ML18029A468

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

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

Text

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BH's RASTER FILE REOULATORY INFORMATION tDSS

./3 l IBUTION SYSTEM (RI FACIL:50 259 Browns Ferry, Nuclear Power Stations Unit 1R Tennessee 05000259 50-260 Browns Ferry Nuclear Power'tations BYNAME Unit 2I Tennessee 05000260 50-296 Br owns Ferry Nuclear Power Stations Unit 3< Tennessee 05000296

,. AUTH AUTHOR AFF lLIATION MAXHELLiR~ 8, Tennessee Valley Authority RECIP ~ NAME RECIPItNT AFFILIATION CUNNINGHAMgA,L~ Region= zp Office of Director 0.'REILLYIJ ~ P, Region zi Office of Director

SUBJECT:

Annual. Rept 1981 '" N/820505 "Environ-Radioactivity Levels<Browns Ferry Nuclear Planti 8 0430 ltrs, DISTRIBUTION CODE: IE2BL COPIES RECEIVED:LTR TITLE: Periodic Environ. Monitoring Rept (50 DKT)-Annual/Semiannual/Effluent/

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C TENNESSEE VALLEYAUTHORITY ENVIRONMENTAL RADIOACTIVITY LEVELS BROMNS FERRY NUCLEAR PLANT ANNUAL REPORT - 1981 TVA/OMS/OHS"82 7 DIVISIONOF OCCUPATIONALHEALTHAND SAFETY 8504100373'Sii231 PDR ADOCK 05000259 R PDR

ENVIRONMENTAL RADIOACTIVITY LEVELS BROWNS FERRY NUCLEAR PLANT ANNUAL REPORT - 1981 TVA OMS OHS-82 7 April 1982

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CONTENTS List of Tables ~, ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ o iii List of Figures. ~ ~ ~ ~ ~ ~ ~ iv Introduction . ~ ~ ~ ~ ~ ~ ~

Atmospheric Monitoring . ~ ~ ~ ~

Terrestrial Monitoring ~ ~ ~ ~ 23 Reservoir Monitoring ~ 0 ~ ~ 41 Quality Control. ~ ~ ~ ~ 53 Data Analysis. ~ ~ ~ ~ ~ ~ ~ ~ 53 Conclusions. ~ ~ ~ ~ ~ ~ ~ ~ 53

I LIST OF TABLES Table 1- Environmental Radioactivity Sampling Schedule 4 Table 2'- Atmospheric and Terrestrial Monitoring Station Iocations - Browns Ferry Nuclear Plant 5 Table 3- Detection Capabilities for Environmental Sampl

~ ~

Analysis 6 Table 4- Results Obtained in Interlaboratory Comparison Program. 8 Table 5- Maximum Permissible Concentrations for Nonoccupational Exposure 13 Table 6- Radioactivity in Air Filter . 14.

Table 7- Radioactivity in Rainwater. 15 Table 8- Radioactivity in Heavy Particle Fallout . 16 Table 9 " Radioactivity in Charcoal Filters 17 Table 10- Radioactivity in Milk . 26 Table. 11- Radioactivity in Vegetation . 27 Table 12- Radioactivity in Soil 28 Table 13 " Radioactivity in Well Water . 29 Table 14- Radioactivity in Public Water Supply. 30 Table 15- Environmental Gamma Radiation Levels 31 Table 16- Radioactivity in Food Crops 32 Table 17- Radioactivity in Soybeans ~ ~ 35 Table 18- Radioactivity in Poultry 36 Table 19- Sampling Schedule - Reservoir Monitoring 43 Table '20- Radioactivity in Surface Water 44 Table 21- Radioactivity in White Crappie (Flesh . 45 Table 22Radioactivity in Smallmouth Buffalo (Flesh) 46 Table 23- Radioactivity in Smallmouth Buffalo (Whole) 47 Table 24 .- Radioactivity in Sediment . 48 Table 25- Radioactivity in Clam Flesh 49 Table 26- Radioactivity in Clam Shell 50

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LIST OF FIGURES Figure l - Tennessee Ualley Region . 3 Figure 2 - Atmospheric and Terrestrial Monitoring Network. 18 Figure 3 - Local Monitoring Stations 19 Figure 4 TLD Locations, BFN 20 Figure 5 Annual Average Gross Beta Activity in Air Filters, Browns Ferry Nuclear Plant 21 Figure.6- Annual Average Gross Beta Activity in Drinking Water, Browns Ferry Nuclear Plant 37 Figure 7- Direct Radiation Levels, BFN 38 Figure 8 - Direct Radiation I,evels, BFN (4-Quarter Moving Average) 38 Figure 9- Direct Radiation Ievels, WBN 39 Figure 10 - Direct Radiation Levels, WBN (4-Quarter Moving Average) . . . 39 ll - Reservoir Monitoring Network 51 'igure Figure 12 - Annual Average Gross Beta Activity in Surface Water 52

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ENVIRONMENTAL RADIOACTIVITYLEVELS BROWNS FERRY NUCLEAR PLANT ANNUAL REPORT 1981 Introduction The Browns Ferry Nuclear Plant (BFN), operated by the Tennessee Valley Authority, is located on a site owned by TVA containing 840 acres of land in Limestone County, Alabama, bounded on the west and south by Wheeler Reservoir (see figure 1). The site is 10 miles southwest of Athens, Alabama, and 10 miles northwest of Decatur, Alabama. The plant consists of three boiling water reactors; each unit is rated at 3,293 MWt and 1,098 MWe. Unit 1 achieved criticality on August 17, 1973, and began commercial operation on August 1, 1974. Unit 2 began commercial operation on March 1, 1975. However, a fire in the cable trays on March 22, 1975, forced the shutdown of both reactors. Units 1 and 2 resumed operation and Unit 3 began testing in August 1976. Unit 3 began commercial operation in January 1977.

The preoperational environmental monitoring program established a baseline of data on the distribution of natural and manmade radioactivity in the environment near the plant site. However, seasonal, yearly, and random variations in the data were observed. In order to determine the potential increases in environmental radioactivity levels caused by the plant, com-parisons were made between data for indicator stations (those near the plant) and control stations (those remote from the plant) in conjunction with com-parisons with preoperational data.

Staffs in the Division of Occupational Health and Safety and the Office of Natural Resources carried out the sampling program outlined in tables 1 and 19. Sampling locations are shown in figures 2, 3, 4, and ll, and table 2 describes the locations of the atmospheric and terrestrial monitor-ing stations. All the radiochemical and instrumental analyses were conducted in TVA's Western Area Radiological Laboratory (WARL) located at Muscle Shoals, Alabama, and Eastern Area Radiological Laboratory (EARL) at Vonore, Tennessee.

Alpha and beta analyses were performed on Beckman Low Beta II and Beckman Wide Beta II low background proportional counters. Nuclear Data (ND) Model 100 multichannel analyzer systems employing sodium iodide NaI(T1) detectors and ND Model 4420 systems in conjunction with Germanium Ge(Li) detection systems were used to analyze the samples for specific gamma-emitting radionuclides. Samples of water, Vegetation, air particulates, food crops, and charcoal (specific analysis for I-131) are routinely counted with NaI(T1) detection systems. If significant concentrations of radioisotopes are identified, or if there is a reasonable expectation of increased radioactivity levels (such as during periods of inc'reased fallout), these samples are counted on the Ge(Li) system.

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

is routinely performed by analysis on the Ge(Li) system. A TVA fabricated beta-gamma coincidence counting system is utilized for the determination of I-131 concentrations in milk.

Data were entered in computer storage for processing specific to the analysis conducted. A computer, employing an ALPHA-M least squares code, using multimatrix techniques, was used to estimate the activities of the gamma-emitting nuclides analyzed by NaI(Tl). The data obtained by Ge(Li) detectors were resolved by the ND4420 software.

The detection capabilities for environmental sample analyses given as the nominal lower limits of detection (LLD) are listed in table 3. Samples radionuclide combinations such as 'u processed by NaI(Tl) gamma spectroscopy were analyzed for 13 specific gamma-emitting radionuclides and radionuclide combinations a . For these analyses, and sZr-Nb are analyzed as one radionuclide. All photopeaks found in Ge(Li) spectra were identified and quantified. Many of the isotopes identified by Ge(Ii) spectral analysis are naturally occurring or naturally produced radioisotopes, such as 7Be, 4oK, Bi 21~Bi 21zpb, z1~Pb, Ra, etc. LLDs for the analysis of the radio-nuclides listed below are given in table 3B. LLDs for additional radio-nuclides identified by Ge(Li) analysis were calculated for each analysis and nominal values are listed in the appropriate data tables. In the instance where an LLD has not been established, an LLD value of zero was assumed. A notation in a table of " values <LLD" for an isotope with no established LLD does not imply a value less than 0; rather it indicates that the isotope was not identified in that specific group of samples. For each sample type, only the radionuclides for which values greater than the LLD were reported are listed in the data tables.

TVA's Radioanalytical Iaboratories participate in the Environmental Radioactivity Laboratory Intercomparison Studies Program conducted by EPA-Las Vegas. This program provides periodic cross-check samples of the type and radionuclide composition normally analyzed in an environmental monitoring program. Routine sample handling and analysis procedures were employed in the evaluation of these samples. The EARL began processing samples in May 1980.

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

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

a The following radionuclides and radionuclide combinations are quantified by the ALPHA-M least-squares computer code: 141>144Ce~ 51Cr'~

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

103~106Ru'4cs.

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Table I ENVIRONMENTAL RADIOACTIVITY SAMPLING SCHEDULE Air Charcoal Rain- Heavy Particle River Well Public Aquatic Life daii t~eetatte Milk liat t Mate llatet aed dedicate Fe de Muscle Shoals W W M Lawrenceburg W W H Rogersville W W M Athens W M Decatur W H Courtland W M Site NW-1 W H Site N-2 W H A Site NE-3 W H Site NW-4 W h M Site WSW-5 W Farm B Farm Bi/Farm P Perm H Perm T Farm L Control Farms Onsite Well Wheeler Dam Elk River Tennessee River Champion Paper Co.

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

Table 2 Atmospheric and Terrestrial Monitoring Station Locations Browns Ferry Nuclear Plant Sam le'Station Approximate Distance and Direction from Plant IM-1 BF, Northwest 1.0 Mile (1. 6 kilometers)

N LM-2 BF, North 0.9 Mile (1.4 kilometers) NNE LM-3 BF, Northeast 1.0 Mile (1.4 kilometers) . ENE LM-4 BF, Trailer Park 1.7 Miles (2..7 kiloineters) NNW LM"5 BF, Davis Farm 2.5 Miles (4.0 kilometers) WSW PM-1 BF, Rogersville, AL 13.8 Miles (22.2 kilometers) NW PM-2 BF, Athens, AL 10.9 Miles (17.5 kilometers) NE PM-8 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 32.0 Miles (51.5 kilometers) W (Control)

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

Farm S 4.75 Miles (7.6 kilometers) N Farm B 7.0 Miles (11.3 kilometers) NNW Farm H 3.75 Miles (6.0 kilometers) N Farm T 7.0 Miles (11.3 kilometers) ENE Farm Bi (Out of business 4.5 Miles (7.2 kilometers) ENE 7/20/82)

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

Farm N (Control) 27.0 Miles (43.4 kilometers) NW Farm J (Control) 40.0 Miles (64.4 kilometers) NNW Farm C (Control) 32.0 Miles (51.5 kilometers) N Farm Ca (Control) 32.0 Miles (51.5 kilometers) W

Table 3 DETECTION CAPABILITIES FOR ENVIBONMENTAL SAMPLE ANALYSIS A. S ecific Anal ses NOMINAL LOWER LIMIT OF DETECTION LLD +

Fish, Air Vegetation Soil and clam flesh, Foods, meat, Particulates Charcoal Fallout Water and grain Sediment plankton, Clam shells poultry, Milk

~C1 ~cr mCi/km ~Ci 1 ~dr/ dr ~ci/ . dr ~cd/ dr ~cd/ dr ccd/irk~a cdcriik Total n 0.4 0.01 1.5 Cross n 0.005 2.0 0.05 0.35 0.1 0.7 Cross 8 0.01 0.05 2. 4 0.20 0.70 0.1 0.7 25 lN 330 l llZ 0.02 0.5 llS 0.005 10 0.25 1.5 0.5 5.0 40 10

'4Sr 0.001 2 0.05 0.3 0.1 1.0 8 2

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

Factors such as sample size, decay time, chemical yield, and counting efficiency may vary for a given sample; these variations may change the LLD value for thc given sample. The assumption is made that all samples are analyzed uithin one veek of the collection date. Conversion factors: 1 pCi ~ 3.7 x 10 Bq; 1 mCi ~ 3.7 x 10 Bq.

Table 3 DETECTION CAPABILITIES FOR ENVIRONHENTAL SAHPLE ANALYSIS B. Camus Anal ses NOMINAL LOMER LIMIT OF DETECTION LLD Air Mater Vegetation Soil and Clam flesh Foods, (tomatoes Meat and particulates and milk and grain sediment Fish and plankton Clam shells potatoes, etc.) poultry

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0 1 te 1 N 1 de Ce 0. 03 38 0.55 0.35 0.35 0.35 38 90 C 0.02 33 0 22 0.06 0.06 0.35 0.06 33 40 "Cr 0. 07 0. 03 60 44 1.10 0.47 0.60 0.10 0.60 0.10 0.56 0.60 0.10 60 44 200 90 1311 0.01 0.01 15 8 0.35 0. 09 0.20 0.02 0.20 0.02 0,07 0.'20 0.02 15 8 50 20 103 ~ 10cgu 0.04 40 0.65 0.45 0.45 0.45 40 150 10CR 0.03 40 0. 51 0.11 0.11 0.74 O.ll 40 90 13<Ca 0.01 0.02 10 26 0. 20 0.33 0.12 0.08 0.12 0.08 0.48 0.12 0.08 10 26 40 50 3 33Cs 0.01 0.01 10 5 0 20 0.06 0.12 0.02 0.12 0.02 0.08 0.12 0.02 10 5 40 15 "Zr-Nb 0.01 10 0.20 0.12 0.12 0.12 10 40 ssZT 0.01 10 O.ll 0.03 0.03 0.15 0.03 10 20 ssNb 0.01 5 0.05 0.01 0.01 0.07 0.01 5 15 "Co 0.02 0.01 15 5 0.23 0.05 0.20 0.01 0.20 0.01 0.07 0.20 0.01 15 5 55 15 s'Mn 0.02 0.01 10 5 0.20 0.05 0.15 0.01 0.15 0.01 0.08 0.15 0.01 10 5 40 15 0 sZn 0.02 0.01 15 9 0 25 0.11 0.23 0.02 0.23 0.02 0.17 0.23 0.02 15 9 70 20 "Co 0.01 0.01 10 5 0.17 0.06 0.11 0.01 0.11 0.01 0.08 0.11 0.01 10 5 30 ~ 15 ttOB K 0.10 150 2 '0 0.90 0.90 0.90 0.15 150 400 3

0.02 15 0.68 0.15 0.15 15 50 l 008a 0.02 25 0.34 0.07 0.07 0.30 '0.07 25 50 1 te 0 La 0.01 I 0.08 0.02 0.02 0.10 0.02 7 15  !

• The NaI(T1) LLD.values are calculated by the method developed by Pasternack and Barley as described in HASL-300 arid Nucl, Instr, Methods 91, 533 40 (1971). These LLD values are expected to vary depending on the activities of the components in the samples. These figures do not represenr the LLD'alues achievable on a given sample. Mater is counted in a 3.5-L Harfnelli beaker. Vegetation, fish, soil, and sediment are counted fn a 1-pint container as dry weight. The average dry weight fs 120 grams for. vegetation and 400-500 graus for soil sediment and fish. Meat and poultry are counted in a 1-pint container as dry vefght, then corrected to vet vefght using an average moisture content of 70Z. Average dry vefght is 250 grams. Air particulates are counted in a well crystal. The counting system consists of a multichannel analyzer and either a 4" x 4" solid or 4" x 5" well Nal(T1) crystal. The councfng time is 4000 seconds. All calculations are peri'ormed by the least-squares computer program ALPHA-H. The assumption fs mage that all samples are analyzed vfthin one week of the colleccion dace.

• >The Ce(bf) LLD values are calculated by the method developed by Pasternack and Harley as described in HASL-300. These LLD values are expected to vary depending on the activities of the components in the samples. These figures do not represent the LLD values achievable on given samples.

Mater is counted in either a 0.5-L or 3.5-L Marinelli beaker. Solid samples such as soil, sediment, and clam shells are counted in a 0.5-L Harinelli beaker as dry ~eight. The average dry ~eight is 400-500 grams. Afr filters and very small volume samples are counted fn petrfe dishes centered on the detector endcap. The counting system consists of a ND-4420 multichannel analyzer and either a 25z, 14z, 16x, or 29z ce(Li) detector. The counting time is normally 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. All spectral analysis is performed using the software provided with the ND-4420.

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

Conversion factorl 1 pCi 3.7 x 10 z Bq.

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

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

Date (+3a) WARL EARL (+30) WARL EARL (+3o) WARL'EARL (+3a) WARL EARL 12/80 21+9 22 23 19+9 24 26 0 2 <2 19+9 20 22 3/81 30+13 31 31 50+9 55 49 18+2.6 18 15 14+9 15 14 6/81, 28+12 29 32 54+9 62 59 19+2.6 19 23 16+9 17 18 9/81 25+11 26 25 51+9 61 54 16+2.6 16 19 19+9 21 20 B. Tritium in Urine (pCi/L)

Date EPA Value (+30) TVA AVERAGE WARL EARL 3/81 .810+549 713 390 6/81 1600+585 1637 1830 9/81 2050+599 2103 11/81 2700+615 2573 2623

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

b. Eastern Area Radiological Laboratory, Vonore, .Tennessee

c. Efficiency curves were checked and known spikes were run. Everything found was within acceptable limits.

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

d. Results were mailed to EPA but not reported by them.

Table 4 (Contd)

Results Obcained in lncerlaboratory Comparison Program E. Hi1k (pCi/L)

Scrontium - 89 Strontium - 90 Iodine - 131 Cesium - 137 Barium - 140 Potassium Cobalt - 60 value TVA AVG. EPA value TVA AVC. EPA value TVA AYG. EPA value TVA AVC. EPA value TVA AVG. EPA value TVA AVC. EPA value TVA AVG.

3 * ~R EPA IIARL EEIL ~30 IIAAL EARL MARL EARL ~3 MARI. EARL I3a IIARL EARL ~33 'MARL EARL ~30 IIARL EAIIL 1/81 0 <10 <10 20 5.2 21 20 26i17 24 21 43+16 40 41 <25 <15 1550i232 1490 1453 4/81 25i9 28 11 i2. 6 13 26+10 21 29 22i9 21 24 <15 <15 1559i135 1513 1674 7/81 25+9 23 30 17i2.6 14 16 .Oli <15 <15 31+9 32 32 <15 <15 1600i139 1623 1620 10/81 23i9 25 28 18+2.6 17 16 52i10 49 47 25+9 27 27 1530i133 1620 1500 F. Foods (pCi/kg, Met Meighc) 3/81 47i9 42 44 29i2.8 38P 119i21 126 121 53+9 56 55 <15 <15 2640i229 2857 2917 7/81 44+9 53 51 31i2. 8 31 32 82i14 80 106 45i9 43 54 <25 <25 2640i229 2870 3437 11/81 38i9 49 54 23i2.6 25 22 hone 3319 29 35 <15 <25 2730+237 2820 2720 30E 9 25 32

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

m. Resulcs vere marginally ouc of limits. Efficiency curves vere checked vich no conclusive findings. Subsequent results have been satisfactory.

n. Only tvo results vere sent to EPA. Results vere not included in cheir analysis.

o. Values for potassium are reporced as mg/kg sample.

p. Invescigacion of this problem vas initiated but no satisfactory conclusions have been reached. Me suspect difficulties arising from sample inhomogeniety.

An incorrecc veighc vas obtained in che gamma analysis of this sample. Further analysis destroyed che sample so chac the correct veighc could noc be determined.

r. Invescigacion vas conducted. No satisfactory explanation vas found. Ocher cross-checks on this isotope in different media are satisfaccory.-

Table 4 (Contd)

Results Obtained in Interlaboratory Comparison Program C. Radiochemical Analyses of Water (pCi/L) f Gross Alpha Gross Seta Strontium 89 Strontium - 90 Tritium Iodine 131 EPA value TVA AVG. EPA value TVA AVG. EPA value TVA AVG. EPA value TVA AVG. EPA value TVA AVG. EPA value TVA AVG.

Dat ~RD MARL EARL ~

(i3o) MARL EARL (i30) MARL EARL (i3a) MARL EARL (i3o) MARL EARL ~(-3R IIAIIL EARL 1/81 9+9 10 9 44i9 49 49 16+9 11 14 34i3. 1 388 28 2/8 1 1760+591 1917 1753 3/81 25+ 10 23 )5i 25+9 26 29 4/81 2710i615 2467 2723 30i10 32 28 5/81 21i9 21 14 14+9 14 16 36+9 40 33 22+2. 6 21 22 6/81 1950i596 1990 1947 7/81 22+10 20 22 15+9 15 18 8/81 9/81 33+14 29 18 i 28i9 29 26 23+9 26 23 11+2. 6 11 10 2630+613 2623 2713 73+13 79 73 10/81 2210i603 2263 2197 11/81 2L+9 21 13 23i9 18 24 12/81 2700i615 2717 2807 76+13 65 56 D. Gamma-Spectral Analysis of Water (pCi/L)

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

Dat* ~ARI MARL EARL ~33) IIARL EARL ~33 IIARL EARL ~AEI MAIIL EARL ~t3 ~ WARL EARL ~t33 MARL EARL 2/81 0 <60 <60 ~ 25+9 25 25 85+9 84 83 0 <40 <40 36+9 39 35 . 4+9 6 10 6/81 0 <60 <60 17+9 18 17 0 <15 <15 15i9 <40 <40 21i9 23 21 31+9 27 30 10/81 34+9 <60 <60 22i9 25 22 24i9 26 21 0 <40 <40 21i9 21 24 32i9 35 32

f. Specific analysis for '

to test the procedures used for the analysis of milk.

g. Investigations of the analytical procedure were conducted and new efficiency curves were determined. Results have been satisfactory since that time.

h. New efficiency curves were determined subsequent to this analysis. Subsequent results were satisfactory.

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

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

Four local air monitors are located on or adjacent to the plant site in the general areas of greatest wind frequency. One additional station is located at the point of maximum predicted offsite concentration of radionuclides based on preoperational meteorological data (see figures 3 and 4). Four per'imeter air monitors are located at distances out to 10 miles from the plant., and two

.remote air monitors are located at distances out to 45 miles. These monitoring stations are shown in figure 2. The remote monitors are used as control or baseline stations. At each monitor, air is continuously pulled through a Hollingsworth and Voss LB5211 glass fiber filter at a regulated flow of 3 fts/min. In series with, but downstream of, the particulate filter is a charcoal filter used to collect iodine. Each monitor has a collection tray and storage .container to obtain rainwater on a continuous basis and a hori-zontal platform that is covered with gummed acetate to catch and ho3.d heavy particle fallout. Thermoluminescent dosimeters are used to record gamma radiation levels at each remote and perimeter station.

Each of the local air monitors is fitted with a GM tube that con-tinuously scans the particulate filter. The disintegration rate of the atmospheric radioactivity is continuously recorded at each station and radio-.

'telemetered into the plant.

Air filters are collected weekly and analyzed for gross beta activ-ity. No analyses are performed until three days after sample collection. The samples are composited monthly for analysis of specific gamma-emitting radio-nuclides and quarterly for Sr and oSr analysis. The results are combined for each station to obtain an annual average. During this reporting period, three samples were not obtained because of equipment malfunction, These data are presented in table 6.

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

, figure 5. Increased levels due to fallout from atmospheric nuclear weapons testing are evident, especially in 1969, 1970, 1971, 1977, 1978, and 1981.

These patterns are consistent with data from monitoring programs conducted by TVA at nonoperating nuclear power plant construction sites. Table 5 presents the maximum permissible concentrations (MPC) recommended by 10 CFR 20 for nonoccupational exposure.

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

, specific gamma-emitting radioisotopes and tritium. The results are shown in table 7.

The gummed acetate that is used to collect heavy particle fallout is changed monthly. The samples are ashed and counted for gross beta activity.

The results are given in table 8.

12 Charcoal filters are collected and analyzed for radioiodine.

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

13 Table 5 MAXIMMPERMISSIBLE CONCENTRATIONS FOR NONOCCUPATIONAL EXPOSURE In Water In Air

~C1/1+ ~Ci/m +

Alpha 30 Nonvolatile beta 3; 000 100 Tritium 3,000,000 200,000 137( 20,000 500 10 3 i 106Ru 10,000 200 144( e 10;000 200 "Zr-"Nb 60,000 1,000 140La

'40Ba 20,000 1,000 131I 300 100 sszn 100,000 2,000 64wn 100,000 "',000 60C 30,000 300 89Sr 3,000 300 90S 300 30 s1C 2i000,000 80,000 1 34Cs 9,000 400 58Co 90,000 2,000

• 1 pCi ~ 3.7 x 10 Bq.

TABLE 6 RADIOACTIVITY IN AIR FILTER PCI/H(3) - 0 ~ 037 BG/H(3)

NAHE OF FACILITY ~CHERRY DOCKET No>>~0-25~9~?96 LOCATION OF FAC'ILITY LIHCSTOQQ A A AHA REPORTING PER I OD 9 TYPE AND LOVER LIHIT ALL CONTROL NUHBER OF TOTAL NUHBER OF ANALYSIS OF DETECTION +

, INDICATOR LOCATIONS HEAN qF)b Log!IIIQ~nv" BlkUggI NAHE al!5I!JIL"La5--

HEAN (F)b LOCATIOtiS HEAN (F)b NONROUT INE REPORTED Pf R fOR~HE ~~LQ RAN('tl" ~$ $ A~C~A(~~R~T~O RAhg~+ R~Nt(f, b ~HA S~UR ~HN T 5 GROSS ALPHA 0 ~ 005 0 ~ 01( 3/ 52) 52 C ~ 01- 0 ~ 01 GROSS BCTA 0 010 (.08( 4S6/ 465)

Dl-LH4 BF TRAILER P 0 '9(

01-50/ 52) oe08( 103/ 104) l-569 0 ~ 0%38 1 ~ 7 HI LES NNM 0F 0 ~ 36 0 0 0 ~ 39 GAHHA (NAI) 49 CE-14 1e 144 0~ 030 0F 05(

03-8/

0 '6 39) LH3 BF NORTHEAST 0 HILE ENE 0 F 06(

06 llD.O6 4) 0 F 0%03" 04( 4/ lc) 0%07 RU-103 '06 0>>C40 D~

0 0

'5(

'5C6( 20/5/ '639) 0 39) 1 ~

LH3 BF NORTHEAST 1 ~ 0 NILE ENE 0

0 0 '6(

~

~

06-ll -4)

DE 06 0%05(

0>>D5 2/

0 10) 05 ZR-95iNB-95 (GELT) 0 '10 0 ~ ATHENS'L 0~ 13( 1/ 3) 0 06( 5/ 10) 0~ 01- 0%13 10.9 HILES NE 0 ~ 13- 0~ 13 De02- 0 ~ 13 I-131 0 010 0~ 02( 6/ 39) DECATUR'L 0 ~ 02( 1/ 5) 10 VALUES <LLD 0~ ol- 0 ~ G2 8 ~ 2 HILES SSE 0 ~ 02- 0 02 BE-7 35/ ATHENS'L '2( 3/

~

10/

09( 39)

'1 3) 1D(

'310)

NOT ESTAB 0 F 0 0 ~

0%01- 0 ~ 21 10 ~ 9 HILES NC 0 ~ 07- 0 0 F 05- 0 ~

GAHHA 94 CE-141 0 010 01( 8/ 78) ATHENS'L 0 '2( 1/ 10) 16 VALUES (LLD CE-144 0

~

C2C 0~

0% 01-04(

0 16/ 78)

'2 10 9 HILES NE ROGERSVILLEe AL 0 '2" 05(

0 2/

~ 0?

10) 0 12( 3/ 16)

~ 0~

0%02 0%07 13 ~ 8 rlLCS NM 0

0 F

~ 04- 0 F 07 0 '2-

~

0 ~ 30 RU-103 NOT ESTAB 0 ~ Gl ( 38/ 78) LH1 BF NOPTHMEST 0 '2( 4/ 8) 01( 7/ 16)

~ ZR-95 D~ 010 0>>

D~

00-03( 34/

0 F 03 78) 1 ~ 0 HILE N ROGERSVILLCw AL 0>>01-0 F 04(

0 '3 5/ 10) 0 0

0 F

F

'2(

01-8/

0 F 02 16) 0 ~ 01 0 06 13 ~ 8 rlLES t(M 0 ~ 02- 0 ~ 06 .0 Gl- 0 03 NB-95" 0~ 010 05( 40/

F

78) DECATUR'L 0 '7( 8)

~

D>>05( 8/

~

16)

K-40 NOT. ESTAB 0~

0%01-0 12( 58/

0~ 15 78) 8 ' MILES SSE LH2 BF NORTH 0 ~

0>>16(

03- 0 3/

~ 12 6) 0 '2 0%13( 13/

0 ~ 09 16) 0 ~ 06-

'4( 0 'C 0 ~ 9 NILE INC 0 ~ 12- 0 ~ 18 0 ~ ll- 0~ 16

.8 I-214 0 '20 0 44/ 78) DECATUR'L 0 F 05( 6/ 8) 0>>04( 7/ 16) 0 ~ 02- 0 ~ 09 8 ~ 2 HI LES SSE 0 ~ 02- 0 F 09 0 ~ 03- 0 ~ 08 81-212 NOT ESTAB 0 04( 1/ 78) DECATUR'L O.04( 1/ 8) 16 VALUES CLLD PB-214 0>>020 0 ~ 04 G~ 04(

0 28/ 78)

'4 8>>2 HILES SSC DECATUR'L 0 ~ 04-0 F 05(

0 '4 3/ 8) 0 '3( 6/ 16) 0 ~ 02 0 ~ DR 8 2 HILES SSE 0>>03- 0 ~ 07 0 ~ 02- 0 ~ 07 PB-2)2 NOT ESTAB 0 ~ 01( 35/ 78) LH3 BF NORTHEAST 0 '2( 1/ 9) 0 ~ 01( 7/ 16)

DE-7 C.osr 0 F 0%08(

00 0 41/ 78)

'3 1~0 HILE ENE DECATUR( AL 0 ~

0 '6(

02- 0F 5/

02 8) 0 ~ 00-0 ~ 07( 9/

0 ~ 02 16)

TL-208 NOT ESTAB 0 ~ 05-0 ~ 01( 14/

0 47 78) 8 ~ 2 HILES SSE LH4 BF TRAILER P 0 05-

~

0 F 01(

0 2/

'7 7) 0 ~ 05-0 F 01( 3/

0 ~ 10 16)

D>>DO 0 F 01 1 ~7 HILES NNM 0 ~ 01- 0 F 01 0%01- 0 F 01 LH5'F SR RR 89 O.DOS Ceool 0>>G1(

0 ~ 01 0 F 00(

18/

7/

0 F 36) 01 36)

DAVIS F 2 ~ 5 HILES MSM ROGERSVlLLEe AL 0~

0 0

~

~

01(

Ol-00(

2/

0>>Dl ll ') 4) 0 0

F F

01(

0 ~ 01-00(

4/

3/

0 ~ 01 8) 8)

RADIOACTIVITY ltt RAI)%MATER PCI/L - 0.037 Ba/L NAHE OF F AC ILITY RR~~(FERRY DOCKET NO%~5-~~96~

LOCATION OF F AC I L I T Z L IH~STO~tt tLABAHA REPORTING PERIOD~~9 I

TYPE AMD LO) EP. L I HI T ALL CONTROL NUHBET OF TOTAL i(UMBER OF INDI CATOF LOCATIONS LOCATIONS NONROUTINE OF ANALYSIS DETFCT I ON a HEAt( (F)b MEAN (F) b REPORTED PERFORHEO (QQD) RANGc b R ~~Gb GAHHA (MA I )

97 CE 14 li144 38 000 77 VALUES <LLO 43 '0- I/ '0 43 ~ 60l 43 20)c RU-103%106 40 F 000 48 48

'0(

20-1/

48 '0 77) DECATUR% AL 8 ~ 2 HILES SSE 48 '0l 48 ~ 20-1/

48 '0 8) 20 VALUES <LLD ZR-95 'tB-95 15 '2( 19/ 77) LH4 BF TRAILER P 20 '0C 3/ 8) 19 '3( 3/ 20) 25 '0 10 '0-10 MOOG 10%10- 25 ~ 10 1%7 HILES NNM 15 ~ 60- 35 10 F

1-131 15 F 000 22%10( 1/ 77) LH5 BF DAVIS F 22%10( 1/ 6)- 2C VALUES <LLD 22 ~ 10- 22 ~ 10 2 ~ 5 NILES MSM 22 F 10 22 '0 51 ~ 80( 49/ LHS BF JA V IS F 67 F 88( 4/ 6) 56 F 86( 14/ 20)

BE-7 NOT ESTAB 7 ~ 30-llew 133 '077) 2 ~ 5 HILES MSM 39 ~ 70- 115 '0 14 F 00- 10'0 GAHHA (GELI) 46 2R-95 10 F 000 40 VALUES <LLO 10 '2( 101/ '2 6) 10%12-t(B-95 5 F 000 9%63( 2/ 40) LHS BF DAVIS F 10 '2( 1/ 7) 13 '2(

13 '2-I/ 6)

K-40 81 8 ~ 93-57(

10 '2 21/ 40) 2 ~ 5 HILES MSM LH3 BF ttORTHEAST 10 ~ 32-125 F 00(

$ 0%32 1/= 6) 58 F 19(

13 82 2/

F 6)

NOT ESTAB 32 '1- 125 F 00 I ~ 0 HI LE EtiE 125%00

'3l 125 F 00 54 '9- 61 78 8 I-214 NOT ESTAB 22 '9(

52-25/

48 '8 40) LH3 BF NORTHEAST 1 ~0 NILE ENE 29 16 ~ 24-4/

48 '8 6) 40 ~ 21 l 23 '9- 3/

70 '1 6)

PB-214 NOT ESTAB 17 '5( 12/ 40) LH3 BF NORTHEAST 28 '8( 1/ 6) 11 '6( 2/ 6) 9 '1- 29 '7 1 ~0 HILE ENE 28 38- 28 '8 8~ 9S 14 16 18 '9(

~

PB-212 MOT ESTAB 14%32( 8/ 40) COURTLAtiDe AL 1/ 3) 6 VALUES <LLD 8 '9-DE-7 t(OT ESTAB 49 '5(

43 '8-18q09 3/ 40) 54 '6 10 ~ 5 BILES MS V LH5 BF DAVIS F 2%5 HILES MSM 18 ~ 09-49 '5(

43 ~ 28-18%09 3/

54 F 06

7) 105 F 00(

.105 F 00-1/

105%00

')

TRIT IUH 330 F 000 117 VALUES <LLO 26 VALUES <LLD 143 ANALYSIS FERFGRHED

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

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

c. Identified as fallout.

HEI TAFLE 8 RADIOACTIVITY IN HEAVY PARTICLE FALLOUT

/KH(2) 37000060 ~ 60 bQ/KH(2) hAHE OF FACILITY 8~RlltJS FJRf(Y DOCKET No.~gg~298

(.OCATIOV OF FACILITY (.(RESTORE ALABAHA REPORTING PERIOD~981 TYoE Ah.D LOVER L IHIT ALL CONTROL NUMBER OF TCTAL t>UMBER OF 'INDICATOR LOCATIO) S I LOCA I Gt) I+/JH H~GHQQ~A~(NUQ~H~AN LGCATIONS NONROUTINE OF ANALYSIS DETECT IONa t(EAN (g)b NA)tE HEAN (F) b HEAN (F)b REPORTED P~(:F ~OH// ~RAN b rEASUREVE)tTS GPOSS BETA '50 G9( 117/ 117) LH4 BF TRAILER i+35( 13/ 13) 1-04( 2e/ 2e) 143 0 1~

0~ 08- 3 '3 1 ~ 7 HILES NNM P

0~ 16- 3 '3 0+12- 2 '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).

TABLE 9 RADIOACTIVITY Iti CHaRCOAL FILTERS PCI/H(3) - 0 ~ GI37 BG/H(3)

NAME OF FACILITY QfiQVCS fE'R'RY DOCKET NO ~ 50-259N260+296 LOCATION OF FACILITY LINGSTONQ ALaoaHA REPORTlhG FERIOD~)9 TYPE AND LOMER L IHIT ALL CONTROL NUHBER OF TOTAL t)UHBER OF INDICATOR LOCATIONS LOCATIONS tAONROUT ItRE OF ANALYSIS DETECTIONa HEAR (f )b NAHE GIRD'TIOID HEAN RANGf (f)b MEAN IF/'AN REPORTED

~HAS~UR tA~hTS (Lt P) AN(t~ QIGT~AMC PQR~~ORH 0 R

'3(

~AM 2/ '2( 13/ 10%)

IODINE IN AIR 570 0 ~ 020 0

0

'2- 62/ 466) 0 '9 COURTLAND ~ AL 10 ~ 5 MILES VSb 0

0 '206(

~

0 '950) 0 0 '2- 0 '%

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

b. Mean and range based upon detectable measurements only. Praction of detectable measurements of specified locations is indicated in parentheses'(P).

~

18 Figure 2

.. ATMOSPHERIC AND TERRESTRIAL MONITORING NETWORK RM.2BF L AWRE NCEBURG yPULASKI FAYETTEVILLE +

PM-IBF WILSON WHEELER ROBE SVIL OAM ATHENS FLORENCE PM-2BF FFIEL MUSCLE HUNTSVILLE SHOALS BROWNS FERRY NUCLEAR PL NT RM. I BF LEIGHTON TU SCUM BIA COURTLAN0$

PM-4 F OECAT PM 3BFO IO MILES pRUSSELLVILLE SVILL NT HARTSELLE OAM 25 HALEYVILLE CULLMAN 45 MILES Q- ENVIRONMENTAL MONITORING STATeN NOTE: THE FOLLOWING SAMPLES ARE COLLECTED FROM EACH STATION:

AIR PARTICULATES RAINWATER RADIOIODINE SOIL HEAVY PARTICLE FALLOUT

Figure 3 LOCAL MONITORiNG STATIONS. 19 BROWNS FERRY NUCLEAR PLANT ATHENS US HV/Y 72 BFN ALA. HWY 20 Legend

~ Air Monitor DECATUR A Automatic Well Sampler N H Dairy Farm Scale 0 I 2 3 4 5 Miles

20 Figure 4

, .I)I 'Itiff I ~

j

'i I I ~

'I ~

rr I pt ()j>>

>>I I>>

ll~ r J

~

I, >> .t H/p '5 I it

>> I~It ~

I 4 ~

'4 t,l fl,.

