximum Minimum Average 12.0 26.3 7.4 16.3 8.7+3.1 19.1+6.8 bData normalized to one quarter (2190 hours0.0253 days <br />0.608 hours <br />0.00362 weeks <br />8.33295e-4 months <br />)Number of stations (normally three TLD's at each station)All averages reported+2a (95%confidence level)

TABLE 16 RADIOACTIVITY IN FOOD CROPS PCI/KG>>0'37 80/KG (WET WEIGHT)NAHE OF PACtLITY 4BQWQS EEBBY---LOCATION OF FACILITY LISESZOHE-DOCKET NOo SOm25%E260a29E AL444I)4 REPORTING PERIOD aR41)TYPE AND TOTAL NUHBER OF ANALYSIS eEBEOBIIEO LOWER LIHIT OF DETECT IONa--CLLQ2---

ALL INDICATOR LOCATIONS HEAN (F)b RANGE3r LOCAZIOu M2ZI(VIGIIESZ 4((((MAL uE4N>NAHE MEAN (F)OlSZ4((CE 480 QIBECIIO((=-

B48GEb--RADIOACTIVITY IN CABBAGE CONTROL LOCATIONS MEAN (F)b BAI(GE b NUMBER OF NONROUTINE REPORTED SEASUBEBEHIS GROSS SETA 2 GAHHA (GELI)2 K>>40 PS 212 25 000 NOT ESTAB NOT ESTAB 44i3o59(1/1)4413'9 4413'9 SHI TH FARH 4413 o 59 (1/1)4~75 HILES N 4413~59>>4413o59 4338~21(1/1)4338 F 21>>4338'1 174So00(1/1)SHITH FARH 1748o00 1748 F 00 4'5 MILES N 16~52(1/1)SHITH FARH 16~52 16o52 4~75 MILES N 1748.00(1/1)1646,00(1/1)1748.00>>1748;00 1646.00-1646.00 16'2(1/1)1 VALUES (LLD 16 52 16o52 RADIOACTIVITY IN CORN 25 F 000 GROSS BETA 2 GAHHA (GEL I)2 K>>40 NOT ESTAB 3535o84(1/1)3535 F 84 3535 F 84 2440o00(1/1)2440~00-2440~0()SHITH FARH 4~75 MlLES N SHITH FARM 4o75 HILES N 3535.84(1/1)9535o84>>353'4 2440o00(1/1)2440 F 00>>2440 F 00 3247'7(1/1)3247,77>>3247o77 1758 o00(1/1)1758 F 00>>175'0 GROSS SETA 2 GAHHA (GELI)2 K>>40 PB'212 25 F 000 NOT ESTAB NOT ESTAB 29i6.00(29i6.0o;, 2916o00 llo17(1/1)1 1 o 17-11~17 SMITH FARH 2916~00(1/1)4~75 MILES'N 2916~00>>2916~00 SHITH FARH llo17(1/1)4o75 HILES N 11~17>>ll~17 RADIOACTIVITY IN GREEN BEANS 4817 18(1/1)SHITH FARM 4817 18(1/1)4817o18>>4817~18 4~75 MILES N 4817~18>>4817olS 4638ob3(1/1)4638o63>>4638o63 2310 F 00(1/1)2310o00>>2310o00 lo,zs(1/10'S>>10'8 a.Nominal Lower Limit of Detection (LLD)as described in Table 3.b.Mean and range based upon detectable measurements only.Fraction of detectable measurements of specified locations is indicated in parenthesis (F).

