ML18032A682

Environ Radioactivity Levels Annual Rept for 1984. W/ 850410 Ltr

ML18032A682
Person / Time
Site:	Browns Ferry, Pilgrim
Issue date:	12/31/1984
From:	Hufham J TENNESSEE VALLEY AUTHORITY
To:	Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
NUDOCS 8712300217
Download: ML18032A682 (67)

Text

1 1 REGUL l RY INFORMATION DISTRIBUTI SYSTEM (RIDS)

ACCESSION NBR 8712300217 DOC. DATE: 85/04/10 NOTARIZED: NO DOCKET FAC IL: 50-259 Browns Ferry Nuclear Power Stationi Unit ii Tennessee 05000259 50-260 Browns Ferry Nuclear Power Station> Unit 2i Tennessee 05000260 50-296 Browns Ferry Nuclear Power Stationi Unit 3i Tennessee 05000296 AUTH. NAME AUTHOR AFFILIATION HUFHAME J. W. Tennessee Valley Authority RECIP. NAME RECIPIENT AFFILIATION QRACEi J. N. Region 24 Ofc of the Director

SUBJECT:

Forwards Environ Radioactivitg Levels monitoring rept.

Program specifically responsive to recommendations 5 requests of US Fish 8c Wildlife Svc.

DIBTRIBUTION CODE: IE48D COPIER RECEIVED: LTR i ENCL l SIZE: Cc72 TITLE: 50. 36a(a) (2) Semiannual Ef fluent Release Reports NOTES: G. Zech 3 cg. 1 cg. ea to: Ebneteri Axelradi S. Richardson 05000259 B. D. Liawi K. Barri Donohewi OI.

Q. Zech 3 cg. 1 cg. ea to: Ebneteri*xelradi S. Richardson'.

05000260 D. Liawi K. Barr4 Donohewi OI.

G. Zech 3 cg. 1 cg. ea to: Ebneter4 Axelrad4 S. Richardsoni 05000296 B. D. Liawi K. Barry Donohewi OI.

REC IP IENT COPIES REC IP IENT COP IES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL JAMERSONZ C 0 PD 5 5 GEARSI G 1 1 STANG> J 1 1 INTERNAL: ACRS 1 1 AEOD/DOA 1 1 AEOD/DSP/TPAB 1 ARM TECH ADV 1 1 NRR/DEST/PSB 1 NRR/DREP/RPB 4 4 NRR/PMAS/ILRB 1 1 01 1 RGN2 F ILE 02 1 RSS/EPRPB 1 1 EXTERNAL: BNL TICHLER> J03 1 LPDR NRC PDR 1 NOTES: 10 10 TOTAL NUMBER OF COPIES REQUIRED: LTTR 34 ENCL 33

I I

TENNESSEE VALLEY AUTHORITY CHATTANOOGA. TENNESSEE 37401 400 Chestnut Street Tower t.

II April 10, 1985 U.S. Nuclear Regulatory Commission Region II ATTN: Dr. J. Nelson Grace, Regional Administrato 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30303

Dear Dr. Grace:

Enclosed is a copy of the following report prepared by <<he Tenness~~

Valley Authority pertaining to the environmental monitor ng at the Browns Ferry Nuclear Plant:

4 Environmental Radioactivity Levels, Browns Ferry Nuclear Plant, Annual Report 1984 This monitoring program is specifioally responsive to the recommendations and requests of the United States Fish and Wildlife Service. We understand that the Office of Nuclear Reactor Regulation will transmit five copies of the repor t to the Seer etary of the Interior.

Very truly yours, TENNESSEE VALLEY AUTHORITY J. W. Hufham, Manager Licensing and Regulations Enclosur e cc: Directo'r of Nuclear Reactor Regulation (Enclosu e: 20)

Attention: Ilr. Hugh Thompson, Director Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555 1983 TVA 50TH ANNIVERSARY An Equal Opportunity Employer

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ENVIRONMENTAL RADIOACTIVITY LEVELS BROWNS PERRY NUCLEAR PLANT ANNUAL REPORT - 1984 TVA/NUC PR/RH F'DR ADQcg 0 R PDR April 1985

CONTENTS List of Tables iii List of Figures. 1.v Introduction Atmospheric Monitoring Terrestrial Monitoring 23 Reservoir Monitoring 43 Quality Control.