'. '('

It rr 5 A

~<< ( PJ'

~

~ il (I \

I

<<)

I I 0

'I I r

(

l,t 5 'I

'J I I I

l I

I

~

Q .I w'

,(.'

I ,'

wtw I Il Pr. I.; ~I

'. l5 ('. ~

f(

I)

}, ~ If I

~

>I, <> ~

I pI s

(

I I ~

A

~ t

~ aS

~I

~ .I<<II 4 <<". ~ .I I l I i P'I4 r 5. ~ * 'I I

(

i I w

I ~

il Jtt',,>>  !

("4 >>if t I

f e

f lpr>>f.

}r,

~ r' I

i"

~ -

Jl 5 I r ~h tt >>I r>>

I ~ Wt >>>>>>I

~ >> IW ~

T I i

<< ~ II was>>>>>> '

~ t~ ~

I

~~

figure 5 ANNUAL AVERAGE .

.30 6ROSS BETA AC:TIVITY IN AIR FILTERS BROWS FERRY NUCmR PLANT Preoperational Phase Operational Phase

.25 CC 0

0 0

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

4J a o 44 C

0 0

.15 Average: Preoperational 4

Phase

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

,1 ~

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

Cow censuses were conducted in May and September 1981. It was determined that'here are no dairy farms nearer the plant than the nearest farm being sampled. During this period however, one of the dairy farms being sampled (farm B, table 2) went out of business and all,cows were sold. Another dairy farm (farm P) was added to the monitoring program on August 3, 1981.

~Ve etation Vegetation is sampled quarterly at the farms from which milk is collected and analyzed for gamma-emitting radionuclides. Approximately 1-2 kilograms of grass is broken or cut at ground level and returned for analysis.

Efforts are made to -sample vegetation that is representative of the pasturage where'cattle graze. Table 11 gives the results obtained from the laboratory analyses of these samples.

Soil Soil samples are collected annually near each monitoring station to provide an indication of a long-term buildup of radioactivity in the environ-ment. An auger or "cookie cutter" type sampler is used to obtain samples of the top two inches (5 cm) of soil. These samples are analyzed for gamma-emitting radionuclides, Sr, and Sr. The results are given in table 12.

Ground Mater An automatic sequential-type sampling device has been installed on a well downgradient from BFN. A composite sample from this well is analyzed for gamma-emitting radionuclides monthly and composited quarterly for determination of tritium. A grab sample is also taken from a control well upgradient from the plant. The results of the analysis of well water are shown in table 13.

Potable water supplies taken from the Tennessee River in the vicinity of BFN are sampled and analyzed for gross beta and gamma-emitting radionuclides, and composited quarterly for tritium, Sr, and oSr analyses. The first potable water supply downstream from the plant is equipped with an automatic sampler with samples collected and analyzed weekly. The sampler is located on the water intake structure and takes the sample from the river as the raw water is drawn into the water treatment facility. Two additional supplies

24 downstream and one public water supply upstream are sampled by taking monthly grab samples of treated water at user points. Table 14 indicates the results from the analysis of drinking water samples. During this reporting period, six of the weekly samples were not taken because of the malfunction of automatic sampling equipment.

Figure 6 shows the trends in gross beta activity in drinking water from 1968 through 1981. The annual average level from the raw water samples tends to run slightly hi:gher than the average for treated water samples; however the levels are consistent with the activities reported in surface water samples taken upstream from BFN (figure 12) and in samples taken from the Tennessee River in preoperational monitoring programs conducted by TVA at other sites.

Environmental Gamma Radiation Levels Bulb-type Victoreen manganese-activated calcium fluoride (Ca~F: Mn) thermoluminescent dosimeters (TLDs) are placed at sixteen stations around the plant near the site boundary, at the perimeter and remote air monitors, and at nineteen additional stations out of approximately five miles from the site to determine the gamma exposure rates at these locations. The dosimeters, in energy compensating shields to correct energy dependence, are placed at one meter above the ground, with three TLDs at each station. They are approxi-'ately annealed and read with a Victoreen model 2810 TLD reader. The values are corrected for gamma response, self-irradiation, and fading, with individual gamma response calibrations and self-irradiation factors determined for each TLD. The TLDs are exchanged every three months. The quarterly gamma radiation ~

levels determined from these TLDs are given in table 15, which indicates that average levels at onsite stations are approximately 2-4 mR/quarter higher than levels at offsite stations. This is consistent with levels reported at TVA's nonoperating nuclear power plant construction sites where the average radiation levels onsite are generally 2-6 mR/quarter higher than levels offsite. The causes of these differences have not been completely isolated; however, it is postulated that the differences are probably attributable to combinations of influences, such as natural variations in environmental radiation levels, earth moving activities onsite, the mass of concrete employed in the con-struction of the plant, and other undetermined influences.

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

Prior to 1976 measurements were made with less sensitive dosimeters, and consequently the levels reported in the preoperational phase of the moni-toring program are 1-2 times the levels reported herein. Those data are not included in this report. Therefore, for comparison purposes, figures 9 and 10 depict the environmental gamma radiation levels measured during the constructior of TVA's Watts Bar Nuclear Plant to the present. Note that the data follow a similar pattern to the BFN data and that, as discussed above, the levels reported at onsite stations are similarly higher than the levels"at offsite stations.

25 Poultr and Food Cro s Food crops and poultry raised in the vicinity of BFN and at control locations are sampled as they become available during the growing season, and analyzed 'for gamma-emitting radionuclides. During this sampling period, samples of cabbage, corn, green beans, peaches, potatoes, turnip greens, tomatoes, soybeans, and poultry were collected and analyzed for specific gamma-emitting radionuclides. No sample of soybeans or cabbage was taken from a control location. The results are given in tables 16, 17, and 18.

TABLE 10 RADIOACTIVITY IN HILK PCI/I. 0 '37 BO/L NAHE OF FACILITY ~RR VNS FjRRY DOCKET t(O ~ 50-25~92~60 296 LOCATIOII OF FACILITY~IIIGTOIIC ALAHAHA RCPORTIttG PERIOD 1'9&1 TYPE ANO LOMER LIHIT ALL CONTROL NUHBER OF .

TOTAL NUHBER OF I)COICATOR LOCATIONS LOCA T~IH IIITH Hj~GH GT Al~lt HAL IITAH LOCATION) NONROUTINE OF ANALYSIS DET EC T IO "A HEAto (F )b NAIIE HEAN ([) HCAN (g) REPORTED

~(Q ) R~A'Qf b QIQJAH~AHQ Cmf,c~lo AAHTTC ~V. Agghf.~llNTS GA)IHA (NAI) 107 CS-137 3/ 3/ '0(

K-40 10 F 000 13H63 (

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

PAGE FARH 8 ~ 75 )(ILES E 13H63(

llo70-

'1( 16 F 00

4) 10 10H20

'5(

1/

10 '652) 12/ 52/ 52)

IODINC IN HILK 150 F 000 OH500 1049H30 1569H20 253 VALUES <LLO THRASHER FARHA 7~0 HILES ENE 1308 1127 '0- 1569 '012) 1232 1037 '0 1391 F 80 201 VALUES <LLD 454 ANALYSIS PERFORI,CO GAHHA (GELI) 6 CS 137 F 000 8 '0( 3/ 6) SHITH FARH 10 F 16( 1/ 1)

K-40 NOT ESTAB 7 54-1500 F 50(

10 6/ 6) 4 ~ 75 HILES THRASHER FARH N 10 ~ 16-1845.00(

10 1/

'6 1) 1287 F 00- 1845 F 00 7HO )(ILES ENE 1845 ~ 00- 1845 F 00 BI 214 NOT ESTAB 20H63(

'9- 5/ 6) SHITH FARH 30 '3( 1/ 1)

PB-214 EST/8 7

18 '5(

30 3/

'3 6) 4H75 HILES BROOKS FARH N 30 ~ 43-20 '3(

30 1/

'3 I) 14 '9-NOT 20 '3 7~0 HILES NNM 20 63- 20 '3 PB-212 NOT ESTAB 14H88( 3/ 6) SHITH FARH 20 '6( 1/ 1) 9 '3- 20 '6 4H75 HII ES N 20 96- 20H96 TL 208 '3( 2/ 6)

~

6.48( 1/

SR 89 NOT ESTAB 10 F 000 61 4

F 18- 6 '8 VALUCS <LLD PAGE FARH 8 ~ 75 BILES E 6 ~ 48- 6 '8 1) 52 VALUES <LI.D 113 ANALYSIS PERFORATED

'5( 61/ 61) 74( 13/ 40/

'913) 33(

'652)

SR 90 F 000 3 SHITH FAR)I 4 4 113 2. 01- 8.19 4H 75 HILES N 3~

~

12- 8 2 '6-

~

7

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

b. Hean and range based upon detectable measurements only. Fraction of detectable measurements of specified locations is indicated in parentheses (p).

TABLE RAOIOACTIVITY IN VEGETATION PCI/O - 0~ 037 80/G (ORY MF IGtlT)

NAME OF FACILITY HROMNS FERRY LOCA T 10tt OF FAC IL I TY L IMESTOttE TYPE RNO LOVER LI HIT ALL CONTROL NUNBER OF TOTAL NUNBCR OF INDICATOR LOCATIONS LO AT ON VT TK KIGKEST ANNUA tlEAN LOCATIONS NONROUT INE OF ANALYSIS OETECTIONa MEAN ( )b NAME NCAN (F)b REPORTED PEP.FORi)ED ~(eO) ~RCCC ~gP~NC AtlQ QIQ~TIQtP ~A~b Qf~k~kklI-GROSS BETA 0 ~ 200 26 '3( 20/. 20) BITTING FARM 35 ~ 32( 2/ 2) 26052(

'7- 16/ 16)

GAHHA (GCLI) 36 7 70- 48082 4~5 NILES Et(C 31088- 38075 10 45 '4 38 CE-141 0 '00 5/

2092

21) THRASHER FARM 7 ~ 0 MILES Ct(C 2 '2(

2 ~ 92-ll 92 4) 2~

1 ~

1~

93(

16-4/

2 '6 17)

CE 0 '20 17/ 21) LOONEY FARM 2060( 2/ 4) 1069( 13/ 17) 5 ~ 49 5075 )(ILES CNC 0 41- R ~ 80 0030- 5025

>P.-14 4 NOT ESTAB 3/ 21)

'121) LOONEY FARM 4 '1( 1/ 4) 2 71( 1/ 17)

RU-103 0 '00 6/

4 5 75 MILES ENE LOONEY FAR)1 4 ~

1053(

61-1/

4 '1 4) F 71-1 ~ 39( 4/

2 '117)

F 14 5075 HILES ENE 1053- 1053 1 ~ 10- 1 ~ 65 RU-106 0 '10 2/ 21) THRASHER FARM 1 SR( 1/ 4) 11( 2/ 17)

CS-137 0 '60 14/

1054 21)

.7.0 HILES ENE SITTING FARH l054-0 ~ 32( 1/

1054 2) 1~

0 '921( 7/

1 ~ 34 17) 2R-95 0

10/ 21)

'2 405 t(ILES ENE BITTING FARtl 0032

'5( 1/

0032 0

0 '6-

~

0 ~ 40 0~ 110 3 2) 90( 8/ 17) 4 '6 4 ~ 5 HILES ENE 3 ~ 95-

'8(

3 '5 0 1~

'0- R031 NB-95 0 '50 18/ 21) BITTING FARM 2/ 2) 2 '5( 13/ 17) 10 '8 '9 4

4~5 MILES ENC 0 8 ~ 36 0 '6- 9026 K-40 '(OT'ESTAB 21/ 21) 25 '8 BROOKS FARM 700 HILES ht(M 12 '6(

2088-4/

22 '6 4) ll2023-37( 17/

28 95 17)

MN-54 0 '50 3/ 21) 0 '0 THRASHER FARM 7 ~ 0 MILES ENC 0 F 10(

1G-ll0010 4) F 10(

0 '8- 4/ 17)

~ 0~ 12 Y-88 NOT ESTAB 1/ 21) OITTING FARN 0002( 1/ 2) 17 VALUES (LLO RI-214 0 '00 9/

0002 21) 405 .'IILES ENE BITTING FARH 0 '2 0049( 1/

0~ 02

2) 0 ~ 30( 10/ 17) .

BI-212 t(OT ESTAB 1/

0 ~ 62 21) 4 05 MILES CNE LHI BF r(ORTHMEST

'0 ~ 49-0 '3( 1/

0 '9 1) 0011-17 VALUES (LLO 0'064 PB-214 0 '3 19/ 21)

I ~ 0 HILE N BITTlt(G FARH 0 33-

'7( 2/ 2)

~ 0~ 33 NOT ESTAB 0021( 12/ 17)

PD-212 NOT ESTAB 20/

0 ~ 41 21) 405 tlILES ENC LH1 BF NORTHMEST 0

0016 0~ 72( 1/

0 '8 1) 0010-F 17( 14/

0050 17)

RA-226 NOT ESTAB 3/

0 ~ 72 21) 1 ~ 0 HILE BROOKS FARil N 0 ~ 72-0014( 1/

0072 4) 0 0'04-0007(

0 '3 2/ 17) 0 ~ 14 7~0 NILCS NNM 0 ~ 14- 0014 0 03- 0011 BE-7 NOT FSTAB 21/ 21 ) LOONEY FARY. 7 '7( 4/ 4) 5

~

'6( 17/ 17)

TL-208 NOT ESTAB 15 ~ 63 16/ 21) 5 ~ 75 NILES CNC LH1 BF NORTHliEST 1012-29(

13 F 61 1/ 1) 2~ 29-05(

14 '0 9/ 17) 0 '9 100 MILE N 0

0

~

~ 29- 0 '9 0F 0001- 0 ~ 16 AC-228 NOT ESTAB 18/ 21) LH1 BF NORTHMEST 0 '6(36-1/ 1) 0017( 14/ 17) 0 F 48 1 ~0 MILE N 0 ~ 0 36 0 ~ 02- 0 ~ 52

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

b. Mean and range based upon detec table measurements only.. Praction of detectable measurements of specified locations is indicated in par'entlieses (P).

TABLC 12 RADIOACTIVITY IN SO IL PCI/G - 0 ~ D37 8(F/G (ORY INC IGHT)

NAME OF FACILITY PRGVHS FERRY (AOCKET !JO ~ 50~5<a 2~60 296 LOCATION OF FAC ILITT~LII! STONC ALA"AHA REPORTING PERIOD~)

TYPE A!JD LO'MER LIMIT ALL CONTROL NUHBER OF TOTAL NUHQCR OF INDICATOR LOCA TI0!JS NONROUTINE OF ANALYSIS DETECTION HE AN (E') LOCATION/

HEAN ([) REPORTED P~CR 0 R Y~C (LLO) R AN~G jusTANO~ ANR I~R .FIRN RaljR4, RANGE ~HASURE~HNTS GAHHA (GCLI )

CE-14 1 ll 0~ 030 0~ 06( 1/ 9) LH2 BF NORTH 0% De( ll 36 1) '696(

2 VALUES <LLO o.oe- D.ne 0 9 HILC NNC 0~ Ce- 0 ~

CE-144 0%G60 0 ~ 13( 4/ 9) ROGERSViLLC ~ AL 0 ~ 24( 1/ )) 10( 2/ 2)

RU 103 NOT ESTAB 0F 08-02( 4/

0 24 9) 13 ~ 8 HILES N)s LH1 BF IVORTHMEST 0~ 24-

'3( 1/

0 ~ 24 1)

D 0%08-0 03(

0 '2 2/ 2) 0~ 0 CS-137 0 '20 0%32-0 '5( 9/

3 AD )3 9) 1 0 HILE !J ROGTERSVILLEC AL 0% (F3-1%82( 1/

0.03 1) 0%02- 0 '3 2/ 2) 0~ 10- F 82 13.8 MILES NV 1~ 82- I ~ 82 0 64 1%28 Zo-95 0 '30 D%06( 8/ 9) POGERSVILLCe AL 0.11( 1/ 1) O.DD( 2/ 2) 0 ~ 04- 0 ~ 11 13 ~ 8 HILES NM 0 ~ 11- 0~ 11 G ~ 04- 0~ 12 NB 95 0%01D 0~ 14( 9/ 9) ROGERSVILLEs AL 0 '5( 1/ I) 0 ~ 14( 2/ 2)

K-4 0 0%250 0 ~ 06-5%42( 9/

0 '5 9) 13 8 HILES NM LH4 BF TRAILER P 0 ~ 35 .

7%13(

~

1/

0 35 1) 0 ~ 09-97(

0%19 2/ 2) 3%90- 7 '3 7 HILES NNM 7%13- 7 ~ 13 4 '7 4%98 81-214 0 ~ 050 1~

0F 01(

51-9/ 9) 1 ~ 40 1

LH2 BF NORTH 0 9 HILE N!JE 1~

1 40(

4O-ll1%40 1) 0%90(

0 '846( 2/

1 ~ 02 2)

BI 212 0 100 O.ee( DECATUR'L o.Be( 1/ 1) 0 2/ 2)

PB-214 0~

F 050 0 ~ 29-1%08( 9/

0 ~ 86 9) 8~2 HILES SSE LH2 BF NORTH 0

1~

~ 86-46( 1/

0 F 86 1)

~

0%34 0%92(

0 '8 2/ 2) 0.5e- 1.4e 0 9 NILC NNE 1 46- 1 ~ 46 0 81- 1 ~ 04 Pj 212 NOT ESTAB F 08(

0%59-9/

43

9) DECATURN AL

' HILES SSE 1~ 43(

43-1/

43

)) 0 '4(

86-2/ 2) 1 ~ 8 1 ~ ) ~ 0 ~ 1 ~ 03 RA 226 050 16( 9/

'3 9) ATHCNSC AL 2 III 3 ( 1/ 1) '0( 2/ 2)

RA 223 CD NOT ESTAB 1

0 '1-6 ~ 36(

2 4/ 9) 1D 9 MILES NE L!.4 BF TRAILEP. P 2 ~ 43-0 46( 1/

2 '3 1) 0 0 78-2 VALUES <LLD F 02 BC 7 160 6 ~ 29-0 ~ 24(

0%46 2/ 9) 1 ~ 7 HILES L".3 BF NORTHEAST NNM D~

~

46-

'a( 1/

0 '6 1) 0 '5( 2/ 2)

TL-208 0

0

~

'20 0

0

'1

'8( 0 9/

'6 9) 1 0 NILE CNE LH1 BF NORTHMEST 0

0~

0 ~

26-48( 1/

0 '6 1) 0 ~ 19 0 ~ 33( 2I 0 ~ 30 2) 0%18 0 F 48 1 ~ 0 NILE !L 0 ~ 48- 0%48 0%31 DE 36 AC-228 0 060 1%12(

'2- 9/ 9) DECATUR'L 46( 1/ 1) 0 '7( 2/ 2)

PA 234M

~

NOT ESTAB 0

3%'50(

1 1/

~ 46 o) 8 ~ 2 MILES SSC LHB BF !JORTH 1 ~

1%46-3 '0( 1/ 50 1) 1 '6 0%90 -

09(

1 ~

1/

05 2)

Sf 89 I ~ 500 3 '0-9 VALUES <LLD 3%50 0 ~ 9 HILE !N:C 3 '0 3 ~

4 4

2

'9VALUES F 09

<LLD 11 ANALYSIS PERFORHED SR 90 0 ~ 300 9 VALUES <LLD 2 VALUES <LLD 11 ANALYSIS PERFORHED

a. I(ojainal Lover Liccit of De taction (LLD) as described in Table 3.

b. Mean and range based upon detectable neasurenents only. praction of detectable cjeasureuents of specified locations is indicated in parentheses (p).

TD(.LE 13 RADIOACTIttITY IN LIELL MATER PC I/L - 0~ 031 80/L NAKE OF FACILITY BROI'tES~fRRY DOCKET tcOG~g-cG~+A2$ ~0 LOCATION OF FACILITY L.IH~TOQf, ~AApAHA REPORT IhG PERIOD~9~

TYPE AND LOltER LIHIT ALL CONTROL t(UHBER OF TOTAL NUMBER OF INDICATOR LOCATIONS (F)b

$ ~00TIGH UITH HIGHEGT Ihkkhh IIEhll, LOCATIONS NONROUTINE OF At(ALYS IS DETECT ION HEAW t<D, E HEAr (F)b KEAN (g)b REPORTED

~PRF9RHf Q lhhkl GAHHA (NAI )

19 12 VALUES <LLD 7 VALUES <(.LD ANALYSIS PERFORHED GAHHA (GEL I) 7 K-40 NOT ESTAB 1 VALUES <LLO 99 ~ 84 ( 3/ 6) 86 F 85- 115 F 50 BI 214 NOT ESTAB I VALUES <LLD 28.00(

28000- 28 'C P8-214 NOT ESTAB 1 VALUES <LLD 12 '9(

7 '2-2/

17 76 6)

PB 212 NOT ESTAB VALUES <LLD 6.48( 1/ 6) 6 '8-1 6048 TRITIUH 330 F 000 4 VALUES <LLO VALUES <LLD 8 ANALYSIS PERFORHED

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

b. Mean and range based upon detectable measurements only. Praction of detectable measurements of specified locations is indicated in parentheses (P).

TAELC 14 RADIOACTIVITY It9 PUBLIC MATER SUPPLY PCI/L - 0 ~ C37 BO/L WANE OF FACILITY PROttttS F/RAY DOCKET AO, rTT!-229AE~&0 296 LOCATION OF FACILITY Q~fSYONr~ AQABANA REPORT ING PERIOO~~SB TYPC AND L04ER L IHIT ALL CONTROL NUHBER OF TOI'AL NUNBCR OF INDICATOP. LOCATI OWS LOCAT I OQS NONROUT I WE OF At(ALYS IS DCTECTIONa FlEAtt (F)b HE'AN (F) HEAN (F)- REPORTED

~RS GROSS BCTA 9'I~SF ~(~ )

'00 3N96(

RAN~G 61/ 72)

Q~TST NC WANE ANO QTRECTTON CHANP ION PAPER 4~1 1(

RANOEO 44/ 46) b

~RAN 3 '0( ll/4 0813) ~NASSER.~NNTS GAHHA (NAI) 85 2

2 '6- 14 '0 TRN 282 ' 2 46- 14 '0 2<<50- F 70 61 VALUES <LLO 9 VALUES <LLO ANALYSIS PERFORNEO GAHNA (GBLI)

K 40 15 WOT ESTAB 74 'l(

72 ~ 49-2/

75 73

11) CHANPIOti PAPCR TRH 282 '

74 F 11(

72<<49-2/

75 ~ 73

8) 101NOO(

101 F 00-1/

101 F 00 4)

BI-214 NOT ESTAB 24 F 80( 8/ ll) St(EFF IELOsAL ROB 28091( I/ 1) 17<<78( 2/ 4)

PB-214 NOT ESTAB 12 ~ 00-15 '3(

43 03 F

4/ 11)

TRN 254 CHANPION PAPCR 28+91-16 '3(

28 '1 3/ 8) 13+60 15 '2(

21 2/

'5 11 ~ 14 23N93 TRH 282 ' 12N52- 23 '3 15N68- 15N95 PB 212 NOT ESTAB llN90 ( 1/ 11) SNEFFIELDs AL 11 90( 1/ 1) 16 18( 2/ 4)

'L"208 NOT ESTAB 11 '0 11 VALUES <LLD ll 90 TRt'. 254 3 ROB ~

I IN90<< 1} 90

~

13N13-5 '4(

19 '2 1/ 4) 5 '4 5 '4 SF( 89 ION000 12 VALUES <LLD VALUES <LLD 16 ANALYSIS PERFORHED SR 90 16 F 000 3 '5(

25-1/

3 25

12) SHEFF TRN IELDIAL ROB 254<<3 3 '5(

3N25-1/.=

3025

4) 4 VALUES <LLD 1/ 1/

IR IT IUH 330NOOO 369N21(

369 '1- 369 '112) CHAHP ION PAP EP.

TRN 282 '

369 ~ 21(

369 ~ 21-1/

369 '1 4) 376~59(

376 '9- 376 '9 4)

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

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

31 Table 15 ENVIRONHENTAL GAMNA RADIATION LEVELS Average External Gamma Radiation Levels at Various Distances from Browns Ferry Nuclear Plant for Each Quarter - 1981 mR/Quarter Distance Avera e External Gamma Radiation Levels b miles 1st uarter 2nd uarter 3rd uarter 4th uarter 0-1 18.8 + .1.2 21.7 + 2.0 21.0 + 1.6 20.0 + 1.5 1-2 17.1 + 1.2 17.3 + 2.2 16.7 + 3.2 20.0 + 5.0 2-4 16.5 + 1.2 15.6 + 1.8 16.2 + 3.3 16.5 + 1.7 4-6 16.6 + 1.1 17.0 + 1.6 17.1 + 2.2 16.6 + 1.3

>6 16.5 + 2.2 16.8 + 2.7 15.9 + 3.5 16.6 + 2.3

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

Average,

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

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

b. All averages reported +1v (68 percent confidence level).

TAPLE 16 RADIOACTIVIT'Z IN FOOD CROPS PCI/KG - 0 ~ 037 BQ/KG (VET VEIGHT)

NAIIE OF FACILITY ORON44S FERQT DOCKET NO ~0~9~A296 LOCATION llF FACILITY~RSm A/A~AHA RCl GRPT ItcG PCR IOD~FQ TZPE At)0 LOVER LIHIT ALL COt(T)EOL NUHBCR OF TCTAL Nbt'BCR OF INDICATOR LOCALIONS LOCATICh VITH HIGHCST AhNUAL HCAN LOCATION) NONROUTINE OF ANALTSIS GETECTIONa HEAN (F) NAKE PEAN (F)o MEAN (g) REPORTED PFRFOR)EFO (L 0) RANGf RA C N I 4 S O ~RR I N I S RADIOACTIVITT IN CABBAGE GROSS PCTA 1

25 F 000 ')286 86(

4286.86- 4266.86 1/ 1) 4 HILES N 4286 4286

'6l

'6- 1/

4286 '6 1)

GAH<A .(GCLI) 1 K-4 0 NOT ESTAB 1873 F 00( 1/ 1) R HILES N 1873 'Cl 1/ 1) 1873 ~ 00- 1873 ADO 1873 F 00- 1873 00 8 I-214 NOT CSTAP 13N40( 1/ 1) HILCS N 13 F 40( 1/ 1) 13 40- 13 F 40 13 F 40 13 40 PB 212 NOT ESTAB 15

~

15 ~ 75 l

~ 75-I/

15 '5 1) 4 H ILES N 15 15

'5l

'5 15I/ '5 1)

F RAGIOACTIVITT IN CORN GROSS BETA 25.a00 4163 ~ 82( 1/ 1) LH2 BF NORTH 4163 ~ 82( 1/ 1) 3995 ~ 66( 1/ 1) 2 4163 82- 4163 ~ 82 0 9 I(ILE t(tJE 4163 ~ 82 416 ~ 82 3995 ~ 66 3995 66 GAHER4 (GCLI )

2 K-v0 NOT ESTAB 1964 ~ 00 l 1/

1964 ~ 00- 1964 ~ 00 1') Ltl2 BF NORTH 1964 F 00( I/ 1) lq32 F 00( 1/ 1) 0~ 9 '9ILE tlNC 1964 F 00- 1964 F 00 1932 F 00 1932 F 00 RAOIOACT IVITV Itt GREEN BEANS 4874 ~ 83( 1/ I) '3( 1/ 1/

GROSS GAHH4 BC TA (GCLI) 2 25 F 000 4874.83- 4874.83 2 HILES NNV 4874 R874 F 83- 4874 '3 1) 3251N74(

3251 '4- 3251 '4 1)

R:

K-40 NOT ESTAB ~ s.132 ~ DD ( 1/ 1) 2 MILES NNV 2132 ~ 00( 1/ 1) 1682 F 00( 1/ 1) 2132 'C- 2132N00 2132NOC- 2132 ~ 00 1682 ~ 00- 1682 F 00 P I-214 t)OT ESTAB I VALUES I:LLO 20 '0( 1/ 1)

'9( 20 ~ 50- 20 '0 I/ 1) 1/

'9 I)

PB-212 NOT ESTAB 6 ~ 89( 1) 2 KILES NNV 6 1/ 29058(

6 ~ 89- 6 ~ 89 6N89- 6 29 ~ 58- 29 F 58

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

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

TABLE 16 (Contd)

RADIOAC'(IVITY I'I FOOD CROPS PCI/KG - 0 ~ C37 CO/KG (MEET VEIGHI )

NAHE OF FtCILITY BROl't(S FERRY (EQCh T )GOD 50-2~59 ?60 LOC A I ION OF F AC IL I IT~M~TO)Aj, A~/AHA REPORTIttG PE(AIOD $ 901 TYPE AND LOWE(E LIMIT ALL CONTROL NUMBER OF TOTAL NUMBER OF INDICATOR LOCATIONS ~CA1 GM II TH I~IGHm~AIIUAAJC~AM LOCATION<b NONROUTINE OF ANALYSIS DETECTION MEAN (F)b NAME 'EAN (F)~ tlEAN ([) REPORTED

~STANCE AAG GTRECTTGM RANGE RAN6E ~HEASU EHEMTS RADIOACTIVITY IN PEACHES GROSS BETA 25 F 000 3127 13( 1/ SHITH 1/

6AHHA (GELI) 2 3127U13- 3127 '3 1) 4 ~ 75 FARM HILES N 3127 ~ 13(

3127 ~ 13- 31?7 ~ 13

1) 2970 ~ 49( 1/

2970 ~ 49- 2970 ~ 49 1) 2 K-4 0 NOT ESTAB 1697 F 00( I/ 1) SHITH FARM 1697 F 00( 1/ 1) 1/

1697 00- 1697 '0 4 ~ 75 MILES 1697 ~ 00- 1697 'G 1252 F 00(

125? F 00- 125? ~ OG 1)81-214 NOT ESTAB 22U43(

22 43-1/ 1) SMITH FARY 22 '3( I/ 1) 1 VALUES <LLO 22+43 75 MILES 22 ~ 43- 22+43 PB-212 NOT ESTAB 19e53( 1/ 1) SMITH FARM 19 '3( 1/

19 ~ 53- 19 ~ 53 4 ~ 75 MILES 19 ~ 53- 19 '3 1) 1 VALUES <LLD RADIOACTIVITY IN POTATOES GROSS BETA 25.000 7112 ~ 16( I/ I) 2 MILES NNN 7112 ~ 16( 1/ 1) 7721U34( 1/

GAMMA (GELI )

2 7112 ~ 16- 7112M)6 7112 '6- 7112U16 7721 '4- 7721 '4 1) 2 K-40 NOT ESTAB 3201 'O( 1/ 1) 2 MILES NN)t 3201 F 00( 1/ 1) 3473 F 00( 1/ 1) 3201 ~ OC- 3201 F 00 3?01 ~ 00- 3201 F 00 3473 F 00- 3473 F 00 81-214 NOT ESTAB 15M62( 1/ 1) 2 MILES NNI 15462( I/ 1) VALUES <LLD PB-212 NOT ESTAB 15 ~ 62-13 '2( 15 F 62

)/ 1) 2 HILES NNM 15 13

~ 62-

'2( 15 1/

'2 1) 1

. 13 ~ 62- 13 '2 13 62-

~ 13 '2 1 VALUES <LLO

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

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

TA<<C 16 (ContTQ RADIOACTIVITY I)

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

NAHC GF FACILITY BRO'aNS FERRY LOCATION OF FACILITY~~HJO)sf A REPORTING PERIOD 198')

TYPE ANO LOMER L I HIT ALL CONTROL NUHBCR OF TOTAL NUHBER OF INDICATOR LOCATIONS ~OCATIOII II ~ttt H H "T AkttllAT~HAN NONROUT INC OF ANALYSIS DETECTION a MEAN (F>b LOCATIONS MEAN ) REPORTED

($

RANGE ~NON~AN TS RADIOACTIVITY IN TOMATOES Iles GROSS BCTA 2

25 ~ 000 5130 21(

5130e21 1/

5130e21 1)

BROOKS FARM 7 ' MILES NNN 5130 '1- I/

5130 ~ 2l (

5130 ~ 21

1) 5669 17(

5669al7- 5669e17 I/

GAMMA (GCLI)

K-40 NOT ESTAB 2513 ~ GO( 1/ 1) BROOKS FAFH 2513 ~ 00( I/ 1) 2381 F 00( I/ 1) 2513 ~ 00 2513a00 7NG MILES NN)i 2513 ~ 00- 2513e00 238le00- 2381 '0 ~

PB 212 NOT ESTAB 11 15( I/ 1)=- BROOKS FARM 11 F 15( 1/ 1) VALUES CLLO F

lla15 llel5 7a0 MILES NNN 11 '5 15 llew RADIOACTIVITY IN TURNIP GREENS 5500a16( 1/ 1) 5500el6( 1/ 1/

'6 1)

GROSS OCTA 25a OOA) 4 )'TILES N . 5969a0$ ( 1) 2 5500 ~ 16" 5500 e1 6 5500el6- 5500 ,

5969 F 01- 5969 F 01 GAHHA (GELI )

2 K 40 NOT ESTAB 2262 F 00( 1/ 1) 4 MILES N 2262 F 00( 1/ 1) 2980e00( 1/ 1) 2262 ~ 00- 2262 F 00 2262 F 00 2262 00 2980 F 00- 2980 00 81-214 NOT ESTAB 22a93(

22 ~ 93-1/

22 ~ 93

1) MILES N 22 '3(

22 ~ 93-1/

'3 1)1) 37 '4(

'4- 1/

'4 1) 22 37 37 PB 214 NOT E'STAB 13e53(

13 ~ 53-1/

13 '3 1) 4 MILES N 13 '3(

53-1/

13 '3 1 VALUES (LLO 13 PB-212 NOT ESTAB 11 ~ 42( 1/ I) MILES N 42( 1/ 1) 26 '1( 1/ I)

BE-7 NOT ESTAB 11 ~ 42-194 '0( 11 F 42 1/ 1) 4 MILES 11 42-

~

194 '0(

11 1/

'2 1) 26 '1- 26a21 VALUES O.'LLO 194 '0 194 '0 N 194 40- 194 40

~ F 1

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

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

TABLE 17 RADIOACTIVITY IN SOYBEANS PCI/6 6 ~ 037 BG/G (DRY VEIGHT)

NAHE OF FACILITY 8ROlJNS FEAR> SOCKET NO ~50- 5) 26~0296 LOCATION OF FAG IL I TY Q~IH SJONE A ABAHA REPGRTING PERIOD ~9

=!i TYPE AND LOVER LI HIT'F ALL CONTRGL NUBBER OF TOTAL NUBBER INDICATOFL LOCATIONS ~O ATION N)TH HIEHEST AhNHAE NEAR LOCATI.ONS NONROUTINE OF ANALYSIS DETECTION a HEAN (F)b NAHE HEAN (F)b HEAN (F)b REPORTED

~PE P~RH 5 RAN E 29 F 53( 2/ 2) f j)~sT Rc 6 h~ui)~~to LH2 BF NORTH 29 '3( REEiiiih 2/ 2) b ~HA Q~RHQN TS 200 GROSS BETA

?

0 29 F 40 29065 009 NILE NNE 29 '0- 29 '5 GAHHA (GELI) 2 15 ~ 74 ( 2/ 2) LH2 BF NORTH 15 74( 2/ 2)

K 40 NOT ESTAB 14070- 16077 009 NILE NNE 14070 16

'3( 1/ 03 2) '7 Bl 214 NOT ESTAB 0003( 1/ 2) LH2 BF NORTH 0 0003-

'5( 0 2/

'3 2)

G 9 LH2 NILE tJNE BF NORTH 0003-

'5( 2/

0 F

?)

PB-214 NOT ESTAB 0 0 0 04- 0 06 0~9 NILE MNE 0~ 04- 0006 BE-7 NOT ESTAB

~

D020( 1/

F

2) LH? BF NORTH 0 '0( 1/

'0  ?)

AC-228 NOT ESTAB 0 '0 0011(

0 '0 I/ 2) 009 LH2 HILE NNE BF NORTH 0020" 0 ~ 11( 1/

0 2) 0~ 11- 0011 009 NILE NNE 0 <<11- ~ 0011

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

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

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

NAKE OF FACILITY BROllNS FERRY LOCATION OF F AC IL I IY~~IH ~OQE A~A/AHA REPORTING PERIOD~98 T YPE ACED LOVER LIHII At. L CONTROL NUHBER OF TOTAL NUMBER OF INDICATOR LOCATIONS uEEATIGN IIITK I~IIGK RT AIIN~NA II All LOCATIONS. NONROUTINE OF ANALYSIS DETECT ION a YEAN CF)b NAHE HEAN (F)b HEAN (F)b REPORTED PERPORTED (LLO) A b GROSS BETA 2

250000 4972066 4972 R~A

'6- C 1/

4972 ~ 66 1)

LH5 BF DAVIS F 2 ' HILES 4972 66(

MSI'972066-I/

4972 66

1) 6458 6458

'6(

'6- 1/

6458 '6 1.)

GAHHA (GELI) 2 K-40 NOT ESTAB 2412 ~ 00C 1/ I) LH5 BF DAV IS F 2412 F 00( 1/ I) 2137000( 1/ 1) 2412000- 2412 F 00 2 5 HILES MSN 2412 F 00- 2412 F 00, 2137 F 00 2137 F 00 8 I-214 NOT ESTAB I VALUES <LLD 19056(

56-I/ I) 19 ~ 19056 PB-214 NOT ESTAB VALUES <LLD 18 '8( I/ I) 1 18 '8

'6( 18 38 1/

'6 I)

PB-212 NOT ESTAB 1 VALUES <LLD 10 10 ~ 86- 10

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

b. Mean and ran8e based upon detectable measurements only. Praction of detectable measurements of specified locations is indicated in parentheses'(P).