TABLE 16 (Contd}RADIOACTIVITY IN FOOD CROPS NAHE OF FACILITY BRQUUS EERBY-LOCATION OF FACILITY LIUKSIOUK PCI/KG 0~037 8()/KG (MET HEIGHT)DOCKET NO~SQa259c26QcV6 ALABAUA REPORTING PERIOD 19()Q TYPE AND LONER LIMIT TOTAL NUHBER OF OF ANALYSIS DETECTION a EEBKORUEQ CLLQl ALL INDICATOR LOCATIONS MEAN (F)b RAUGK3 LOCAIIOU MIIU UlGUESI AUUUAL VEAU NAME HEAN (F)b QISIAUCE AUQ QCBECIIOU--BAUGEb CONTROL NUMBER OF LOCAT IONS NONROUT INE MEAN (F)b REPORTED BAUGEk UEASUREUEUIS GROSS BETA 2 GAHHA t GEL I)I 2 K+40 25.000 NOT ESTAB 5600'4(1/1)5690'4-5690'4 2183~00 (1/1)2183~Oo 2183~00 RADIOACTIVITY IN PEACHES SMITH FARM 5690~34(1/1)4'5 HlLES N 5690'4 5690 F 54 6935~15 (1/1)6935~15~6935~15.SHITH FARH 2183~00(1/1)1888~00(1/1)4~75 MILES N 2183~00.2183~00 1888 00, 1888~00 25 000 GROSS BETA 2 GAHHA (GELI)2 K~40 NOT ESTAB 7789.95(1/1)7789.95-7789.95 4121~00(1/1)HARGROVE FARM 412leoo 4121~00 3~75 HlLKS N 4121soo(1/1)4121~00~4121~00 3483 F 00(1/1)3483 F 00~3483 F 00 RADIOACTIVITY IN POTATOES HARGROVE FARH 7789~95(1/1)8228~30(1/1)3~75 HlLES N 7789'5~7789'5 8228'0 822be30 GROSS BETA 2 GAHHA (GEL I)2 K 40 25.000 NOT ESTAB 487be55(1/1)4876o55~4876'5 2485.OO(1/1)2485.0O-2485>00 RADIOACT1VITY IN TOHATOES SHITH FARH 4~75 H1LKS N 4876'5(1/1)4876.55 4876r55 SHITH FARH-2485 F 00(1/1)4o75 MiLKS N 2485eoo~2485 F 00 4844'4(1/1)4844.24 4844,24 2456.00(1/1)2456eoo 2456 F 00 a.Nominal Lower Limit of Detection (LLD)as described in Table 3.b.Mean and range based upon detectable measurements only.Fraction of detectable measurements of specified locations is indicated in parenthesis (F).

TABLE 17 RAOlOACTIVITY IN SOYBEANS PCI/G~0'37 80/G tORY WEiGHT'NAHE OF FACILITY BRQWUS EEBRY-LOCAT ION OF FAC IL I TV LIBEiZOUE ALARAHa DOCKET NO~Spe25Ra26pa-REPORTING PERIOD 1RBO TYPE ANO TOTAL NUHBER OF ANALYSIS REREORBEO GROSS BETA 1 GAHHA (GEL I)1 K~40 BI 214 P B-214 LOWER LIHIT OF OETECT ION a LLLQl=0.200 NOT ESTAB NOT'STAB NOT ESTAB 17 F 07(17 tOT 0'6(0'6 0'6(Oe06 1/1)17e07 1/1)0'6 1/1)0'6 AiL INDICATOR LOCATIONS MEAN (F)b b RAhlQE 40'9(1/1)40'9-40'9 HARGROVE FARH 3'5 HILES N HARGROVE FARH 3e75 HILES N HARGROVE FARM 3'5 HlLES N 17e07(17e07~Oo06(0'6~0'6(0'06~1/1)17s07 1/1)0'6 1/1)0'6 LOCAZIOU l(IZU)jIGNSZ auhlUAL HE4((~NAME MEAN ($)QISIAHCE Ahlp QIBE{;ZIPU RAQGE HARGROVE FARH 40e89(1/1)3'5 HILES N 40 89 40 89 CONTROL NUHBER OF LOCATION)NONROUTINE HEAN ())REPORTEO RABGEHEASUREHEUZS a.Nominal Lower Limit of Detection (LLD)as described in Table 3.b.Mean and'ange based upon detectable measurements only.Fraction of detectable measurements of specified locations is indicated in parenthesis (F).