Data Analysis. 55 Conclusions. 55

LIST OF TABLES Tab l.e I - Environmental Radioactivity Sampl.ing Schedule Table 2 - Atmospheric and Terrestrial Monitoring Station Locations - Browns Ferry Nuclear Plant . 4 Table 3 - Detection Capabilities for Environmental Sample Analysis Table 4 - Results Obtained in Interlaboratory Comparison Program 7 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 Table ll 12 -

- Radioactivity Radioactivity in in Vegetation Soil 27 28 Table 13 - Radioactivity in Well Water 29 Table 14 - Radioactivity in Public Water Supply 30 Table 15 - Environmental Gamma Radiation Levels 31 Table 16 Radioactivity in Cabbage 32 Table 17 - Radioactivity in Corn 33 Table 18 - Radioactivity in Peaches ~ . 34 Table 19 - Radioactivity in Peas 35 Table 20 Radioactivity in Potatoes 36 Table 21 - Radioactivity in Poultry 37

'fable 22 - Radioactivity in Tomatoes 38 Table 23 - Sampling Schedule - Reservoir Monitoring ~ . 45 Table 24 - Radioactivity in Surface Water 46 Table 25 - Radioactivity in Wh'ite Crappie (Flesh) 47 Table 26 - Radioactivity in Smallmouth Buffalo (Flesh) 48 Table 27 - Radioactivity in Smallmouth Buffalo (Whole) 49 Table 28 - Radioactivity in Sediment 50 Table 29 - Radioactivity in Clam Flesh . 51 Table 30 - Radioactivity in Clam Shell ~ . 52

LIST OF FIGURES Figure 1

- Tennessee Valley Region 10 Figure 2 - Atmospheric and Terrestrial Monitoring Network l8 Figure 3 - Local Monitoring Stations 19 Figure 4 - TLD Locations, BFN 20 Figure 5 - Annual Average Gross Beta Activity in Air Filters, Browns Ferry Nuclear Plant 21 Figure 6 - Annual Average Gross Beta Activity in Drinking Water, Browns Ferry Nuclear Plant 39 Figure 7 - Direct Radiation Levels, BFN 40 Figure 8 - Direct Radiation Levels, BFN (4-quarter Moving Average) 40 Figure 9 - Direct Radiation Levels, WBN 41 Figure 10 - Direct Radiation Levels, WBN (4-(}uarter Moving Average) 41 Figure ll - Reservoir Monitoring Network 53 Figure 12 - Annual Average Gross Beta Activity in Surface Water

0 ENVIRONMENTAL RADIOACTIVITY LEVELS BROWNS FERRY NUCLEAR PLANT ANNUAL REPORT 1984 Introduction The Browns Ferry Nuclear Plant (BFN), operated by the Tennessee Valley Authority, is located on a site owned by TVA containing 840 acres of land in Limestone County, Alabama, bounded on the west and south by Wheeler Reservoir (see figure 1). The site is 10 miles southwest of Athens, Alabama, and 10 miles northwest of Decatur, Alabama.

The plant consists. of three boiling water reactors; each unit is rated at 3,293 MWt and 1,098 MWe. Unit 1 achieved criticality on August 17, 1973, and began commercial operation on August 1, 1974.

Unit 2 began commercial operation on March 1, 1975. However, a fire in the cable trays on March 22, 1975, forced the shutdown of both reactors. Units 1 and 2 resumed operation and Unit 3 began testing in August 1976. Unit 3 began commercial operation in January 1977.

The preoperational environmental radiological monitoring program established a baseline of data on the distribution of natural and manmade radioactivity in the environment near the plant site.

However, seasonal, yearly, and random variations in the data were observed. In order to determine the potential increases in environmental radioactivity levels caused by the plant, comparisons were made between data for indicator stations (those near the plant) and control stations (those remote from the plant) in conjunction with comparisons with preoperational data.

Radiological Health (Office of Nuclear Power) and the Office of Natural Resources and Economic Development carried out the sampling program outlined in tables 1 and 23. Sampling locations are shown in figures 2, 3, 4, and ll, and table 2 describes the locations of the atmospheric and terrestrial monitoring stations. All the radiochemical and instrumental analyses were conducted in TVA's Western Laboratory (WARL) located in Muscle Shoals, Alabama.

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

Nuclear 'Data (ND) Model 6700 system, in conjunction with germanium detection systems, were used to analyze the samples for specific gamma-emitting radionuclides. Specific analysis for iodine-131 in charcoal filters is performed using NaI(Tl) well detector systems attached to single channel analyzers. A TVA fabricated beta-gamma coincidence counting system is utilized for the determination of iodine-131 concentrations in milk.