Figure 6 ANNIAL AVERAGE Preoperational Operational 6ROSS HEfA kTIVITY Phase Phase I N HRI N<I I5 MATER SUPPLIES IO C HROH% FERRY }%LLEAR KAhT O Sl JJ g

O o

Jl Ch C 4I le CI}

o

~4 cV le0

'o 4Jc 0

M Q Average:

Preoperational Phase 19 8 19 9 19 0 1 1 19 2 19 3P 19 30 19 4 1 5 19 6 1 7 .19 8 1 9 19 0 1 1

38 Figure 7 21 Olrect Rod)at)on Levels 8rowns Fer ry Nuclear P lani Onstte I 0

'1 1

\

1 I1 O

C.

\

1 i

\

1 I'

Q 18 \ '1 C7 I 4, 1

I 6

I 6 o ~'o -o 16  !

! o' I

60'sl te 1976 1977 1978 1979 )988 1981 Figure 8 OlreCI Radtat tcn LevelS Srowns Ferry Nucleor Plant

~-auar ter Hovtng Aver oge 22 C.

Q Ons I t e

)8 ,A 8 .P" 0: p" '0 8 / ' b

.AI 16 ,P 0

Of fs) te

)976 1977 1978 )979 )988 198)

Figure 9 39 2t Olrect Radtot ton Levels Wot ts Bar Nuclear Plant 22 C. OesI'Ie s 18 Cf OC 8 Of fst te o p-~

\

I I

I I

b I 1976 1977 1978 1979 1988 1981 Figure 10 Olrect Radtot ion Levels Mot ts Bar Nuclear Plont 0-Quar ter Moving Average

'2 Oust te 16 1976 1977 1978 1979 1988 1981

b

.I

Reservoir Monitorin Samples are collected from the Tennessee River as detailed in table 19. Samples collected for radiological analysis include plankton from three of these cross sections and bottom fauna and sediment from four cross sections. The locations of these cross sections are shown on the accompanying map (figure ll) and conform to sediment ranges established and surveyed by TVA.

Water Water samples are collected automatically by sequential type sampling devices at three cross sections and composite samples analyzed monthly for gamma-emitting radionuclides. Further composites are made quarterly for strontium and tritium analyses. In addition to these required samples, grab samples were also collected monthly from the vicinity of the plant discharge to the Tennessee River, and at a point on the Elk River, and analyzed for gross beta, gamma-emitting radionuclides, and strontium. Results are displayed in table 20. Figure 12 presents a plot of the gross beta activity in surface water from 1968 through 1981. No gross beta measurements were made in surface water samples in 1978. The levels reported are consistent with gross beta levels measured in surface water samples taken from the Tennessee River in preoperational monitoring programs conducted by TVA at other sites.

Fish Radiological monitoring for fish is accomplished by analysis of composite samples of adult fish taken from each of three contiguous reser-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 BFN preoperational monitoring program. Two species, white crappie and smallmouth buffalo, are collected representing both commercial and game species. Sufficient fish are collected in each reservoir to yield 250 to 300 grams oven-dry weight for analytical purposes. All samples are collected semiannually and analyzed for gamma-emitting radionuclides. The composite samples contain approximately the same quantity of flesh from each fish. For each composite a subsample of material is drawn for counting.. Results are given in tables 21,. 22, and 23.

Plankton As indicated in table 19, net plankton (all phytoplankton and zoo-plankton caught with a 100 p mesh net) is collected for radiological analyses at each of three stations by vertical tows with a 1/2-meter'et. At least 50 grams (wet weight) of material is necessary for analytical accuracy. Samples are collected semiannually and submitted for gross beta analysis, and when quantities are sufficient, for gamma activity and Sr and Sr content.

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

42 Sediment Sediment samples are collected from Ponar dredge hauls made for bottom fauna. Gamma radioactivity and Sr and 9o Sr content are determined

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

Locations of these stations are shown in table 19. Results are shown in table 24.

Bottom Fauna The flesh and shells of Asiatic clams collected semiannually from the cross sections at four stations (table 19) are analyzed for gamma-emitting radionuclides. Levels of Sr and Sr are determined on the shells, and on the flesh when sufficient amounts were available. A 50-gram (wet weight) sample provides sufficient activity for counting. During this reporting period, one sample of clam flesh contained insufficient volume for analysis.

Results are given in tables 25 and 26.

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

Zooplankton, chlorophyll, Benthic River/river mile phytoplankton fauna Sediment Pish =(co8ecEe5 mlnMly)

Tennessee 277.9 X Tennessee 285.2 Tennessee 288.7 Tennessee 291.7 Tennessee 293.5 Tennessee 293.7 X (discharge area)

Tennessee 305.0 (Control)

Tennessee 307.5 X (Control)

Elk 20.5 (Control)

a. Gill net and/or electroshocker will be used for collection. Samples of fish are collected from Guntersville, Wheeler, and Wilson Reservoirs.

b. Automatic sampler.

c. Grab sample.

TABLE 20 RADIOACTIVITY Itl SURFACE rATER TOTAL PC, I/L - 0 ~ 037 BQ/L NAME OF FACILITY BRO) NS FERRY DOCKET NQ ~ 50-2~59 260A296 LOCATION OF FACILITY ~JflfQJOQf.

TYPE AND LOltER L IHIT ALL CONTROL NUHBER OF TOT AL t.'JHBER OF INDICATOR LOCATIONS LOCATION JITH HIGHEST ANNUAL HEAtt LOCATIONS NONROUTINE OF AttALYSIS OETECT IONa MEAN (F)b NAME MEAN ([)b MEAN (F) REPORTED PERFORiMFD (LLD) RANGEb OISTAttCC At'g DIRECTIOtt RANGE RAt'GEb GROSS BETA 2~400 3 53( 14/ 17) TRP. 293+5 3 '6( 2/ 2) 5~27(

'9- 12/ 15)

GAHHD (to A I )

32 2 '3- 5a16 3 '0- 4 '2 2 F 58 45 27 VALUES <LLO 18 VALUES <LLD ANALYSIS PERFORMED GAHHA (GELI) 20 K-40 NOT ESTAB 105 '0(

'2- 5/ 12) TRH 293 ' 139 '5( 2/ 3) 96 '3( 2/ 8)

'5-81-214 NOT ESTAB 51 15~99(

~

159 'i) 5/ 12)

BFlt DISCHARGE TR)'i 285 ~ 2 119 10-18 F 60(

159 F 80 2/ 3) 74

'4( 118 '0 6/ 8) 31 4 '6- 23I/ 8712)

F IBol4- 19 '6 F 00-27 '4(

8'5 4/ 8)

PB-214 NOT ESTAB 26 00( TRH 293 26e 00 ( 1/ 3) 55 '9 F

26.00- 26.00 BFte DISCHARGE 26 ~ 00- 26 00 10 44-15 '5( '2( 13 '3(

F 3/ 12)

PB-212 NOT ESTAB 12 '3- 17~62 TR4 285 ~ 2 17 17 ~ 62-1/

17 '2 3) 8 '2- 223/ '1 8)

SR 89 10 F 000 20 VALUES <LLD 16 VALUES <LED Sb ANALYSIS PERFORMED SR 90 2 F 000 F 81(

'1- 1/ 20) TRH 293 '

BFA'ISCHARGE 2 '1(

2i8)-

1/ 12) 2 '7(

2~07-I/ 16) 36 2 2~81 F 81 2og7 372ell( 293 ' 379 '5(

TRITIUM 20 330 F 000 364 F 86- '792/ '512) TRH 379 ~ 35-1/

379 ~ 35

4) VALUES <LLD

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

b. Mean and range based upon detectable measurements only. Praction of detectable measurements of specified locations is indicated in parentheses (P).

TAbLE 21 RADIOACTIVIT'I IN liHITE CRAPPIE (FLESH)

PCI/G - 0 ~ 037 BO/G (DRY MEIGIsT)

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

TYPE AND LOMER L I HIT ALL CONTROL NUHBER OF TOTAL NUHBER OF INDICATOR LOCATIONS NONROUTINE LOCATIONS HEAN (F)

OF ANALYSIS DETECT ION a HEAN (F)b NAPE HEAN CF)b REPORTED PERFORHED CLLJ) RA>>G b R~N~ ~RII S U~R ~SR T S 0 ~ 100 35018( 4/ 4) MILSON RESERVOIR 35 '6( 2/ 2) 34 F 87(

'3- 2/ 2)

GROSS GAHHA BETA (GELI) 33004- 37 '6 TRH 259-275 34 '8,- 350b4 33 36 F 72 6

CS 137 0 '20 0~ 12( 4/ 4) MILSON RESERVOIR 0~ 13(

0013-2/ 2) 0 '4(

'9- 2/ 2) 0 09- 0~ 14 TRH 259 275 0 ~ 13 0 0 ~ 18 K-49 NOT ESTAB 14 '5( sl/ 4) MILSON RESEPVOIR 15 20(

'7 2/

'3 2) 17 '0C

'9- 2/

'1 2) 12 ~ 72- 15063 TRH 259-275 14 15 15 19 BI-214 0 '20 0007( 2/ 4) MHEELER RES 0009(

09-1/ 2) 0 ~ 06(

06-1/ 2)

'6 0 ~ 05 0.09 TRH 275-349 0~ 0009 0 ~ 0 PB-214 NOT ESTAB 0007 ( 2/ 4) MILSON RESERVOIR 0 07( 1/ 2) 2 VALUES (LLD 0 '6 0 '7 4) TRH 259-275 0 ~ 07-

'2(

0007 1/ 2) 02( 1/

PB-212 NOT ESTAB 0 ~ 02(

0~ 02-1/

0 '2 MHEELER RES TRH 275-349 0

0 02- 0002 0

0~ 02- 0 '2 2)

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

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

TAFLE 22 RADIOACTIVITY IN SHALLHOUTH BUFFALO (FLESH)

PCI/G: 037 80/G (ORY VEIGHT)

NAHE OF FACILITY BROVNS F/RRY LOCATION OF FACILITY LIHESJONE A/AGAMA DOCKET NOR ~~9ggg 296 REPORT 1NR PERRON~RE TYPE ANO LOVER LIHIT ALL CONTROL NUMBER 'OF TOTAL:iU."OER OF INDICATOR LOCATIONS llew LOCATIONS NONROUTINE OF'NALYSIS DETECT IOM) MEAN (F) b MEAN (F)b REPORTED

~Q'00 FT ANGEb 4/ 4) iOI STANCE ANO DIRECTION

'7(

RANGLb 2/ 2)

~R4 N 2/

~HAS()~RM NTS GRASS GAMMA BETA (GELT) 0 23N 19P 07(

04- 27 ~ 20 VHEELEF RES TRH 27$ -349 25 2'4 27 '0 22NRO(

20 F 12 24 '8 2) 6 CS-137 '20 "0 ~ 05( 4/ 4) VHEELEP RES 0 ~ 05( 2/ 2) 0 08( 2/ 2)

K-40 0

NOT ESTAB OP OR-9N64 ( 4/

0 ~ 06 4)

TRH 271 RRn MHEELER RES 0 ~ CR 03(

0 2/

'6 2) 0 8

'7 F

'2( 0 '8 2/ 2) 7 ~ 36- Ill 56 TRH 275-349 10 '908( 11 '6 F 00- 10 '4 OI-214 0 '20 0~ 06( 3/ 4) VILSON EEESER VAIR 0F 1/ 2) F 14( 1/ 2)

F 05- 0 F 98 TRH 259-275 0 ~ 08- 0 ~ 08 0 '4- 0 ~ 14 PB-214 NOT ESTAB F 06(

0 F 05-2/

0 '7 4)4) VHEELER RES TRH 275-349 0 '7(

'7 1/

0F 07

2) ON09(

0+09-1/

0 '9 2) 0 PB-212 NOT ESTAB 0F 04( 1/ VHEELER RES 0~ C4( 1/ 2) 2 VALUES <LLD 0F 04- 0 F 04 TRH 275-349 0 ~ 04 OoCR TL-208 0 '20 0F 02( 1/ 4) VTHEELER RES ON02( 1/ 2) 2 VALUES <LLO F 02- 0 F 02 TRH 2?5-349 0 ~ 02- 0 F 02 SP 89 0 ~ 500 1 VALUES <LLO 0 VALUES <LLO ANALYSIS PERFORHED SR 99 0 F 100 1 VALUES <LLO 0 VALUES <LLO ANALYSIS PERFORMED

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

b. Mean and ran8e based upon detectable measurements only. Fraction of detectable measurements of specified locations is indicated in parentheses (F).

TABLE 23 ~

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

PCI/O - 0 0 7 BO/G (ORY )(EIGhT)

NaVE OF FACILITY QROVNS JERRY LOCATION OF FACILITY LJHQSJQPQ AL,a~AHA IIEPORIING PERIOO I.~R TYPE AND LOVER L IH IT ALL COt(TROL NUMBER OF TOTAL t(U."BER OF INDICATOR LOCATiONS LOCATION VITH HIGH(:ST At(NUA H AN LOCATIONS NONROUT INE OF ANALYSIS DETECT IONa MEAN (F)b NAME HEAN (F) MEAN (f ) REPORTED RANGEb IZIEH~N~~LECCTLJUL ~AKiK R~Af, P~RF ~R~u P

'6( 2/ '4( 2/

GROSS BETA 6

0 100 19N22(

18 '7- 4/

19N95

4) VMEELER RES TRH 275-349 19 IBN57- 19 '5 2) 20 14 '7- 26 '1 2)

GAHHA (GEL I)6 03( 2/ 4) 0+03( 1/ 2) F 04( 1/ 2)

CS-137 0~ 020 0~

0~ 03-4/

0 ~ 03 4)

VHEELER RES TRH 275-349 0 '3

'0( 2/

0 '3 2) 0 F 04-7 '8(

0 '4 2/ 2) 8N08(

K-4 0 NOT ESTAB

.F 83- F 11 VHEELER RES TRH 275-349 8

7 ~ 50- 8 '9 F 10- 9 '7 BI-214 0 '20 0 '6(

'4- 4/

0 08

4) MILSQW RESERVOIR TRH 259-275 0F 0

06(

04-2/

0 F 08

2) 0F 0

06(

'3- 2/

ONOB 2)

PB-214 NOT ESTAB 0

ON07( 3/

F

4) (tILSOtt RESERVOIR 0 '2(

12-1/

'2 2)2) 0 F 08(

0.08-1/

0.08 2) 04- 12 TRH 259-275 0~ 0 PB-212 NOT ESTAB 0~

0~ 03( 2/

0 ~

4) VHEELER RES 0 '3( I/ 0 '3(

'3- 2/ 2)

'0 ~ 50 0 0 03- 0 '3 VALUES CL'LD TRH 275-349 0003- 0 F 03 0 0

0 VALUES GiLLO F 04 SR 89 1 ANALYSIS PERFORMED SR 90 0 ~ 100 1 VALUES (LLO 0 VALUES (LLD ANALYSIS PERFORMED

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

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

I D

TABLE 24 RADIOACTIVITY Itt SEOIKEttT PCI/G - 0~ 037 80/G (DRY itEI GUT)

NAKE GF FACILITY QROQNS F/RRY DOCKET t(04~50- $ ~9~60A+g LOCATION OF FACILITY LIK~STO~N ALAHAHA t(EPORTlttG PERIOD 1981 TYPE At(D LOitER LI HIT ALL CONTROL t(UHBER OF TOTAL "tUHBER OF INDICATOR LOCATIONS OCATION itI TH HIGH(R ST AkhUAL KEAtt )GONROUTINE OF ANALYSIS DETECT I Oka HEAN (F>b kAHE HEat ([)b LOCATION) REPORTED PfEEKBFD GAHHA (GELI )

~(JJ) ) gJ~TNC~ANg QiRfC/lGN R~AkG ~A~~N TS 8

CO 60c 00010 llew 0 14( 5/ 6> TRH 293 F 7 0 20( 2/ 2) 2 VALUES <LLO CS-134 00080 C ~ 07-0013( 1/

0 '1 6)

BFN TRH DISC(tARGE 293 '

0

~

~

'3(

19- 0 ~ 21 1/ 2) 2 VALUES <LLD 0 '3- '3~

BFN DISCHARGE 0

0 ~ 13 0013 CS 137c 0 '20 70(

'3-1 ~

0 0

6/ 6) 2 '5 TRH 277 '8 2 '4(

2023 2/

2 '5 2) 0 0

'7(

'3 2/

0431 2)

ZR 95 0 '30 6 VALUES <LLD 0 '7(

0407-1/ 2) 0 ~ 07 NB-95 0.010 6 VALUES <LLD 0012( 1/ 2)

K-40 NOT ESTAB 14 '0( 6/ 6) TRH 288 '8 15e75( 2/ 2) 0412 14 '5l 0

2/

'2 2)

'2 15 '6

~

42 16 .15007 16 ~ 42 13 64-

~

Htt 54 0 '10 0F 05(

'4- 2/ 6) 0006 TRK 29307 BFN DISCHARGE 0 F 06(

06-1/

0006

2) 0 '3(

03-1/

'3 2) t) 1-214 0 ~ 020 0

1035(

1~ 11-6/

1 e53

6) I'RH 277 '8 0 ~

1 ~

1~

44(

35-2/

1053 2) 0~

1 '9l 2/ 96 2) 1061 0

1 ~

Bl 212 0 '0C 06( 5/ 6) TRti 288.78 33( 1/ 2) 15( 2/ 2) 1

'8- 1033 1 ~

1033- 33 1 ~

93- '6 PB-214 NOT ESTAB 0

1~ 50l 6/ 6) TRH 277 '8 1 ~ 68(

1 ~

2/ 2) 0 ~

1.86( 2/

1 2)

PB-212 NOT ESTAB 1018-1 ~ 86(

1 ~ 57-1 ~

6/

71 2 ~ Cb

6) TRK 288 '8 2 'l(

1 ~ 66-98-1 ~

2/

F 05 71 2) 1 2F

~ 64 00(

82 F 09 2/

2 '8 2) 277 '8 1 ~ 1 ~

RA-226 NOT ESTAB 1 35( 6/ 6) TR< 44( 2/ 2) 1479( 2/ 2) 1 ~ ll- 1 ~ 53 '5 1 ~

1053 1061- 1096 RA-223 t(OI ESTAB 0 49( 2/ 6> 'IRH 293 7 1

0050( 1/ 2) 0 '5( 2/ 2)

TL-208 0 020 0 47-3 ~ 57(

0 6/

~ 50 6)

BFN TRH DISCtiARGE 277 'R 0 F

'5(

50 2/

0 ~ 50 2) 0 0

'273( 2/

0 F 87 2)

AC-228 0

~

'60 0044-1.72(

0 '7 6/ 6> TRK 277.98 0

0 '2 1 ~ 89( 2/

0 '7 2)

F 0068 2 '2( 2/

0 '8 2) 1 35- 1 ~ 94 1083- 1094 1~ 95- 2 68

~

SR 89 1 ~ 5') 0 6 VALUES <LLD 2 VALUES <LLO AtiALYSIS PERFORHED SR 90 0 ~ 300 6 VALUES <LLD 0052( 1/ 2)

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

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

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

TABLE 25 RADIOACTIVITY IN CLAN FLESH PCI/O - 0 ~ 037 BC/G (ORY MEIG)sT) hAHE OF FACILITY PROUJJS FERRY OGCKET hOo~5 - ~59 LOCATION OF FACILITY LIH~STG~N ALABAHA REPORTING PERIOD )981 TYPE AND LOUER L IHIT ALL CONTROL hUHBER OF TOTAL LUHAEW OF INDICATOR LOCATIONS LOCATION MITH HIGHEST ANNUAL HEAN LOCATIOJJS NOsJROUTINE OF ANALYSIS DETECT IONa HEAN (F) b HEAN (F)b REPORTED (Q Q) RANGfb I'/~AS ~R~Hh S GAHHA (GELI) 7 K-40 hOT ESTAB 8 ~ 97(

6 ~ 49-4/

12 '5 5) TRH 288 '8 9+32(

6 ~ 49-2/

12 F 15

2) 17 F 11(

17 ll- 1/

17 F 11

2) s 4

81-214 NOT ESTAB 4 27( 5/ 5) TRH 277 '8 6 '0( 1/ 1) 2 72( 2/ 2) ch-214 NOT ESTAB 1

4

~

70-

'9( 7 5/

F 05

5) TRH 277 ~ 98 bo40 9 '5(

6 1/

'0 1)

F 4

12-

'1( 2/ 2) 3 '2 PB-212 NOT ESTAB 1

F 10-12(

9 '5 3/ 5) TRH 288 78 9+05-17(

F 05 1/ 2)

F 80-0 '0( 7 1/

'3 2)

TL-208 NOT ESTAB 1 ~ 02-0 ~ 40(

1 ~

I/

17

5) TRs( 288a78 1 F 1+17-0 ~ 40(

1 1/

'7 2) 0 2

~ 50- 0 VALUES (LLD

'0 0 ~ 40- 0+40 Oo40- 0+40

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

b. Hean and range based. upon detectable measurements only. Praction of detectable measurements of specified locations is indicated in parentheses (P).

TABLE 26 RADIOACTIVITY It'LAH SHELL PCI/G - 0~ 037 8( /G (DKY L'EIGHT)

RAI'I OF FAOILIII RL~R FEE~R DOCKET NO ~

LOCA I ION OF F AC IL I TY L IHES TONE AgarAHA REPORT I tIG PERIOD 1981 TYPE AtJO LOMER LI HI T ALL CONTROL NUHBER OF TOTAL NUHOEQ OF IIIOICATOR LOCATIONS LOCATIO)IbS NONROUTINE OF ANALYS IS DETECTIONa HEAN (F)b NAHE HEAth (F)b HEAN (F) REPORTED (LLO) RANGL OISTANC ANO OI RECT IOtt RANG& RAMOjb ~HAS~UR H NTS GAu>A (GELI) 8 K-4 0 NOT ESTAB 0

1~ 15(

'9- 6/

3 '2 6) TRH 277 '8 2 ~ 4((

0 '9" 2/

3 '2 2) 0 13(

'6-1 ~ 2/

i+41 2)

(FI-214 0 '50 6/ 6) TRH 277 '8 0+92( 2/ 2) Oe46( 2/ 2)51-212 0 100 F 11-20(

1 ~ 57 I/ 6) TRH 293 '

0 ~ 27-20(

1 ~

1/

57 2) 0 '0 0 2 VALUES (LLD 52 0

0

'0- 0 '0 6) BFN DISCHARGE 0 ~

0+20- 0 20 PB-214 0~050 0 0

'6(

'9- 6/

leOS TRH 277 '8 0 ~ 63(

0 ~ 21-2/

~

1+05

2) 0 0

'6(

'2 2/

0 '0 2)

PB-212 NOT ESTAB 0~ 39(

09-5/

90

6) TRH 277 ~ 98 0 ~ 49(

0~ 09-2/

0 '0 2)2) 0 0~

'5(

27 2/

0F 44 2)

RA-226 0 '50 0

0 0~

'8(

F II-6/

0 ~

1 ~ 57

6) TRH 277 '8 0 0 '7

~ 92( 2/

i+57 0 F 46(

Oa40-2/

0 ~ 52 2)

TL-208 0 020 0 06( 4/ 6) TRH 293 ' F 10( 2/ 2) '3(. 2/ 2) 4C-228 0+060 0~

0 05-

'1( 3/

0 ~ 11 6)

BFA'(

TRH DISCHARGE 288.78 0009-0 32(

F 11 1/ 2) 0 0

0

~ ll 53(

0 1/

'4 2)

R 0 '8" 0 33 0 ~ 32- 0 '2 0 '3" 0 53 SR 89 F 000 6 VALUES (LLD 2 VALUES (LLD ANALYSIS PERFORHED 99( 6/ ' '9( 2/ '2( 2/

SR 90 1 F 000 1 ~

1 ~ 28- 2 70

6) TR<

BFN 293 OISCI<ARGE 2

2~27- 2 '0 2) 2 2o31- 2 '3 2)

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

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

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

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

Champion Paper Co.

ile 28878 mile 293.50 0

Cour tland mile 305.0 mile 293.70 Decatur mite 307.52 Scale of Miles

~ - Automatic Sam ler

Figure 12 Adieu AVERAGE IO Pt'eoperational Operational 6ROSS HETA ACTIYI 7/

C P CO C Phase Phase IN SURFACE )IATER 44 P C

III 44 IhaeS FERRY NuCLEAR Purr Ir V' 44 W C P Ii 44I C

m 0P Average:

Preoperational Phase T

1 1968 1969 1970 1971 1972 1973P 1 9730 1974 1975 1976 1977 1 78 1 79 1980 1 81

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

Data measured at the control stations for each medium were averaged for each sampling period. In order to describe the distribution of control station data, a mean, standard deviation, and 3<<sigma limits were calculated.

We can expect that background concentrations would be distributed within these limits. This prov'ides us the basis for comparing control and,.indicator data.

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

Conclusions A vast majority of the indicator station data was found to be within the distribution defined by the control station data. The data analysis software identified concentrations slightly exceeding the limits of the control station data for a small number of radionuclides in samples from indicator stations. Many of these values may be discounted because the error reported by the analysis program was greater than the calculated concentration. The remaining isolated elevated concentrations may be the. result of fallout, fluctuations in the existing environment, computer program artifacts, or analytical errors. The same type of isolated high values occurred in the control station data and may be attributed to the same sources.

Increased levels of radioactivity were observed in rainwater, air particulates,- heavy particle fallout, and in vegetation in the winter and spring following the atmospheric nuclear weapons testing conducted by the Republic of China in mid-October 1980. This'increase was seen in control stations as well as indicator stations. The primary radioisotopes identified in the atmospheric media were Zr, .Nb, I, ~Bi, and o Ru.

Dose estimates were made from concentrations of radioactivity found in samples of environmental media. Media sampled include, but are not limited to, air, milk, meat, vegetation, drinking water, and fish. Doses estimated for persons at the indicator locations were essentially identical to those determined for persons at control locations. Greater than 99 percent of those doses were contributed by the naturally occurring radionuclide potassium-40,

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

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

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

Attention: A. L. Cunningham Suite 3100, 101 Marietta Street Atlanta, GA 30303 The enclosed report No.. TVA/OMS/OHS-82/7 "Environmental Radioactivity Levels Browns Ferry Nuclear Plant - Annual Report - 1981," is furnished for your. information and use.

Very truly yours, R. B. Max@ 11, Chief Radiological Hygiene Branch Enclosure Q~y~G~>+

An Equal Opportunity Employer

TEMMESSEE VALLEY AUTHORITY CHATTANOOGA. TENNESSEE 3740t 400 Chestnut Street Tower II April 30, 1982 U.S. Nuclear Regulatory Commission Region II ATTN: James P. O'Reilly, Regional Administrator 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 Dear Mr.

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

Environmental Radioactivity Levels, Browns Ferry Nuclear Plant, Annual Report 1981 This monitoring program is specifically responsive to the recommendations and requests of the United States Fish and Wildlife Service. We understand that the Office of Nuclear Reactor Regulation will transmit five copies of the report to the Secretary of the Interior.

Very truly yours, TENNESSEE VALLEY AUTHORITY Nuclear Licensing Enclosure cc: Director of Nuclear Reactor Regulation (

Enclosure:

20) ~ ~ )

Attention: Mr. Darrell G. Eisenhut, Director Division of Licensing U.S. Nuclear Regulatory Commission Washington, DC 20555 An Equal Opportunity Employer

TENNESSEE VALLEYAUTHORITY ENVIRONMENTAL RADIOACTIVITY LEVELS BROWNS FERRY NUCLEAR PLANT ANNUAL REPORT " 1981

, TVA/OMS/OHS-82 7 DIVISIONOF OCCUPATIONALHEALTHAND SAFETY

ENVIRONMENTAL RADIOACTIVITY LEVELS BROWNS FERRY NUCLEAR PLANT ANNUAL REPORT " 1981 TVA/OMS OHS"82 7 April 1982

CONTENTS List of Tables ~ ~ . ~ 4 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ill List of Figures. ~ ~ ~ ~ ~ 4 ~ ~ ~ 4 ~ ~ ~ iv Introduction . ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

Atmospheric Monitoring ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

Terrestrial Monitoring . ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 23 Reservoir Monitoring . ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 41 equality Control. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 53 Data Analysis. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 53 Conclusions'. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 53

LIST OF TABLES 1- Environmental 2- Atmospheric andRadioactivity Table Sampling Schedule 4 Table Terrestrial Monitoring Station Locations - Browns 3- Detection CapabilitiesFerry Nuclear Plant 5 Table for Environmental Sample Analysis 6 Table 4- Results Obtained in Interlaboratory Comparison Programs 8 5- Maximum

~ o ~ ~ ~ o o o ~ o ~ ~ o ~ ~ ~ ~ ~ ~

Table Permissible Concentrations for Nonoccupational Exposure 13 Table 6- Radioactivity in Air Filter 14 Table 7" Radioactivity in Rainwater. 15 Table 8" Radioactivity in Heavy Particle Fallout . 16 Table 9 Radioactivity in Charcoal Filters 17 Table 10- Radioactivity in Milk .

Table ll- Radioactivitg in Vegetation .

Table 12- Radioactivity in Soil 26 27 28 Table 13- Radioactivity in Well Water 29.

Table 14- Radioactivity in Public Water Supply. 30 Table 15- Environmental Gamma Radiation Ievels 31 Table 16- Radioactivity in Food Crops 32 Table 17- Radioactivity in Soybeans ~ ~ 35 Table 18- Radioactivity in Poultry 36 Table 19- Sampling Schedule - Reservoir Monitoring 43 Table 20- Radioactivity in Surface Water 44 Table 21- Radioactivity in White Crappie (Flesh . 45 Table 22 " Radioactivity in Smallmouth Buffalo (Flesh) 46 Table 23- Radioactivity in Smallmouth Buffalo (Whole) 47 Table 24 .- Radioactivity in Sediment . 48 Table 25- Radioactivity in Clam Flesh . 49 Table 26- Radioactivity in Clam Shell 50

LIST OF FIGURES Figure 1 - Tennessee Valley Region . 3 Figure 2 - Atmospheric and Terrestrial Monitoring Network. 18 Figure 3 " Local Monitoring Stations 19 Figure 4 TLD I,ocations, BFN 20 Figure 5 Annual Average Gross Beta Activity in Air Filters, Browns Ferry Nuclear Plant 21 Figure 6 - Annual Average Gross Beta Activity in Drinking Water, Browns Ferry Nuclear Plant 37 7- .j Figure 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 Levels, WBN (4-Quarter Moving Average) . . . 39 Figure ll - Reservoir Monitoring Network 51 Figure 12 - Annual Average Gross Beta Activity in Surface Water 52

ENVIRONMENTAL RADIOACTIVITYLEVELS BROWNS FERRY NUCLEAR PLANT ANNUAI REPORT 1981 Introduction The Browns Fer'ry Nuclear Plant (BFN), operated by the Tennessee Valley Authority, is located on a site owned by TVA containing 840 acres of land in Limestone County, Alabama, bounded on the west and south by Wheeler Reservoir (see figure 1),. The site is 10 miles southwest of Athens, Alabama, and 10 miles northwest of Decatur, Alabama. The plant consists of three boiling water reactors; each unit is rated at 3,293 MWt and 1,098 MWe. Unit 1 achieved criticality on August 17, 1973, and began commercial operation on August 1, 1974. Unit 2 began commercial operation on March 1, 1975. However, a fire in the cable trays on March 22, 1975, for'ced the shutdown of both reactors. Units 1 and 2 resumed operation and Unit 3 began testing in August 1976. Unit 3 began commercial operation in January 1977.

The preoperational environmental monitoring program established a baseline of data on the distribution of natural aqd manmade radioactivity in the environment near the plant site. However, seasonal, yearly, and random variations in the data were observed. In order to determine the potential increases in environmental radioactivity levels caused by the plant, com-parisons were made between data for indicator stations (those near the plant) and control stations (those remote from the plant) in conjunction with com-parisons with preoperational data.

Staffs in the Division of Occupational Health and Safety and the Office of Natural Resources carried out the sampling program outlined in tables 1 and 19. Sampling locations are shown in figures 2, 3, 4, a'nd ll, and table 2 describes the locations of the atmospheric and terrestrial monitor-ing stations. All the radiochemical and instrumental analyses were conducted in TVA's Western Area Radiological Laboratory (WARL) located at Muscle. Shoals, Alabama, and Eastern Area Radiological Iaboratory (EARL) at Vonore, Tennessee.

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

II and Beckman Wide 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.

water, vegetation, air particulates, food crops, and charcoal (specific Samples'f analysis for I-131) are routinely counted with NaI(Tl) detection systems. If significant concentrations of radioisotopes are identified, or, if there is a reasonable expectation of increased radioactivity levels (such as during periods of increased fallout), these samples are counted on the Ge(Li) system.

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

is routinely performed by analysis on the Ge(Li) system. A TVA fabricated beta-gamma coincidence counting system is utilized for the determination of I-131 concentrations in milk.

Data were entered in computer storage for processing specific to the analysis conducted. A computer, employing an ALPHA-M least squares code, using multimatrix techniques, was used to estimate the activities of the gamma-emitting nuclides analyzed by NaI(Tl). The data obtained by Ge(Li) detectors were resolved by the ND4420 software.

The detection capabilities for environmental sample analyses given as the nominal lower limits of detection (LLD) are listed in table 3. Samples processed by NaI(T1) radionuclide combinations such as 'u gamma spectroscopy were analyzed for 13 specific gamma-emitting radionuclides and radionuclide combinations . For these analyses, and Zr-Nb are analyzed as one radionuclide. All photopeaks found in Ge(Li) spectra were identified and quantified. Many of the isotopes identified by Ge(Li) spectral analysis are naturally occurring or naturally produced radioisotopes, such as 7Be, ~OK, Bi y Bl ) Pb p ~

Pb p Ra y etc LLDs for the analysis of the radio-nuclides listed below are given in table 3B. ILDs for additional radio-nuclides identified by Ge(Li) analysis were calculated for each analysis and nominal values are listed in the appropriate data tables. In the instance where an LLD has not been established, an LLD value of zero was assumed. A notation in a table of " values <LLD" for an isotope with no established LLD does not imply a value less than 0; rather it indicates that the isotope was not identified in that, specific group of samples. For each sample type, only the radionuclides for which values greater than the LID were reported are listed in the data tables.

TVA's Radioanalytical Laboratories participate in the Environmental Radioactivity Laboratory. Intercomparison Studies Program conducted by EPA-Las Vegas. This program provides periodic cross-check samples of the type and radionuclide composition normally analyzed in an environmental monitoring program. Routine sample handling and analysis procedures were employed in the evaluation of these samples. The EARL began processing samples in May 1980.

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

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

a The following radionuclides and radionuclide combinations are quantified by the ALPHA"M least,-squares computer code: + 'Ce; s Cr; 1311. 103~166Ru; Cs; .Cs, sZr-Nb. Co; Mn'n; Co; OK 7 and Ba-La

LOUISVLLE I N D. P~

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-HARTSVILLE NUCLEAR PLANT fggjj -PHIPPS BEND NUCLEAR PLANT M I SS. tmBT-CLIIICH RIVER BREEOER I

A L A.B A M A GEORG I A REACTOR

-WATTS BAR NUCLEAR PLANT

-SEQUOYAH NUCLEAR PLANT I --BELLEFONTE NUCLEAR PLANT BROWNS FERRY NUCLEAR PLANT

- YELLOW CREEK NUCLEAR PLANT I

Table 1 ENVIRONNENTAL RADIOACTIVITY SANPLING SCHEDULE Air Charcoal Rain- Heavy Particle River Well Public .Aquatic Life st rio loaati a pilter palter Water p llo t . soil ~pe et tire Milk:water litter watei aad sedi a t l'da Muscle Shoals M Laurenceburg M Rogersville' Athens Decatur Courtland M Site NW-1 M Site N-2 Site NE-3 A Site NM-4 W Site WSW-5 W Farm B Farm Bi/Farm P Farm T Farm L Cl Control Farms k t

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

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

Table 2 Atmospheric and Terrestrial Monitoring Station I,ocations Browns Ferry Nuclear Plant Approximate Distance and Direction from Plant LM-1 BF, Northwest 1.0 Mile (1.6 kilometers)

LM-2 BF, North 0.9 Mile (1. 4 kilometers) NNE LM-3 BF, Northeast 1.0 Mile (1.4 kilometers) . ENE LM-4 BF, Trailer Park 1.7 Miles (2..7 kilometers) NNW LM"5 BF, Davis Farm 2.5 Miles (4.0 kilometers') WSW PM-1 BF, Rogersville, AI 13.8 Miles (22.2 kilometers) NW PM-2 BF, Athens, AL 10.9 Miles (17.5 kilometers) NE PM-3 BF, Decatur (Trinity), AL 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 32.0 Miles (51.5 kilometers) W (Control)

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

Farm S 4.75 Miles (7.6 kilometers) N Farm B 7.0 (11.3 kilometers) NNW Miles'.75 Farm H Miles (6.0 kilometers) N Farm T 7.Q Miles (11.3 kilometers) ENE Farm Bi (Out of business 4.5 Miles (7.2 kilometers) ENE 7/20/82)

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

Farm N (Control) 27.0 Miles (43.4 kilometers) NW Farm J (Control) 40.Q Miles (64.4 kilometers) NNW Farm C (Control) 32.0 Miles (51.5 kilometers) N Farm Ca (Control) 32.0 Miles (51.5 kilometers) .W

Table 3 DETECTIOH CAPABILITIES FOR EHVIRONMENTAL SAMPLE ANALYSIS A. S ecific Anal ses NOMINAL LOWER LIMIT OF DETECTIOH LLD

• Pish, hir Vegetation Soil and clam flesh, Foods, meat, Particulates Charcoal Fallout Mater and grain Sediment plankton, Clam shells poultry, Milk

~Cf ~cf ~ Cf/k CCCff1 ~CI/ ~dr ~Ctl . d ~Cii ~dr ~C1/ d ~fk~~ff Ccf//11 Total a 0.4 0.01 1.5 Cross n '0. 005 2.0 0.05 0.35 0.1 0.7 Gross 9 0. 01 0.05 0.20 0.70 0.1 0.7 25 4H 330 4 441 0.02 0.5 "Sr 0.005 10 0. 25 1.5 0.5 5.0 40 10 44Sr 0.001 2 0.05 0.3 0.1 1.0 8 2 4hll LLD values for isotopic separations are calculared by the method developed by Pasternack and Harley as described in HASL-300.