TABLE 18 RADIOACTIVITY IN POULTRY PCl/KG 0~037 BQ/KG (NET MEIGHT)NAHE OF FACILITYRROilUS EERRY DOCKET NO~EQm25Ra26Qc295 LOCATION OF FACILITY LIHESIO5E ALABAMA REPORTING PERIOD 198O TYPE AND TOTAL NUHBER OF ANALYSIS REREORIIEO GROSS BETA 2 GAHHA (GEL I)2 CS-137 K~40 Bl 214 PB 214 TL~208 LOMER LIHIT'F DETECTION a CLLOZ25 F 000 15~000 NOT ESTAB NOT.ESTAB NOT ESTAB NOT ESTAB ALL INDICATOR LOCATIONS HEAN (F)BAt)GEJ 45i4,98(1/1)4514~98-4514~98 18 96(1/1)le 96-18'6 1950 F 00(1/1)1980 F 00-1950 F 00 1 VALuES<LLD VALUES<LLD 20e01(1/1)20 F 01 20 F 01 SHITH FARH 4~75 H ILES N SHITH FARH 4e75 HlLES N 18'6(1/1), 18e96~18'6 1950s00(1/1)1950 F 00~1950 F 00 SHITH FARH 4~/5'lLES N 20~01(1/1)20~01~20~01 LOCAZZOV)(IXV IIIGUESZ A((((UAL.VEAU'~

NAHE HEAN (F)OISIAUCE-AHO QIRECZIOH-RA((GE SHITH FARH 4514e98(1/1)4e75 MlLES N 4514e98~4514e98 CONTROL LOCATIONS HEAN ([)b RANGE 2496o29(1/1)2496 e 29~.2496~29 1 VALUES<L'LD 2152 F 00(1/1)2152~00~2152~00 19e74(1/1)19'6~19'6 lie 81(1/1)llew 81~llew 81 1 VALUES<LLD NUHBER OF NONROU TINE REPORTED BEASVREIIEHZS a.Hominal Lower Limit: of Detection (LLD)as described in Table 3.b.Mean and range based upon detectable measurements only.Fraction of detectable measurements of specified locations is indicated in parenthesis (P).

H Reservoir Honitorin Samples are collected from t'e Tennessee River as detailed in table 19.Samples collected for radiological analysis include plankton from three of these cross sections and bottom fauna and sediment from four cross sections.The locations of these cross sections are shown on the accompanying map (figure 5)and conform to sediment ranges established and surveyed by the Data Services Branch, TVA.Water Water samples are collected automatically by sequential type sampling devices at three cross sections and composite samples analyzed monthly for gamma-emitting radionuclides.

Further composites are made quarterly for strontium and tritium analyses.In addition to these required samples, grab samples were also collected monthly from the vicinity of the plant discharge to the Tennessee River, and at a point on the Elk River, and analyzed for gross beta, gamma-emitting radionuclides, and strontium.

Results are displayed in table 20.Fish Radiological monitoring for fish is accomplished by analysis of composite samples of adult fish taken from'each of three contiguous reser-voirs-Wilson, Wheeler, and Guntersville.'o 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 Browns Ferry Nuclear Plant preoperational monitoring program.Two species, white crappie and smallmouth buffalo, are collected represent'ing both commercial and game species.Sufficient fish are collected in each reservoir to yield 250 to 300 grams oven-dry weight for analytical purposes.All samples are collected semiannually and analyzed for gamma-emitting radionuclides.

The composite samples contain approximately the same quantity of flesh from each fish.For each composite a'subsample of material is drawn.for counting.Results are given in tables 21, 22, and 23.Plankton As indicated in table 19, net plankton (all phytoplankton and 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 anal'ysis, and when quantities are sufficient, for gamma activity and Sr 34 and Sr content.During'his reporting period, all samples contained in-sufficient volume of material for gross beta, strontium, or gamma analyses.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 19.Results are shown in table 24.Bottom Fauna The flesh and shells of Asiatic clams collected semiannually from the cross sections at four stations (table 19)are analyzed for gamma-emitting radionuclides.

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

A 50-gram (wet weight)sample provides sufficient activity for counting.'During this reporting period, one sample of clam flesh contained insufficient volume for analysis.Results are given in tables 25 anl 26.