Data were entered in computer storage for processing specific to the analysis conducted. The data obtained by -germanium detectors were resolved by the appropriate analyzer software and the software program routine HYPERMET.'

The detection capabilities for environmental sample analyses given as the nominal lower limits of detection (LLD) are listed in table 3. All photopeaks found in germanium spectra were identified and quantified. Many of the isotopes identified )by germanium spectra'l analysis are naturally occurring or naturally produced radioisotopes, Be 4oK 212Bi 214Bi 212pb 214pb 226Ra etc LLDs for radionuclides identified by Ge(Li) analysis were calculated for each analysis and nominal values are listed in table 3B. In the instance where an LLD has not been established, an LLD value of zero was assumed.

A notation in a table of " values <LLD" for an isotope with no established LLD does not imply a value less than 0; rather it indicates that the isotope was not identified in that specific group of samples.

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

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

This program provides periodic cross-checks on samples of the type and radionuclide composition normally analyzed in an environmental radio-logical monitoring program. Routine sample handling and analysis pro-cedures were employed in the evaluation of these samples. The results received during calendar year 1984 are shown in table 4. The +30 limits based on one measurement were divided by the square root of 3 to correct for triplicate determinations.

Table 1 ENVIRONMENTAL RADIOACTIVITYSAMPLING SCHEDULE Air Charcoal Rain- Heavy Particle River Well Public Aquatic Life Station Locations Filter Filter water Fallout So'1 V~eetation Milk 'Water Water Water and Sediment Foods Muscle Shoals M M M Lawrenceburg M M Rogersville M M M Athens M M M Decatur M M Courtland M M M Site 1 (N) M M M Site 2 (NNE) M M Site 3 (ENE) M M Site 4 (NNW) M M Site 5 (WSW) M M M Farm B M

Farm S"'arm P M Farm L M M

Farm E Farm W M

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

Various local Farms

" Weekly M - Monthly (Every 4 Weeks) Q

- Quarterly S - Semiannually A - Annually W

"'Discontinued operation November 1984

Table 2 ATHOSPNERIC AND TERRESTRIAL MONITORING STATION LOCATIONS BROWNS FERRY NUCLEAR PLANT Approximate Distance Approximate Direct,'ion Sam le Station From Plant From Plant LH-1 BF, North 1.0 Mile ( 1.6 kilometers) N LH-2 BF, North-Northeast 0.9 Hile ( 1.4 kilometers) NNE LH-3 BF> East-Northeast 1.0 Mile ( 1.4 kilometers) ENE I.H-4 BF> North-Northwest 1.7 Hiles ( 2.7 kilometers) NNW I.M-5 Bl', West-Southwest 2.5 Hilcs ( 4.0 kilometers) WSW PH-1 BF> Rogersvillc, AL 13.8 Hiles (22.2 kilometers) NW PH-2 BF> Athens, AL 10.9 Hiles (17.5 kilometers) NE PH-3 BF> Decatur (Trinity), AL 8.2 Hiles (13.2 kilometers) SSE PH-4 BF> Courtlan<1, AL 10.5 Miles (16.9 kilometers) WSW RH-1 BF> Huscle Shoals, AL 32.0 Hiles (51.5 kilometers) W (Control)

RM-2 BF, Lawrenceburg, TN 40.5 Hiles (65.2 kilometers) NNW (Control) g>

Farm 4.75 Hiles ( 7.6 kilometers) N S"'arm B 7.0 Miles (11.3 kilometers) NW Farm 1. 5.0 Hiles ( 7.0 kilometers) NE I'arm P 8.8 Miles (14. 1 kilometers)

Farm E 6.1 Miles ( 9.8 kilometers) NE Farm W 6.9 Miles (11.0 kilometers)

Var>a N (Control) '7.0 Miles (43.4 kilometers) NW Farm J (Control) 40.0 Hiles (64.4 kilometers) NNW Farm C (Control) <<32.0 Miles (51.5 kilometers) 'N Farm Ca (Control) 32.0 Hiles (51.5 kilometers) W Farm Cb (Control 22.5 Miles (36.2 kilometers E Farm M (Control) 22.5 Miles (36.2 kilometers) ENE Discontinued operations November 1984

Table 3 DETECTION CAPABILITIES FOR ENVIRONMEhTAL SAK1PLE ANALYSIS A. S ecific Anal ses NOMINAL LOWER LIMIT OF DETECTION LLD)*

Fish Air Vegegation Soil and Clam Flesh, Foods, Meat, Particulates Charcoal Fallout