Factors such as sample size, decay time, chemical yield, and counting efficiency may vary for a given sacaple; these variations may change the LLD value for the given sample. The assumption is made that all samples are analyzed crithin one creek of the collection date. Conversion factors: 1 pCi ~ 3.7 x 10 Bq; 1 mCi ~ 3.7 x 10 Bq.

Table 3

'DETECTION CAPABILITIES FOR ENVIRONMENTAL SAHPLE ANALYSIS B; Gamma Anal ses NOMINAL LOWER LIHIT OF DETECTION'LD Air Water Vegetation Soil and Clam flesh Foods, (tomatoes Meat an" particulates and milk and grain sediment Fish ' and plankton Clam shells potatoes, etc.) poultry

~ct/ ~Ce Li

'al*

odl

~ct/I NaI ~Ce Li

~et/

.'laI ~Ce d

Li

~Ctl NaI dd ~

~Ce{Li

~Ctl II ~CLI

~C1/

C

'd I ~ce Lt

~CI/

NaI ~Ce dr Li Nal Ci wet C~eLi

~CI / k

!Iai Ge{Li1

'r:

I tt 1 1 ~ 1 dt Ce 0.03 38 0.55 0.35 0.35 0.35 38 90

0. 02 33 0.22 0. 06 0.06 0. 35 0.06 33 4C S1C 0.07 0.03 60 1.10 0.47 0.60 0. 10 0.60 0.10 0. 56 0. 60 . 0.10 60 44 200 1 ill 0.01 0.01 15 44 8 0.35 0.09 0.20 0.02 0.20 0.02 0.07 0.20 0.02 15 8 50 90 20 1 01 d 1 0 cgu 0.04 40 0.65 0.45 0.45 0.45 40 150 106R 0.03 40 0.51 0.11 0.11 0.74 0.11 40 90 136G 0.01 0.02 10 26 0. 20 0.33 0.12 0.08 0.12 0.08 0.48 0.12 0.08 10 26 40 50 11SC 0.01 0.01 10 5 0. 20 0.06 0.12 0.02 0.12 0.02 0.08 0.12 0.02 10 5 40 15 scZr-Nb 0.01 10 0. 20 0.12 0.12 0.12 10 40 SCZr 0. 01 10 0.11 0.03 0.03 0.15 0. 03 10 20 SSNb 0.01 5 0.05 0.01 0.01 0.07 0. 01 5 15

'Oco 0.02 0.01 15 5 0.23 0.05 0.20 O.D1 0.20 0.01 0.07 0.20 0.01 15 5 55 15 0.02 0.01 10 0.20 0.05 0. 15 0. 01 0.15 0.01 0.08 0.15 0.01 10 5 40 15 6

Hn Szn . 0.02 0.01 15 5

9 0.25 0.11 '.23 0.02 0.23 0.02 0.17 0.23 0.02 15 9 70 20 "Co 0.01 0.01 -10 5 0.17 0.06 0.11 0.01 0.11 0.01 0.08 O.ll 0.01 10 5 30 . 15 K 0.10 150 2.50 0 90 0.90 0.90 150 400

'"4Ba-l.a 0.02 15 0. 68 0.15 0.15 0.15 15 50 40 0.07 0.30 1

Ba 0. 02 25 0.34 0.07 0.07 25 50 La 0. 01 7 0.08 0. 02 0.02 0.10 0.02 7 15  !

• The NaI(T1) LUl.values are calculated by the method developed by Pasternack and Barley as described in I{ASL-300 and Nucl. Instr. Methods 91, 533-40 (1971). These LLD values are expected to vary depending on the activities of the components in the samples. These figures do not represent the LLD values achievable on a given sample. Water is counted in a 3.5-L Marinelli beaker. Vegetation, fish, soil, and sediment are counted in a 1-pint container as dry weight. The average dry weight is 120 grams for. vegetation and 400-500 grams for soil sediment and fish. Heat and poultry are counted in a 1-pint container as dry weight, then corrected to wet weight using an average moisture content of 70Z. Average dry weight is 250 grams. Air particulates are counted in a well crystal. The counting system consists of a multichannel analyzer and either a 4" x 4" solid or 4" x 5" well Nal(T1) crystal. The counting time is 4000 seconds. All calculations are performed by the least-squares computer program ALPHA-H. The assumption is made that all samples are analyzed within one week of the collection date.

• • The Ce(hi) LLD values are calculated by the method developed by Pasternack and Harley as described in HASL-300. These LLD values are expected to vary depending on the activities of the components in the samples. These figures do not represent the LLD values achievable on given samples.

Water is counted in either a 0.5-L or 3.5-L Harinelli beaker. Solid samples such as soil, sediment, and clam shells are counted in a 0.5-I.

Harinelli beaker as dry weight. The average dry ~eight is 400-500 grams. Air filters and very small volume samples are counted in petrie dishes centered on the detector endcap. The counting system consists of a ND-4420 multichannel analyzer and either a 25I, 14I, 16I, or 29Z Ce(l.i) detector. The counting time is normally 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. All spectral analysis is performed using the software provided with the ND-4420.

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

Conversion factor: 1 pCi << 3.7' 10 Bq.

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

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

Date (+3a) WARL EARL (+3a) WARL EARL (+3a) WARL -EARL (+3a) WARL EARL 12/80 21~9 22 23 19+9 24 26 0 .= ~ 2 <2 19+9 20 22 3/81 30+ 13 31 31 50+9 55 49 18+2. 6 18 15 14+ 9 15 14 6/81 28+ 12 29 32 54+9 62 59 19+2.6 19 23 16+9 17 . 18 9/81 25+11 26 25 51+9 61 54 16+2 ' 16 19 19+9 21 20 B. Tritium in Urine (pCi/L)

Date EPA Value (+30) TVA AVERAGE WARL EARL 3/81 .810+549 713 390 6/81 1600+585 1637 1830 9/81 2050+599 2103 11/81 2700+615 2573 2623

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

b. Eastern Area Radiological Laboratory, Vonore, Tennessee

c. Efficiency curves were checked and known spikes were run. Everything found was within acceptable limits'e are awaiting the next cross-check for further investigation.

d. Results were mailed to EPA but not reported by them.

caw 1 w.~~ ln~t wn analvsgs. There was insufficie5t time ta obtain another sample from EPA and reanalyze.

Table 4 (Contd)

Results Obtained fn Interlaboratory Comparison Program E. Milk (pCf/L) k Strontium - 89 Strontium - 90 Iodine 131 Cesium - 137 Barium - 140 Potassium .Cobalt - 60 EPA value TVA AVC. EPA value TVA AVC. value TVA AVG. value AVG. value TVA AVG. value TVA AVC. EPA value TVA AVC.

Date (i3s) MARL EARL ~33 3 MARL EARL EPA

'MARL EARL EPA

~33 TVA IIARL EARL EPA

'3a MARL EARL EPA

~3 IIARL EARL ~3 a EARL EARL 1/81 0 <10 <10 20i5.2 21 20 26i17 24 21 43i16 40 41 <25 <15 1550i232 1490 1453 4/81 25i9 28 11+2.6 13 26i10 21 29 22+9 21 24 <15 <15 1559+135 1513 1674 7/81 25i9 23 30 17+2. 6 14 16 .Oli <15 <15 31i9 32 32 <15 <15 1600i139 1623 1620 10/81 23+9 25 28 1gi2. 6 17 16 52ilo 49 47 25i9 27 27 1530i133 1620 1500 F. Foods (pCf/kg, Met Weight) 3/81 47i9 42 44 29+2.8 38 21 119i21 126 121 53i9 56 55 0 <15 <15 2640i229 2857 2917 I 7/Bl 44+9 53 51 31+2. 8 31 32 82i14 80 106 45+9 43 54 0 <25 <25 2640i229 2870 3437 q 11/81 3819 49 54 23i2. 6 . 25 22- Noae 33i9 29 35 0

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

m. Results vere marginally out of linfts. Efffcfeacy curves vere checked vfth no conclusive findfngs. Subsequent results have bees satisfactory.

n. Only tvo results vere sent to EPA. Results vere not facluded in their analysis.

o. Values for potassium are reported as ng/kg sample.

p. Investigation of this problem vas faftfated but no satisfactory conclusions 'have been reached. We suspect difficulties arising from sample inhomogeafety.

An incorrect vcfght vas obtained fn the gamma aqalysfs of this sample. Further analysis destroyed the sample so that the correct vefght could aot be determined.

r. Investigation vas conducted. No satisfactory explanation vas found. Other cross-checks on thfs isotope in different media are satisfactory.-

aa Table 4 (Contd)

Results Obtained in Interlaboratory Comparison Program c)

C. Radiochemical Analyses of Water (pCi/L) f Cross Alpha Cross Beta Strontium - 89 Strontium 90 Tritium Iodine 131 EPA value TVA AVG. EPA value TVA, AVG. EPA value TVA AVC. EPA value TVA AVG. EPA value TVA AVG. EPA value TVA AVG.

Date ~33a MARL EARL (33a) 'WAIIL EARL (33a) MARL EARL (I3a) IIARL EllllL (i3a) WARL EARL ~(aaa WARL EARL 1/81 9+9 10 9 44i9 49 49 16+9 11 14 34i3. 1 388 28 2/81 1760+591 1917 1753 3/81 25i10 23 15i 25+9 26 29 4/81 2710i615 2467 2723 30i10 32 28 5/81 21i9 21 14 14+9 14 16 36+9 40 33 22i2.6 . 21 22 6/81 1950i596 1990 194)7 7/81 22+10 20 22 15+9 15 18 8/81 9/81 33+ 14 29 18 i 28i9 29 26 23i9 26 23 11i2.6 11 10 2630i613 2623 2713 73+13 79 73 10/81 2210i603 2263 2197 11/81 2L+9 21 13 23+9 18 24 12/81 2700i615 2717 2807 76+13 6s sd D. Gamma-Spectral Analysis of Water (pCi/L)

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

3 Date ~(ARI MARL EAIIL ~I)a) IIAIIL EARL ~aa IIARL EARL ~aa MARL EARL ~RI wARL EARL ~aa wARL EARL 2/81 0 <60 <60 ~ 25i9 25 25 85+9 84 83 0 <40 <40 36i9 39 35 - 4i9 6 10 3' 6/81 0 <60 <60 17i9 18 17 0 <15 <15 15i9 <40 <40 21i9 23, 21 31i9 27 30 10/81 34i9 <60 <60 22i9 25 22 24+9 26 21 0 <40 <4'0 21i9 21 24 32+9 35 32 E. Specific analysis for ' to test the procedures used for the analysis of milk.

g. Investigations of the analytical procedure were conducted and new efficiency curves were determined. Results have been satisfactory since that time.

h. New efficiency curves were determined subsequent to this analysis. Subsequent results were satisfactory.

i. Excess humidity in counting room and a change in the amount of solid introduced into the sample by EPA are suspected in the difficulty with this sample type. Steps have been taken to correct or compensate for these items.

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

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

Four local air monitors are located on or adjacent to the plant site in the general areas of greatest wind frequency. One additional station is located at the point of maximum predicted offsite concentration of radionuclides based on preoperational meteorological data (see figures 3 and 4). Four peiimeter air monitors are located at distances out to 10 miles from the plant, and two

.remote air monitors are located at distances out to 45 miles. These monitoring stations are shown in figure 2. The remote monitors are used as control or baseline stations. At each monitor, air is continuously pulled through a Hollingsworth and Voss LB5211 glass fiber filter at a regulated flow of 3 fts/min, In series with, but downstream of, the particulate filter is a charcoal filter used to collect iodine. Each monitor has a collection tray and storage .container to obtain rainwater on a continuous basis and a hori-zontal platform that is covered with gummed acetate to catch and hold heavy particle fallout. Thermoluminescent dosimeters are used to record gamma radiation levels at each remote and perimeter station.

Each of the local air monitors is fitted with a GM tube that con-tinuously scans the particulate filter. The disintegration rate of the atmospheric radioactivity is continuously recorded at each station and radio-telemetered into the plant.

Air filters are collected weekly and analyzed for gross beta activ-ity. No analyses are performed until three days after sample collection. The samples are composited monthly for analysis of specific gamma-emitting radio-nuclides and quarterly for Sr and s Sr analysis. The results are combined for each station to obtain an annual average. During this reporting period, three samples were hot obtained because of equipment malfunction. These data are presented in table 6.

The'nnual averages of the gross beta activity in the air particulate filters at the indicator stations (local and perimeter monitors) and at the control stations (remote monitors) for the years 1968-1981 are presented in figure 5. Increased levels due to fallout from atmospheric nuclear weapons testing are evident, especially in 1969, 1970, 1971, 1977, '1978, and 1981.

These patterns are consistent with data from monitoring programs conducted by TVA at nonoperating nuclear power plant construction sites. Table 5 presents the maximum permissible concentrations (MPC) recommended by 10 CFR 20 for nonoccupational exposure.

Rainwater is collected monthly and a 3.5-liter sample analyzed for specific gamma-emitting radioisotopes and tritium. The results are shown, in table 7.

The gummed acetate that is used to collect heavy particle fallout is changed monthly. The samples are ashed and counted for gross beta activity.

The results are given in table 8.

12 Charcoal filters are collected and analyzed for radioiodine.

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

13 Table 5 NAXIMM PERHISS IBLE CONCENTRATIONS FOR NONOCCUPATIONAL EXPOSURE In Water In Air

~Ci/ I* yCX/m'+

Alpha 30 Nonvolatile beta 3, 000 100 Tritium 3,000,000 200,000 1 31CS 20,000 500 103~ 106Ru 10,000 200 144Ce 10;000 200 96Zr-93Nb 60,000 1,000 140 '40Ba 20,000 1,000 131Z 300 100 Zn 100,000 2,000 100,000 1,000

'4'0C 30,000 300 89Sr 3,000 300 90Sr 300 30 "Cr 2,000,000 80,000 134Cs 9,000 400 58Co 90,000 2,000

• 1 pCi ~ 3.7 x 10 Bq.

TALLE RAOIOACTIVITY IM AIR FILTEP PCI/H(3) - 0 037 BQ/H(3)

MAHE OF FACILITY ~o~t'%~ERRY -- DOCKET Woe~0-25~/~29/

LOCATION OF F AC'ILITY L~IH STD~M A A AHA REPORTING PERIOD TYPE ANO LOIIER L IH IT ALL Cot)TROL NUHBER OF TOTAL NUHBER OF ItlCICATO% LOCATIONS ~~A~T~VTH ~Hfdf AgH~~HAM

.HEAN (F)b LOCATIONS (F)

NONROUT INE OF ANALYSIS DETECT ION ~ tIEAM LF)b WAkE HEAM REPORTED Pf RQQR~H ~L,Ql RANQL ~gy~AC ~AN gaff r JOM RA~M+ ~ R MG b ~HA S~UR ~HM T 5 GROSS ALPHA 0 005

~ 0 F 01( 3/ 52) 52 0 01- 0 F 01 GROSS BETA 0 ~ 010 6F 08( 456/ 465) 01-LH4 BF TRAILER P 0F 09( 50/

'652) 0 '8(

~

103/ 104) 569 0 F 0 38 I ~ 7 MILES NNM 0 01- 0 0 ~ 01- C ~ 39 GAHHA CHAI) 49 CE 141'44 0~ 030 05( 8/ 39) I.H3 BF NORTHEAST 06( 1/ 4) Oa04( 4/ 1C)

RU-103'06 0 '40 0F 0 '3 0%05( 5/

o.e6 39) 1 ~ 0 MILE EME LH3 BF NORTHEAST 0

0~

F 06-0 ~ 06(

0 1/

'6 4) 0 F 0~05(

03- 0+07 2/ 10)

ZR-95eNB-95 0~ 010 0 05-0~06(

0 '6 20/ 39) 1 ~ 0 HILE ENE ATHENS'L 0 ~ 06-0 ~ 13(

0 1/

'6 3) 0 F 05-0 '6( 0 F 05 5/ 10)

I-131 0 010 0~

0F 01-02(

0 '3 6/ 39) 10.9 HII.ES NE DECATUR'L 0 ~ 13 0 F 02(

0~

1/

13 5) 0 F 02 10 VALUES CLLO 0 '3 0~ Dl- 0 ~ G2 8~2 HILES SSE 0 F 02 02 BE-1 NOT ESTAB 0~ 09(

0~ 01.-

35/ 39) ATHEMS4 AL 0 '2(07-DE 3/ 3) 0

'5-

~ 10( 10/ I G) 0021 10 ~ 9 HILES ME 0 ~ D&21 0 0 ~ 23 .

GAHHA (GELI) 94 CE 141 00010 0~ 01( 8/ 78) ATHENS'L 0~ 02( I/ 10) 16 VALUES <LLO oool- 0 F 02 10 9 HILES NE 0 ~ 02- 0 02 CE-144 0 ~ 02C 0~ C4( 16/ 78) ROGERSVILLE+ AL 0 F 05( 2/

F

10) 0 '2(

'2- 3/ 16) 0 02- 0 ~ 07 13 ~ 8 HILES N)t 0 ~ 04- 0 ~ 07 0 0 ~ 30 RU-103 NOT ESTAB D~GI( 38/ 78) Lkl BF NORTH(tEST 0 F 02( 4/ 8) 01( 7/ 16)

ZR-95 0 '10 0 ~ 00-03(

0 '3 34/ 78)

I ~ 0 NILE ROGERSVILLEs AL M 0 ~ 01-0 F 04(

0 '3 5/ 10) 0 0

F F 01-02(

0+02 8/ 16)

NB-95 0~010 0F 0 ~ 01-De05(

0 '6 40/ 78) 13 ~ 8 HILES MM OECATURt AL 0 ~

0007(

02- 0 4/

F 06 8) 0 0

~

F 01-G5(

0 8/

~ 03 16)

K 40 NOT. ESTAB 0~ 01-12(

0 '5 58/ 78) 8 ~ 2 HII.ES SSF LH2 BF NORTH 0 ~ 03-

'6( 0 3/

~ 12 6) 0~

0 0

'2-13(

0 13/

~ 09 16)

SI-214 0 ~ D20 0

0 0

'6

'4( 44/

0 ~ 30 78)

De9 HILE t(ME DECATUR'L 0

0 0

~

~

12-05(

0 6/

~ 18 8) 0 0~04(

ll- 0 7/

16 16)

D~ 02- O9 8 ' HILES SSE 0 ~ 02- 0 09 0 ~ 03- 0 08 BI-212 NOT ESTAB 0 '4(

04-1/

O

78) 6ECATURy Al. 0*04(

Oa04-I/ 8) 16 VALUES (LLO F

0~ 0 ~ 04 8 2 HILES SSE 0 ~ 04 PB-214 0 '20 0~ 04( 28/ 78) DECATUR% AL D.O5( 3/ 8) 0 ~ 03( 6/ 16) 0002- 0 F 08 8 ~ 2 HILES SSE 0 ~ 03- D~ 07 0 ~ 02- 0~ 07 PB 212 NOT ESTAB Geol( 35/ 78) LH3 BF NORTHEAST 0 '2(02-1/ 9) 0 F 01( 7/ 16) 0~ Go- 0 ~ 03 leO tllLE ENE 0 ~ 0+ 02 D~ 00 DE 02 BE-7 0 05 08( 41/ 78) DECATUR'L 0 ~ 16( 5/ 8) 0 ~ 07( 9/ 16)

TL 208

~

ESTAB

('OT 0F 0~

0F 05-01( 14/

0 ~ 47 78) 8 ~ 2 HILES SSE LH4 BF TRAILER P 0005 0 ~ OI (

0 2/

'7 7) 0 ~ 05-0 F 01(

0 ~ 10 3/ 16) o.eo- 0 ~ 01 1 ~ 7 HILES NNll 0 ~ 01- 0 ~ 01 0~ 01- 0 ~ 01 SR 89 0 F 005 0F 01( 18/ 36) LH5 BF DAVIS F 0 ~ 01( 2/ 4) F 01( 4/ 4) 0~ 01- 0 ~ 01 2 5 tIIL'ES MSM 0 01- 0401 0 ~ 01- 0F 01 SR 90 0~001 0F 00( 7/ 36) I 0 F 00( 1/ 4) 0 F 00( 3/ 8) 44 0~ 00-. 0 ~ 00 0 ~ 00- 0~00

RADIOACTIVITY Itt RAIhVATER PCI/L - Oo037 BO/L NAHE OF FACILITY QRR~NFERRY DOCKET NO ~ 50-$ 5~9 LOCATION OF FAC)L ITY~IH~STO~tt lLAQAHA REPORTIttG PERIOD 9 TYPE <<ND LG'4EP. LIHIT ALL CONTROL NUHBER OF TOTAL NUMBER OF It(DICATOF LOCATIONS LOCATIONS NONROUTINE OF ANAL'YSI 8 DETFCT ION a HEAth (F ) HEAN (F) b REPGRTED PERFORNEO CLLO) RANGE b II I r Qf 1 ~HASU~R~Hrt4TS GAtlt4A (NA I )

97 Cr 141 ~ 144 38 F 000 77 VALUES <LLG 43 '0- I/ '0 43 60(

43 20)c RU-103 '06 40 000 48 '0( 1/ 77) DECATUR'L 48 ~ 20( 1/ 8) 20 VALUES <LLD 48 ~ 20- 48od0 8 2 tlILES SSE CLAVIS 48o20- 48o20

'48-q5 15 '2( 19/ 77) LH4 BF TRAILER P 20 ~ 20( 3/ 8) 19 63( 3/ 20)

ZR-95 10oOOG 10 ~ 10- 25 F 10 1 7 HILES NNV 15 ~ 60- 25010 10 '0- 35 '0 1-131 15o000 22 F 10( 1/ 77) LHS BF DAVIS F 22olOC 1/ 6) =-

2C VALUES <LLD BE-7 NOT ESTAB 22olO-51 ~ 80(

22 '0 49/ 77) 2 ~ 5 HILES VSV LHS BF F 22 ~ lG-67o88(

22 10 4/ 6) 56 '6( 14/ 20) 7 ~ 30- 133 '0 2 o5 H ILES VSV 39%70 115o10 14 00-F 108o10 GAHHA (GELI) he ZR-95 10 F 000 40 VALUES <LLD 10 '2(

10ol2-1/ 6) 10ol2 F 000 9<<63( 2/ 40) LH5 BF DAVIS F 10 ~ 32(

Shan 1/ 7) 13 '2( 1/ 6) 13 '2-WB-95 K-40 8 ~ 93- 10 '2 21/ 40) 2<<5 tlILES VSlt LH3 BF t(ORTHEAST 10 ~ 32-125o00(

$ 0o32 1/ 6) 58 '9(

13o82 2/ 6)

NOT ESTAB 81 ~ STC 32 F 71- 125 F 00 loO HILE EteE 125o00 125o00 54 '9- 61o78 BI-214 t(OT ESTAB 22 '9( 25/48 '840)

'2- LH3 BF NORTHEAST' NILE 29 '3(

16 ~ 24-4/

48o38

6) 40 21(

23 '9- 3/

70 '1 6) 11 ~ 0 ENE PO-214 NOT ESTAB 17 '5( 12/ 40) LH3 BF NORTHEAST 28 '8(

'8 1/

'8 6) 11 ~ S6C 2/ 6)

F 41- 29 '7 1 ~0 HILE ENE 28 28 8 'S- 1'le 16 PB-212 NOT ESTAB lh 32( 8/ 40) COURTLAf4D~ AL 18 '9( 1/ 3) 6 VALUES <LLO 8 '9- 18 '9

~

10 ~ 5 HI LES VS V 18o09- 18009 Dr-7 NOT ESTAB 49 '5( 3/ 40) LH5 BF DAVIS F 49 ~ 35( 3/ 7) 1 05 F 00( 1/ 6) 43 '8- 54o06 2 ~ 5 HILES. VSV 43 ~ 28- 06 I 05 F 00- 105 00 TR ITIUH 330 F 000 117 VALUES <LLD 26 VALUES <LLD 143 ANALYSIS FERFGRHED

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

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

c. Identified as fallout.

TABLE 8 RADIOACTIVITY IN HEAVY PARTICLE FALLO47 HCI/KH(2),- 370COOCO ~ GO bQ/KH(2) hAHE GF FACILITY BRQMNS Ff RRY DOCKET NO~~~

LOCATION OF FACILITY LIHESTONE ALABAMA REPORT ltJG PERIOD 1901 ORHELP TY~E AKD L OMEFE L I HI T ALL CONTROL tJUHBER OF TCTAL tiUHBER OF INDICATOR LOCATIOhS LOCATIONS NOtJROUTINE OF <<NALYSIS Dr TFCT IONa MEAN ( ()b NAME HEAN (F) b MEAN (F)b REPORTED P~f:F (ll,Q) RANGE OJSTA4~CA~tJ i DIR~TION RAh'G~b ~RAN fb PE'ASUREHC)JTS GROSS BETA 0 '50 09( 117/ 117) 'LH'I BF TRAILER P 35( 13/ 13) I ~ 04( 26/ 26) 163 1~

0 '8- 3<<73 I~ 7 MILES tJNlt .

1 0 ~ 16- 3 ~ 73 0<<12- 2+79

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

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

TABLE 9 RADIOACTIVITY Iti CH>RCOAL F ALTERS PCI/tF l3) - 0 ~ 637 BO/H(3)

NAME OF F AC ILITY ~Ru~t.'ERRY LOCATION OF FACILITY LIHfSTONQ ALADAHA REPORTII 9 FEII TOO~99 ALL CONTROL NUHBER OF TYPE AND LO)tER L IH IT TOTAL ttUHBER OF INDICATOR LOCATIONS EOCATI~OI ~TH 'EEOE ~AY EO~II A LOCATIONS NONROUTItRE OF ANALYSIS DETECT IOka HEAR l f )b IIEAN IF& REPORTED RAN ~HAS~UR l I LR)

Pf,R~~ORH 0 IODINE IN AIR 0 ~ 020 0

'2-R

$ 3t ANtt~o 62/ 466)-

Oa09 COURTLANDe AL 10 ~ 5 MILES VS) 0 '6l 0 ~ 02-2/

0 ~

50) 09 0

0

~ 02l

'2- 13/ 104) 0 F 04 tA~hTE'.

570 0

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

b. Mean and range based upon detectable measurements only. Praction of detectable measurements of specified locations is indicated in parentheses (P).

18 Figure 2

. ATMOSPHERIC AND TERRESTRIAL MONITORING NETWORK RM.28F LAWRENCEBURG yPULASKI FAYETTEVILLE PM-IBF WILSON WHEELER ROBE SVILL OAM ATHENS FLORENCE PM-2BF FFIEL MUSCLE HUNTSVILLE SHOALS BROWNS FERRY NUCLEAR PL NT RM-I 8F LEIGHTON TUSCUMBIA COURTLANO$

PM-4 F OECAT PM SBF0 IO MILES pRUSSELLVILLE GUNT SVIL HARTSELLE HALEYVILLE CULLMAN 45 MILES 0- ENVIRONMENTAL MONITORING STATION NOTE: THE FOLLOWING SAMPLES ARE COLLECTED FROM EACH STATION:

AIR PARTICULATES RAINWATER RADIOIODINE SOIL HEAVY PARTICLE FALLOUT

Figure 3 LOCAL MONITORING STATIONS 19 BROWNS FERRY NUCLEAR PLANT ATHENS US HWY 72 BFN ALA. HWY 20 Legend

~ Air Monitor DECATUR Automatic Well Sampler H Dairy Farm Scale 0 I 2 3 4 5 Miles

I, 20 Figure 4

'I ( *I I (I

I

""( >

~

/

C>.C /I~ C.

/

II I ~J P

P J 4

'yP w~ (t'p 4TI

,~I~

I j5 TLD LOCOIIOll5 "~

Palo ~ r> '\ ~

PI

't g 144$

~ IP >1@+~9

~

')

I .", ~ SI 5. ) , I ~

>rC/I

(, n

. C/r'I-

"-ki r.

) ',')

c,l.

'. 'E'5(

w la 4 I r I(

w '/

r,' ,gq

'( ','

P rnj r t

( ( ('(',l '

~

I I

oC

,.f. O oj

',~-

I 4PP (II AI ~

~

/I C

'I

~ J P/()I I

(

I I I>

w>W ~

'g, 4(

IJ.,P ) il .

!( 4 'I . CI

~ I fX ~

I 'Io g'Eq (

P P I) ( CC4J I A r(,. / ~ ~

.I.' 'I .

I rsH r C I' a C'CI o - pwj

~ I 1' XI ~ (

~ I (t. C I 4 I5 t t

~ .w~ ~ '. 1-I (.. IC C

r

( '

CPP

'Ic h rII

<"eQ

'f.,

.g'I I,, l

(',l

(!

/((.(. I r I Pl I I ((',

I,

~"

'44 aa

'/I P

'~I

' ~ ..-'-"r. ' ) ) >q

~,, I ", Pr A i 4>

5z ~((

~I

~4 ~I Q ~ 0 I ~ I

'C I

rs/boa r/r 41

figure 5 AWUAL AVERAGE .

.30 6ROSS 8ETA kTIVITY IN AIR FILTERS BROmS FERRY NUCLEAR PLANT Preoperational Phase Operational Phase

.25 CC o

9

.20 IJ IJ IQ C IJ IfI 0

IJ 0'4

~ w IJ l

0

.15 w 4l Average: Preooerational Phase

.10

.05 1968 7 72 1973 1 9730 197>> 1975 1976 1977 1978 l979 1980 198 1

s *-

~ j I

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

Cow censuses were conducted in May and September 1981. It was determined that there are no dairy farms nearer the plant than the nearest farm being sampled. During this period however, one of the dairy farms being sampled (farm B, table 2) went out of business and all .cows were sold. Another dairy farm (farm P) was added to the monitoring program on August 3, 1981.

V~e etation Vegetation is sampled quarterly at the farms from which milk is collected and analyzed for gamma-emitting radionuclides. Approximately 1-2 kilograms of grass is broken or cut at ground level and returned for analysis.

Efforts are made to sample vegetation that, is representative of the pasturage where cattle graze. Table analyses of these samples.

ll gives the results obtained from the laboratory Soil Soil samples are collected annually near each monitoring station to provide an indication of a long"term buildup of radioactivity in the environ-ment. An auger or "cookie cutter" type sampler is used to obtain samples of the top two. inches (5 cm) of soil. These samples are analyzed for gamma-emitting radionuclides, sSr, and oSr. The results are given in table 12.

Ground Water An automatic sequential-type sampling device has been installed on a well downgradient from BFN. A composite sample from this well is analyzed for gamma-emitting radionuclides monthly and composited quarterly for determination of tritium. A grab sample is also taken from a control well upgradient from the plant. The results of the analysis of well water are shown in table 13.

Potable water supplies taken from the Tennessee River in the vicinity of BFN are sampled and analyzed for gross beta and gamma-emitting radionuclides, and composited quarterly for tritium, ~Sr, and oSr analyses. The first potable water supply downstream from the plant is equipped with an automatic sampler with samples collected and analyzed weekly. The sampler is located on the water intake structure and takes the sample from the river as the raw water is drawn into the water treatment facility. Two additional supplies

24 downstream and one public water supply upstream are sampled by taking monthly grab samples of treated water at user points. Table 14 indicates the results from the analysis of drinking water samples. During this reporting period, six of the weekly samples were not taken because of the malfunction of automatic sampling equipment.

Figure 6 shows the trends in gross beta activity in diinking water from 1968 through 1981. The annual average level from the raw water samples tends to run slightly hi'gher than the average for treated water samples; however, the levels are consistent with the activities reported in surface water samples taken upstream from BFN (figure 12) and in samples taken from the Tennessee River in preoperational monitoring programs conducted by TVA at other sites.

Environmental Gamma Radiation Levels Bulb-type Victoreen manganese-activated calcium fluoride (Ca~F: Mn) thermoluminescent dosimeters (TLDs) are placed at sixteen stations around the plant near the site boundary, at the perimeter and remote air monitors, and at nineteen additional stations out of approximately five miles from the site to determine the gamma exposure rates at these locations. The dosimeters, in energy compensating shields to correct energy dependence, are placed at approxi-mately one meter above the ground, with three TLDs at each station. They are annealed and read with a Victoreen model 2810 TLD reader. The values are corrected for gamma response, self-irradiation, and fading, with individual gamma response calibrations and self-irradiation factors determined for each TLD. The TLDs are exchanged every three months. The quarterly gamma radiation levels determined from these TLDs are given in table 15, which indicates that average levels at onsite stations are approximately 2-4 mR/quarter higher than levels at offsite stations. This is consistent with levels reported at TVA's nonoperating nuclear power plant construction sites where the average radiation levels onsite are generally 2-6 mR/quarter higher than levels offsite. The causes of these differences have not been completely isolated; however, postulated that the differences are probably attributable to combinations of it is influences, such as natural variations in environmental radiation levels, earth moving activities onsite, the mass of concrete employed in the con-struction of the plant, and other undetermined influences.

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

Prior to 1976 measurements were made with less sensitive dosimeters, and consequently the levels reported in the preoperational phase of the moni-toring program are 1-2 times the levels reported herein. Those data are not included in this report. Therefore, for comparison purposes, figures 9 and 10 depict the environmental gamma radiation levels measured during the construction of TVA's Watts Bar Nuclear Plant to the present. Note that the data follow a similar pattern to the BFN data and that, as discussed above, the levels reported at onsite stations are similarly higher than the levels'at offsite stations.

Poultr and Food Cro s Food crops and poultry raised in the vicinity of BFN and at control locations are sampled as they become available during the growing season, and analyzed 'for gamma-emitting radionuclides. During this sampling period, samples of cabbage, corn, green beans, peaches, potatoes, turnip greens, tomatoes, soybeans, and poultry were collected and analyzed for specific gamma-emitting radionuclides. No sample of soybeans or cabbage'as taken from a control location. The results are given in tables 16, 17, and 18.

TABLE 10 RADIOACTIVITY IN MILK PC I /L 0 ~ G37 BQ/L NAME. OF FAG ILITY 8~RUNS F fRRY COCKET IIO ~ O~C-T O T~OO 'TO LOC*TIOH OF FACILTTT~II OTOHE tLABAHA REPORTIttG PERIOD 1981 TYPE AND LO'NER LIMIT ALL CONTROL NUtcBER OF .

TOTAL ttUMBER OF INDICATOR LOCt TIONS LOCATION) tTONROUTINE OF ANALYSIS DETECT IO", MEAtt (F )b HEAR (j) RCPORTED

~(21 R~giggb QECTCN~THC~EEE~TC IIAmf, RAN~ ~V. AEt~f,HAUNTS

~AMMA (NAI) 107 CS-137 10 F 000 13 '3(

lle70-3/ 55) PAGE FARH 13 '3(

'0- 3/ 4) 10 '0(

'0- 1/

'652) 16 F 00 8 F 75 MiLES C 11 16 F 00 10 10 1308 '1( 1232 '5(

K-40 150 000 1246i91( 55/ 55) THRASHER FARt: 12/ 12) 52/ 52)

IODINE IN HILK 0 ~ 500 1049 '0- 1569 253 VALUES <LLD

'0 7 ' MILES ENE 1127 '0- 1569 '0... 1037 '0 1391 F 80 201 VALUES <LLD 454 ANALYSIS PERFORHCD GAHHA (GELI )

6 CS-137 5 ~ 000 8 90(

'4- 3/ 6) SHITH FARH

~ 75 HILES 10 '6( 1/ 1) 7 10O16 4 N 10 16 10%16 1500 '0(

F K-40 F(OT ESTAB 6/ 6) THRASHER FARM 1845 F 00( 1/ 1) 1287 00- 1845 F 00 7 0 MILES ENE 1845 ~ 00- 1845 F 00 20 '3( '3(

F BI-214 NOT ESTAB 5/ 6) SHITH FARH 30 1/ 1) 7 '9- 30 '3 4 '5 MILES N 30 ~ 43- 30 '3 1)

PB-214 NOT ESTAB 18 05( 3/ 6) 20 F 63( 1/

14 '9-BROOKS FARH 20 '3 20 '3 F

7a 0 MILES NN)t 20 63-SR PB-212 TL 208 89 NOT ESTAB NOT ESTAB 10 F 000 14 88(

9 '3-4 '3(

F 18 61 VALUES <LLD 3/ 6) 20 '6 2/ ')

6o48 SMITH FARH 4i75 tllLES PAGE FARM 8 ~ 75 MILES C N

20+96(

20 96-

~

6 '8(

6 '8 1/

20 '6 1/

6 '8 I) 1)

52 VALUES <LLD 113 ANALYS IS P ERFORiREO SR 90 113 F 000 3 2 'I'5( 61/ 51) 8 ~ 19 S

4 HI TH F AR I)

'5 t(ILES N 4

3 74 (

'2-

~ 13/

8 '913) 4 2F

'3(

06-40/

7 '6SP)

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

b. Mean and range based upon detectable measurements only. IFraction of detectable measurements of specified locations is indicated in parentheses (P).