Table 19.SAMPLING SCHEDULE-RESERVOIR MONITORING Biolo ical sam les collected semiannuall River/river mile Zooplankton, chlorophyll, Benthic fauna a Sediment Fish'ater samples (collected monthl)Tennessee 277.9 Tennessee 285.2 Tennessee 288.7 Tennessee 291.7 Tennessee 293.5 X Tennessee 293.7 (discharge area)X Tennessee 305.0 Tennessee 307.5.Elk 20.5 a.Gill net and/or electroshocker will be used for collection.

from Guntersville, Wheeler, and Wilson Reservoirs.

b.Automatic sampler.c.Grab sample.Samples of fish are collected Figure 5 R ES ER VOI R MONITOR IN 6 NETWORK Elk River WHEELER DAM mile 274.90 mile 277.98 Rogersvilte 0 mite 282.6~mite 285.2 rnite 29l.76 Athens 0 B.F.NUCLEAR PLANT A Champion Paper Co.0 Cour tland te 288.78 mile 293.50 mile"295.70 0 Decatur mile 305.0~-Automatic Sara ter mile 30752 Scale of Mites 0 TABLE 20.RADIOACTIVITY IN SURFACE MATER TOTAL PCl/L Qo037 BQ/L NAME.OF FACILITY,RRONUS KERRY DOCKET NO~SOaRSRaZlhOa~

LOCATION OF FAC IL ITY~LIHESIO9E 4L46454REPORT ING PER IOb 1QBO 81 214 P8-214 NOT ESTAB NOT ESTAB PB 212 NOT ESTAB SR 89-SR 90 TRIT IUH 38 38 20 10~000 Ro000 33Q~000 TYPE AND LONER LIHIT TOTAL NUMBER OF OF ANALYSIS DETECTION a REREORUEO CLLQLGROSS BETA 2'00 26 GAHMA (NAI)50 GAHHA (GELI)15 Kr40 NOT ESTAB ALL INDICATOR LOCATIONS MEAN (F)b 84blGK b 3o88(6/13)2'7" beb3 26 VALUES<LLD ANALYSIS PKRFORHED 92e20(6/13)53~90 156'D 23.30(9/13)To75 39~11 18 F 04(4/13)ll~96 R e~02 16'0(5/13).Bo04-24e93 21 VALUES<LLD ANALYSIS.PERFORMED g,l.VALUES

<LLD ANALYSls PERFORHEQ 460,e44(R/, 1R}4%le 76 489e12 TRH 293o7 BFN DISCHARGE TRH 293o7 BFN 01SCHARGE TRH 293o'7 BFN DISCHARGE TRH 285'10be54(64e34r 24.50(12'4r 19.91(19.91r 18~62(12,09r 4/6)156eRD 3/6)30~93 1/6)19~91 4/5)R4~93 TRM R85~2 489elR(1/4)489 e 1Rr 489 e 1R LOCAIIOB-MCIU hllGQESI-485UAL 5548-NAHE MEAN (F)b OISI4((CK Auo RIKE(;Ital KaME b TRH 293'3e88(6/13)BFN DISCHARGE 2'7r 6~63 CONTROL NUHBER OF LOCATIONS NONROUT INE HEAN (F)b REPORTED RaUGEb BEASUREHNIS 4'2(10/13)2'4r 12'5 24 VALUES<LLD R VALUES<LLD 13o99(1/2)13o99r 13e99 R VALUES<LLD 2 VALUES<LLD 17 VALUES<LLD 17 VALUES<LLD 599e32(1/8)599'2r 599e32'-a.Nominal Lower Limit of Detection (LLD)as described in Table 3.b.Mean and range based upon detectable measurements only.Praction of detectable measurements of specified locations is indicated in parenthesis (P).