~CK/ ~Ci/ C /K, /rri/K Water and Grain IK~ci F~Dr Sediment Kerr/

Plankton, DrKD p~Ci/ i~Dr D

Clam Kerr/

Shells r

DDr Poultry, r~cr/K D*r Milk Kcr/r Gross e 0.005 2.0 0.05 0.35 0.1 0.7 Gross B 3H 0.01 0.05 '.3 0.20 0.70 0.1 0.7 25 330 1311 0.02 0.05 89Sr 0.005. 10 0.25 1.5 0.5 5.0 40 10

>>Sr 0.001 2 0.05 0.3 0.1 1.0 8 2

~A11 LLD values for isotopic separations are calculated by the method developed by Pasternack and Parley as describ'ed in HASL-300. Factors such as sample size, decay time, chemical yield, and counting efficiency may vary for a given sample; these variations may change the LLD value for the given sample. The assumption is made that all samples are analyzed within one week of the collection date. ,Conversion factors:

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

Table 3 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS B. Gamma Anal ses NOMINAL LOWER LIMIT OF DETECTION (LLD Air Water Vegetation Soil and Clam flesh Foods (tomatoes Meat and particulates and milk and grain sediment Fish and plankton Clam shells potatoes, etc.) poultry

~ct/ot ~CL/t ~ct/ de ~ct/~dct f>~Ci/,~dr ~Ci/~dry p~Ci/ drrr Ct/N e ~dt/ ee NaI* ~Ge Li ** NaI ~Ge Li . NaI ~Ge Li NaI ~Ge Li Net ~Ge Lt N t ~G* Lt NaI ~Ge Li NaI Ge(Li) NaI ~Ge Li 141'144Ce 0.03 38 0.55 0.35 0. 35 0.35 38

>>4ce O.O2 33 0.22 0.06 0.06 0.35 0.06 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 90 131I 103 '06Ru Ru 0.01 0.04 0.01 0.03 15 40 8

40 0.35 0.65 '.45 0.09 0.51 0.20 0.02 O.ll 0.20 0.45 0.02 0;11 0.07 0.74 0.20 0.45 0.02 0.11 15 40 40 20 90 134Cs 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 137Cs 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 962r-Nb 0. 01 0.20 0.12 0.12 0.12

>>Zr O.O1 0.01 10 10 5 <

0. 11 0.05 0.03, 0.01 0.03 0.01 0.15 0.07 0.03 0.01 10 10 5

40 20 15 58Co 0.02 0.01 15 5 0.23 0.05 0.20 0.01 0.20 0.01 0.07 0.20 0.01 15 5 55 15 6"Mn 0.02 0.01 10 0.20 0.05 0.15 0.01 0.15 0.01 0.08 0.15 0.01 10 5 40 15 662n 0.02 0.01 15 9 0.25 0.11 Q.23 P.02 0.23 0.02 0.17 0.23 0.02 15 9 70 20 6 Co 0.01 0.01 10 5 0. 17 0. 06 . 0. 11 0. 01 0.'ll 0. 01 0.08 0.11 0.01 10 5 30 15 40K 140Ba-La

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2. 50 0.68 0.34

'.150. 90 0.07 0.90 0 )5 0.07 0.30 0.90 0.15 0.07

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150 15 25 400 50 50 140) 0.01 7 0.08 0.02 0.02 0.10 0.02 7 15

~e NaI(T1) LLD values are calculated by the method developed by Pasterna and Harley as described fn HASL-300 and Nucl. Instr. Methods 91, 533-40 (1971). These LLD values are expected to vary depending on the ac 'vitfes of the components in the samples. These figures do not represent the LLD values achievable on a given sanple. Water is counted in a 3.5-1 Marinelli beaker. Vegetation, fish, soil, and sediment are counted fa 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, tIten corrected to wet weight using an average nofsture content of 702. Average dry weight is 250 grams. Air particulates are counted in a [sell crystal. The counting system consists of a nultichannel analyzer and either a 4" x 4" solid or 4" x 5" well NaI(T1) crystal. The counting time is 4000 seconds. All calculations are performed by .

the least-squares computer progran ALPHA-M. The assumption is made that all samples are analyzed within one week of the collection date.

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~~e 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 sanples. These figures do not represent the LLD values achievable on Water is counted in either a 0.5-L or 3.5-L Marinelli beaker. Solid samplesd such as soil, sediment, and clam shells, are counted given samples.