TABLE 11 RAOIOACT I V I'IY IN VEGETATION PCI/G - 0~ 037 80/G CDRY VEIGHT)

NAME OF F)C ILITY BROMNS FERRY OOCKCT NO ~ 50-2 9 60 LOCa T10 tt OF F AC I L I IY~I ME'S TO tt E TYPC 4NO LOVER LI HIT ALL CONTROL NUMBER OF TOTAL NUHBCR OF It(OICATOR LOCATIONS LOCATIONS NONROUT INE OF ANALYSIS DETECTION )b REPORTED

~(LO) ~RAl G GROSS BETA 0~ 200 26 '3(

Ta70-20/. 20) SITTING FARM ~ 35a32( 2/ 2) 26~52( 16/ 16)

~ASQQf~MNTS 36 48a82 4~5 MILES ENC 31 88- 38 75 10 F 07- 45~74 GAIIHA (GCL I) 38 CC-141 0 '00 1~ 93( 5/ 21) THRASHER FARM 2 '2( 1/ 4) 93l 4/ 17) 144 0~220 1~

1 21-56( 17/

2+92 21) 7.0 MILES CNC LOONEY FARM 2+92-2060(

2 '2 2/ 4) 1 ~

i+16-1 '9( 2 13/ 17)

'6

>P-144 NOT ESTAB 0

3

~ 23-

'0( 3/

So49 21) 5.75 MILES Et;E LOONEY FARH 0 41-4061( 1/

80 4) 0~

F 71(

30- 5 '5 1/ 17)

RU-103 0~200 I ~ 43 I ~ 25( 6/

4 '121) 5 75 t(ILES CNE 4o61- 4~61 2 ~ 71- 2 '117)

LOONEY FARM 1~53( 1/ 4) lo39( 4/

0 22- .2+14 5+75 t(ILES ENE 53- 1+53 RU-106 0~510 1 '8(

~

2/ 21) THRASHER FARM 1

1 ~ 54( 1/ 4) 1~ 10 11( 2/

1 ~ 65 17)

CS-137 0.060 1+01-0~ 16(

lo54 14/ 21)

~ 7 ~ 0 HI LES CNE BITTING FARM 1 ~ 54-,

'2( 1/

1~54 2) 1 ~

0 '9

'1C 7/

1 ~ 34 ZR-95 110 0 ~

'6(

07- 0 10/ 21)

'2 ha5 MILES ENE 0

0+32- 0~32 0

0 ~ 06- 0 '0 17) 0 ~ 1 BITTING FARtt 3 ~ 95( 1/ 2) I ~ 90( 8/ 17)

NB-95 0 '5G 0

2

~

'4(

17-18/

4 ~ 46 21 )

4 ~ 5 HILCS CNE BITTING. FARM 3 ~ 95-4 '8( 2/

3 '5 2) 0 ~ 30-2 '5l 4

13/ 17)

'1 0 06- 10 ~ 28 4 ~5 MILES ENE 0 39- 8~36 0 06- 9 '6 Ila37( 17/ '7)

~

12 '6(

~

K-40 NOT ESTAB )0+40( 21/ 21) BROOKS FAR( 4/ 4) 2 ~ 00- 25 98 7~0 MILES ht(M 2088- 22 '6 2~23- 28 '5 MN-54 0 '50 0 '8(06-3/ 21) THRASHER FARM 0 10( 1/ 4) 0 ~ 10( 4/ 17) 0 F 10 7 0 MILES ENE 0~ 10- 10 08-Y 88 NOT ESTAB ~ 0 '2(

~

1/ 21)

'221 ) OITTING FARH 0~02( 1/

0~

2) 0 ~

17 VALUES <LLO 0~ 12 0002 0 4 ~5 MILES CNE 0 ~ 02- 0 02 AI-214 0 '00 0 ~ 35l '9/ BITTING FARH 0 49( 1/

F

2) 0 ~ 30( 10/'7) 8 I-212 NOT ESTAB 0 ~

'3(

14- 0 1/ 21)

'2 4a5 HILES LHl BF t(ORTHMEST CNC "0+49- 0+49 Oo1 1- 0'+64 0 0~ 33( 1/ 1)

>8-214 ttoT EST~8 0 ~ 33-20( 19/ 21) 0 '3 I ~ 0 MILE N 0 ~ 33- 0033 17 VALUES <LLO.

0~ BITTl(IG FARH 0 ~ 27( 2/ 2) 0+21( 12/ 17) 0 ~ 31- 0 ~ 41 4 S HILCS ENC 0 ~ 16- Ga38 0~ 10- 0050 oO" 212 NOT ESTAB 0 ~ 18( 20/ 21) LH1 BF NOR TIIMEST 0~ 72( 1/ 1) F 17( 14/ 17).

RA-226 NOT CSTAB 0 ~ 03-

'9( 3/

0 ~ 72 21) 1 0 HILE N 0 72-0 ~ 14( 1/

0~72 4) 0 ~'04 2/

0 '317)

BE-7 NOT CSTAB 0

0 ~ 06-5 ~ 65( 21/

0 '4 21 )

BROOKS FARIL 7 ~ 0 MILES NNM LOONEY FARt".

0 ~ 14-

'7( 4/

0~ 14 4) 0 F 07(

0 ~ 03- 0 ~ 11 96( 17/ 17)

I'L-208 ESTAB lo12- 15 08( 16/ 21)

'3 LH1 Se75 MILES EWE 7

1

'9(12- 13 '1 1) 5 2 ~ 29- 14 '0 NOT 0~ BF NORTHliCST 1/ 05( 9/ 17) 0 ~

'3(

00- 0 '9 leO NILE N 0

0~ 29- 0 ~ 29 0

0

~

01- 0 16 AC-228 NOT ESTAB 0 07-18/ 21)

'8 L.'ll I

BF NORTHMEST HILE 0 '6(

36-1/ 1)

~

0 ~ 17( 14/ 17) 0~ 0 ~ 0 N 0 ~ 0 36 0 ~ 02- 0 ~ 52

a. Homin al Lowe r Limit of Bete ction (LLD) as scribed in Table de 3.

b. Mean and ran Se base d upon d etectable measur emeute only.. Fraction of detectable measurements of specified locations is indicated in parentlieses (F).

TAbLC 12 RADIOACTIVITY IN SOIL oCI/G - 0 ~ 037 84/G (DRY vCIGHT) t'AHE OF FACILITY QRCVNS FgoRY (AOCKET t 0 ~ 50-259A2~60 296 LOCATION OF FAEILTTT~LIR STORE ALAr>HA RCPORT ING PERIOD~1 T TPC At(D LOVER L 1t! I T ALL CONTROL NUHBER OF TOTAI. NUHBC4 CF INDICATOrs LOCATIONS LOCAT I GNRI NONROUTINE OF ANALYSIS DETCCT ION HCAN (E) HEAN ($ ) REPORTED FERFORIIEO R~ATAt G RANGE ~HASUR~~HTS OAFIIA TOELII 11 CC-141 G ~ 030 0~ 06( 1/ 9) LHZ BF NORTH o.oe( I/ 1) 2 VALUCS <(.LO o.oe- 0.06 Coo HILC NNC 0 ~ C&- 0 F 06 CE-144 0 '60 0 '3(

08-4/ 9) ROGCRSVILLCo AL 0 ~ 24( 1/ I) 0~ 10( 2/

0 F 0o24 13 ~ 8 HILCS Nli 0 ~ 24- 0o24 0 ~ 08- oolZ RU-103 tiOT ESTAB 0 F 02( 4/ 9) LHl BF NORTHVEST Oo03( 1/ 1) 0 ~ 03( 2/ 2)

CS-137 0 '20 ~

0 0

oolo-32-

'5( 0

)/

F 82

>3 9) 1 ~ 0 NILE ROGCRSVILLCs AL 13 8 HILCS tJV N 0 ~ 63-1 ~ 82(

1 ~ 82-0 1/

F 03 I ~ 82 1) 0 ~ 02-0 ~ 96(

0o64-2/')

oo03 le28 2 EA-95 0 ~ 030 0 0~

06(

04-8/

0 ~ 11 9> POGCRSVILLE ~ AL 13 8 HILES NV 0~ ll(

oell-1/

F 11 I> 0 F 08(

0 ~ 04-2/

0 12 2) ti'8-95 0~ 010 0~ 14( 9/ 9) ROGERSVILLCt AL 0 ~ 35( 1/ I) 0 '4( 2/ 2) 0 ~ 06- 0 ~ 35 13e8 tlILCS NV 0 o 35-. oe35 0~ 09- 0 19 K-4 0 0 ~ 250 5o42( 9/ LH4 BF TRAILER P 7ol3( 1/ 1) 4 o97( 2/ 2)

To13 9)'o90-I ~ 7 HILES NNV 7 ~ 13- 7 ~ 13 4 ~ 97- 4o98 GI-214 0 050 lool( 9/ 9) LH2 BF NORTH 40( 1/ 1) Oe90( 2/ 2)

~

0 '1- 1 ~ 40 oe9 HILE Nt(E 1 ~

1 ~ 40- 1 40 0 ~ 78- F 02 81-212 0 F 100 0 '6( 9/ 9) DECATU4t AL O.86( 1/ 1> 0 ~ 46( 2/ 2) 0 ~ 29- 0 ~ 86 8 ~ 2 HI LES SSC 0 ~ 86- 0 ~ 86 0~ 34- 0 ~ 58 PB-214 0~ 050 lo08( 9/ 9) LH2 BF NOPTH 1 ~ 46( 1/ 1) 0 92( 2/ 2)

PB-212 NOT ESTAP 0 'P-I ~ 08(

Oe59-1 9/

1

~

~

46 43 9) 0e9 HILE DECATURE AL 8 '

NtJE HIILES SSE 1 ~ 46-1~

1~

43(

43-1 ~

1/

46 I ~ 43 I) oe81-0 ~ 94(

0 ~ 86-1 ~

2/

1 ~

')

04 03 RA-226 -".50 I ~ 16( 9/ 9> ATHENS'L 2e43( I/ 1) 0 ~ 90( 2/ 2)

RA-223 C

NOT ESTAB 0 ~ 51-6 ~ 36(

2(43 4/ 9) 10 9 HILCS NE LV4 BF TRAILER P 2 ~ 43-0 ~ 46(

2 1/

'3 I) 0 ~ 78-2 VALUES <LLD 1 ~ 02 G ~ 29- 0 ~ 46 I ~ 7 HILCS ttNV oo46- 0 46 OC-7 0 F 160 0 '4(

'1- 2/ 9) L"3 BF NORTHEAST loo NILE 0 ~ Za( 1/

~

1) 0 '5(

19-2/ 2)

~

0 0 ~ 26 CNE 0 ~ 26- 0 26 0 0 30

'8( ~ ~

~ ~

TL-208 0 020 0 9/ 9) LH1 BF NORTHVCST 0 ~ 48( I/ 1) 0 ~ 33( 2/ 2)

AC-228 0

~

060 0~ 18-1 ~ 12(

0 9/

~ 48 9) 1 ~ 0 H I LE ti UECATURE AL 0 ~ 48-I ~ 46(

0 1/

'8 1) 0 ~

0 31-

'7(

0 2/

~ 36 2) oe52- 1 ~ 46 8 ~ 2 HILES SSE 1 ~ 46- 1 ~ 46 0 '0- 1 05, PA-234il NOT ESTAB 3 '0( 1/ o) LHZ GF NORTH 3 50( 1/ 1> 4 '9( 1/ 2)

Sr 89 1 ~ 500 F 50-9 VALUES <LLD 3 50 0 ~ 9 HI LE tttt E 3 ~ 50- 3 '0 4 2

'9- ~ 4 VALUES <LLD

'9 11 ANALYSIS PERFORHED SR 90 0 ~ 300 9 VALUES <LLD 2 VALUES <LLD .

11 ANALYSIS PERFORHED

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

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

TD( LE 13 RADIOACTIVITY IN llELL NATER PC I /L - 0 ~ 037 80/L tiARE OF FACILITY CAROL'tsS~JRRY LOCATION OF FACILITY Q~R~STOQf, ~aa jjAh

• DOCKET NOU~~4$ ~0~

REPORT IhG PERIOD~'~9 TYPE AND LOiiER LIN IT ALL CONTROL NURSER OF TOTAL NUBBER OF IliDICATOR LOCATIONS LOCATIONS tiONROUTINE OF At( ALYS I S OETECTIOI4 MEAti (F)b BEAN (g)b REPORTED RANG b A ~Ah Pj A S Ufjf~RS S GANNA (NAI) 19 12 VALUES <LLD 7 VALUES <LLD ANALYSIS PERFORNED GAMBA (GELI) 7 K-40 NOT ESTAB 1 VALUES <LLD 99 F 84( 3/ 6)

BI-214 NOT ESTAB 1 VALUES <LLD 86 85-28 F 00(

115 1/

'0 6) 28~00- 28 'G P8-214 NOT ESTAB VALUES <LLO 12%59( 2/ 6) 1 7 '2- 17 '6 PB-212 NOT ESTAB 1 VALUES <LLD 6~48( 1/ 6)

F 48 6U48 TR I T I Ut( 330 F 000 VALUES <LLO VALUES <LLO 8 ANALYSIS PERFORNEO

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

Nean and range based upon detectable measurements only. Fraction of detectable measurements of specified locations is indicated in parentheses (P).

TAELC I4 RADIOACTIVITY ItA PUBLIC )tATCR SUPPLY PCI/L - 0 ~ 037 BO/L

.'4 4 HE OF F AC I L I T Y P R OL4>l~~ F /R R Y LOCATION Of FACILITY ~IHLSYOQ~

CONTROL NUt(BER OF TYPE AND LO)IER LIMIT ALL NONROUTIttC TOTAL NUMBER Of LOCATIONS LOCATIONS (F)

'NDICATOR OF At4ALYS IS DE TEC T I 0)t HEA(4 (F)b t(AHE MEAN (F) b MEAN REPORTED

~RRFDR~R ~(L~ ) RAN~Gb Q~ISTAMC AttD QIRQCTIDII Il(

RARGGG 44/

RAN

'0( 11/ 13)

GROSS BETA 85 F 400 3%96 (

2G46-61/

14 ~

72) 70 CHAMPION FAPER TRH 282 '

4~

2 46- 14 '046) 3 2~50- 4 F 08 GAHHA (NAI) 70 61 VALUES <LLO 9 VALUES <LLO ANALYSIS PERFORMED GAMMA (GEL I )

15 2/ 11) CHAMP IOti PAPER 74 F 11( 2/ 8) 101 F 00( 1/ 4)

K-40 tlOT ESTAB 74 F 11(

72 '9- 75 '3 TRH 282 ~ 6 72e49- 75 '3 I/ I) 101 F 00-

'8(

101 F 00 24G80( 8/ ll) SHEFF IELD ~ AL ROB 28 ~ 91( 17 2/ 4) ct 1-214 NOT ESTAB 12 00- 43 F 03 TRM 254 3 2&+91- 28 '1 8) 13G60-15 '2(

21 '5 15 '3(

F 4/ 11) 16 ~ 33( 3/ 2/ 4)

'3 1) 15 '5 PB-214 NOT ESTAB CHAMPIOt4 PAPCR 11 14-

~

Ii+90(

23 1/ 11)

'3 TRH 282 ' 12 ~ 52-II 90(

23 1/

15G68-16 18( 2/ 4) 13 '3- 19 '2 PB-212 NOT ESTAB SHEFFIELD>AL ROB ~

11 90 11 90 TRt'54~3 II ~ 90>> 11 90 5G84( I/ 4) 5 '4 TL-208 NOT CSTAB 11 VALUES <I.LD 5 84-SR 89 10 F 000 12 VALUES <LLD R VALUES <LLO 16 ANALYSIS PERFORHEO 90 F 000 3 25( 1/ 12) St(EFF ICLOrAL ROB 3 '5( 1/ 4) R VALUES <LLD SR 16 3 '5- 3 '5 TRt4 254 ' 3 25-369 '1(

~

'I/3e25 4) '9(

TRITIUM 16 330G000 369G21(

369 '1- 369 '1 1/ 12) CHAMPION PAPER T(AK 282G6 369G21- 369 '1 376 376 '9- 1/

376 '9 4)

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

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

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 Avera e External Gamma R adxatxon Levels miles 2nd uarter 0-1 18.8 + 1.2 21.7 + 2.0 21.0 + 1.6 20.0 + 1.5 1"2 17.1 + 1.2 17.3 + 2.2 16.7 + 3.2 20.0 + 5.0 2-4 16.5 + 1'2 15.6 + 1.8 16.2 + 3.3 16.5 + 1.7 I

4-6 16.6 + 1.1 17.0 + 1.6 17.1 + 2.2 16.6 + 1.3

>6 16..5 + 2.2 16.8 + 2.7 159+35 16,6 + 2.3

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

Average,

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

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

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

TAPLE 16 RADIOACTIVITY IN FOOD'ROPS PCI/KG - 0~ D37 89/KG ((JET MEIGHT)

DOCKET NOe~~5< -6."A296 LOC < T ION OF FAC ILITY~~IN ~TNr TYPE At,'D LO)JER LIMIT ALL CONTROL NUMBER OF TCTAL t(UPBER OF INDICATOR LOCATIONS L ATIOh MITH HIGHES ANNUAL MEAN LOCATION) NONROUTINE OF ANALYSIS DETECT IONa ."EAN (F) NAME rEAN (F)o MEAN (() RFPORTED RAN ~HAS ~R~HE TS RADIOACTIVITY IN CABBAGE GROSS PETA 25 F 500 4286e86(

'6- 1/

'6 I) t(ILES N 4286 '6( I/ 1)

'6-GA)t"4 (GELI )

1 4286 4266 4286 428'6 1

K-40 NOT ESTAB 1873~00( 1/ 1) 4 MILES 1873 'G( 1/ 1) ol-"14 'JOT EST AP 1873 00- 1873 13 '0(

'0 I/ 1) MILES N

N 1873+00- 1873+00 13 '0( I/ I)

PB-212 NOT ESTAB 13 4C-

~

15 75(

13+40 I/ I) 4 t(ILES tl 13 '0 15~75(

13 '0 I/ I) 15 '5 '5

~

15 75-

~ 15e75- 15 RADIOACTIV IT'I IN CORN GROSS BETA 25 ~ DOO 4163+82( I/ I) 4163 ~ 82- 4163 ~ 82 LN2 BF NORTH 0 9 NILE t'NE 4163e82(

'2- 416'21/ I) 3995 '6(

3995+66- 3995+66 I/ I) 2 4163 GA)t" 4 (GELI) 2 K-4 0 NOT ESTAB 1964.00( I/ 1) Lt(2 BF ~ORTH 1964.CO( I/ I) 1432.00( I/ I) 1964 DO- 1964 F 00 0 ' 'NILE tJNE 1964 00- 1964 F 00 1932 00- 1932 '0 ,

RADIOACTIVITY IN GREEN BEANS GROSS BETA 25 F 000 4874 ~ 83( I/ I) 2 NILFS NN(J 4874 '3( 1/ I)

'4- 3251I/ 74 I) 3251~74(

2 4874~83- 4874+83 4874 83- 4874 83 3251 GAMI44 (GELI )

C

'K hn NOT ESTAB 2132 ~ OD( 1/ 1) 2 MILFS NNO 2132 F 00( I/ 1) 1682 F 00( I/ I) 2132 'C- 2132 ~ 00 2132 'C- 2132 F 00 1682 F 00- 1682 'C

'0( I/ 1) 9 I-214 PB-212 NOT ESTAB NOT ESTAB I VALUES (LLD 6+89(

6 ~ 89-I/ I) 6 ~ 89 2 )(ILES NNU 6 ~ 89(

5 ~ 89-1/

6.89 I) 20 20 29

'0-29 '8(

58-

'/ '0 20 29 58 I)

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

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

TABLC 16 (Contd)

RADIOACTIVITY I"A FOOD CROPS PCI/KG - OHC37 EO/KG ('~CT VCIG)Sl)

NAHC OF F AC ILITY BROI'NS FCRRY LOCA I ION OF FAC IL I TY~H~~T>hL AI A/AHA REPORT))SG PERIOD-1481 TYPE hNO LOQEIG LIHIT ALL ~

CONTROL NUHBER OF TOTAL NUHBER OF INDICATOR LOCATIONS ~C41 OH II TH HIGHm~TA I UA JIEAH LOCATIoi($ NONROUT INC OF AHACTSIS OETECTIOH MESH I[IS NAHE HEAD (F~l HEAN (5) REPORTED RANGE ~FASU FEMTS RADIOACTIVITY IN PEACHES GROSS BETA 2

25eooo 3127e13( 1/

3127 ~ 13- 3127 ~ 13 ll SHITH FARH 3127e13( 1/ ll 2970e49( 1/ ll 4 ~ 75 HILES K 3127 ~ 13- 31?7 ~ 13 2970 49- 2970 49 GAHHA (GCLI) 2 K~40 NOT ESTAB 1697 00 t I/

1697 ~ 00- 1697 AGO I) SHITH FARH 1697 F 00( 1/ 1) 1252 F 00( I/ 1) 4 ~ 75 H ILES 1697 F 00- 1597 ~ 0G 125'G BI-214 '3( I/ 1257 F 00

'3- I/

NOT ESTAB 22 1) SHITH FARr 22 F 43( 1) 1 VALUES <LLD 22 ~ 43- 22e43 4 ~ 75 HILES 22 22e43 PB-212 NOT ESTAB 19e53( 1/ 1) Ss(ITH FARH 19e53( 1/

19 '3 19 ~ 53 4 ~ 75 HILCS 19 '3- 19 '3

1) 1 VALUES <LLO RADIOACTIVITY IN POTATOES

/ I/ '4(

'4- 7721I/.'4 1)

GROSS BETA 25 F 000 7112 ~ 16 ( I I) 2 MILES NY)s' 7112 F 16( 1) 7721 2 7112 ~ 16- 7112 F 16 7112 F 16- 7112e16 7721 GAHHA (GELI )

2 K-40 NOT ESTAB 3201 ~ CO( 1/ I) HILES NNM 3201 ~ PO( 1/ I) 3473 F 00( I/ 1) 3201 ~ 00- 3201 F 00 3?01 ~ 00- 32Ol.OO 3473.00- 3473.00 Bl-214 NOT ESTAB 15 '2( 1/ 1) 2 HILCS 15 '2( 1/ 1),

15 ~ 62-

'2( 15 I/ 1)

'2 NN)T 15 ~ 62- 15 '2 1 VALUES <LLO PB-212 NOT ESTAB 13 13 '2 2 HILCS NNM 13 '2( 1/ 1) 13 '2 1 VALUES <LLO 13 ~ 62- 13e62-

a. -

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

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

EAS

TABLE 16 (Contd)

RADIOACTIVITY IN POOD CROPS PCI/KG - 0.037 8(t/KG (MET MEIGHT)

NAME CF FACILITY BRoitJS FERRY OGCK I NO ~50-250 2600206 LOCATION OF F AC IL I TY~~HJON( Q~AA A REPORTING PERIOD 198)

CONTROL NUMBER OF TYPE AND LOMER LIMIT ALL TOTAL NUHBER - OF INDICATOR LOCATIONS AOCATIOII HI~TH H GH "I AHIIUAQ~HA LOCA I IONG NONROUTINE OF ANALYSIS DETECTION a HEAN (F) HEAN (f ) REPORTED

,02;II~MR ~RANG ~MR~UN II T 0 22 RAN~

RADIOACTIVITY IN TOMATOES GROSS BETA 25 000 5130H21( 1/ 1) BROOKS FARM 5130 '1(

'1- 513PI/ 1) 5669 5669

'7l

'7- 1/

5669 '7 1) 2 5130 H21- 5130 H21 ~ Ti 0 MILES NN)t 5130 ~ 21 Git(KA (GEL I )

K-4 0 2

NOT ESTAB 2513 'O( 1/ 1) BROOKS FARM 2513 F 00( 1/ 1) 2381+00( I/ 1) 2513 F 00- 2513 F 00 7 ~ 0 MILES NNL 2513 00- 2513 F 00 2381 00- 2381 00 PB-212 NOT ESTAB 11')5( I/ 1) BROOKS FiRN 11 ~ 15( 1/ 1) 1 VALUES CLLD llH15- 11 '5 7~0 MILES hNli 11 ~ 15- 11 ~ 15 llew RADIOACTIVITY IN TURNIP GREENS 5500 ~ 16 l 1/

'6 I 25+000) 5500M 16( 1/ 1) 4 tlILES N 1/ ) 5969~ 01 ( 1)

GROSS BETA

'6-

~

? 5500 '6- 5500HI6 5500 5500 5969 F 01- 5969 F 01 GAMMA (GEL I )

2 K-4 0 NOT ESTAB 2262 F 00( 1/ 1) HILFS N 2262 F 00( 1/ 1) 2980 F 00( 1/ 1) 2262 ~ 00- 2262 F 00 2262 ~ 00- 2262 00 2980i00- 2980H00 BI-214 '3( 1/ 1) MILES tt 22 '3( 1/ 1) 37 '4( 1/ I)

NOT ESTAB 22 22 ~ 93- 22 '3 1) 22 ~ 93- 22 ~ 93 37 '4- 37 '4 PB-214 13 53( 1/ MILES tt 13 53( 1/ 1) VALUES (LLD NOT ESTAB 13 ~ 53- 13 '3 13 ~ 53-

'2l 13 1/

'3 1) 1 26 '1( 1/ 1)

PB-212 42( 1/ 1) MILES 11

'2 I) 26 '1 NOT ESTAB 4 N ll 42- 11 '2 11 ~ 42- 11 26021 194 '0( 194 '0l

~

BE-7 1/ 1) HILES 1/ 1 VALUES 0.'LLO 194 '0 NOT ESTAB N

.194 40- 194 '0

~ 194 40-

~

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

b. Hean and range based upon detectable measurements only. Fraction of detectable measurements of specified locations is indicated in parentheses (P)..

RADIOACTIVITY IN SOYBEANS PCI/G - 6~ 037 80/G (CRY VEIGHT)

NArC OF FACILITY BROUNS FEAR)

COCIIIION OF FACILIIT /~IN STOAT/ A~ARANA REPORTING PERIOD~)9 TYPE AND LOVER LIMIT ALL CONTROL NUNBER OF TOT>L NUi(BER GF INDICATOR LOCATI ONS LOCATIONS NONROUT LNE OF ANALYSIS DETECTION a NEAN (F)b NEAN (F)b REPORTED

~PE QFI~RO ~IO l 2/ '3( 2/

b GROSS BETA GANNA CGEL I )

2 0~ 200 29453(

29 F 40 29 '5 2) LN2 BF NORTH 0~9 NILE NNE 29 29440 29 '5 2) 2 K-40 NOT ESTAB 15474 2/ 2) LN2 BF hORTH 15474C 2/ 2)

Bl-214 NOT ESTAB 14470 0 ~ 03(

C 16 ~ 77 1/ 2) 0 9 NILE NNE LN2 BF hORTH 14 ~ 70-0 '3( 16 '7 1/ 2T PB-214 iNOT ESTAB 0403-0 ~ 05(

0 '3 2/ 2) 0.9 NILE Li(2 NNE BF NORTH 0~

0 03- 0

'5C 2/ ?)

'3 0 ~ 04- 0006 0 9 NILE NNE 0404- 0406 BE-7 NOT ESTAB 0 ~ 20( 1I 2) LN2 BF NORTH 0420( 1/ 2) 0.20- 0 1/

~ 20 2) 0.9 LN2 NI1.E Nt E '0 '0" 0 ~ 11(

0 '0 1I 2)

AC-228 NOT ESTAB 0~ 11C BF NORTH 0411 0 ~ 11 0 9 NILE NNE F 11 -0411

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

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

TABLE 18 RADIOACTIVITY Itl POULTRY PCI/KG OP037 BO/KG ()lET MEIGHT)

NAHE OF FACILITY BROUNS FERRY COCKET hOH~O-259 0~

LOCATION OF FACILITY~~INC TO~E A A'AHA REPOITINO PERIOO~99 TYPE ANO LOMER LIt'.IT ALL CONTROL ICUHBER OF TOTAL tNURCOER OF INDICATOR LOCATIONS LOCATION VITH RICHEST ANNI~I~HAH LOCATIONS. NONROUTINE OF ANALYSIS DETECTION a BEAN (F)b NAHE HEAtt (F)b t(EAN (F )b. REPORTED PERFORt'EO CLI Q) REFERRER REEL b H TS GROSS BETA 2

25 000 4972%66(

4972 R~A

'6- 1/

4972 '6 1)

RIF 2 5 HILES RE~Nu~oRMRE'H5 DAVIS F

)tgl'972'6- 4972466( I/ I) 4972 66

~

6458 6458

'6(

'6- 1/

6458 36 I)

GAHHA (GELT) 2 K-4 0 NOT ESTAB 2412 ~ OOC 1/ I) LH5 BF DAVIS F 2412 F 00( 1/ I) 2137 F 00( 1/ 1) 2412~00- 2412 F 00 2~5 MILES )tS)i 2412 F 00 2412 F 00 , 2137 F 00 2137 F 00 8 I-214 NOT ESTAB VALUES <LLO 19H56( 1/ 1) 19 ~ 56- 19 ~ 56 PB-214 NO'I ESTAB VALUES <LLO IBH38( 1/ 1)

PB-212 NOT ESTAB 1

1 VALUES <LLO 18 10

'8

'6(

18 1/

'8 1) 10 ~ 86- 10 F 86

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

b. Mean and range based upon detectable measurements only. IPraction of detectable measurements of specified locations is indicated in parentheses",{P).

Figure 6 ANNuu AVERAGE Operational 6ROSS HEfA ECTIVITY Preoperational Phase Phase IN Rl H<I% RATER SUPPLIES CO C

o cl 1hOWM FERRY Noae MhT ll la Q

C Jl 4J CA 4J 4 Ch o

4J 0

Ci Jl "0 C C 0 H Q Average:

Preoperational Phase I

19 8 19 9 19 0 1 1 19 2 19 3P 19 30 19 4 1 5 19 6 1 7 .19 8 1 9 19 0 1 1

Figuxe 7 38 Otrect Radtat ton Levels Browns Ferry Nuclear Planl Ons1 te 0

/I

\

I 1 C. \

O I

\

0 18 I I I /

8 I j g \

I O" I I 8 I 'i i o

I '%i o'

I

~ Of fsllte 12 1976 1977 1978 1979 1988 1981 Figure 8 Otrect Radlatlon Levels Browns Ferrv Nuclear Plant I-Ouar ter Movtng Aver age 22 Onstte 16 12 1988 1981 1976 1977 1978 1979

Figure 9 39 Oirect Radiot ion Levels Wot ts Bar Nuclear Plant 22 C. Onsiie C

s 18 Ct s Offsi tee I f' I

I b I b-4 12 1976 1977 1978 1979 1988 1981 Figure 10 0 iree t Radiation Levels Wo t t s Bar Nuc lear P ion 1 4-Quarter Moving Average 22 Onsite C.

0 C.

0 18 8 /

/

ts b.~.~ .a.w s

Of fsi le o.~.~ tt 16 'e I 1976 1977 1978 1979 1988 1981

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

Zooplankton, chlorophyll, Benthic River/river mile phytoplankton fauna Sediment Fish (co8ecfe5 mlnMly)

Tennessee 277.9 X X Tennessee 285.2 Tennessee 288.7 X X Tennessee 291.7 Tennessee 293.5 Tennessee 293.7 (discharge area)

Tennessee 305.0 (Control)

Tennessee 307.5 X (Control)

Elk 20.5 (Control)

a. Gill net and/or electroshocker will be used for collection. Samples of fish are collected from Guntersville, Wheeler, and Wilson =Reservoirs.

b. Automatic sampler.

c. Grab sample.

TABLE 20 RADIOACTIVITY ltl SURFACE rATErt TOTAL PC I/L - 0 ~ 037 80/L RANE OF FACILITY BRO'FANS FERRY LOCATION OF FACILITY-MI~HQ~OJtg CONTROL NUHBER OF TYPE AND LOMER LIHIT ALL NONROUTINE TOTAL t)JHBE( OF INDICATOR LOCATIOt:S LGCATIOL4 A)TH HIGHEST ANNUAL HEA(J LOCATIONS OF ANALYSIS OETECTIONa HE AN (F )b NAME MEAN ($ )b HE'AN (F P REPORTED (LLD) RANGE b O~S Tat(CC At'P PIRECTIOrt RANGE sar.~s> ~H~ASUR MEhT~c PERFORMED

'00 3 53( 14/ 17) TRH 233 ~ 5 3 '6( 2/

'2 2) 5 27(

'9- 121

'8 15)

GROSS BETA 32 2

2 '3- F 16 3+30- 4 2 9 GAMMA (NAI ) 1'060( 18 VALUFS <LLO 45 27 VALUES <LLD ANALYSIS PERFORMED GAHHA (GEL I)20 K-40 NOT ESTAB 105 ~ 50( =

5/ 12) TRH 293 ' 13'5( 2/ 3) 96 '3(

'5- 2/

'0 8)8) 51 52- 159 F 60 BFN DISCHARGE II9 )0-

~ 159 F 80 74 118 5/ 12) 285 ' 2/ 3) 31 14( 6/

83 '5 15~99(81-214 NOT ESTAB 4 '6- 23~87 TRH 18 ~

26i00(

14- 19 1/

'6 3)

F 5a00-27 '4( 4/ 8) 1/ 12) 293 ~ 7 PB-214 NOT ESTAB 26 00(

F 26.00- 26.00 TRH OFT DISCHARGE 26.00- 26 00 10 '4-13 '3(

55 '9 8)

PB-212 NOT ESTAB 15 '5( 3/ 12) TRM 285 ' 17 '2( 1/

'2 3) 42-3/

'1 12 03- 17 62 17 ~ 62- 17 8 F 22 SR 89 10 F 000 20 VALUES <LLD 16 VALUES <LLO ANALYSIS PE,RFORHEO SR 90 F 000 2 81( 1/ 20) TRM 233~7 ~ 2 ~ 81( 1/ 12) 2 '7(

2+07-I/ 16) 2 F 81- F 81 BFt DISCHARGE 2 ~ 81- F 81 2i07

' 1/ VALUES <LLD TRIT IUH 20 330 F 000 372 F 11(

364 F 86-

~ 2/

37'5

12) TRH 293 379 35(

379 35- 379 '5 4) 8 a Nominal Lover Limit of Detection (LLD) as described in Table 3 ~

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

TabLE 21 RADIOACTIVITY INI ) HITE CRAPPIE (FLESH)

PCI/G - 0 ~ 037 BQ/G (DRY )TEIG)GT)

LOCATION NAHE OF OF FACILITY //~0M FACILITY LIHESTONE

~f EPRY BAAL)AHA DOCKET NO 50-259A~~O REPGRTTIIG PERTUSSIS I TYPE AND LOMER LIHIT ALL CONTROL NUHBER OF TOTAL NUHUER OF INDICATOR LOCATIONS NONROUTINE LOCATIONS OF ANALYSIS DETECT ION a BEAN (F)b NAPE HEAN (F)b HEAN (F) REPORTED PERFORHED (LLR)) RANGE b ~RUG U GERS~US IITS

'7(

~ll 0 ~ 100 35 F 18( 4/ 4) WILSON RESERVOIR 35 ~ 26( 2/ 2) 34 2/ 2)

'6 33 '3- '2 GROSS BETA ES 33s04- 37 TRH 259-275 34's98- 35 ~ 54 36 GAHHA (GEL I )

6 CS-137 0 '20 0 ~ 12( 4/ 4) MILSON RESfRVOIR 259-275 0 '3(

13-2/

OP13

2) 0 14(

'9-

~ 2/

0 ~ 18 2) 0%09 0 ~ 14 TRH 0 0 K-49 NOT ESTAB 14 '5( 4/ 4) NILSON RESEPVOIR 15P20( 2/

'3 2) 17 50(

15 '9-2/ 2)

BI-214 0~ 020 12 ~ 72-0+07(

15 2/

'3 4)

TRH 259-275 MHEELER RES 14 0

~

F 77-09(

15 1/ 2) 0 F

F 06(

19 '1 1/ 2) 0005 OP09 TRH 275-349 0 ~ 09- 0009 0 F 06- Os06 PB-214 NOT ESTAB 0+07(

06-2/ 4) MILSON RESERVOIR 259-275 0 '7(

07-I/

0+07

2) 2 VALUES (LLD 0~ 0 07 TRHi 0 ~

PB-212 NOT ESTAB 0 '2(

02-1/

F

4) VHEELER RES 275-349 0 '2(

02-1/

02

2) 0 ~ 02(

02-1/

'2 2) 0~ 0 F 02 TRH 0 0 0 ~ 0

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

b. Hean and range based upon detectable measurements only. Fraction of detectable measurements of specified locations is indicated in parentheses Q').