TABLE 21 RADIOACTIVITY IN WHITE CRAPPIE (FLESH)PCI/G>>Oe037 BO/G (DRY WEIGHT)NAHE OF FACILITY BROWSES EERRYDOCKET NQ~5OmRKRB26Qa296 LOCATION OF FACILITY LIHESIOHE ALaaDdD=REPORTING PERIOD 12()Q TYPE AND TOTAL NUMBER OF ANALYSIS REEEQB1)EQ GROSS BETA 6 GAMMA (GELI)6 CS 137 K>>40 BI 214 PB 214 PB 212 LOWER LIMIT OF DETECTIONa LLLQ?0.100 0 F 020 NOT ESTAB 0'20 NOT ESTAB NOT ESTAB 0.10(0 F 08>>15ell(13e40" Oe05(Oe05 0 F 08(Oe06" Oe03(0~03-4/0~11 4/4)16,84 2/4)0'6 3/4)-0~ll 1/4)0 F 03 ALL INDICATOR LOCATIONS MEAN (F)b BDNGE b 33'9(4/4)28e97 36e75 WILSON RESERVOIR TRH R59"275 WHEELER RES TRH 275-349 WHEELER RES TRH R75-349 WILSON RESERVOIR TRH R59 275 WILSON RESERVOIR TRH R59-275 Oe 10(0'9>>15e12(13e40>>0'6(Oe06>>0 F 08(0'6>>Oe03(0 F 03>>2/2)Oell 2/2)16,84 1/2)0'6 2/2)0~11 1/2)Oe03 LOCDIIQt))(DU UIGUESI D((UUDL I)ED((NAHE MEAN (F)b QISIDHEE D((Q QIRECXIQ((-ED((GEb WHEELER RES 35e32(2/2)TRH 275"349 33'9>>36'5 CONTROL LOCATIONS MEAN (F)b BASGE b 46'9(2/2)43'8 48'1 Oe09(2/2)Oe08 0~10 17'5(2/2)16~80>>18~10 Oe06(1/2)0'6 Oe06 0 F 05(1/2)-Oe05 Oe05 2 VALUES<LLD NUMBER OF NQNRQUTINE REPORTED ((EASUBEBEBIS a.Nominal Lover Limit of Detection (~)as described in Table 3.b.Mean and range based upon detectable measurements only.Fraction of detectable measurements of specified locations is indicated in parenthesis (F)~

TABLE 22 RADIOACTIVITY IN SMALLHOUTH BU"FALO (FLESH)PCI/G>>0~037 BQ/G (ORY MEIGHT)NAME OF FACILITY&BOWLS EERRY OOCKET NOe EQn25Ra26Oa399 LOCATION OF FACILITY LIHESIOBE-

---

OL48484 REPORTING PERIOD 1980 TYPE ANO LOWER LIHIT..ALL CONTROL NUMBER OF TOTAL NUMBER-OF INDICATOR LOCATIONS LOCOIIOU MIIU UIGBESZ OUULJAL I)EOU LOCATIONS NONROUTINE OF ANALYSIS OETECTIONa HEAN (F)b NAHE HEAN (F)HEAN (F)REPORTEO REREORBEQ ILLQl ROUGE QISIOHCE OUQ QIRECEIO((R4t(GEb RO((GE ()EOSURE((EBLIS GROSS BETA 0 100 26~30(4/4)MHEELER RES 30e91(2/2)31~17(2/2)'20~48 31~03 TRM 275 349 30~78>>31~03 29~83>>32~52 GAHHA (GELI)6.-CS 137 K>>40 BI 214 PB 214 PB 212 0'20 NOT ESTAB 0.020 NOT ESTAB NOT ESTAB 0'4(Oe03 ll F 70(F 66 Oe07(Oe04-0~07(0'd 0 F 01(0'1 3/4)0 F 05 4/4)13'3 3/4)0'9 2/4)0 F 08 1/4)0.01 MHEELER RES TRH 275 349 WHEELER RES TRM 275>>349 MILSON RESERVOIR TRH 259 275 WILSON RESERVOIR TRH 259 275 MILSON RESERVOIR TRH 259-275 0~05(0~05>>12~82 (12~41>>Oe08(Oe07>>0 F 08(0 F 08>>Oe01(0 F 01>>1/2)0i05 2/-2)13e23 2/2)0'9 1/2)0 F 08 1/2)0~01 0'5(0'4>>15e39(15~08>>0~14(0~14 Oelo(Oe 10>>0'7(Oe04>>2/2)Oe05 2/2)15~69 1/2l 0~14 1/2)Oe10 2/2)Oe09-a.Nominal Lover Limit of Detection (LLD)as described in Table 3.b.Mean and range based upon detectable measurements only.Fraction of detectable measurements of specified locations is indicated in parenthesis (F).