Marinelli beaker as dry weight. The average dry weight fs 400-500 grams. Air filters and very small volume sanples are counted fn inpetri a 0.5-L dfshes centered on the detector endcap. The counting system consists of a ND-6620 nultichannel analyzer and gdrnaniun detector having an 20 percent. The counting time is normally 4'-15 hours. All spectral analysis fs performed using the software program HYPERMFT efffcfency of The assumption is made that all samples are analyzed within one week of the collection date.

Conversion factor: 1 pCi ~ x.7 x 10 Bq.

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

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

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

Date EPA value (+30) ~TVA Av 2/84 2383+608 2466 11/84 2012+598 2047

a. Sample fouled in preparation. Procedure modified to prevent recurrence.

b. Lost in analysis.

TABLE 4 (Continued)

RESULTS OBTAINED IN INTERLABORATORY COMPARISON PROGRAN C. Radiochemical Analysis of Mater (pCi/1)

Gross Al ha Gross Beta S troat ium-89 Strontium-90 Tritium Iodine-131 EPA value EPA value TVA EPA value TVA EPA value TVA EPA value TVA EPA value TVA Date TVA'(33a

~A (+3O) ~Av . (+30) ~Av . (+3o) ~Av ~3a> ~A (i3a) ~Av .

1/84 10+9 10 1219 15 36i9 39 24+3 23 3/84 5+9 6 20+9 20 4/84 3508+630 3580 6i0.8 6 5/84 3+9 4 6i9 6 25+9 32 5+3 6/84 3081+622 2770 7/84 8/84 6+9 ~ 6 13+9 16 2817+617 2607 34+10 36 9/84 519 5 1619 12 34+9 41 19+3 18 10/84 2810+617 2517 10/84 14+9 11 64+9 60 llk9 12 12+3 .13 11/84 719 8 2019 22 12/84 3182+624 3400 36+10 33 D. Gamma-Spectral Analysis of Mater (pCi/1)

Chromium-51 Cobalt-60 Zinc-65 Ruthenium-106 Cesium-134 Cesium-137 EPA value TVA EPA value TVA EPA value TVA EPA value TVA EPA value TVA EPA value TVA Date (+3o) ~Av . (+3a) ~Av . (+3a) ~Av . ~(s3a ~Av ~(+3a ~(3a ~A 2/84 40+9 <44 10i9 11 50+9 50 6119 53 31i9 29 16+9 6/84 66+9 72 31+9 32 63i9 66 29+9 <40 47+9 44 37+9 10/84 40+9 43 20+9 22 147+9 151 47+9 48 31+9 29 2419 26 10/84 14+9 17 2i9 <5 14+9 16

c. Laboratory performance evaluation study

TABLE 4 (Continued)

RESULTS OBTAINED IN INTERLABORATORY COMPARISON PROGRAM E. Poods (pCi/kg, Wet Weight)

Strontium-89 Strontium-90 Iodine-131 Cesium-137 Potassium-40 d EPA value TVA EPA value TVA EPA value TVA EPA value TVA EPA value TVA Date (+3a) ~Av . (f3a) ~Av . (+30) ~Av (+3a) ~Av . (+3a) ~Av .

1/84 34i9 40 20+3 19 20f10 20 20+9 21 2730+236 2670 7/84 25+9 N/A 20+3 N/A 39+10 40 25+9 26 2605+226 2624 F. Milk (pCi/1)

Strontium-89 Strontium-90 Iodine-131 Cesium-137 Potassium-40 f EPA value EPA value EPA value value Date ~(333 TVA

~A (+3a) 'Av TVA

. ~(+33 TVA

~A EPA (f30)

TVA

~Av .

EPA value

(+35)

TVA

~Av 3/84 6+0.9 6 6/84 25-9 24 17+A 18 43+10 39 35i9 34 1496+-130 1483 10/84 22+9 26 16+3 15 42xlo ~ 40 32+9 30 1517+132 1563

d. Values reported as mg K/kg.

e. Lost in sample preparation.

f. Values reported as mg K/1.

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11 Atmos heric Monitorin The atmospheric monitoring network is divided into three groups. Four local air monitors are located on or adjacent to the plant site in the general areas of greatest wind frequency. One additional station is located at the point of maximum predicted off-site concentration of radionuclides based on preoperational meteorological data (see figures 3 and 4). Four perimeter air monitors are located at distances out to 10 miles from the plant, and two remote air monitors are located at distances out to 45 miles. These monitoring stations are shown in figure 2. The remote monitors are used as control or baseline stations. At each monitor, air is continuously pulled through a Hollingsworth and Voss LB5211 glass fiber particulate filter at a flow rate of 3 fts/min. In series with, but downstream of, the particulate filter is a charcoal filter used to collect iodine. Each monitor has a collection tray and storage container to obtain rainwater on a continuous basis and a horizontal platform that is covered with gummed acetate to catch and hold heavy particle fallout. Thermoluminescent dosimeters are used to record gamma radiation levels at each remote and perimeter station.