9 TahLE 22 RADIOACTIVITY Itl SHALLHOUTH BUFFALO (FLESH)

PCI/G - .'9037 BO/G (DRY ME.IGHT) lAl'E OF FACILITY BPOMNS Ff RRY DGCKET NOO~~9QA296 LOCAL ION OF FACILITY L INES TOtlE AQAOAHA REPORTIHG PER I00~901 TYPE lNO LOMER LIHIT ALL CONTROL tlUHBER OF TOTAL:lU."DER OF INDICATOR LOCATIONS RGGATJOA~UTH ~!GHOST A UUAR HEAR LOCATIONS NONRDUTINE OF AtlALYSIS DETECT IONa MEAN (F) b RlauE MEAN (F)b HEAtG (F)b REPORTED

~(L Il 8 ANGEb D I STANCE Al'0 DIR CTIOtl RANGLb H /~ASHN T S G'ROSS BETA 6

0 ~ 100 23007(

19 F 04-4/

27 '0 4) MHEELEP RES TRH 275-34a 25 '7(

'4- 2/

27a20

2) 22 40(

20 '2- 2/

24 '8 2) 24 GbuHA (GELI )

6 CS 137 '20 0.05( VHEELEP RES 0 05( 2/ 2) 0 08( 2/ 2)

K-40 0

NOT ESTAB 0004-9 ~ 64( 4/

0 '6 4) TRH 27'-'49 MMEELER RES 0~

11

~

04-

'3( 0 2/

'6 2) 0 '7-

~

8 F 82(

0 F 08 2/ 2) 7 '6- 11056 TRH 275-3GI9 10 ~ 49- 11 56

~ F 00- 10 '4 2)

DI 214 0 020 0.06( 3/ 'MILSON EAESERVOIR 0 OBC 1/ 2) 0 14( 1/

~

0 F 05- 0 F 08 TRH 25+ 275 0 ~ 08- 0 08 0 '4-

~

0014 PB-214 NOT ESTAB 0 '6(

05-2/

'7 4)4) MHEELER RES 0007( 1/

F

2) 0 F 09(

09-1/ 2) 0~ 0 TRH 275-349 Oe07- DE 07 0 ~ 0 F 09 PB-212 NOT ESTAB G~ 04( 1/ MMEELER RES 0 ~ 04C 1/ 2) 2 VALUES <LLD 0 F 04- 0 F 04 TRH 275 349 0 ~ 04- 0004 TL-ZnH 0~020 0 F 02( 1/ 4) VHEELER RES 0 ~ 02( 1/ 2) 2 VALUES <LLD 0.02- 0.32 TRH 275-349 0002- 0002 0 '00 1 VALUES <LLD 0 VALUES <LLD ANALYSIS PERFORHED SR 93 0 ~ 100 1 VALUES <LLD 0 VALUES <LLD ANALYSIS PERFORHED

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

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

TABLE 23 RADIOACT IVIT'Y IN SNALLI-'OUTH BUFFALO (VHOLE)

PCI/O - GN037 BC/G (DRY VEIGhT)

NAI'E OF FACILITY QROMNS FLURRY DOCKET NO 55~259 6 LOCATION OF FACILITY L~MQSJOPQ ALA~AHA PER IOD~4~8 29'EPORTING TYPE AND LO'VCR LIMIT ALL .CONTROL N(UNBCR OF TOTAL ttUPBER OF INDICATOR LOCATIONS LOCATION VI TH HIGHEST AHHUA H AH NOtJROUT INC (F)b NEAN (F) LOCATION/

IIEAN ((I REPOITTED OF ANALYSIS DETECT IONa MEAN NAME

~( RAHGEb Ql&EH~AB~~RTIRB 19 '6(

~5M 2 ONNE Mg A S ~Un ~MN T~

~PRFttR~u GROSS BETA 0 ~ 100 19 '2(

18 F 57-

'l/

19 '5 4) VHEELER RES I'RM 275-349 18 '7- 2/

19 '5 2) 29 99(

14 97-2(

26 ~ 91 2(

6 GAMMA (GEL I) 6

'3( 2/ 4) @HEELER RES 0%03( 1/ 2) 0 '4( 1/ 2)

CS-137 0~ 020 0 0503- 0 03 TRH 275-349 0~ 03 0 '3 0 7 '8(

F 04- 0504 8 '8(

~

K-40 4/ 4) VHCCLER RES 8 ~ 20( 2/ 2) 2/ 2)

NOT ESTAB 6 '3- F 11 '(RN 275-349 7 ~ 50- 8 '9 5510-

'6( 9 '7

'6(

~

BI-214 020 4/ 4) VILSOt( RCSERVOIR 0 F 06( 2/ 2) 0 2/ 2) 0~ 0 0 '4- 0+08 TRN 259-275 0+04- 0 F 08 ON03- ONOS PB-214 NOT EST~8 0 '7(

'4- 3/

F 12

4) VILSOtt RESERVOIR TRN 259-275 F 12(

0012 1/

0 12

2) 0F 0508-08( 1/

0508 2) 0

'3( '3( 1/

~

'3( 2/ 2)

PB-212 NOT ESTAB 0 0 ~ 03-2/

0 ~ 03

4) VHEELER RES TRM 275-349 0

ON03- 0 '3 2) 0 0 '3- 0 F 04 VALUES ((LLO SR 89 0 F 500 1 VALUES  %.'L'LD G ANALYSIS PERFORMED SR 90 0 '00 1 VALUES (LLO 0 VALUES (LLD ANALYSIS PERFORNED

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

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

TABLE 24 RAOIOACTIVITT IN SEOIHCNT PCI/G - 0 '37 80/G (DRY MCIGHT)

NAKE OF FACILITY QROuNS FLURRY DOCKET NOo~0- $ ~$ 60AQQ LOCATION OF FACILITY LIH~STO~N ALABAMA REPORTING PCRIOO 1981 (YoC AND LOiIER LIMIT ALL CONTROL NUMBCR OF TOTAL NUHBCR OF LOCATION) hONROUT INC OF ANALYSIS OE TEC T REPORTED

=PQKRB KEG LD)

ION'(

lluult ~onM~CQNQ plllfggIIIM ~II@MS ~HA QPf,~HQ T S GAMHA (GEL I )

8 CO-60 c 0 ~ 010 0~ 14(

'7- 5/ 6)

'1 6) TRH BFN 293 ' 0 '0(

0 ~ 19-2/

'1 2)2) VALUES (LLO 0 0 DISCHARGE 0 CS-134 0 ~ 080 0 '3(

13-1/ TRHi 293o7 0 ~ 13(

13-1/ VALUES <LLO 0~ D~ 13 BFN DISCHARGF. 0~ Do13 137c '20 I ~ 70( 6/ '4( 2/ '7( 2/ 2)

CS ZR-95 0

0 '30 Do83-6 VALUES 2 '5 (LLD

6) T8 Hi Z 77 ~ 98 2 2o23- 2 '5 2) 0 0

0

'307( 0 1/

'1 2)

NB-95 010 (LLO F

Do07-0 F 12(

0 1/

'7 2) 0 6 VALUES K 40 NDT CSTAB F

14 'D( 6/ 6) TRH 288 '8 15 '5( 2/ 2) 0 14

~ 12-

'5(

0 2/

'2 2)

'2- '2 6) 15 '6

~

11 16 15 ~ 07- 16o42 13 ~ 64-HN-54 0 ~ 010 0

0~ 05l

'4- 2/

0 '6 TRH BFN 293 '

DISCHARGC 0

0

'6(

06 1/

Do06

2) 0 0~

'3l 03-I/ 2) 0 03 BI-214 Do020 I 35(

1~

~

11-6/ 6) 1 ~ 53 TRH 277 '8 1 F

~ 44l 1 ~ 35-2/

lo53

2) lo79(

1 ~ 61-2/

~

1096 2)

BI-212 0 '00 06( 5/ 6) TRH 288 F 78 1 ~ 33( 1/ 2) F 15( 2/ 2) 0 '8-1 ~

1%33 33- 1 ~ 33 0 93- '6 PB-214 NOT CSTAB 1 '0(

I ~ 18-6/i 6) 1 ~ 71 TRH 277 '8 1~

Io68(

1 ~ 66-2/

71 2)

~

1 ~ 86(

64-1 2/

2 ~ 09 2) 288 '8 1 ~ 1~

PB-212 NOT ESTAB 1 ~ 86( 6/ 6) TRK 2 01( 2/ 2) 2F 00( 2/ 2)

RA-226 NOT ESTAB 1 ~

1 35(

57- 2 6/ 6)

'b TRK 277 '8 F

lo98-1 ~ 44(

2 2/

'5 2) 1082-1 '9( 2/ 2)2 '8 RA-223 NOT ESTAB 1 ~ 11-0 '9( 2/

1 ~ 53

6) TRH 293 '

1 0

'5

'0( I ~ 53 1/

1061 Do75(

1~

2/

96 2)

Do47- 50 OFN DISCHARGE 0 50- 50 0 62- 0 F 87 TL-208 0 '20 0

) ~ 57l

'472( 6/

0 0

F

'7 6) TRM 277 '8 0 0

~

'5(

62-0 2/

0

~

'7 2) 0

~

Oo73(

'8 2/

0 78 2) 277 '8 F

AC-228 0 '60 1~ 6/ 6) TRH I ~ 89(

lo83-Z/ 2) 2 '2( 2/ 2)

I 35- 1 ~ 94 I 94 I 95" 2 68 SR P9 1 ~ 530 6 VALUES (LLD 2 VALUES <LLD ANALYSIS PERFORHEO SR 90 0 '00 6 VALUES (LLD 0 ~ 52( 1/ 2)

a. Nominal Lowef Limit of Detection (LLO) as described in Table 3. 0 '2- 0 '2

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

c., The distribution of Co and Cs between indicator and contrail locations reported herein is comparable to the distribution reported in the

~ oo<=or~ a)so comoarable with levels reported in samples from the

~

TAoLC 25 RAOIOACTIVITY IN CLAP FLESH PCI/O - 0 '37 UC/G .(ORY UEIGKT)

NARC OF FACILITY PROVt(S FERRY OGCKET NUo~5 LOC AT ION OF F ACIL YII L~HSTO~tt ALABAHA REPORTING PER IOO )981 TYPE AND LOMCR L IHIT ALL CONTROL hurBER OF TOTAL LUHBER OF INOICATOR LOCATIGNS LOCAT10l4 Ml TH HIGH/ST ANhUAL HEAN LOCATIOtts t:ONROUTINE OF ANALYSIS OETECT IONa HEAN (F) b NAHE HEAN (F) HEAN (F)b REPORTEO

~(Q) R AhGLb P Q~A~R~HN S GAHHA (GELI)

K-40 7

NOT ESTAB 8 ~ 97(

6 ~ ') 9-4/

12 '5 5) TRH 288 '8 9 '2(

6+49-2/

12 '5 2) 17 17

'I(

ll- 1/

17 'l 2) 8 I-214 NOT ESTAB 4 ~ 27( 5/ 5) TRH 277 '8 6 ~ 40( 1/ 1) 2 '2( 2/ 2) 1~70- F 05 6 ~ 40- 6 '0 2 '2- 3 '2 "214 NOT ESTAB '9( 5/ 5) TRH 277 '8 9 ~ 05( 1/ 1) 71( 2/ 2)

F H PB-212 NOT ESTAB 4

1 ~

F 10-12(

F 05 3/ 5) TR)'88 '8 9 ~ 05-lel7(

9 1/

'5 2) 4 F

0 ~

80-50(

7 '3 I/ 2) 1~ 02 i+17 1 17- I ~ 17 G ~ 50- 0+50 TL-208 NOT ESTAB 0040( 5) TRH 288 76 Oa40( 1/ 2) 2 VALUES (LLD Oo40- Oa40 0040 0 ~ 40

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

b. Hean and range based upon detectable measurements only. Fraction of detectable measurements of specified locations is indicated in parentheses (p).

TABLE 26 RADIOACTIVITY IN CLAH SHELL PCI/G - 0.037 Bl /G lORY VEIGHT)

NAME OF FACILITY BRQVQS FLP~ COCKET NO+ ~g$ ~9~4?~

REPORTING PERIOD 1981 LOCATION OF FACILITY L IHESTGNE ALABAMA CONTROL NUHBER OF TYPE ANO LOVER LIMIT ALL TOTAL NUMBER OF ItlDICATOR LOCATIONS NONROUTINE LOCATIONS OF ANALYSIS DETECT I ON a MEAN (F)b MEAN (F) REPORTED (LLO) 8 ANGLb RAPGEb ~HASU~RH NTS GAR>A (GELI)

K-40 8

NOT ESTAB 1~ 15(

19-6/

3 '2 6) TRH 277 '8 2 0

'6(

99-2/

3 '2 2) 1 0

13(

86-2/

1 ~ 41 2)

GI-214 0 ~ 050 0

3~

~

46( 6/ 6) TRH 277 '8 0

~

'2( 2/ 2) 0 '6(

'0- 2/ 2)

Os)i- I ~ 57 0+27- 1 57 0 0 ~ 52 91-212 0 ~ 100 0 '0(

'0- 6/I/ '0 6)6) TRH BFN 293+7 DISCHARGE 0 ~ 20(

0+20 1/

0420

2) 2 VALUES <LLO PB-214 Oa050 0

0 '6( 1+05 0 TRH 277 '8 0 '3( 2/ 2) 0 '6( 2/

'0 2) 0 ~ 09- Oo21- 1~05 0 ~ 22- 0 0.39( 5/ 277 98 0 ~ 49( 2/ 2) '5( 2/ 2)

PB-212 NOT ESTAB G ~ 09- 0 ~ 90 TRH 0009- 0 '0 0 0~ 27"

'6(

Oo44 RA-226 0 '50 0 '8(

Oel)-

6/

i+57

6) TRH 277 ~ 98 0 ~ 92(

0 ~ 27-2/ 2)

I ~ 57 0

Oa40-2/

0 F 52 2)

TL-208 020 0 06( 4/ 6) TRH 293 ' F 10( 2/ 2) 0 ~ 13(

ll- 2/ 2)

AC-228 0 ~

0+060 0

0

'5 F

'1( 3/F 11 6)

BFN TRH DISCHARGE 288 '8 0 09-0 '2(

F 11 1/ 2) 0~

0 ~ 53(

F 14 1/ 2) a F 000 0 '8 6 VALUES <LLO 0 0 32- 0 ~ 32 0 ~ 53-2 VALUES <LLO 53 SR 89 ANALYSIS PERFORHEO SR 90 1 F 000 1 ~ 99( 6/ 6) TRH 293 ' 2 '9( 2/

'0 2) 2 42(

'1" 2/

'3 2) 28- 2 70 BFN DISCHARGE 2 ~ 27- 2 2 2

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 51 R ESERVOIR MONITORING NETWORK N

Elk River

'ttI/HEELER DAM mile 274.90 mile 277.98 Rogersville 0

rnite 29l.76 Athens mile 282.6

~mile 2852 B.F. NUCLEAR PLANT 8

Champion Paper Co, ife Z88.78 293.50 0tland mite mile 306.0 Cour mite 295.70 Decatur rnite 307.52 Scale of Miles

~ - Automatic Sam ler

Figure 12 keeu AvaeGE 6ROSS SETA ACTIVITY n Preoperational Operational o cl Phase il n Phase IN SURFACE tlATER o

N lJ Jl

-~

IhOWS FaeV NOCI.EAR Purr l M o

JJ W e 0 V I

~n 00 hverage:

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

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

Data measured at the control stations for each medium were averaged for each sampling period~ In order to describe the distribution of control station data, a mean, standard deviation, and 3-sigma We can expect that background concentrations liiits were calculated.

would be distributed within these limits. This prov'ides us the basis for comparing control and.indicator data.

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

Conclusions A vast majority of the indicator station data was found to be within the distribution defined by the control station data. The data analysis software identified concentrations slightly exceeding the limits of the control station data for a small number of radionuclides in samples from indicator stations. Many of these values may be discounted because the error reported by the analysis program was greater than the calculated concentration. The remaining isolated elevated concentrations may be the result of fallout, fluctuations in the existing environment, computer program artifacts, or analytical errors. The same type of isolated high values occurred in the control station data and may be attributed to the same sources.

Increased levels of radioactivity were observed in rainwater, air particulates, heavy particle fallout, and in vegetation in the winter and spring following the atmospheric nuclear weapons testing conducted by the Republic of China in mid-October 1980. This increase was seen in control stations as well as indicator stations. The primary radioisotopes identified in the atmospheric media were S Zr, .Nb S I, ~Bi, and O Ru.

Dose estimates were made from concentrations of radioactivity found in samples of environmental media. Media sampled include, but are not limited to, air, milk, meat, vegetation, drinking water, and fish. Doses estimated for persons at the indicator locations were essentially identical to those determined for persons at control locations. Greater than 99 percent of those doses were contributed by the naturally occurring radionuclid'e potassium-40,

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

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

ENVIRONMENTAL RADIOACTIVITY LEVELS BROWNS FERRY NUCLEAR PLANT ANNUAL REPORT - 1982 TVA/POWER/RHS April 1983

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

Atmospheric Monitoring ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

Terrestrial Monitoring ~ ~ ~ 0 ~ ~ ~ ~ ,~ ~ ~ ~ e ~ 23 Reservoir Monitoring ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 41 Quality Control. 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 53 Data Analysis. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 0 ~ ~ ~ 53 Conclusions. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 53

l' LIST OF TABLES Tab'le 1 Environmental Radioactivity Sampling Schedule 3 Table 2 Atmospheric and Terrestrial Monitoring Station Locations - Browns Ferry Nuclear Plant 4 Table 3 Detection Capabilities for Environmental Samp le Analysis .5 Table 4 Results Obtained in Interlaboratory Comparison Program. ~ ~

Table 5 Maximum Permissible Concentrations for Nonoccupational Exposure 13 Table 6 Radioactivity in Air Filter 14 Table 7 Radioactivity in Rainwater. 15 Table 8 Radioactivity in Heavy Particle Fallout 16 Table 9 Radioactivity in Charcoal Filters 17 Table 10 Radioactivity in Milk 26 Table.ll Radioactivity in Vegetation ~ ~ ~ 27 Table 12 Radioactivity in Soil 28 Table 13 Radioactivity in Well Water 29 Table 14 Radioactivity in Public Water Supply. 30 Table 15 Environmental Gamma Radiation Levels 31 Table 16 Radioactivity in Corn 32 Table 17 Radioactivity in Green Beans. ~ ~ ~ ~ 33 Table 18 Radioactivity in Potatoes ~ 34 Table 19 Radioactivity in Tomatoes 35 Table 20 Radioactivity in Turnip Greens 36 Table 21 Sampling Schedule - Reservoir Monitoring 43 Table 22 Radioactivity in Surface Water. 44 Table 23 Radioactivity in White Crappie (Flesh). 45 Table 24 Radioactivity in Smallmouth Buffalo (Flesh) 46 Table 25 Radioactivity in Smallmouth Buffalo (Whole) 47 Table 26 Radioactivity in Sediment 48 Table 27 Radioactivity in Clam Flesh . 49

'Table 28 Radioactivity in Clam Shell 50

N R

A C h

E

LIST OF FIGURES Figure l - Tennessee Valley Region 10 Figure 2 - Atmospheric and Terrestrial Monitoring Network. 18 Figure 3' Local Monitoring Stations 19 Figure 4 TLD Locations, BFN 20 Figure 5 Annual Average Gross Beta Activity in Air Filters, Browns Ferry Nuclear Plant 21 Figure 6- Annual Average Gross Beta Activity in Drinking Water, Browns Ferry Nuclear Plant 37 Figure 7- Dire'ct 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 Levels, WBN (4-Quarter Moving Average) 39 Figure 11 - Reservoir Monitoring Network 51 Figure 12 - Annual Average Gross Beta Activity in Surface Water 52

ENVIRONMENTAL RADIOACTIVITY LEVELS BROWNS FERRY NUCLEAR PLANT ANNUAL .REPORT 1982 1ntroduction The Browns Ferry Nuclear Plant (BFN), operated by the Tennessee Valley'uthority, is located on a site owned by TVA containing 840 acres of land in Limestone County, Alabama, bounded on the west and south by Wheeler Reservoir (see figure 1). The site is 10 miles southwest of Athens, Alabama, and 10 miles northwest of Decatur, Alabama. Th'e plant consists of three boiling water reactors; each unit is rated at 3,293 .MWt and 1,098 MWe.. Unit 1 achieved criticality on August 17, 1973, and began commercial operation on

.August 1, 1974., Unit '2 began commercial operation on March 1, 1975. However, a fire in the. cable trays on March 22, 1975, "forced the shutdown of, both reactors. Units 1'nd 2 resumed operation and Unit 3 began testing in August 1976. Unit 3 began commercial operation in January 1977.

I The preoperational environmental monitoring program established a baseline of data on. the distribution of natural and manmade radioactivity in the environment near the plant site. However, seasonal, yearly, and random variations in the data were'observed. fn order to determine the potential increases in environmental radio ictivit.y levels caused by the plant, com-parisons were made between data for indicator stations (those near the plant) and control stations (those remote 'from the plant) in conjun'ction w'ith com-parisons with preoperational data.

.The Radiological Health Staff (Office of Power) and the Office of

. ~

Natural Resources carried out, the sampling program outlined in tables 1 and 21.

Sampling locations are, shown in figures 2, 3, 4, and 11, and'able.2 describes the locations of the atmospheric and terrestrial monitoring stations. All the radiochemical and instrumental analyses were conducted in TVA's Western Area

, Radiological Laboratory (WARL) located at'uscle Shoals, Alabama, and Eastern Area Radiological. Laboratory (EARL) 'at Vonore, Tennessee. Alpha and beta analyses were performed on Beckman Low Beta II and Beckman Wide Beta II low background proportional counters. Nuclear Data (ND) Model 100 multichannel analyzer systems employing sodium iodide NaI(Tl) detectors and ND Model 4420 systems in conjunction with Germanium Ge(Li) detection systems were used to an'alyze the samples for specific gamma-emitting radionuclides. Samples of water, vegetation, air particulates, food crops, and charcoal (specific analysis for I-131) are routinely counted with NaI(Tl) detection systems.

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

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

is routinely performed by analysis on the Ge(Li) system. A TVA fabricated betq-gamma coincidence counting system is utilized for the determination of "

I-131 concentrations in milk.

Data were entered in computer storage for processing specific to'he analyst.s conducted. A computer, employing an ALPHA-M least squares- code, using multimatrix techniques, was used to estimate the activities of the gamma-emitting nuclides analyzed by NaI(T1). The data obtained by Ge(Li) detectors were resolved by the appropriate analyzer software and the metric minimization routine HYPERMET.

The detection capabilities for environmental sample analyses, given as the nominal lower limits of detection (LLD) are listed in table 3. Samples processed by NaI(Tl)

'u gamma spectroscopy were analyzed for 14 specific gamma-emitting radionuclides.and radionuclide combinations a . For these analyses, radionuclide combinations such as and sZr-Nb are analyzed as one radionuclide. All photopeaks found in Ge(Li) spectra. were identified and quantified. Many of the isotopes identified by Ge(Li) spectral analysis are naturally occurring or naturally produced radioisotopes, such as .Be, , K,

.Bi, Bi, Pb, Pb, Ra, etc. TLDs for the analysis of the radio-nuclides listed below are given in table 3B. LLDs for additional radio-nuclides identified b'y Ge(L;),.an~>ysis were calculated for each analysis and nominal values are listed in the appropriate data tables. In the instance where an LLD has not been established, an LLD value of zero was assumed. A notation in a table of ". values <LJ,I)" for an isotope with no established LLD does not imply a value less than 0; rather it indicates that the isotope was not identified in that specific group of samples. For each sample -type, only the radionuclides f'o r which values greater than the LLD were reported are.

listed in the data tables.

TVA's Radioanalytical Laboratories participate in the Environmental Radioactivity Laboratory Intercomparison Studies- Program conducted by EPA-Las Vegas. This program provides periodic cross-check samples of the type and radionuclide composition normally analyzed in an environmental monitoring program. Routine sample handling and analysis, procedures were employed in the evaluation of these samples. The results received during calendar year. 1982 are shown in table 4. The +3v limits based on one measurement were divided by the square root of 3 to correct for triplicate determinations.

a the, ALPHA-M least-squares computer code:

Cs a Cs,

'e; Cr; 'u; The following radionuclides and radionuclide combinations are quantified by I;

5Zr-Nb~ ssCo; 54Mn; 65Zn; 59Fe; 60Co; 40K; and i40Ba-La.

Table 1 EhVIROhHENTAL RADIOACTIVITYSAMPLING SGHEDULE Station Location Air F'tter Charcoal Filter Rain- Heavy Particle

<< ter Fallout do i V~eetati River 'ell 'Public Aquatic Life a.'Hilk Water litter '<< ter aad dediueat'ooda Muscle Shoals A Lawrenceburg W W M H . ~ A Rogersville W W H .

M A

Athens H H A Decatur W W H . M A Courtland W W . M H A Site 1 N W W H H A Site 2 NNE W H H A Site 3 (EhE W M H A Site NNW W H H A Site 5 (WSW) W W H H .

A Farm B Q

~

W Farm S Q W Farm P .Q W Farm L Control Farms Onsite Well Wheeler Dam Elk River-Tennessee River Champion Paper'Co.

Various Local Farms W - Weekly H - Honthly (every 4 weeks) Q

- Quarterly S - Semiannually A -'nnually

4 Table,2 t

Atmospheric and Terrestrial Monitoring. Station Locations.

Browns,.Ferry Nuclear Plant Approximate Distance and Direction from Plant LM-.l BF, North 1.0 Mile (1.6 kilometers) N LM-..2 'BF, North-Northeast 0.9 Mile (1.4 kilometers) NNE LM-3 <<BF, East-Northeast 1.0 Mile (1.4'kilometers), -

ENE LM-.4"BF, North-,Northwest ~

1.7 Miles (2.7 kilometers) NNW LH-.S IBF,, West-Southwest 2.5 Miles (4.0 kilometers) WSW PM-1~>BF, 'Rogersville, AL 13.8 Miles (22.2.kilometers) 'NWi PM-2 <BF, Athens, AL, 10.9 Miles (17.5 kilometers) NE PM-3 ~BF, Decatur (Trinit'y), AL '.2 Miles (13.2 kilometers) SSE PM-4 BF, Courtl'and, AL 10.5 Miles (16.9 ki'lometers) WSW RM-1,BF, Muscle Shoals,,:AL '32.0 Miles (Control) 4 (51.5 kilome'ter's) W RM-2 'BF, Lawrenceburg, TN- 40.5 Miles (65.2 kilometers) NNW

-'Control)

Farm S 4.75 Miles (7.6 kilometers) 'N Farm'B 7.0 Miles", (11.3 kilometers) NNW Farm 'L , 5.0 Miles (7:0 'ilometers) NE Farm T (Out of business, 7.0 Miles (11.3'flometers) ENE

, after, 1/18/82) .

,i

"'a rm'.'P 8.'8"Miles (14.'1 kilometers)

E Farm N (Control) 27: 0* Hiles (43.4 kilometers) NW Farm J .(Control) ',40.0 Miles (64.4 kil'ometers) NNW Farm C (Con'trol) .32.0 Hil'es (51..5 kilometers) N Farm Ca (Cont.rol) 32.0 >tiles (51..5 kilometers) W

Table 3 DETECTION CAPABILITIES FOR ENVIRONMENl'AL SAMPLE ANALYSIS A. S ecific Anal ses NOMINAL LONER LIMIT OF DETECTION LLD

• Pish, Air Vegetation Soil and clam flesh, Foods, meat, Particulates Charcoal Fallout Mater and grain Sediment plankton, Clam shells poultry, Milk

~ct/ ~ct/ Ct/k ~ct t ~dt/ dr ~dt/ . dr ~Ct/ d ~ct/ d PC i/k~gt ~Ci/I Total a 0.4 0.01 1.5 Gross a 0. 005 2.0 0.05 0.35 0.1 0.7 Cross B 0. 01 0.05 2 ' 0.20 0.70 0.1 0.7 25 H 330 1311 0.02 0.5 0SS 0.005 10 0.25 1.5 0.5 5.0 40 10 sOSr 0.001 2 0.05 0.3 0.1 1.0 8 2

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

Factors such as sample size, decay time, chemical yield, and counting efficiency nay vary for a given sample; these variations may change the LLD value for rhe given sample, The assumption is made tha't all samples ale analyzed within one week of the collection date. Conversion factors: 1 pCi 3.7 x 10 Bq; 1 mCi ~ 3.7 x 10 . Bq.

Table 3 DETECTION CAPABILITIES FOR E.'>VIRONMENTAL SAMPLE ANALYSIS B. Ca~ Anal ses NOMINAL LOVER LIMIT OF DETECTION {LLD

,) ~"

Air Vater Vegetation Soil Clam flesh Foods, (tomatoes Meat"'n

'r and particulates and milk and grain sediment Fish . and plankton Clam shells potatoes, etc.) poultry,

~ct/e Fat* Ll. **

~C1/1 Lai ~CLI)

~Ct/

ital Lt

~CI / dr I Ce(LI)

~CS/ dr P*i .CALI)

~nl Fel dr Lt

~ct/ dr N I C~LI Ci/

Na I wet ~ct/ I Nai Ge{lil

~ce ~ce N ~ce C~eLi 161> 166Ce

0. 03 38 0.55 0.35 0.35 0.35 38 90 1 4{ 0.02 33 0.22 '.06 0.06 0.35, 0. 06. 33, 40 "Cr 1311

0. 03 '.07 60 44 1.10 0.47 0.60r 0.10 0.60 0.10 0:56 , 0.60 0. 10 60 44'00 90 0.01 0.01 15 8 0.35 . 0.09 0;20 0.02 0.20 0.02 0.07 0.20 0. 02 15 8 50 20 103 ~ 306R 0. 45 0.04 40 0.65 0.45* 0.45 40 150 106R 0. 03- 40 0.51 0.11 0.11 0 . 7I4 0.11 40 90 136CS 0.01 0.02 10 26 0.20 0.33 0.12 0.08 0.12 0.08 ~

0. 48 0.12 0.08 10 26 40 50 1 33CS 0.01 0.01 10 5 0.20 . 0.06 0.12 . 0.02- 0:12 0.02 0 . 08 0.12 0.02 10 5 40 15 ssZr-bb 0.01 10 0.20 0.12 0.12 0.12 10 40 332? 0.01 10 0.11 0.03 0. 03 0.15 0. 03 10 20 ssgb 0.01 5 0.05 0.01 0.01 0.07 0. 01 5 15 "Co 0.02 0.01 15 5 0.23 0.05 0.20 0.01 0. 20 0.01 0.07 0.20 0. 01 15 5 55 15 Mn '0.02 0.01 10 5 0.20 0.05 0.15 0.01 0.15 0.01 0.08 0.15 0.01 10 5 40 15 6 sZn 0.02 0.01 15 9 0.25 0.11 0.23 0,02 0.23 0.02 0.17 0.23 0.02 15 9 70 20 "Co 0.01 0.01 10 5 0. 17 0. 06 0.11 0.01 0. 11 0. 01 0.08 0.11 0.01 10 5 30 15 K - 0.10 150 2.50 0.90 0.90 0.90 150 400 Ba-La 0. 02 15 0.68 0.15 0.15 0.15 15 50 3

>cog 0. 02 25 0.34 0,07 0.07 0.30 0.07 25 50 160La 0. 01 7 0.08 0;02 0.02 0.10 0.02 7 15

• e

• The NaI(TI) LLD values are calculated by the method developed by Pasternack and Harley as described in HASL-300 and Nucl. Instr. Methods 91, 533-40 (1971). These LLD values are expected to vary depending on the activities of the components in the samples. These figures do not represent the LLD values achievable on a given sample. Vater is counted in a 3.5-L Marinelli beaker. Vegetation, fish, soil, and sediment are counted in a 1-pint container as dry weight. The average dry weight is 120 grams for vegetation and 400-500 grams for soil sediment and fish. Meat and poultry are counted in a 1-pint container as dry weight, then corrected to wet weight using an average moisture content of 70X. 'Average dry weight is 250 grams. Air particulates are counted in a well crystal. The counting system consists of a multichannel analyzer and either a 4" x 4" sol.id or 4" x 5" well NaI(T1) crystal. The co~nting time is'4000 seconds. All calculations are performed by the least-squares computer program ALPHA-M. The assumption is made that all samples are analyzed within one week o! the collection date.

0+The Ge(Li) LI.D values are calculated by the method developed by Pasternack and Harley as described in HASL-300. These LLD values are expected to vary depending on the activities of the components in the samples. These figures do not represent the LLD values" achievable on given samples.

Vates is counted in eithel' 0;5-L or 3.5-L Marinelli beaker. Solid samples such as soil, sediment, and clam shells are counted in a 0.5-L Marinelli beaker -as dry weight. The average dry weight is 400-500 grams. Air filters and very small volume samples are counted in petrie dishes centered on"'the 'detectoi endcap. The. counting system consists, of a hT3<<4420 multichannel analyzer and either a 25X, 14X, 16X, or 29X Ge(Li) detector.;he counting time is normally 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. All sPectral anal'ysis is Performed using the software Provided with the ND-4420. The assumption is made that all samples are analyzed within one week of the collection date.

Conversion factors 1 pCi 3.7 x 10 Bq.

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

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

Date (a3u) WARL EARL (+3o) WARL EARL (+3o)

WARL EARL (+3o) WARL EARL 3/82 27+12 23 28 55+9 63 56 16+2.6 16 15 23+9 24 24 9/82 32+14 28 28 67+9 57 52 20+2. 6 . 17 'g14 g 27+9 22 22 B. Tritium in Urine (pCi/L)

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

l Table 4 (Continued).

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

Gross Al ha Gross Beta Strontiumt- 89'"-"

Strontium - 90 .

Trltiun). ~

Iodine -131

= .-

EPA.value T~VAVG. EPA value TVA'VG; EPA value TVA AVG. 'PA value TVA AVG. EPA.value TVA AVG EPA value TVA AVG.

G ee WARL EARL ~('3a WARL EARL ~3e) I:ARL EARL ~3a MARL EARL ~3a MARL ~3= 'WARL EARL

~3a'1/82 24i10 20 19 32'9 33 28 . 21 9 20 22 12a2.6 13 12 6h 8.7 7.3 2/82 1820M592 2007 1793 3/82 . 1949 19 20 1969 ,

F 19 20 4/82 2860+624 2907 2923 62-11 61 61 5/82 27.5~12 27 '38.3 29'9 26 33 2259 24 . 22 13i2.6 11 8 6/82 1830i589 1620 1810 2h 5.3 3.6 7/82 . = 16A9 23 9 ZO 21 2890i624 32'6 8/82 2903 2793 9/82. 29i13 f 40 9 f 24.5 30 14.5i2.6 13.8 14.8 87=15 93 79

'2 38 9 21 10/82 2560-'606 2690 2510 11/82 19'9 19 15 24i9 23 12/82 1990G598 1943 1993 37=10 37 D. Ga( w-Spectral Analysis of Water (pCi/L)

Chromium - 51 ve1 e Yl,'A

'obalt Ava. Ep'A vel e lvA 60 Avr.. EPA Zinc.

value

- 65 ..

~P~VG. EPA Ruthenium vel e ~VVA

- 106 va. EPA Cesium 134 value ~~~V EPA Cesium value

- 137 Date ( 3tl) 'ARL EARL '~3a WARL EARL ~3II VARL EARL ~(~3a WARL EARL -3 a WAIIL EIIRL ~3a 4'ARL EARL

<".5 15i9 . 16 16 20i9 <40 <30 22a9 21 19 23 9 24 22

.2/82 6/82 0

23+9

<44 4d <35 2069 29'9 .

21 32 '422 2649

~

29 26 0 <40 <30 35'9 31 32 25 9 24 27 10/82 51i9 55 <35 ."n 9 18 21 24~9 25d 2 30G9 39d <36 19~9 19d 17 20-'9 20d 22

Table 4. (Continued)

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

Strontium - 89 . 'Strontium '- 90 Iodine - 131 . Cesium -. 137 'arium 140 Potassium~ Cobalt - 60 EPA value TVA AVG. EPA el e TVA AVG. EPA al e TVA AVG. EPA al e TVA AVG. alue TVA AVC. val I Date ~3a WARL EARL ~(~3e MARL 'EARL ~(3a ~ . MARL EARL ( 3e) WARL EARL EPA

~3a) WARL EARL '~3 EPA e TVA AVG.

WARL EARL EPA

~3a) e ~TVA VC.

WARL EARL 4/82 2549 7/82 29 28 16~2.6 16 13 5.4t1.4h '.7 .5.1 '2 28f9 31 30 0 <29 <15 1500i130 1590 1413 30A6 32 29' 10/82 0 <10 <10 18.6~2.6 19.5 12.8 42i10 .43 3469 ' . 34) 'IS <25 . <20 15603135 1563 1639 F. Foods (pCi/kg, Wet Weight)

St'rontium - 89 Strontium - 90 Iodine 131 Cesium "137 Barium - 140 value Potassium EPA TVA AVG. EPA value TVA AVG. EPA value TVA AVG. EPA value TVA 'EPA value Date ~3a WARL EARL (=3o) 'ARL EARL (-3v) WAIIL . EARL ~3a WARL AVG.

EARL (i3a)

TVA AVC MARL EARL EPA value (a3o) WARL EARL 7/82 2649 30 28 20 94615 98 98 2069 24 26 0 <25 <14 11/82 24~k 2400~208 2810 9 2733 9 0 <10 <40 27.8=2.6 30.6 25310 20 29 27+9 28 27 ~

0 <25 <14 2780f242 2670.- 2903' Western Area Radiological Laboratory, Muscle Shoals, Alabama b

Eastern Area Radiological Laboratory, Vonore, Tennessee c

No known explanation. Investigation underway.

d Analysis completed after report date e

Equipment malfunction, analysis completed after report date f Poor analysis. Equipment taken out of service for recalibration. Further results satisfactory.

Previous and e

Subsequent resi)lts satisfactory. Nn known explanation.

h NRC/EPA Low-level I study.

i Experimental detection limit is being reviewed.

Potassium values are mg/1 or mg/kg.

k Revie~ of procedure is in progress.

LOVISVLLE D.

N EVANSVLI.E'ENNESSEE I

VALLEY- REGION 4.

,1fOWENSSOIIO (TVA NUCLEAR PLANT SITES) w V A K. E N T U- C K Y,

.r I

'g ( PADIPCAN I' V~ (

/)

SOWLING GRE EN O

..J /

g ~/

/ PSN gIENi S (

/M~~ / )

g t

NASlHVILL L,r OAK R(DOER I

+N~ N N E S

/ I

'L/I CKSONe (

'~

~wH

(

/ (

7 I

NEVPMS SWN J A l CHATTANOOGA~

I.

e I J CN 8I.N jItUNTSVILLE

/

S CAR.

MVSCL8 SHOALS LEGEND

- HARTSVILLE NUCLEAR PLANT

/ ~ I 'gg -PHIPPS BEND NUCLEAR PLANT M. I S S. J YK!RP CLINCII RIYER BREEDER A L A 8 A. M. A G EORG I:A REACTOR BAR NUCLEAR PLAIYT

'.-WATTS Xg *-SEQUOYAH NUCLEAR PLANT, jKg' BELLEFONTE NUCLEAR PLANT 9E5[ - BROWNS FERRY NUCLEAR PLANT.

'~-- YELLOW CREEK NUCLEAR PLANT

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

Four local air monitors are located on or adjacent, to the plant site in the general areas of greatest wind frequency. One additional station is located at the point of maximum predicted offsite concentration of radionuclides based on preoperational meteorological data (see figures 3 and 4). Four perimeter air monitors are located at distances out to 10 miles from the plant, and two remote ai.r monitors are located at distances out to 45 miles. These monitoring stations are shown in figure 2: The remote monitors are used as control or baseline stations.. At each monitor, air is continuously pulled through a Hollingsworth and,Voss LB5211 glass fiber filter at a flow of 3 fts/min.'n series wi:th, but downstream of, the particulate'ilter is a charcoal filter used 'to co'llect iodine. Each monitor has a collection tray and sto'rage container to obtain rainwater on a continuous basis and a horizontal platform that .is covered with gummed acetate to catch'nd hold heavy particle fallout.

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

Each 'of the local air monitors is fitted with a GM tube that con-tinuously. scans the particulate filter. The disintegration rate of the atmospheric radioactivity is continuously recorded at each station and radio-telemetered into the plant.

Air filters are collected weekly and a'nalyzed for gross beta activ-ity;

. No analyses are performed until three days after sample collection. The

. samples are'omposited monthly for analysis of specific gamma-emitting radio-nuclides and, quarterly for Sr and Sr analysis. The results are combined for each station to obtain an annual average. During this reporting period, one sample,was not obta'ined,because of equipment malfunction. These data are presented in table 6.