TABLE 23 RADIOACTIVITY IN SHALLHOUTH BUFFALO (WHOI,E)PCI/G>>Oo037 BQ/G (DRY WEIGHT)NAHE OF FACILITY BRPWh(S EERRYDOCKET NO, 5Oa252r2lhOrWS LOCATION OF FAC IL ITY LIBESIOhlE

--'LABAh(4'EPORTING PERIOD 1QBQ TYPE AND TOTAL NUHBER OF ANALYSIS REREQRHEO GROSS BETA 6 GAHHA (GELI)6 CS-137 K>>40 Bl 214 PB 214 PB 212 SR 89 SR 90 LOWER LIHIT.OF DETECTION a CLLQl 0.100 0'20 NOT ESTAB Oo020 NOT ESTAB NOT ESTAB 0'00 0~100, ALL INDICATOR I.QCAT IONS HEAN (F)b b RANGE i5.ex(10o86 20'2 0.03(3/4)0'2 De03 7o63(4/4)6~25-9'7 0~11(3/4)0~08" De lb Oo ll (3/4)0 F 05 0'1 VAI.UES<LLD 2 VALUES<LLD ANALYSIS PERFORHED 0'2(2/2)0~1)0~13 WILSON RESERVOIR TRH 259<<275 WHEELER RES TRH 275-349 WHEELER RES TRH 275 349'WHEELER RES TRH 275 349 0'3(Oe03>>8~81(7e95 0~lb(De16>>0'1(0~21>>1/2)Oe03 2/2)9eb7 1/2)0~16 1/2)De 21 WHEELER RES TRH 275 349 0~12(2/2)0~ll>>De 13 LQCAZIQhl-WIZII UCGHESX 4((hlUAI IIEAhl NAHE MEAN (F)b QISEAh(CE-A((Q-OCREGIlQh(RA((GE b WHEELER RES 19oll(2/2)TRH 275>>349 17'0>>20e92 CONTROL LOCATIONS MEAN (F)b RA((GE b 13'5(2/2)ll~11>>15~99 0'3(1/2)0 F 03>>Oo03 8o38(2/2)7'5>>,8~Bl 0'7(1/~2)0 F 07>>0'7 0 F 03(1/2)0 F 03>>0'3 0 F 03(1/2)0'3>>0'3 0 VALUES<LLD NUHBER OF NONRQUT INE REPORTED hIEASURE)IEI(ZS-a.Nominal Lower Limit of Detection (LLD)as described in Table 3.b.Mean and range based upon detectable measurements only: Fraction of detectable measurements of specified locations is indicated in parenthesis (F).

HAHE OF FACILITY BRQMHS EERBC LOCATION OF FAC IL ITYLI((ESIOHE TABLE 24 RADIOACTIVITY IN SEDIHENT PC I/G 0~037 BQ/G (DRY HEIGHT)-DOCKET NO~EQn25Ra26Qa~