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

Air Filters Air filters are collected weekly and analyzed for gross beta activity. No analyses are performed until three days after sample collection. The samples are composited monthly for analysis of specific gamma-emitting radionuclides and quarterly for Sr and Sr analysis.

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

These data are presented in table 6. During this reporting period, three samples were not obtained because of equipment malfunction. One sample was damaged beyond use.

The annual averages of the gross beta activity in the air particulate filters at the indicator stations (local and perimeter monitors) and at the control stations (remote monitors) for the years 1968-1984 are presented in figure 5, Increased levels due to fallout from atmospheric nuclear weapons testing are evident, especially in 1969, 1970, 1971, 1977, 1978, and 1981. These patterns are consistent with data from monitoring programs conducted by TVA at nonoperating nuclear power plant construction sites. Table 5 presents the maximum permissible concentrations (MPC) specified in 10 CFR 20 for nonoccupa-tional exposure.

Rainwater Rainwater is collected monthly and a 3.5-liter sample analyzed for specific gamma-emitting radioisotopes and tritium. The results are shown in table 7. During this reporting period, one sample from each station (ll) was not available due to extended drought conditions.

Fallout The gummed acetate that is used to collect heavy particle fallout is changed monthly. The samples are ashed and counted for gross beta activity. The results are given in table 8. During this reporting period, one sample was inadvertently destroyed and could not be analyzed.

Charcoal Filters Charcoal filters are collected and analyzed for radioiodine.

The filter is counted in a single channel analyzer system. The results are shown in table 9. During this reporting period, three samples were not taken because of equipment malfunction or filter damage, two samples were destroyed during filter change, and two samples were lost during analysis.

13 Table 5 MAXIMUM PERMISSIBLE CONCENTRATIONS I

FOR NONOCCUPATIONAL EXPOSURE In Mater MPC

'n Air

~Ci/1* ~Ci/m

• Alpha 30 Nonvolatile beta 3, 000 100 Tritium 3,000, 000 200,000 1 37(. 20,000 500 103>>106R 10,000 200 144( 10,000 200 "zr-96Nb 60,000 1,000 140Ba 140L 20,000 1,000 131I 300 100 6SZn 100,000 2,000 4Mn 100,000 1,000 60Co 30,000 '00 89Sr 3,000 300 "Sr 300 30

$ 1Cr 2,000,000 80,000 1 34(. 9,000 400 6 BCo 90,000 2,000

• 1 pCi = 3.7 x 10 Bq.

TABLE 6 RACIOACTIVITY. IN AIR FILTER PCI/H(3) - 0 ~ 037 EO/V(3)

NAME GF FACILITY EBQMQS EEBBX DOC<ET NO ~ SQ=2S2c2EQA22E LOCATION OF~EACJLITY LIHESIQHE TYPE AND LONER LIMIT ALL CONTROL NUMBER OF TOTAL NUMBER CF INDICATOR LOCATIONS I.QChIIQb )tIIU lfIQBESI khUQhl HE'S~ LOCATIONS NONROUT INE OF ANALYSIS DETECTION MEAN (F)b NAME MEAN ()) MEAN (F) REPORTED BEBEQBUEQ ILLQ2 BBHQEb QISI65QE SUE QIBEQIIQ5 BASTE BAtUQE UE8SQBELEUIS GROSS ALPHA 0 ~ 005 0 ~ 01 ( 1/ 50) 50 0 ~ 01- G~ 01 GROSS BETA 0 ~ 010 CD 02( 437/ 466) ATHENS'L 0 ~ 02( 50/ 52) 0 ~ 02( 96/ 1G2) 568 c.a1- O.G4 1C ~ 9 MILES NE 0C1- 004 0 ~ 01- 0%04 GAMMA (GELI) 143 K-40 NGT ESTAB C.02( 58/ 117) LH2 BF NORTH 0%C2( 5/ 13) 0 ~ 01( 12/ 26)