The annual averages of the gross beta activity in the air particulate filters at the indicator stations (local and perimeter monitors) and at the control stati,ons (remot'e monitors) for the years 1968-1982 are prese'nted in figure 5.. Increased levels due to fallout from atmospheric nuclear weapons

'testing are evident, especially in 1969, 1970, 1971, 1977, 1978, and 1981.

These patterns are consistent with data from monitoring programs conducted by.

TUA at nonoperating nuclear power plant construction sites. Table 5 presents the maximum'permissible concentrations (MPC) specified in 10 QFR 20 for non-occupational exposure.

Rainwater is collected monthly and a 3.5-liter sample analyzed for specific gamma-emitting radioisotopes and'ritium. The results are shown in table 7.

'The gummed acetate that is used to collect heavy particle fallout is changed monthly. The samples are ashed and counted for gross beta activity.

The results are given in table 8, Thirteen samples were los't, destroyed, or damaged and analysis was not performed..

12 Charcoal filters are collected and analyzed for radioiodine.

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

~ ~

I Table 5 MAXIMUM PERMISSIBLE CONCENTRATIONS FOR NONOCCUPATIONAL EXPOSURE In Water In Air

~Ci/1* ~Ci/m +

Alpha 30 I

Nopvolatile bq)a 3,000 100 Tritium 3,000,000 200,000

'"cs 20,000 500

) 03'06R 10,000 200

]44C 10,000 200

",Zr-"Nb 60,000 1,000 140/a 140La 20,000 1,000 k 3) I 300 100 65ZQ 100,000 .2,000

'"Mn 100,000 1,000

",Co 30,000 300

""Sr 3,000 300 "Sr. 300 30 "Cr 2,000,000 80,000

]34(s 9,000 400 SSG 90,000 ',000

>1 pCi ~ 3,7 q 10 Q~.

TABLE 6 R'AOIOACTIVITY IN AIR FILTER PCI!H(3) - 0 '37 BO/H(3)

I NAHE OF FACILITY BROVNS ~FRRY DOCKET .NOe~2~59 ~660'96 c LOCATION OF FACILITY $ $ H~S~TNf, ~AA Akll REPORTING PERIOD 198g

~ A A~

TYPE ANO LOVER LIMIT ALL CONTROL NUMBER OF TOTAL NUMBER

. OF ANALYSIS P f RF0R II E D OF DETECTION CLLD)

INDICATOR LOCATIONS MEAN (F)

RANGE T N NAHE - 'EAN HATH HIGH~AT. AHH~UL II ANN (f.)

LOCATION)

HEAN (F)

RANGE R

- JIONROUTINE REPORTED HEASUREHf NTS GROSS ALPHA 0 '05 0 ~ 01 (- 1/ "'51 )

51 0 ~ 01- 0 ~ 01 GROSS BETA 0 '10 0 '2( 426/ 468) DECATUR'L 0 '2( 47/ '52) 0 02( 96/ 103)

GAHHA (NAI) 571 0 01- 0 '4 8 ' MILES SSE 0 F 01-. 0 F 04 0 F

F 01=

\ 0 '4 83

-C E-1 41 y 144 0+ 030 0 '5(

'4- 2/ 67) LH2 BF NORTH 0 '5(

'5-' 1/ 7) 16 VALUES <LLD 0 100 67 0 0 VALUES-<LLD

'5 ~ 0 ~ 9 MILE Nt(E 0 0202(

F 05 0 '2( 1/ 16)

'2

~

K-40'E-59 GN12- 0 NOT ESTAB 0 F 00( 6/ 67) DECATUBU AL 0 F 00( 8) 16 VALUES <LLO 0 00- . ONOG 8;2 HIiES SSE 0 ~ GO- 0 F 00 I-131 0 010 0 '2( 4/ 67) DECATUR'L 1'/ '

~

) 16 VALUES <LLO BE-7

~

NOT ESTAB 0F 0F 01-'

07(

'2 67/ 67) 8 ' MILES SSE ATHENSU AL 0

D 0~

~ 02-05-'/

08(

OR 8/'c 8) 02 0 '7( 15/ .16)

GAHHA (GELI) 0 F 01- 0 '0 10 ~ 9 I ILES NE 0~ 0 '0 0 '5- Gall 60 K-40 NOT ESTAB 0 0

'2(00" 32/ 50) 04 LH4 BF TRAILER P 1.7 MILES t)NV 0F 0~

02(

02-3/

0 04

5) 0 '2(

0.00-8/

0.03 10) 0 ~

8 I-214 0~ 020 F F

05( 3/

F 50) 05 ROGERSVILLE ~ AL 13 ~ 8 HILES NV 0 '5(05-1/

05

7) 0 '3C 03-1/ 1G)

'3 0 04 0F 0~ 0 0 0 PB 214 020 0 F 04( 3/ 50) ROGERSVILLE ~ AL 0 04( 1/ g) 10 VALUES <LLO

~ 0 ~

0 '3- - ON04 13 8 r. ILES'il " 0 '400( 0 '4 5)

~

P.B-212 NOT ESTAB 0 F 00( 26/ 50) DECATUR'L 0F 2/ 0 00( 4/ 10)

RA-226 NOT ESTAB 0.00-ON02(

0.00 5/ 50) 8 ~ 2 MILES SSE COURTLANDy AL

.0 ~

ON04(

00- 0 1/

F 00 5) 0 F

F 00-10 VALUES <LLO 0 '2 BE-7 050 0 F 00-0 F 06(

0 20/

F 04 50) 10 ~ 5 H ILES VSV LH5 BF DAVIS 0 ~ 04-0 '7( 0 1/

'4 5) 06( S/ 10)

TL-208 0 ~

NOT ESTAB 0 ~ 05-0 F 00(

0~

15/'0) 07 2 ~ 5 MILES VSV LH4 BF TRAILER P F

0 ~ 07-0 F 00(

0 1/

F 07 5),

G ~

0 G ~

'500( 0 '0 5/ 10) 0 F 00- 0 ~ GG 1 ~ 7 MILES NIVV 0~ 00- 0F 00 0 F 00- 0 F 00 AC-228 NOT ESTAB 0 F 01( 2/ 50) ATHENSU AL ~ 0 '1( 1/. 5) 10 VALUES <LLO 0 F 00- 0 F 01 10 ~ 9 'l'ILES NE 0 01 F 0 F 01 SR 89 0 '05 36 VALUES <LLD 8 VALUES <LLD

'I 44 ANALYSIS PERFORHED SR 90 0@001 ,

36 VAI.UES <LLD 8. VALUES <LLD 44 ANALYSIS PERFORHED

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

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

TABLE 7 RADIOACTIVITY IN RAINVATER I/L - Oo 037 BQ/L .

NAHE OF LOCATION OF FACILI TY~Q~~Q~'C ~AA FACILITY BROVNS. FERRY Mg COCKET 00 REPORTING 00-2~59 260 290 PERIOD~98~

TYPE ANO LOVER LI NIT ALL CONTROL NUMBER OF TOTAL NUMBER OF INDICATOR LOCA/TONS CO~CAT 0 III TH HIGHEST AHIIOAE~II Ag L'OCATION) NONROUTINE OF ANALYSIS DETECTION HEAN (f ) NANE HEAN (F) MEAN (F) REPORTED

~PRFORIIEO ~(f,D ) RANGE DISTANCE AtlD DIRECT'ION RANGE RANGE HEASURENENTS GAHNA (NAI )

119 FE-59 NOT ESTAB 2 76(

'0- 14/ 97) LH3 BF NORTHEAST 4 '5( 2/ 10) 5 '5(

'0- 4/ 22) 0

~

.5 '0 54/ 97) loO,MILE ENE . 4 ~ 40-45 '1(

F 50 7/

0 45 '5(

50 14/. 22)

BE-7 NOT ESTAB 36 ~ 64 (

lo70- 71 'O LH5 BF DAVIS F 2 ~ 5 MILES VSV 30o00- 66 '010) 15990-. 84 '0 GAHNA (GELI )

24 K-40 NOT ESTAB F 05(

'8- 2/ 20) ROGERSVILLEO AL 6 '1( 1/

'1 2) 76(

'6-1 ~ 1/

'6 4) 1

'1( 6 '1 13 ' NILES NV 6 ~ 71-

'1( 6 1/

1 1 8 I-214 NOT ESTAB 1/ 20) ROGERSVILLE ~ AL 2) 4 VALUES <LLD 0

0 '1- Oo31 13 ~ 8 MILES t(V 0

0 31-7 '1(

0 '1 PB-212 NOT ESTAB 3 '8( 12/ 20) LH2 BF NORTH 1/ 1) '2 ~ 36 ( 2/ 4) 0' 24 7 '1 0 ' MILE Nt)E 7 31-

~ 7 '1 2 '1- 2 '1 BE-7 NOT ESTAB 53o42( 3/ 20) ROGERSVILLEe AL 75 '6( 1/ 2) VALUES <LLO 31 55- 75 '6 13 ~ 8 N ILES t(V 75936- 75 36 1/ 20) 1/

AC-228 TRITIUH 15 F 000 330 ~ OGO 17%90(

17 '0-117 VALUES <LLO 17 '0 LH3 BF NORTHEAST 1 ~ C HILE ENE 17990(

17 '0 17 '0 3) 4 VALUES <LLO 26 VALUES <LLD 143 ANALYSIS PERFORHED

a. Nominal Lover Limit of Detection O.LD} as described in TAble 3.

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

-TABLE 8 RADIOACTIVITY IN HEAVY PARTICLE FALLOUT HCI/KH(2) - 37000000 ~ 00 80/KH(2)

'LL NAHE OF F'AGILITY BROVNS FLURRY DOCKET NO ~ 50-~2A 2~0 LOCAT ION OF F ACILI TY~~H~STONf, ALABAHA REPORTING PERIOD 1902 TYPE AND LONER LIHIT- CONTROL NUMBER OF TOTAL NUHBER ~~AT VI TH ll~llE4$

OF ANALYSIS OF DETECTION INDICATOR LOCA'LIONS HEAN

~R (F)

QN NAME H~IGH ST 4~1ttl MEAN (F~ LOCATIONS HEAN (()

NONROUTINE REPORTED f,~AQ~R~H/S EQKQE5Q? EANQK H GROSS BETA 130 0 ~ 050 0 0

'1(

'5- 107/ 10T) 0 '4, COURTLANDo AL 10 ~ 5 MILES MSV 0

0~

'1(

14-,12/0 ~

12) 44 0

0

'0(

F 07 23/

0 '123)

a. Noainal Lover Liqit of Detection (LLD} as described in Table 3.

b. Mean and range based upon=detectable ncasurements only. Fraction of detectable neasurenents at specified locations is indicated in parentheses (p).

TABLE 9

. RADIOACTIVITY IN CHARCOAL. FILTERS PC I/H.(3) - 0 ~ 037 'Q/H (3)

NAME OF FACILITY /ROVERS FLURRY DOCKET >0 ~252x2fdlx2~~

LOCATION OF FACILITY -LIMESTONE ll~lI 8 A IIA REPORT ING. PERIOD 19RP TYPE AND LOMER LIMIT ALL CONTROL NUHBER OF TOTAL NUHBER. OF INDICATOR LOCATIONS LOCATION UI TH H~GM QT A~NN /~MAN LOCATIONS NON ROUTINE OF ANALYSIS

~PR QRMQQ DETECTION HEAN (() HBAN (Fb)b REPORTED RANGE RANGE IODINE IN AIR 0 '20 0 '3( 39/.467) ROGERSVILLEi AL 0+03( 12/ 52) 0 03( 10/ 102) 569 0 02- 0 '7. 13 8 HILES NM = 0 ~ 02- .,0 ~ 07 0 F 02- 0 '6

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

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

18 Figure 2 ATMOSPHERIC AND TERRESTRIAL MONITORING NETWORK

'RM.28F LAWRENCEBURG yPULASKI FAYETTEVILLE' WILSON PM-IBF WHEELER ROGEPSVILI g FLORENCE OAM ATHENS PM-2BF FFIEL MUSCLE HUNTSVILLE SHOALS BROWNS FERRY RM-I BF C

NUCLEAR PL NT LEIGHTON

'TUSCUMBIA

.COURTLANO PM-4 F OECAT R PM 38FD IO MILES g pRUSSELLVILLE GUNT SVIL HARTSELLE OAM HALEYVILLE

~CULLMAN 45 MILES Q-ENVIRONMENTAL MONITORING STATION NOTE

I THE FOLLOWING SAMPLES ARE COLLECTED 0 FROM EACH STATION:

I AIR PARTICULATES RAINWATER 5 RADIOIODINE SOIL

,"HEAVY PARTICLE FALLOUT

Figure 3

'.. LOCAL MONITORING STATIONS 19 BROWNS FERRY NUCLEAR PLANT ATHENS US HWY 72 ALA. HWY 20 Legend

~ Air Monitor DECATUR Aufoin'otic Well Sampler H Dairy Farm 0 l,.2Scale B 0 6 Miles

20 Pigure 4

'(j r+ 'if) 4 f 'ta 'P j

/a i

'j"~~ ~'.$ V)f f'

~ y TLD Locations

)

I' ~ I a~If') ".~'~

t I'II Q)

]jf

.)I I j

1 r ro fr

)l ltl tip'

>>i

/+(.)

f f

~ l f)

I

)IC I(

1 1 gf

't ~

')I(4

~

(

I I I I

I n.V I(

<<I

,~

a

~ l

~ 1

Figure 5 Amuu AERAGE

.30 6ROSS BETA kTIVITY IN AIR FILTERS HROWS FERRV Noae PueT-Preoperational Phase I Operational Phase

.25 C

C 0

C IJ 0

.20 C~

IJ IJ 0

M IJ IJ M 0

IJ C 0 IJ C

C 0

.15 w CJ Ave~ra e: Preo~erational Phase

.10

.05 1968 1969 1970 1971 1972 1973P 19730 '974 1975 1976 1977 1978 1979 1980 1981 1 82

23 Terrestrial Monitorin Milk Milk is collected from four larms within a 10-mile radius of the plant (see figure 3), and from at least one of four control farms. Raw milk i'nalyzed weekly'or I, and monthly .for gamma-emitting isotopes and for radiostrontium. The results are shown in table,10.

Cow censuses were conducted in May and September.1982. It was determined that there are no dairy farms nearer the plant than the nearest

'arm being-sampled. During this period however,'ne of the'airy farms being

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

~Ve etation

'egetation is sampled quarterly at the farms from which milk is collected and analyzed for gamma-emitting radionuclides. Approximately 1-2 kilograms of grass is broken or cut at ground level and returned for analysis'.

Efforts are made'o sample vegetati,on that is representative of the-pasturage where cattle graze. Table- ll gives the results obtained from the laboratory analyses of these samples.

Soil Soil. samples are collected annually near each monitoring station to provide an indicati,on of a long-term buildup of radioactivity in the environ-ment, An auger or. "cookie cutter" type sampler is used to= obtain samples of the,top, two inches (5 cm) of soil. These samples are analyzed'or gamma-emitting radionuclides, Sr, and Sr. The results are given in table 12.

Ground~.Water An automatic sequential-type sampling, device has been installed on a well downgradient from BFN. A composite sample from this well is analyzed for

.gamma-emitting 'radionuclides monthly and composited quarterly for determination of tritium-. A grab sample is also taken from a control well upgradient from the plant. The. results of the analysis of well water are shown in table 13.

Drinkin Water Potable water suppli.es taken from the Tennessee River in the vicinity of BFN are sampled,and analyzed for gross beta and gamma-emitting radionuclides, and composited quarterly for tritium, Sr, and Sr analyses. The first potable water supply downstream from the plant is equipped with an automatic sampler with samples collected and analyzed weekly. The sampler is located on the water intake structure and takes the sample from the river as the raw water is drawn j.nto the water treatment facility. Two addi.tional supplies

24 downstream and one public water supply upstream are sampled by taking monthly grab'samples of treate'd water at user points. Table 14 indicates the results from the analysis of drinking water samples. During this reporting period, one of the weekly samples was not taken because of the malfunction of automatic sampling equipment. Another sample was missed due to inaccessability caused by bad weather.

I e Figure 6 shows the trends in gross beta activity in drinking water from 1968 through 1982. The annual average level from the raw water samples tends to run slightly higher than the average for treated water samples; however, the levels are consistent with the activities reported in surface water samples taken upstream from BFN (figure 12) and in samples taken from the Tennessee River in preoperational monitoring programs conducted by TVA at other sites.

Environmental Gamma Radiation Levels Bulb-type Victoreen manganese-activated 'calcium fluoride (Ca~F: Mn) thermoluminescent dosimeters (TLDs) are placed at sixteen stations around the plant near the site boundary, at the perimeter and remote air monitors,and at nineteen additional stations out to approximately five miles from the'ite to determine the gamma exposure rates at these locations. The dosimeters, in energy compensating shields "o correct energy dependence, are placed at approxi-mately one meter above the ground, with three TLDs at each station. They are annealed and read with a Victoreen model 2810 TLD reader. The values are corrected for gamma response, self-irradiation, and fading, with. individual gamma response calibrations and self-irradiation factors determined for each TLD. The TLDs are exchanged every three months. The quarterly gamma radiation levels determined from these TLDs are given in table 15, which indicates that "

average levels at onsite stations are approximately 3-5 mR/quarter higher than levels at offsite stations. This is consistent with levels reported at TVA's nonoperating nuclear power plant construction sites where the average radiation levels onsite are generally 2-6=mR/quarter higher than levels offsite. The causes of these differences have not been completely isolated; however, postulated that the differences, are probably attributable to combinations of it is influences, such as -natural variations in environmental radiation levels, earth moving activities onsite, the mass of concrete employed in the con-struction of the plant, and other undetermined influences.

Figure 7 compares plots of the data from the onsite or site boundary stations with those from the offsite stations over the period from 1976 through 1982. To reduce the variations present in the data sets, a four-quarter moving average was constructed for each set. Figure 8 presents a trend "plot of the direct radiation levels as defined by the moving averages. The data the same general trend as'he raw data, but the curves are smoothed 'ollow considerably.

Prior to 1976 measurements were made with less sensitive dosimeters, and consequently the levels reported in the preoperational phase of the moni-toring program are 1-2 times the 'levels reported herein. Those data are not included in this report. Therefore, for comparison purposes, figures 9 and 10 depict the environmental ganuna. radiation levels measured during the construction of TVA's Watts Bar Nuclear Plant to the present. Note that the data follow a similar pattern to the BFN data and that, as discussed above, the levels reported at onsite stations are similarly higher than the levels at offsite stations.

25 F~ood Cro o Food crops raised in the. vicinity of BFN and at control locations are sampled- as they. become available during the growing season, and anal'yzed for gamma-emitting radionuclides. During this sampling period,. samples of corn, green beans,. potatoes, turnip greens, and tomatoes were collected and analyzed for speci.'fic gamma-emitting radionuclides. No sample of turnip greens was taken from a control location. The results are. given in tables 16, 17, 18, 19, and 20.

TABLE 10 RADIOACTIVITY IN HiILK PCI/L - 0 '3) BQ/L NAHE Of FACILITY RROMNS FERRY DOCKET NO ~ ~g+9k~xk99i LOCATION OF FACILITY LIHEQQONg ALABAHA REPORTING PERIOD'982 TYPE <<ND LOVER L IHIT ALI CONTROL. NUHBER OF TOTAL iVUHBEo QF. INDICATOR LOCATIONS LOCATIONS NONROUT INE OF ANALYSIS DETECT '.HE AN (gllew

) HEAN (F ) b REPORTED

~E~F ~gRffTION ION'I DISTANCf~AN PANGE R ANGP - H~AQRQ~HN$ $

"EQ l.Ql RANG/

GAHHA (NA I )

83 CS-137 10 F 000 11 '0(

'0- 1/ 42) 10 PAGE FARH 75 I(ILES 11 ll F 10(

10-1/

11 '0 10) 41 VALUES <LLD 11 1373 '1(

8 ~ E ~

K-40 150 F 000 1306 '2( 42/ 42) PAGE FARH 10/ 10)

. 1297 ~ 16( 41/ 41) 684 F 00- 1553o60 6 ~ 75 HILES E 1156 ~ 80- 1455 '0 1036o60- 1451o60 I OO I iVE-1 31 0 ~ 500 212 VALUES <LLO. 204 VALUES <LLO 916 ANALYSIS PERFORHED o

GAHHA (GELI )

'- 26 CS-137 F 000 6 '1( 3/ 11) PAGE FARH '2( 2/ 9 VALUES <LLD F 50- 7 '1 11/ 11) 8 75 .",ILES E 5~9 46(

3-'354 7.

2/

~ 51

2) 1256 '7( 9/ 9) 1269 F 10(

K-,I) 0 NOT ESTAB 747 '1 1499 '311) LOONEY FARH 5 ~ 75 ')iILES ENE 1209 F

10- 1499 F 83 1175 '6- 1362 '5 BIo214 49 '9( 2/ SHI TH ARHf ,49 '9(

~

2/ 3) 9 VALUES <LLD NOT ESTAB 38 '9- ~

61 '9 4 ~ 75'iILES N 38 ~ 2'9-41 '5(

61 '9 3) 214, 41 '5( 2/ 11) SWITCH FARM 2/ &~ 02( 2/ 9) 61 '4 NOT ESTAB PB

?0 '6- 61 '4 '} ~ 75 MILES 20 ~ 76- 7 "22- 8 82 6/ ll) '3/ 2/ 3/

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

11 VALUES <LLO 4.08 '."06-BROOKS FARP 7 0 QILES NNM 2

1 ~ 58 4 '8 3?

3 ~ 44(

li94 3o03(

2 '5-

'/"')

5 'o 9) 3 '1 SR 89 1'0 F 000 VALUES <LLO 50 VALUES .<LLO 103 ANALYSIS PERFORHEO SR 90 2 000 ) ~ 3&,(. 49/ 53) 2o09- . 10 F 14 SHI TH FAP'5 4 ~ 75 HILES N'

~ "

. 5 3

'5!

'6- 12/

10 '413) 3 '9(

08-,

46/

9 72 50) 103 o

a. No'nin'al Lower-Liriit of Detection (LLD) as described in Table 3.

b. Mean and range based upon detectable neasurenents only.'raction of detectable measurements at specified'ocations i is indicated in parentheses (F).

TABLE RADIOACTIVITY IN VEGETATION PCI/G - 0 ~ 037 BQ/G (OR Y )JEIGHT) i(AHE OF FAC ILITY BRO)JNS FERRY DOCKE'T tJOo~50- 59A260AQ96 LOCATIO)J OF FACILITY LIMESTONE ALABAMA REPORTING PERIOD 19~2 TYPE AND LO)JER L! MI T ALL NUMBER OF TOTAL NUMBEP OF ANALYSIS

~PR FOR."~ ~ ~

~a~

OF

'E TEC T-I 0 lJ INDI'CATOR LOCATIONS HEAN (F) b RANGFb Q~OA~TC)N CJI TH ~HGHgST tJAHE 'EAN6'3'ONTROL A;JNUAQ Mf AN (F)+

LOCATIONS MEAN (F 0 RANGEb NONROUTINE REPORTED GROSS BETA 200 23 82( 17/ 17) THRASHER FARH 59 ~ 43 ( I/ 1) 30 '3( 16/

'416) 0 GAH.JA (G=L 3%

I)33

~

3 '9- 69 '3 7 ~ 0 BILES ENE 69 '3- F 80- 57 CS-137 0 '60 0~ 13( 4/ 17) -SMITH FARM 0 ~ 18( I/ 4) 0 ~ 07( 3/ 16) 0F 07- 0 ~ 18 4 75 MILES 0 ~ 18- 0 ~ 18 0 ~ 07- 0 F 06 K-4 0 NOT ESTAB 14 F 92( 17/ 17) THRASHER FARM 46 1/ 1) ?0( 15/ 16) 8 I-214 0 100 1 ~ 87 0 10(

't6 ~ 29 1/ 17) 7 ~ 0 MILES Et(E SMITH FARH 46 ~

0+10(

29- 46+29 1/ 4) 4 '5 20 AD F 16(

46 F 06 1/ 16)

F 0 ~ 10- 0 '0 4 ~ 75 MILES N 0 ~ 10- 0 ~ 10 0 ~ 16- 0 '6 BI-212 NOT ESTAB 17 VALUES <LLO 0 '1(31-1/ 16) 0 ~ 0 ~ 31 PB-214 0 ~ 09( 8/ 17) SHITH FAR.'I 0 12( 3/ 4) 07( 8/ 15)

PB-212 0 ~ 01-0 ~ 06( 15/

0 ~ 13

17) .

4 ~ 75 MILES SMITH FARM N 0 0

~

'7(

~ 09- 0 4/

'3 4) 0 0

0

~

F 00"

'6C 0

12/

~ 18 16) 0 ~ 00- 0 ~ 16 4 ~ 75 MILES i'J 0 ~ 00- 0 ~ 16 0 ~ 02- 0 ~ 11.

RA 226 0 ~ 11( 8/ 1?) PAGE FARH 0 26( 2/ 4) F 07( 9/ 16)

BE-7 tJOT. ESTAB 0 ~ 02-5 ~ 86( 17/

0 ~ 50 17)

. 8 ~ 75 MILES E BROOKS FARM 0

7

~

'2(

~ 02- 0 4/

'0 4) 0 0 ~ 01-

'7( 0 '6 15/ 16) 15 '6 4

0 ~ 33- ~

15 ~ 36 ?o 0 HILES NN)J 2 ~ 35-. 0 92- 8~8 TL-208 IJOT ESTAB 0 ~ 02( 11/ 17) 06, TtlRASHER FARM 0 ~ 04( I/ 1) 0 '4(

~

10/ 16)

AC 228 'JOT ESTAB 0 ~ 00-0~ 17 ( 12/

0 ~

17 )

7) 0. MILES'NE THP ASHER FARM

~ 0 ~ 04-al5(

0 1/

F 04 1) 0 0

~ 01-

'4C 8/ 16) 0 '6 0~ 02- 1 ~ 15 ?o0 HILES ENE.

1 I 15-

~ 1 ~ 15 0~ 03- 0 '6

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 at specified locations is indicated in parentheses (P).

TABLE 12 RADIOACTIVITY IN SOIL PCI/G - 0~ 037 80/G (DRY MEIGHT)

NAME OF FACILiTY l)~RQ~QR DDCKET MO ~EEREDEAEEO LOCATION OF FACILITY LIMESTONE Al.ABAMA REPORTIMG PER IOD~19G CONTROL NUHBER OF TYPE AND LOMER LIMIT ALL TOTAL NUHBER OF INDICATOR LOCATIONS J,OCATION MITH H GH T ANN LOCATION) NONROUTINE ANALYSIS DETECT IOtla HEAN (g) o NAME HEAN (g) REPORTED RAN//,

OF EKEEQEEKR ~LLQ2 RANGE D~GTAM ~AM ~RECTIOM RANGE (GELI)

GAHMA CE-144 ll 0 '60 9 VALUES <LLD 0~ 12( I/ 2)

.0 12- 0 ~ 12 CS-137 0 ~ 020' 0 '0(

-0 ~ 050

- 9/

1017

9) ATHENS'L 1,0 9 HILES NE 1 ~ 17(

1'017-1/

1 17

1) 1 ~ 17(

le01-.

2/

1 '3 2)

K-40 '50 95 '2( 9/ 9)

~

LM4 BF TRAILER P 8 '3( 1/

~

1) 4,57( "2/ 2)

'7- 5 '7 010 3 '6-02(

2/ 9)

'3 1 ~ 7 MILES NNM LH5 BF ~ DAVIS 8 ~ 13-0~ 02( 1/

8 ~ 13 1) 4 2 VALUES <LLD HN-54 0 F 0 F F 0001- 0 ~ 02 2 ~ 5 MILES MSM 0 ~ 02 0 ~ 02

' 2/ 2)81-214 0 F 050 0091( . 9/. 9) LH4 BF TRAILER I 1 ~ 18( 1/ 1) ~

0 ~ 81(

0'055- 1 ~ 18, ~ 7 NILES NNV 1'0 18- 1 g18 0 ~ 73- 0 ~ 89 8 I-212 0 F 100 1 ~ 33(' 9/ 9) LN4 BF TRAILER P 1 ~ 78( 1/ 1) 1~ 03( 2/ 2)

Oe68- 1078 1 ~ 7 NILES NNM 1 ~ 78- 78 0091 1~ 15 PB-214 0 050 4 ~ 02 ( .9/ 9) LH2 BF NORTH 1 ~ 33( 1/

1 ~

1) 0 '0(

'3 2/

'7 2)

~

0 '5 9/

1 ~ 33 9) 0 ~ 9 HILE hhE LH4 BF TRAILER

.1 ~ 33-1 ~ 45( 1/

1 ~ 33 I

0 86(

0 2/ 2)

PB-212 NOT ESTAB ~

1 ~ 09(

0 ~ 62- 1 ~ 45 1 ~ 7 MILES tRNM P

1 ~ 45- 1 ~ 45 1 0 0

F F 80 0

'1( 2/ 89 2)

'2 RA-226 050 91( 9/ 9) LN4. BF TRAILcR P 1.18 ( 1/ 1) 0 0 ~ 0 0 '5-

~

1~ 18 1 ~ 'I MILES NNM 1 ~ 18- 1 ~ 18 0~ 73 0~

RA 223 NOT ESTAB 0 '1(

24-6/

'0, ~ 37

9) LH3 BF NORTHEAST 1~0 HILE ENE 0 ~ 37(

0 ~ 37 1/

0 '7 1)1) ~

0 97(

'0-1 ~ 2/ 2) 3 '4 0

RA-224 ESTAB

'OT 0 ~ 99( 4/ 9) LH4 BF TRAILER P 1042( 1/ 2 VALUES <LLD 0 ~ 53- -F 42 1 ~ 7 tlI LES WN'TR 1~ 42- 1042 0 '1( 2/ 2)

BE"7 0 ~ 160 9 VA'l.UES <LLO 0020".. 0 '2 6 '0(

TL-208 36( 9/ 9) LN4 BF TRAILER P 0 ~ 45( 1/

'5 1)

'8- 2/2/ '3 2) 0 ~ 020 0~

0 ~ 20r -. 0 ~ 45 1~ 7 MILES t(NM 0 ~ 45- 0 0 0 AC-228 0 ~ 060 I F 12(

0 ~ 60- '

9/"

~ 51

9) LM4 BF TRAILER P 1 ~ 7 MILES NNV F 51(

1 ~ 51-

'5(

1/

1 ~ 51-1/

1)

.1) 0 '938( 1/ '8.2)2) 0088(

-0

. "PA 234M NOT ESTAB - '2 F 81( 4/ 9) LN5 BF DAVIS F 3 1 1038-'

2 ~ 44-, '3 ~ 15 2~ 5'ILES MSM 3~ 15- F 15 ~ 38 SR 89, 10500 1082'( 1/ 9) ATHENSD AL 1 ~ 82( 1/ 1) 2 VALUES <LLO 1 ~ 82" 1 ~ 82 10 ~ 9 MILES NE 1~ 82- , 1 ~ 82 SR 90 0 '00 9 VALUES <LLD 2 VALUES <LLD ANALYSIS PERFORMED

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

b. Mean and range based upon detectable measu'rements only, Fraction of detectable measurements at specified locations is indicated in parentheses

TABLE I3 RADIOACTIVITY IN, MELL MATER PCI /L - ~ 0~ 037 80/L NAHE OF FACILITY DROWNS FERRY DDOKET NO 59-259 268 296 LOCATION. OF FACILI TY~~~TQj ~/~ASH REPORTING PERIOD"1982 TYPE AND TOTAL NUHBER LOVER LIHIT, OF ALL INDICATOR LOCATIONS CONTROL .NUMBER CF NONROUTJNE LOCATIONS OF ANALYSIS DETECTION HEAN (f ) (()

~(~ HEAN REPORTED

~PR ~RH ) RANGE HKASQKU~NTS GAHHA (NAI) 19 FE-59 NOT ESTAB 8 VALUES <LLD 4 35( 2/ 11)

I-131 15 F 000 8 VALUES <LLD

~

22990-15+20(

5 1/

'011)

'15 ~ 20- 15 '0 GAHHA (GELI)

'/

7 BI-214 'OT ESTAB 14 ~ 36(

'6- 1/,

'6.5) BFN WELL s6 14 '6( 1/ 5) 2 VALUES

'6 14 ~ 36-

<LLD'0 14 14 Oa02 HILES V 14 PB-212 '

NOT ESTAB 1~ 58(

1925- 1990

5) BFN WELL 06 C2 MILES 1 ~ 58(

25-2/

90 S.) '9(

0978-2/ 2) 0 1~ 1 ~ 20 2 '5(

1 TL-208 2/ 5) '5( 2/

BFN WELL s6

'6 5)

NOT ESTAB 2 2 VALUES <LLD 1 '5- 3 '6 0~ 02 HILES V 1~ 85- 3 TRITIUH 330 F 000 4 VALUES <LLD VALUES <LLD 8 ANALYSIS PERFORHED

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

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

TABLE 14 RADIOACTIVIT'Y IN PUBLIC VATER SUPPLY PCI/L - 0 ~ 037 BQ/L NAIIE OF FACILITY N~ll lt EENTSY DOCKET NO ~ 50-259NPQ~O 296 LOCIITION OF FACILITY L~l> STONE ALAPAHA REPORTING PERIOD ~19 2 LOMER LIHIT ALL CONTROL NUHBER OF TYPE ANO INDI CATOR LOCATIONS LOCA~I~NO TN NENNEO~TLILINAL ~FAN LOCATION) NONROUTINE

.TOTAL NUHBER OF OF ANALYSIS DETECTION HEAN ( j)P HEAN (F) REPORTED (LLO) RANGE RANGE HQQSU~R HAUNTS PQRFO~RH

'0( 51/ 76) CHAHPION PAPER '3( 42/ -50) 2 '7( 3/ 13)

GROSS BETA 89 2 ~ 400 ~ 3 2 42- 13 '3 TRH 282 '

3 2 '7- 13 '3 2 F 58- F 17 GAHHA (NAI )

70 6/ '0( 1/ 11) 8 VALUES <LLO FE-59 NOT ESTAB 3 ~ 85(

I ~ 00- . 6 '062) SHEFFIELONAL ROB TRiH 254 ~ 3 6

6 ~ 6C- 6N60 GAHHA.(GELI)

K-40 19 NOT EST AB . 1 ~ 04( 1/ 14) CHAHPION PAPER 1 '4( 1/ 10) 9 '6(

'6- 1/

'6 5)

I 04- 1 ~ G4 TRH 282 ' 1~ 64 1 ~ 04 9 9 8 '7(

~

~

1/ 1/ 10) 5 VALUES <LLO PB-214 NOT ESTAB 8 ~ 47(

8 ~ 47- 8 '714) CHAHPION TRH 282 '

PAPER 8 '7 8 ~ 47 3 '8( 9/ 14) MHEELER DAHN AL 3N98( 1/ 2) 78( 3/ 5)

PB-212 NOT ESTAB IN03-

'9 TRH 274 ' 3 ~ 98- 3 '8 1 ~

1 ~ 32- 2

'9( 2/ 88 5)

'7 52(

4 5/ 14) MHEELER DAHN AL '3( 1/ 2)

TL-208 NOT ESTAB 0 ~

6 ~ 25-. Oa88 TRu 274 '

0 0 '3 0 '3 1 ON70-4 1~

VALUES <LLD SR 89 10 F 000 12 VALUES <LLD 16 ANALYSIS PERFORHEO SR 90 2 '60 12 VALUES <LLO VALUES <LLO 16 ANALYSIS PERFORi".ED 2/ 419 '4( 1/

'4 4) VALUES <LLO

'412) 330 F 000 395 05( CHAHPION PAPER 4 TRITiUM 16 37'6- 419 TR>> 282 ' 419 ~ 24- 419

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

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

31 Table 15 ENVIRONMENTAL GAMMA RADIATION LEVELS Average External Gamma Radiation Levels at 'Various Distances from Browns Ferry Nuclear Plant for Each Quarter - 1982 mR/quarter Distance Avera e External Gamma Radiation Levels b miles 1st uarter 2nd uarter 4th uarter 0-1. 20,.8 +. 1.1. 20.3 + 1.7 21.3 + 1.5 21.9 + 1.6 N

s 1-2 18.6 + 2.0 16.8 + 3.2 18.1 + 2.1 16s3 +

4.0'5.8 2-4 17.9 + 1.7 16.3 + 1.5 17.5 + 1.8 + 3.8 4-6 17.4 + 1.6 16.1 + 1.4 17.6 + 1.6 15.5 + 3.6 17.4 + 2.6 16.4 + 3.0 17.3 + 3.3 15.6 + 3.2

Average, 0-2 miles (Onside) 20.3 + 1.6 19.4 + 2.6 20.5 + 2.1 20.5 + 3.4

Average,

>2 miles (Offsite), 17.6+ 1.9 16.2 + 2.0 '7.5 + 2.2 15.6 + 3.4 a,'ata normalized to one. quarter (2190 hours0.0253 days <br />0.608 hours <br />0.00362 weeks <br />8.33295e-4 months <br />),

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

TABLE 16 RADIOACTIVITY IN CORN PCI/KG - 00037 BQ/KG (MET )'EIGHT)

NAME OF FACILITY-L)ROMNS-FERRY OOCIIET NO 52-25~252 295 LOCATION OF FACILITY L IH~STONQ ALABAHA REPORTING PERIOD 1'982 TYPE ANO LOVER LI HIT ,ALL CONTROL NUMBER OF TOTAL NUMBER OF "'NDICATOR LOCATIONS LOCA~7 ON MITM HIGHEST ANNUAL MEAN LOCATION( NONROUTINE

'ANALYSIS (F ) MEAN (Fb) MEAN (F )~ REPORTED OF P~Rf ~RM DETECTION

~IEQ I 25 F 000 3667 MEAN

'2(R~Afjj 1'/ 1)

TEIIEENN HILES f

NAHE ANTI OIRECTIQN 3667 ~ 62(

~RlN 1/

j 1)

~RA N 4983 F 14( 1/ 1)

HQ~AQ~R~HN J S GROSS BETA 2 3667 '2-. 3667 '2 7 NNM 3667 F 62- 3667 '2 4983 14- 4983 14 GAMMA (GELI )

K-40 2

'5( 1/ HILES 1990 '5( 1/ 1) 2040 '2( 1/ 1)

PB-212 NOT'ESTAB NOT ESTAB 1990 1990 ~ 35- 1990

.,1- ~ 38 ( 1,/

'5 1)1 )

7 7 HILES NNM NN)(

1990 '5 1038(

1990 1/

'5 1)

' 2040

'2- 2040 '2 VALUES <LLO 1 38- 1 ~ 38 1 ~ 38- 1038

'3( '3(

'3 l) 1/

TL-208 NOT ESTAB 0 0 ~ 03-1/

0 7 MILES NNM 0 0 '3" 0 '3 1) 1 VALUES <LLO

a. Koninal Lover Linit of Detection (LLD) as described in Table 3.