AL484(}4REPORTING PERIOD 1RBQ TYPE AND TOTAL NUMBER OF ANALYSIS REREORBED GAHHA (GELI)8 CO 60 CS-137 K~40 SI 214 81 212 PS 214 PS 212 RA 2Z6 RA 223 SE 7 TL 208 AC-Zas SR 89 SR 90 0~010 0~020 NOT ESTAB 0'20 0'00 NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB 0'20 0.060 lo500 0%300 0 10(5/6)Oe06-0~14 le3?t 6/6)0'4~2'6 15o79(6/6)8'0>>25'1 leS3(6/6)0'3 2'7 lo05t 6/6)Oe51 1~60 1.58(6/6)0'9 2e53 1 82(6/6}0'9 2'9 1'0(6/6)'ebb.ROAST 0'3(3/6)Oej0~0 F 80 Oe22(.1/6)0'2 0'2 0.58t 6/6}0'7 0'0 F 77(6/6)OeBZ Ze78 6 VALUES<LLD ANACYSIS PERFORMED Oe32(2/6)0'2 Oe32 LONER LIHIT ALL OF INDICATOR LOCATIONS DETECTION a MEAN (F)b LLLQ1 RANGE.TRH 293e7 BFN DISCHARGE TRH ZTT~98 TRH 288 78 TRM 277'8 TRH RSB~78 TRH 288 78 TRH R88.78 TRH 288'8 TRH 288'8 TRH 293o7 BFN 0 ISCHARGE TRH 288'8 TRH 288o78 0.10(Oe06~2'8(2'0i 20'9(14e46i le63(le45~le24 t Oe87%le91 t le 28~2~R4(1~89~1e80(le23~Oe65t Oe50r Oe2Rt OeRRi OeTlt 0'2>>2~21(]eb4e R/2)0'4 2/2)RE 36 2/2)25'l 2/2)1~85 2/2)leb0 2/2)2o5S 2/2)2e59 2/2)2'7 2/2)0 F 80 1/2)OeRR 2/2)0'0 R/2)F 78 TRH R93e7 BFN DISCHARGE Oe32(1/2)0 F 32~0'2 LQCAZIOU}(lEU HlG'UESX 4((((UAL BE48 NAME MEAN (g)b QSSE4(ICE 4((Q QIRECZIOU=R4UGE CONTROL LOCATIONS MEAN (i:)b RA((GEb 0.07(0 F 07~0'5(0,11'3e67(10~63~1e25(le 10 0'7(0 F 84~1e32(1~18~le46t le29 le 25(1 o 10~0.56(De56, 2 VALU ,1/2)0 F 07 2/2)0~99'/2)lbe71 2/2)1~41 2/2)le 10 2/2)le47 2/2)leb3 2/2)le41 1/2)De56 ES<LLD De50(2/2)0'4 De56 1~56(2/2)1~28 1~84 2 VALUES<LLD 2 VALUES<LLD NUMBER OF NDNROUTINC REPORTED t(EASUREHE((IS a.Nominal Lover Limit of Detection (LLD)as described in Table 3.parenthesis (P).b.Mean and range based upon detectable measurements only.Fraction of detectable measurements of specified l ti i i di d oca ons s n cate in TABLE RADIOACTIVITY IN CLAM FLESH PC I/G 0~037 80/G (DRY'HE IGHT)NAME OF FACILITY,BRO)(US EERRY DOCKET NO~SQn259a26Qa&N LOCATION OF FACILITYL18ESZOUE ALABA(IA'REPORTING PERIOD 1RBQ TYPE AND TOTAL NUMBER OF ANALYSIS REREORMEO GAMMA (GEL?)7 K~40 8 I>>214 PB-214 PS~212 TL 208 LOMER LIMIT OF DET(FACT ION a CLLQl NOT ESTAB NOT ESTAB NDT ESTAB NOT ESTAB NOT ESTAB 18'$(10'3 2e26(le24-3e41(le54 1~52(Oe47 0'8t 0'8 3/5)32'6 4/5)3'4 3/5)4'3 5/5)2'8 1/5)0'8 ALL INDICATOR LOCATIONS MEAN (F)b RAUGE----b TRM 288'8 TRM 293'BFN DISCHARGE TRM 288'8 TRM 277'8 TRM 293e7 BFN'ISCHARGE 32'6t 32'6m 2e39(]~24i 4'3(4e93~le 75 (1~75~0.58(Oe58~-1/2)32'6 2/2)3'4 1/2)4'3 1/1)1 e75 l/2)Oe58 LOCAXIOU)(XIV ULGUESI auUUAL IIEJLII>NAME MEAN tF)OLSIAUCE AUO QlRECIIOhl-----RkhlGEb-

--21'0(2le40'e5lt 1~34>>2'3(1~30~.2e64(le07 1~16(1~lb+1/2)2le40 2/2)3eb7 2/2)3e 37 2/2)4e22 1/2)1~16 CONTROL LOCATIONS MEAN I[)b RA 1(GE NUMBER OF NONROUT INE REPORTED IIEASUREIIEBIS a.Nominal Lower Limit of Detection (LLD)as described in Table 3.b.Mean and ranpe based upon detectable measurements only.Fraction of detectable measurements of specified locations is indi'cated in parenthesis (F).