G Ga- 0 C4 0 ~ 9 MILE NNE 0 ~ C1- 0.04 0 ~ 01- C~ 02 BI-214 0 '20 CD 02(

'2- 1/ 117) LM1 BF NORTHMEST a.c2( 1/ 13) 0 02( 1/ 26) 0 0 '2 1 ~C MILE N 0 ~ 02- 0 Q2 0 ~ 02 0 ~ 02 0 '1( 1/ 26 VALUES <LLG BI-212 NOT ESTAB C ~ 01 1/ 117) 0 ~ 01 RGGERSVILLEr AL 13 ~ 8 MILES NM 0 ~ G1(

0 ~ C1-- 0 '113)

PB"214 0 '20 CD 02(

02-2/ 117) LM1 BF NORTHMEST O.C2(

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PB-212 NOT ESTAB 0 00( 21/ 117) LM5 BF DAVIS F a.ca( 2/ 13). 0 00(

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C ~ 00- 0 ~ Ga 2 ~ 5 MILES LSM 0 ~ Ca- 0 F 00 0 00- 0 F 00 0 '7(

F BE-1 0 ~ G50 06( 85/ 117) ATHENS'L 0%C7( 10/ 13) 18/ 26)

CD C ~ 05- 0 '1 10 ~ 9 HILES NE 0 ~ C5-1/

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TL-208 NOT ESTAB G 00( 19/ 117) COURTLANOi AL 0 CO(

0%00- 1G ~ 5 MILES MSM 0 ~ Ca- 0 F 00 0%00- 0 F 00 AC-228 NOT ESTAB 0 00(

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00--

2/ 26) 0 00- 0 Ca 1 ~C HILE ENE 0 ~ 00- 0 F 00 0 0 ~ 01 PA 234M 'NOT ESTAB F

18( 2/'17) RGGERSVILLEr AL 0 '9( 1/ 13) 26 VALUES <LLD SR 89 0 ~ C05 CD CD 17-36 VALUCS <LLO 0 '9 13 8 MILES NM 0 ~ 19- G~ 19 8 VALUES <LLC 44 ANALYSIS PERFORMED SR 90 0 ~ 001 36 VALUES <LLD 8 VALUES <LLC 44 ANALYSIS PERFORHEO

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's'ndicated in,.parentheses (F) .

TABLE 7 RACIOACTIVITY IN RAINWATER PCI/L - 0 ~ 037 80/L NAHE OF FACILITY fBQBll5 EfBBI DOCKET HO 5Q=252A20Qc29f LOCATICN OF FACILITY l, jtffSIQUf REPORTIHG PERIOD 1256 TYPE ANO LONER LIMIT ALL CONTROL NUMBER OF TOTAL NUHBcR OF INDICATOR LCCRTIONS LQGBIIQB HJIU bZQUERI hhUQhl, BfBU LOCATIONS NONRCUTIhc OF ANALYSIS D ET ECTION MEAN (F)P NAME MEAN (FT HEAN (F)b REPORTED Pf BEQBBfQ LLLQl BBUQf QIDIhllQf 65Q QIBHIIQtl BESQE BBUQfb lfhfQBfkf5IX GAMHA (GELI) 132 33( 9/ 108) 38 ~ 51( 1/ 12) 2'7 ~ 22 ( 2/ 24)

K-4C NOT ESTAB 22 6 '7-

~

45 '8 LH1 BF NORTHWEST 1 0 MILE N 38 ~ 51- 38 '1 21 '5- 33 F 00 BI-214 NOT ESTAB 5 '3(

13-52/ 108) 28 '8 CCURTLAHOr AL 10 ~ 5 MILES NSX 7 56(

0 ~ 77-11/ 12) 28 ~ 18 6 45(

0 '0-14/ 24) 28 F 88 PB-214 NOT ESTAB CD F 08( 29/ 10S) COURTLANDr AL 6 20(

46-8/ 12) 9 '9(

'2- 5/ 24)

C 07- 20 11 10 ~ 5 MILES MSil 1 ~ 20 ~ 11 3 24 73 PB-212 NOT ESTAB 1 '0(

18-35/ 108) 4 o2 ATHENSr AL 1G ~ 9 MILES NE 2 ~ 46(

1 ~ 20-5/ 12) 4 ~ 62 F

0 80(

79" 5/

3 24) 64 BE-1 NOT ESTAB 49 '7(

C 28/ 108) RCGERSVILLEr AL 58 F 88( 4/ 12) 45 '9(

'5- 8/ 24) 29 '6- 99 '0 13 ~ 8 MILES NX 42 ~ 48- 99 30 38 71 F 09 TRITIUH 330 F 000 108 VALUES <LLD 24 VALVES <LLD 132 ANALYSIS PERFORMED