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

TABLE 17 RADIOACTIVITY IN GREEN BEANS PCI/KG - 0 ~ 037'O/KG (BET WEIGHT)

NAME OF FACILITY BROVNS FfRRY DOCKET NO ~ ~0-$ ~59 ~20 296 LOCATION OF FAG ILIT'Y Q~Mf STONf ALABAHA REPORTING PERIOD 1982 TYPE ANO LO'llER LI HIT ALL CONTROL NUMBER OF TOTAL NUHBER OF INDICATOR J,ORAT~ON VITM HI'GHEST ANNUAL MEAN LOCATIONS NONROUTINE OF ANALYSIS ZKEQEHfII DETECTION HEAN LOCATIONS

($ ) NAME MEAN (g 'EAN (,F) REPORTED, RPQSf

'1( Qf AQQQf ~MNgS

'1 I) I)

GROSS BETA 25.000 4257 1/, 7 HILES NNN)I '. 4257 ~ 41( 1/ 4751 ~ 82( 1/.

2 4257 F 41- 4257 ~ 41- 4257 ~ 41 .- 4751 ~ 82- 4751 ~ 82 I)'257 GAHHA (GEL I) ~

2 K-40 NOT ESTAB 1900 '0(

'0- 1/ I) 7 HILES NNV 1900 '0( . 1/ 1) 1/

PB-212 NOT ESTAB 1900 I ~ 68(

1900 1/

'0 I> 7 MILKS NNM 1900i30- 1900 '0 $ 034 ~ 02(

2034 ~ 02- 2034 ~ 02 1) 1 ~ 68( 1/ 1) 4 ~ 08( 1/ 1) le68- lo68 I ~ 68- 1 ~ 68 4 ~ 08- 4 ~ 08

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

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

TABLE 18 RADIOACTIVITY IN POTATOES PCI/KG 0~ 037 BO/KG ('MET MEI GHT)

NAHE OF FACILITY BROMNS FERRY OGONET NO, $ 2-2$ ERERRR2 IR LOCATION OF FAC'ILITY~~IH STON~ ALABAHA REPORTING PERIOD 19II2 LOMER LIHIT ALL CONTROL NUMBER OF TYPE AND OF INDICATOR LOCATIONS LOCATION MITH HIGHEST ANNUAL HEAN LOCATIONS NONROUTINE TOTAL NUHBER ANALYSIS DETECTION HEAN (() HEAN (F REPORTED OF P~R~f+H~

GROSS BETA

~(~000 25 F

) REMK 5373 ~ 00 ( I/ 1)

~ITANC~AN~IRQCTION 7 HILES NNM 5373 ~ 00(

RAN~

1/ 1) '9( f'7280 1/ 1)

HQAQQ~R HfggS 2 5373 F 00- 5373 00 5373 F 00- 5373 F 00 7280 F 19" 7280 F 19 GAHHA (GELI)

K-40 2

NOT ESTAB . 3549 ~ 88( 1/ 1) 7 HILES NNM 3549 F 88( 1/ 1) 3337 '7(

'7- 1/

'7

-1) 3549 F 88- 3549 F 88 3549 F 88- 3549 F 88 3337 3337

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

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

TABLE 19 RADIOACTIVITY IN TOHATOES PCI/KG - 0 ~ 037 BQ/KG (MET )'EIGHT)

NAHE OF FACILITY RROMNS, F jRRY DOCKET NO ~ 50-259

. '60 296-LOCATION OF FACILITY= LI~HSTONQ REPORTING PERIOD 1982

'LABAHA TYPE AND LOMER LI HI T ALL CONTROL NUMBER OF TOTAL NUMBER OF INDICATOR LOCA)IONS ~IICIITIOM VI TH HIGHEST IIH:ICAL IIEAH 'LOCATIONS NONROUTINE OF ANALYSIS 0 ET E.C I I ON HEAN (j ) NAHE HEAN,(F) MEAN ($ )b REPORTED Pf~RR HQ) ~(42) HAHSE GROSS BETA 25 F 000 3989 89I 3987 89- 3987 Il II I

'9 IIILES HHV 3989 89I ll'9 I> 4577 '5( 1/

'5 1)

'/'4 2 ~ 3987889- 3987 9577 ~ 95 4577 GAHHA (GELI )

2 K-40 NOT ESTAB 2172 '2(

'2- 1/

'2 I) 7 NILE S NNM 2172 '2(

2172 52- 2172 1/'

'2 ) 2158 '4(

'4- 1) 2172 2172 . 2158 2158

'4( 1/ 2 '4( 1/ 1/ 1,)-

PB"212 NOT ESTAB 2 2 '4- 2854

1) 7 HILES NN)(

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

4 ~ 76 4 ~ 76

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

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

TABLE 20 RADIOACTIVITY IN TURNIP GREENS PCI/i(G - 0~ 037 BOPKG (VET 'VEIGHT)

NAHE OF FACILITY BROVNS FERRY DOCKET NO ~ 50-259 260 296 LOCATION OF FACILITY~~~Nf AQ~AAPQ REPORT ING PERIOD ) 982 TYPE AND LOVER LIHIT ALL CONTROL NUMBER OF TOTAL NUHBER OF INDICATOR LOCATIONS LOCATION V)TH HIGHEST ANNUAL HEAN LOCATIONS NONROUTINE OF ANALYSIS DETECTION ~

HEAN '(F)- "NAHE ~ MEAN (F P HEAN .(F)b REPORTED Q) RANGE b 0 ISTANCf AN5 51RECTI ON ~ R'ANGEb RANGLb

'7( NNV'719 GROSS BETA 1

25~000 ,7719 7719 '7- 1/

7719 '7 1) 7

/

HILES 7719 F 47 47(. 1/

7719 '7 I)

GAMMA CS-137 (GELI) 1 F 000

'. '7 '

/

"7 ~ 03-(. '/F 03 I) 7 HILES NNV 7 '3(

.7 ~ 03-1/,

7 '3 1),

K-40 NDT ESTAB 3209 ~ 21( 1/ 1) 7 HILES NNV 3209421( 1/ 1) 3209 ~ 21- 3209 '1 1) 3209 '1- 32 09421 PB-212 NOT ESTAB . 7 '8('48-1/ 7 MILES NNV 7 '8(

7e.48-1/

7448 1) 7 ~ 7 ~ 48

')

'/

BE-7 NOT ESTAB " 105 ~ 52(, 1) 7 HILES NNV 105 ~ 52(, 1/ 1) 105o52- '105+52 105 '2-,' 05(52 TL-208 1/ 15(' 1/

NOT ESTAB 2 ~ 15(

2 ~ 15- F 15 7 MILES NNV F

~ 15- 2 '5 1)

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

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

Figure 6.

ANNIAL AyERAGE =

Operational 'ROSS HETA kTIVITY Preoperational Phase Phase I N HRI tKI IG MATER.SUPPLIES ~

CO C

o 1haum FERRY Nun.EAR Purr C I JJ o CS W JJ JJ (0 C IJ CIJ o

JJ c o Cl

'o c I o.

'L 1 8 19 9 19 0 1 1 19 2 19 3P 19 30 19 4 1 5 19 6 -

1 7 .19 8' 9 '19 0 1 1.- '2

38 Piguro 7 Oirect Rodtotion Levels Browns Ferry Nuclear Plont

.22 Onst te

'1

/1 I

C. \

1 I

)8 1 C7 6 1 It:

s j gr I '1

/

./ '1

~

i'1 I \

'5 i '1,d l/

16 I 1/' 1 0

5 I

I

<Offst te

'2 '1 976 1977 1978 1979 1988 1981 1982 Ptguru 8 Oirect Radiation Levels Brawns Ferry Nuclear Plant 8-Quarter Having Average 22 CT

.18 P.'~.4t Onstte

.r yW~ +c 0

It" r'.

)y rO,,R

~'r

.s, 16 EI Of f st te 12 1976 '977 1978 1979 1988 1981 ~

1982

39 Fteurc 9 Oif ect Radiation Levels Watts Bor Nuclear Plont 22 C

Onstte t

18 Cf rL S Offsiteo I 9

\

16 I

'ij II 12 1976 1977 1978 1979 , 1988 1981 1982 Fteurc 10 2t Dtrect Radiation Levels Watts Bor Nuclear Plant

'I-Quarter Moving Average

'22 Onstte o

t ft"9 g 18 CS /./

K s

Of fsI te o-.o..~ tf

/

0 .o-~ ~ ~o o+ p o 16

/

e. /

/

tr 12 "'1981 1982 1976 1977 1978 1979 1986

I 41 Reservoir Monitorin Samples are collected from the Tennessee River as detailed in

.table 21. Samples collected for radiological analysis include plankton from three of these cross sections and bottom fauna and sediment from four cross sections. The locations of these cross sections are shown on the accompanying map (figure ll) and conform to sediment ranges establi:shed and surveyed by TVA.

Water Water samples are col'lected automatically by sequential type sampling devices at three cross sections and composite samples analyzed monthly for gross beta and gamma-emitting radionuclides. Further composites a'e made quarterly for strontium and tritium analyses. In addition to these r'equired samples, grab samples were also collected monthly from the vicinity of the plant discharge to the Tennessee River, and at a point on the Elk River, and analyzed for gross beta, gamma-emitting radionuclides, and strontium. Results are displayed in table 22. Figure 12 presents a plot of the gros's beta activity in surface water from 1968 'through 1982. No gross beta measurements were made'n surface water samples in 1978. The levels reported are consistent with gross beta levels measured in surface water samples taken from the Tennessee River in preoper-ational monitoring programs conducted by TVA at other sites.

Fish Radiological monitoring for fish is accomplished by analysis of composite samples of ad>>lt fish taken from each of three contig>>ons reser'-

voirs--Wilso>>, Wheeler, <<>>d Guntersviile. No perma>>ent sampling statlo>>s have been established within each reservoir; this reflects the movemeht of fish species within reservoirs as determined by TVA data from the BFN preoperational monitoring program. Two species, white crappie and'mallmouth buffalo, are collected representing both commercial and game species. Sufficient fish are collected in each reservoir to yield 250 to 300 grams oven-dry weight for analytical purposes. All samples are collected semiannually. and, analyzed for gamma-emitting radionuclides. The composite samples contain approximately the same quantity of flesh from each fish. For each composite a subsample of material is drawn for counting. Results are given in tables 23, 24, and 25.

Plankton As indicated in table 21, net plankton (all phytoplankton and zoo-plankton caught with a 100 ij mesh net) is collected for radiol'ogical analyses at each of three stations by vertical tows with a 1/2-meter net.. At least 50 grams (wet weight) of material is necessary for analytical accuracy. Samples are collected semiannually and submitted for gross beta analysis, and when quantities are sufficient, for gamma activity and Sr and oSr content.

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

42'ediment Sediment samples are collected from. Ponar dredge hauls made for bottom fauna. Gamma radioactivity and Sr and Sr content are determined semiannually in composite 'samples collected fromm each of four stations.

Locations, of thesestations are shown in table 21. Results are shown in tabl'e 26.

Bottom, Fauna.

The flesh, and shells of Asiatic clams collected, semiannuallyc from the cross sections at four stations (table 21) are analyzed for gamma-emitting, radionuclides. Levels of Sr and o Sr are- determined on the shells, and on

, the flesh when, sufficient amounts were avail, able.. A 50-gram (wet weight) sample provides sufficient activity for counting. During this reporting period, two samples of clam flesh contained insufficient volume. for analysis.

Results are given in t'ables 27 and 28.

Table 21.

SAMPLING SCHEDULE RESERVOIR MONITORING Biolo ical sa les (collected semiannuall )

Zooplankton, chloro'phyll, Benthic Water Samples River/river mile phytoplankton fauna Sediment Pish (collected monthly)

,Tennessee 277.9 Tennessee 285.2 b Tennessee 288.7 X Tennessee 291.7 X Tennessee. 293.5 Tennessee 293.7 (discharge area)

Tennessee 305.0

. (Control)

Tennessee 307.5 X (Control)

Elk 20.5 c (Control)

a. Gill net and/or electroshocker will be used for collection. 'amples of fish are collected from Guntersvil'le, Wheeler, and Wilson Reservoirs.

.b. Automatic sampler.

c. Grab sample.

TABLE 22

'OCKET RADIOACTIVITY IN SURFACE VATER TOTAL PC I/L - 0 037. eO/i

.NAME OF FACILITY ~ROMPS FLURRY NO ~

50 2$ 9AQQ@296 LOCATION OF FACILITY~I+<STONQ A~ABAHA REPORTING PERIOD ~9/

TYPE AND LOMER L IHIT ALL CONTROL NUYBER OF TOTAL NUYBER OF INOICtTOR LOCATIONS 0 ATION 0 MITH HIGHEST ANNUAL HEAN LOCATIONS NONROUT INE OF ANALYSIS DETEC TI ON vEAN (F)b . NAHE MEAN ($ ) HEAN (F)b REPORTED RANGEb. QISTANCE ANO DIRECTION RAt4GC RANGE HEAS~UR NTS GROSS BETA 2 ~ 400 3 69( 35/ 39) TRH 285+2 4 '1(

'2- 12/ 13) 3 '3(

'2- 20/ 26)

~Y GAHHA (NAI) 65 2

~

~ 4'7-. 8 ~ 35 2 8+35 2 6 '5 FE-59 NOT ESTAB 5 ~ AOl 70-3/

10 '0 24) TRYi 293+5 10 ~ 70(

10 F 70-1/ 7) 4 '8(

00-5/ 20)

F 10 F 70 F 7 50 I-131 15 F 000 16 '0(

'G- 16(70 1/ 24) TRYi 293 ' 16+70(

'0- 1/ 9) 2C VALUES <LLD F

16 BFN OISCHAPGE 16 16 F 70 GAYHA (GELI) Iles 21 LA-140 7 000 13 ~ 64 ( 1/ 15) 'TRH 293 ' 13o64( 1/ 4) 6 VALUES <LLD K-40

~

NOT ESTAB 13 +64-,1 3 19 ~ 68( 2/

64 15)

BFN DISCHARGE TRH 285 '

13 22

'4

'6l 13 1/

i64 S) 13 75( 1/ 6) 16 '0- 22 '6 22 ~ 76- 22 F 76 13 '5-

~

13 '5 81-214 2Sl 1/ 15) 25l 1/ 51( 1/ 6)

PB-214 NOT ESTAB NOT ESTAB 4

4

~

~ 25-15 VALVES <LLO 4 ~ 25 TRH 293 ~ 5 4 4

~

~ 25- 4 '5 6) 2 2 51-

),I ~ 961 2

1/

'1 6) 96- 11 '6 PB-212 NOT ESTAB 16( 4/ 15) TRH 29347 2 '3( 1/ 4) 2 '1( 5/ 6)

SR 89 10 F 000 2 ~

'I ~ 55-12 VALUES <LLD 2 '9 BFN DISCHARGE 2 '3- 2 '3 2+35-8 VALUES <LLD 2 '6 20 ANALYSIS PERFORMED SR 90 2 ~ 000 12 VALUES <LLD 8 VALVES <LLO 20 ANALYSIS PERFORMED TR I T I\JH 2G 330 F 000 351 +8(

336 '93-S/

370 ~ 86

12) TRH 293 '

BFN DISCHARGE 362~22(

353 ~ 57-2/

370-86

4) 370 '3l 351 86-2/

390 F 00 8) 4 a.. Nominal Lover Limit of Detebtion (LLD) as described in Table 3.

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

TABLE23 RADIOACTIVIT'Y IN MHITE CRAPPIE'FLESH)

PCI/G - 0~ 037'O/G (DRY MEIGHT)

NAHE OF FACILITY PR~M~ Ff RRY DOCKET NO ~ 50-2~92~02'~9 LOCATION OF FACILITY L IHESTONE ALABAMA REPORTING PERIOD~1 TYPE 'AND LOMER LIMIT CONTROL NUHBER OF H~~gQT 100'LL TOTAL NUHBER OF INDICATOR LOCA/I ONS L~OA~Tg~NM T A ~NN AL Hg AN -LOCATIONS NON ROUTINE OF ANALYSIS DETECTION HEAN (F) MEAN (F)b REPORTED RANG+

(l LQ) RANGE GROSS BETA 0 ~ 34 '3(

'2-

- 4/

40 '5 4) MILSON PESERVOIR TPP 259-275 34 ~ 93(

29 '2 2/

40 F 55

2) 32~76(

2 l~3x 2/

4i,la 2) 6 29 .

(GELI)

GAHHA CS-137 6

0 '20 0+13( 4/ .4) MILSON RESERVOI'R 259-275 0 '4(

0.10-2/

F 17

2) 0 ~ 13(

Oi10 2/ ')

16 C ~ 15- 5 ~ 17 TRH 5 ~

'5( 4/ 4) 15 '5( 2/ 2) 14 ~ 36( 2/ 2);

K 40 NOT ESTAB 15 14 ~ 58- 16 '0 MHEFLER RES.

TRH 275-349 15 ~ 04- 16 F 86 13 '5- 1/')

15e26 PB-212 NOT ESTAB 0 F 01( 3/ 4) VHEELER RES 0 ~ 01C 2/ 2) 0 01(

0 ~ 01- Qo01 TRH 275-349 0~ 01- Qo01 0~01- 0 F 01 R A-22'6 NOT ESTAB 0 ~ 02( 2/ 4) MHEELER RES 0 ~ 02( 2/ 2) 2 VALUES CLLD 0 ~ 02- F 02 TRH .275-349 0 ~ 02- 0 F 02

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

b. Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified" locations is indicated in parenthese's (P).

T'ABLE 24 RADIOACTIVITY IN SHALLHOUTH BUFFALO (FLESH)

'CI/G - 0~ 037 BO/G (DRY MEIGHT)

NAME OF FACILITY BROVNS Ff DOCKET NO ~ 50-P59M260 ~ 296 OF FACILITY L~TN STOT!f RRY'OC/TION A~ABAHA REPORTING PER IOD~~98 TYPE ANO LOVER LIMIT ALL CONTROL NUMBER OF TOTAL NUMBER INDICATGR LOCATIONS NONROUTINE

) b LOCATION(

HE AN (F) REPORTED OF ANALYSIS OF'ETECT IONa HEAN (

(I LQ) RAA ~G EEISTANC~4M OIRECTIOM I!Al Of RANGE llfAS~UR tl NTS Pg~RF R~H 100 22 '6( 4/ 4) MHEELER RES 24 '8( 2/ 2) ZPM5](

'6- P/

'7 2)

GROSS BETA 6

0 ~

18 '9- 29 '1 TRH 275-349 19M76- 29 '1 21 23 GAHHA CS-137 (GELI) 6 0 ~ 020 0 04(

04-3/ 4)

QM,05 VHEELER RES TRH 275-349 0

0

~

~

04(

04-

'/ 0 F 05

2) 0 0

F 07(

'6- 2/ 2) 0 '9 2) f(-4 0 0 F 04(" 4/ 4) VHEELER RES 11 '5( 2/ 2) 9 57( 2/

9 '0 9 '3 NOT ESTAB 11 7 '6- 13 1/

'0 4)'

TRH 275-349 10 ~ 60-0 F 01(

IZ ~ 69 1/ 2)

PB-214 NOT ESTAB 01( MHEELER.RES 2 VALUES <L(.O 0F 01-01( 3/

0 '1 4) TRH 275-349 0 F 01

'2( 1/

0 ~ 01 2). 2 VALUES <LLO PB-212 NOT ESTAB 0F MHEEEER. RES 0 0 F 00-

'2( 1/

0 '2 4) TRH 275 349 0 ~ 02 0 ~ 32( 1/

0 02

2) 2 VALUES <LLO BE-7 NOT ESTAB .0 MHEELER RES 0 '2- 0 '2 TRH 275-3fs9 0 32- GM32 VALUES <LLD

.SR 89, 0 ~ 500 2 VALUES <LLO 0 ANALYSIS PERFORMED SR 90 0 ~ 100 2 VALUES <LLO 0 VALUES <LLD ANALYSIS PERFORHEO

a. MocIinal Lover Linit of Detection (LLD) as dcscribcd in Table 9.

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

TABLE 25 RADIOACTIVITY IN SHALLHOUTH BUFFALO (MHOLE)

PC I/G - C~ 037 80/G (ORY 'MEIGHT)

NAME OF FAG I LITY'ROMNS FERRY DOCKET NO ~ 50-2~59 260A296 LOCA /ION OF FACILITY~IH&TOHf AI A/AH/ REPORT ING PERIOD 19AP P

TYPE AND LONER LIHIT ALL CONTROL 'NUHBER OF TOTAL NUHBER OF INDICATOR LOCATIONS QOCATIOh MITH HIGHEST ANNUAL njAh hONRvUTINE ANALYSIS (F) b MEAN (F) LvCA TIDE OF DETECTION HEAN NAHE HE AN (() REPOR'TEO

,~(I 0)100 'ANGEb STANCE ANO DIRECTION RANGE RANGE MEASUREMENTS GROSS BETA 0 ~ 17 ~ 60( 4/ . 4,) MHEELER RES 20 13(

'3- 2/ '2) 17 '9( 2/ P)

'6.

6 14 ~ 94 20 ~ 43 TRH 275-349 . 19 20 16 F 81- .'18 GAHHA (GELI )

6 CS-137 0 '20 0 0

~ 03(

02-3/

0 '4 4) MHEELER RES TR)i 275-349 F

0 03(

02-2/

0 04

2) 0 '4(

'3- 2/ '4.2)'

6 '8(

~ 0 K-4 0 NOT ESTAB 4/

'9 4) MHEELER RES 7 '8( 2/

F

2) 6 '7( 2/ 2) 4 ~ 75- , 7 TRH 275-349 I ~ 56- 7 '9 2) 5 '2- 7 '3' 8 I-214 0~ 020 0F 08( 2/ 4) MHEELER RES 0~ 12( 1/

'2 2) '4( 1/, 2)

PB-21.4 . NOT ESTAB 0 ~ 03-v~02( 1/

0. ~ 12 4)

TRH 275-349 MHEELER RES

,0 ~ 12

'0 02(.

0 1/

0 2

F 04-VALUES 0 '4 (LLD 0 ~ 02- 0 ~ 02 -'TRH 275-349 0~ 02- 0+02 PB-212 NOT ESTAB C ~ 01( 4/ 4) MHEELER RES 0F 02( 2/ 2) 01( 2/ 2)

RA-226 0+01-2/

0 ~ (13 TRH 275-349 Oo 01-. 0 '3. 0 0

F F

'44 01- 0 F 01 0 F 08(

'2 4) v ~ 12( 1/ 1/

NOT ESTAB MHEELER RES 2) 0 2) 0+03 0 TRH 275-349 0 12- F 12 ' F 04- 0 F 04

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

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

c

'v

TABLE 26 RADIOACTIVITY IN SEOIIIENT PCI/G - 0 '37. BO/G (PRY )(EIGHT)

NAME OF'ACILITY QROk~ Ff RRY DOCKET. NO ~ 5'0"259',26~0 $ 96 LOCATION OF FACILITY, LIMESTONE ALABAMA REPORTING PERIOD~19 TYPE ANO LONER LIHIT ALL CONTROL NUHBER OF TOTAL NUPiBER OF INDICATOR LOCATIONS j O~A~TI N ~)I TH Hajj)(/~<AT'JNIJII XfAQ LOCATIONS NONROUTINE .

OF ANALYSIS BET EC T I.ON MEAN (() ME AN tg )P REPGRTED P f,~RF 0 1 L (I I 9) RAIJGE RAIJGE.

GAMMA (GELI )

8 CE-144 060' 0 '0( 2/ 6) TRH 293 ~ 7 20( 2/

'6 2)', 2 VALUES <LLO CO 60 c

0 ~

'10 G 15-23(

0 6/ 6)

'6 BFN TRH DISCHARGE 288 '8 0

0

~

'2(

~ 15- 0 2/ 2) 0 '3( 1/ 2)

G ~

0.08-09('/ 09 6). 0.51 0

13-G 4444(

~

Ci51 0 '3- . 0 F 03 CS-134 0 '80 0 TRM 293o7 09( 1/ 2) 2 VALUES <LLD CS-137

=

c 0 '9-

~

0 6/

~ BFN DISCHARGE

'8 G ~

0 ~ 09-94(

0 2/

'9 2'/ 2) 35(

'9-6) 277 2) Co16(

GiC20 TRM 1 ~

'1- 1 ~

lu- 2.79 '4- Ci18 K-40 NOT ESTAB ~

0 14 '7(

12 '1- '5 '1 2

6/ 6)

~

TRM 277 '8 ll 1 ~

15 '6 15 '1 0

15 '1(

14 '7-2/

16 '5 2)

ZN-65 0 '20 0 0

~ 08(

08-1/

0 F 08

6) TRM BFN 293 ~ 7 DISCHARGE C~

0 08(

u8

.if 08 n

2 VALUES <LLO 81-214 0 ~ 020.

F 1 ~ 30(

1 ~ 13- -

6/

1 '5 6) TRY, 277 ~ 98 . i'5(

1

~

25-2/

1 ~ 45

2) 1 ~ 22( 2/

1 ~ 40 2)

BI-212 lo85( 6/ 6) 89( 2/ li75( 2/

0 100

~

1 ~ 61- 2ou6 6/

TRM 288 ~ 78 1 ~

1 ~ 78- 2 ~ 01 2/

2) 1 ~ 39-lo31(

2 il2)2)

PB-214 NOT ESTAB 36( 6) 7RH 277o98 1,53( 2) 2/

1 ~

0 '7- lo57

'8 1 ~ 46" 1 ~ 57 1 ~ 15- 1 ~ 46 PB-212 NOT ESTAB 1 ~ 56( ' 6/ 6) TRH 277 1 ~ 78( 2/ 2) 1.47( 2/ 2) 1 ~ 20- ~ 89. 67 89 1 ~ 30- 64 277 '8 1 ~ 1 ~ ~ 1 ~

RA-226 NOT ESTAB 1 ~ 30( 6/ 6) TRM 35( 2/ 2) o22( 2/ 2)

' i13- o45 1~

25- 45 .

1 1.05- 'I 40 RA-223 NCT ESTAB 0 '8(

1 3/ 6) TRH 293 '

1 0 '3( 1 ~

2/ 2) 'ot 1/

~

2)

RA-224 NOT ESTAB G ~ 56-83(

0 '9 5/ 6)'

BFN DISCHARGE 293o7 loC4(

56- O)89 1/ 2) 0 0

~ 29-I ~ 72(

0 1/

'9 2)

F TRM 43- F 02 BFIJ DISCHARGE 1 ~ 94- 94 1 72- 1 72 TL-208 0 '20 0

~

'6(.

'4- 6/ 6) TRH 277 ~ 98 ei60(

1 ~

2/ 2) 0 '9( 2/

~

2)

AC-228 0~ 060.

0 F 62(

0 6/

'1

6) TRM 277o98 C ~

1~

59-70(

0 2/

'1 2) 0~

1 45-51( "

2/

0 ~ 53 2) 1 ~ 37- 1 ~ 75 1~ 65- 1 ~ 75 29- 1 ~ 73 A-234 H NOT ESTAB 3 '0( 1/ 6)' TRH 293 ~ 7 3 '0( 1/ 2) 4i64( 1/ 2)

P

'0

~

SR 89 1 F 500

'0'=

2il3(

~ 3

'1/ 6)

'0 BFN 0 ISCHARGE TRM 293i7 3

2

'07

'3( 3 1/ 2) 2 64-VALUES <LLO 4 i 64 SR 90 8

0 ~ 300 2o13-6 VALUES <LLD 2 '3 BFN DISCHARGE 2i13- 2i13

(' 34 ( 1/ 2) 8- Co34- 0 ~ 34

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

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

c. The distribution of Co and Cs between indicator and control locations reported herein is comparable to the distribution reported in the preoperational monitoring program from 1968 to mid-1973. The levels repoited,are .also comparable with levels reported in samples from the Tennessee River in 'preoperational monitoring programs conducted by TVA ai other sites.

n

TABLE 27 RADIO'ACTIVITY IN CLAM FLESH PCI/G - 0 ~ C37 BQ/G (DRY 'AJEI GHT)

NAIIE OF FACILITR B~RIINS FERVOR DOCKET NON~P~~Q~9 LOCATION OF FACILITY LIHESTONE ALABAHA REPORTING PERIOD 1982 TYPE AND LOlJER LIMIT ALL CONTROL. NUMBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCATION lJITH HIGHEST ANNUAL HEAN LOCATIONS NONROVTINE

([)

OF ANALYSIS EKEEQEHKR GAHHA (GELI)

~2)

DETECTION MEAN RANGE REPORTED 6

C0-60 0 F 080 0 0

'8(

24-2/

0 '3 4) TRH 293NT BFN DISCHARGE 0N53(

0 53-1/

0 '3 2) 2 VALUES <LLD CS-137 0 ~ 080 0 0

~

~ 17(

17-I/ '7 4) 0 TRH 288 '8 0 0

~

~ 17(

~ 17-I/ 1) 0 '7 2) 2 VALUES <LLD 2 '7( 4/ 2/ 34( 2/

K-40 NOT EST AB 1~ 11 4~ 53

4) TRQ BFN 293N7 DISCHARGE 2N82(

1~ ll- '3 4 2

2 '4-

~

2 '5 2)

ZN-65 0 ~ 170 1 ~ 33( 2/ 4) TRH 293 ' 1~ 67( 1/ 2) 2 VALUES <LLD ON98- lN67 BFN DISCHARGE 1 67- 1 ~ 67 BI-214 0 ~ 42( 3/ 4) 288 'S

~

76( 1/ 1) '9( 2/ 2)

PB-214 NOT ESTAB 0 01-

'9(

~ 0 4/

~ 76 4)

TRH TRH 288 '8 0 F 0~76 0.80(

0 1/

'6 1) 0 0 '2-

'4( 2/QN37 2)

NOT ESTAB 0 3 CN21- 0 ~ 80 0 ~ 80- 0 1/

~ 80 0~ II-

'2(

0 '8 I/ 2)

PB-212 0 ~ 66( 2/ 4) TRH 288 F 78 F 87( 1) 0 NOT ESTAB 0 4R 0 2/

F 87

4) '8 0

0 ~ 87-0.76(

0 1/

'7 I) 0~ 22- 0 ~ 22 RA-226 NOT ESTAB 0 ~ 39( TRH 288 2 VALUES <LLD 01- ON76 0 ~ 76- 0076 288 '8 0 ~

TL-208 13( 3/ 4) TRH 0~ 18( 1/ 1) 0 16( 1/ 2)

NOT ESTAB 0 0

~

~ 10 F 18 2/

0~ 18-

'1( 1/ 1)

~ 0 '8 F

~

16- '- 0 ~ 16

'1 4)

AC-228 0 ~ 31( TR'( 288N78 0 2 VALVES <LLO NOT ESTAB ON21- 0 ON41 0 '1

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

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

TABLE 28 RADIOACTIVITY IN CLAH SHELL PCI/G - 0 ~ 037 BO/G (ORY WEIGHT)

NAME OF FACILITY BROWNS F jttRY DOCKET NO ~ 50-259 260 796 LOCATION OF FACILITY~I V~STONf A~ABAHA REPORTING PERIOD~9//

LOWER LIHIT ALL CONTROL NurBER OF TYPE AND NONROUTINE OF INDICATOR LOCAbTIOtiS LOCA T I Ot( WITH HIGHEST ANNUAL HEAN LOCATIONS TOTAL NUMBER EAtt (F) b OF ANALYSIS DETECTION t'EAN ([) NAHE DISTANCE AttO DIRECTION HEAN (IF)

RAt(GE RANGE REFORTED rEAsUREHEt(Ts (Q~L) RANGE GAHHA C0-60 (GELI )

8 0+010 0 0

'8(

~ 02-2/

<<J ~

')

13 TRV 293 '

BFN DISCHARGE 0 '3(

0>>13-

'2(

1/

2/

Oil3 2) 2)

2 VALUES <LLD 1 ~ 51( 1/ 2)

K-40 NOT ESTAB 0.22( 3/ 6) TRH 288 F 78 0 15- 0~ 15- 0 30 1~51- I ~ 51

'50 C ~

'7( 5/

0 ~ 0

6) TRr..288.78 '8( 2/

~

2) 0 '7( 1/ 2)81-214 0 0 07- "~ 45 0

0~ 10- 0 '5 0 67-

'7( 0 F 87 PB-214 0 '50 0 ~

0 '2(

07-5/ 6) TPH 288 '8 0 '0(

13-2/

0 68

2) 0 0 '7- 2/

0 '7 2) 0 ~ 68 0~

'1(

F PB-212 NOT ESTAB 0 ~

11( 5/ 6) TRH 288 '8 0 2/ 2) '2.(

'0 '2-0 1/

'2 2) 0 '9 0 ~

04- 0~ 12- 0 29 0 0 '8(

~

0 ~

RA-226 0 F 050 0 '7(

07-5/

'5 6)6) TRH 288o78 0 10-2/

0 '5 2)2) 2 VALUES <LLO TL-208 0 '20 G ~

0 '5( 5/

0 TRH 288 '8 0F

~

05(

0 ~ 05-2/

'6 2. 2 VALUES <LLD C2- 06 0 288 '8 0

AC-228 0 '60 0 ~

0.18( 5/

~

6) TRV, 0 '7(

24-2/

'0 2) 0 ~ 10(

10-1/

10 2) 09- 0 ~ 30 0 0 CD 0 ~

89 5 F 000 0

5

~

'5( I/ 6) TRH 277.98 5 '5(

~

1/

'5 2) 2 VALUES <LLD SR 000 5 ~ 25-I ~ 66(

5 '5 6/ 6) TRH 288 '6 5 25-1~

~

86( 2/

5 1 ~ 36( 1/ 2) 90 SR 1 F I ~ 19- 2 '0 I ~ 63- F 10 I ~ 36- I ~ 36

a. Honinal Lower Lini.t of Detection (I.LD) as described in Table 3.

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

Pigure 1l R ESERVOI R MONITORING 'ETWORK Elk River WHEELER DAM mile 274.90 mile 277.98 Rogersville 0

mile 29l,76 Athens rnite. 282.6 0

~mi(e 285.2 B;F,. NUCLEAR PLANT 8

Champion Paper Co.

ile 288.7B mite 293.50 0

Cour tland mile 305.0 fnile 295.70 Decatur rnite 307.52 Scale of Miles

~ - Automatic Sam ler 0

Eigure 12 ANNNL AVERAGE Qperational ASS SETA ACjlVITY Preoperational O CO Phase IN SURFACE 1'IATER C Phase 0

EemS FERRV i"IUCLEAR I'ueT C

C V) o V

c ov o V C

'C O Average:

Preoperational Phase 7$

C 7

1968 1969 1970 ,1971 1972 1973P 19730 1974 1975 1976 1977'978 1979 1980 1 81 19 2

a. No gross beta measurements made in 1978.

, ~~

53 F

A quality .control program has been establi.shed with the Alabama Department of Public Health Environmental. Health Admini'stration Laboratory and the Eastern Environmental Radiation Facility, Environmental Protection Agency, Montgomery, Alabama. Samples, of air, water, m'ilk, and ve'getation collected around BFN are 'forwarded to these laboratories for analysis, -and results are exchanged foi comp'arison.

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

We cari expect that background concentrations would be distributed within these

~ limits'. This provides us the basis for comparing control and indicator data.

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

Conclusions A vast majority of the indicator station data was found to be within the distribution defined by the control station data. The data analysis software identified concentrations slightly exceeding the limits of the control station data for a small number of radionuclides in samples from indicator stations. Many of these values may be discounted because the error 'reported by the analysis program was greater than the calculated concentration. The remaining isolated elevated concentrations may be the result of fallout, fluctuations in the existing environment, computer program artifacts, or.

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

Dose estimates were made from concentrations of radioactivity found in samples of environmental media. Media sampled include, but are not limited to,'ir, milk, meat, vegetation, drinking water, and fish. Doses estimated for persons at the indicator locations were essentially identical to those determined for persons at control -locations. Greater than 99 percent of those doses were contributed by the naturally occurring radionuclide potassium-40,

54 and.'y, stronti.um-90'nd'esium-137 which are long-, lived radioisotopes f'ound in fallout from nuclear'eapon testing.

Zt is concluded from; the above analysis. of the d'ata and; from, the trend; plots'resented'. earlier that there were no measurable increases in the'xposure to, members oE the general public attributable. to the operation'..

of BFN. Indications. of the presence of smal'1 quantities of fission products:

have been seen. in'quatic media (for example, A'siatic cl'ams)'. The were extremely low for. example near the nomimal lower limits. of levels'easured, detection and: several hundred'imes lower than the reporting levels outlined'y the Nuclear Regulatory; Commission. No~ increases of radioactivity. have been.

seen: in water samples. These media wi:ll. be monitored: closely for indications of, increases,.

TENNESSEE VALLEY AU HORI CHATTANOOGA, TENNESSEE 37AO 400 Chestnut Street Tower II May 3, 1983 U.S. Nuclear Regulatory Commission Region II ATTN: James P. O'Reilly, Regional Administrator 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30303

Dear Mr. O'Reilly:

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

Environmental Radioactivity Levels, Browns Ferry Nuclear Plant, Annual Report 1982 This monitoring program is specifically responsive to the recommendations and requests of the United States Fish and Wildlife Service. We understand that the Office of Nuclear Reactor Regulation will transmit five copies of the report to the Secretary of the Interior.

Very truly yours, TENNESSEE VALLEY AUTHORITY L. M. Mills, M nager p>>;,

Nuclear Licensing ( <<'>7 l;-J Enclosure >>yt cc: Director of Nuclear Reactor Regulation (20)

Attention: Mr. Darrell G. Eisenhut, Director Division of Licensing U.S. Nuclear Regulatory Commission Washingtoh, D.C. 20555

+il ppp[QQjL C An Equal Opportu ity Employer

a N

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