TABLE 26 RAOlQACTIVITY IN CLAH SHELL PCI/G 0~037 BQ/0 (ORY)(EIGHT)TRH R93e7 BFN DISCHARGE TRH 277'8 0.020 Oe04(2/6)0'2 0'5 I,~78(6/6),0'3 6~96 0'e39(bt 6)0~18 0~79 0~28(2/6)0'5 0'1 Oe39(6/6)Oe14>>0 F 88 OeR9(6/6)0~11 0~47 0'.39(6/6)0.18-0,79 0~10(4/6)0 F 05 0~lS Oe46(3/6)0'2.Oe58 6,VALUES<LLO ANAiYSIS PERFORHEO 3~11(6/6)" F 97 4e08 1/Oe05 2/2)be96 R/2)Oe79 1/2)Oe31 2/2)0 F 88 2/R)Oe47 2/R)0'9 2/2)0~15 2/2)Oe58 Oe05t Oe05>>3'9(0,43>>0 F 48(0~18>>Oe31(Oe 31>>Oe51(0~14>>Oe44(Oe40>>Oe48(Oe18>>F 14(0~13>>Oe53(0 F 48>>NQT.-ESTAB 0.050 0.100 0.050 NOT ESTAB 0.050 0'20 0'60 K>>40 81 214 81 212 TRH 277'8 TRH 293'BFN 0ISCHARGE TRH 277'8 TRH 293'BFN OISCHARGE TRH 277e98 PB 214 P8>>212 RA>>226 TL 208 AC 2RB TRH 293'BFN OISCHARGE TRH 293'8FN OISCHARGE 5 F 000 SR 89 SR 90 TRH 288'8 3'0(R/2)3'l>>F 08 1.000 NAME OF FACILITY BBQ)t(IS EEBBY---------OQCKET LOCATION DP FACILITYiXBESIQIIE

'AL454)I4 REPORTI TYPE AND LDMER LIHIT ALL TOTAL NUHBER OF INDICATOR LOCATIONS LQCAIIQ(t)(IIU BIGUESI AHW4L lt(48 OF ANALYSIS DETECTION a HCAN (F)b NAME-MEAN (P)b REBEQBHEQ CLL()l: aAttGE OISIAUCE 4((Q QIBECIIQU B4QGE)t GAHHA (GELI)8 CS-137 CONTROl.LOCATIONS HEAN (F)b BA((GE 1/2)0 F 03 2/2)lel2 2/2)0~Sl 1/2)0~45 2/2)0'9 2I R)0'5 2/2)0'1 2/2)Oe17 2/2)Oe50 S<LLO 0'3(0'3>>1~08(le 05>>0 F 44(0'7>>0'5t 0 F 45>>0 F 43(Oe 3b.>>0,36t 0'6>>Oe44(0'7>>OelRt 0'7>>0'9(OeRB>>2 VALUE 4~35(2/2)3'4>>-4'5 NQ.St)iamaaZbaa224 NG PERIOD:1M()

NUHBER OF NONRQUT INE REPORTED)(EASUBE)(EHIS a.Hominal Lover Limit of Detection (LLD)as described in Table 3~b.Mean and range based upon detectable.

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

A quality control program has been established with the Alabama Department of Public Health Environmental Health Administration Laboratory and tPe Eastern Environmental Radiation Facility, Environmental Protection Agency, Montgomery, Alabama.Samples of air, water, milk, and vegetation collected around the Browns Ferry Nuclear Plant are forwarded to these laboratories for analysis, and results are exchanged for comparison.

Data Anal sis Data measured at the control'stations for each medium were aver-aged for each sampling period.In order to describe the distribution of control station data, a mean, standard deviation, and 3-sigma value were calculated.

We can expect, with 99 percent confidence, that background concentrations would be distributed within these limits.This provides us the bjsis for comparing control and indicator data.If the indicator data fall w'ithin the limits defined for control data, we can say, with 99 per-cent confidence, 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 pl'ant.Conclusions A vast ma)ority of the indicator station data was found to be within the distribution defined by the control station data.The ALPHA-M least"squares computer program 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 ALPHA-M program was greater than the cal-culated concentration.

The remaining isolated elevated concentrations may be the'result of fallout, fluctuations in the existing environment, com-puter,'program artifacts, or analytical errors.The same type of isolated high values occurred in the control station data and may be attributed to the same sources.Increased levels of radioactivity"were observed in milk, rain-water,air particulates, heavy particle fallout, vegetation, and in atmos-pheric radioiodine in October, November, and December following the atmo-spheric nuclear weapons testing conducted by the Republic of China in mid-October.

This increase was seen in control stations as well as indicator stations, and was widely reported in the eastern portion of the United Stateh.Levels;of I in milk as, high as 1.2 pCi/1 were observed.The primary radioi'sotopes identified in the'atmospheric media were 5Zr, Nb, I, 214Bi" and 103Ru.

46 Dose estimates were'ade 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 occur-ring radionuclide potassium-40, 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 that there were no significant increases in environmental radioactivity attributable to the operation of Browns Ferry Nuclear Plant.