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

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

TABLE RADIOACTIVITY IN HEAVY PARTICLE FALLOUT MCI/KM(2) - 570COOOG B'AME

~ 00- EQ/KF(2)

OF FACILITY QEQggg gf EEI DOCKET NO 50=222c2BQA22B LOCATION OF, FACILITY LIQPBIQQP BLBeBuB REPORTING PERIOD JQQB TYPE ANO LOMER LIMIT ALL CONTROL NUMBER OF, TOTAL NUHBER OF INDICATOR LOCATIONS LQKBIIQB HJIU hIQUESI BhdUBL ZEBU~ LOCATIONS NOhROUTINE OF ANALYSIS DETECTION a MEAN (F) NAME MEAN ($ ) HEAN (f)P REPORTED EEEEQE5iQ SLLQ?

~

Bn5QR

-b QIKIBUQE BUQ QIEPQIIQU EBHQC EBHQf HFBRQEELEBI5 0 ~ 46( 12/ 12) 0 ~ 16( 25/

GROSS BETA 142 Oo050 C.22( 114/

0 06- 1 11 25

6) LM4 BF TRAILER P 1 ~ 7 HILES NNM 0 21- 1+25 0 '6- 0 '626)

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

b. Mean'nd ran'ge based uponetectable measurements only. Fraction of detectabl'e measurements at specified locations is indicated. in parentheses (P).;

TABLE 9 RADIOACTIVITY IN CHARCOAL FILTERS PCI/H(3) - 0 ~ 037 BQ/H(3)

NAME OF FACILITY BBQ)tgS EEBBI DOC<ET NO ~ SQ=2S2c24QA225 LOCATION OF FACILZTY LIHESIQHE hl BEh58-- RsPORTING PERIOD TYPE AND LOWER LIHIT ALL CONTROL NUHBER OF TOTAL NUHBER OF ZNDICATOR LOCATIONS LQQBIIQh HIIU t)IQUESI hhU!lhL EEPH ~ LOCATIONS NONRCUTINE OF ANALYSIS DETECTION a HEAN (F) b NAHE MEAN (F) MEAN (F) REPORTED BEBEQB5EQ SI LQ? B689E b QISIhUGE BN QIBEQIIQ5 BhUGE BSHGE HESSQBEIEHIS IODINE-131 02( 27/ 463) O.C3( 2/ 52) 0 ~ 02( 10/ 1C2) 565 0 020 C~

0 02- 0 '4 LH2 BF NORTH 0 ~ 5 NILE HNE 0 ~ 02 0 ~ 03 0 '2- 0 03

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

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

18 Figure 2 ATMOSPHERIC AND TERRESTRIAL MONITORING NETWORK RM 2BF LAWRENCEBURG

+PULASKI FAYETTEVII LE Q PM-IBF WILSON WHEELER ROBE SVILL DAM OAM ATHENS FLORENCE PM-2BF FFIEL MUSCLE HUNTSVILLE SHOALS BROWNS FERRY NUCLEAR PL NT RM-I BF LEIGHTON TUSCUMBIA 44 COURTLANO PM-4 F OECAT R PM-3BFO IO MILES pRUSSELLVILLE GUNT SVII.

HARTSELLE DAM 25 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

t Figure 3 LOCAL MONITORING STATIONS 19 BROWNS FERRY NUCLEAR PLANT ATHENS U. ~ Y 0

0 BFN ALA. HWY 20 Legend

~ Air Monitor DECATUR AUtomatic Well Sampler 0 Dairy Farm Other Farm" Scale 0 I 2 3 4 5 Miles

20 Figure 4 c= ~, ~ ~ . i n.' )/-

54 ~Q, 'g* ~,,'tnt',

t* ,'A t ~

jtg... ilj/,

I

/

4)

I Ia I ~ ~ Il I",g TLD locations I, I l I

IP

, ')'tf;,i,

'VII L l/ ~ I II,

~ r rr rr L,V /$~4 ta',

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Pigure 5 AmW AVamaE

.30 ASS Bva PCrIVm IN AIR FILTERS 1hOWS FaaV NuCLIm Purr Preoperational Phase I Operational Phase

.25 I

o ll0 HC0

.20 4J 4l co c 4J Se Ch o I cI 0 o Sl C

o

.15 m V "e

Ave~ra e: P~ro~erational Phase 0

.10

.05 1971 1972 1973P 19730 1974 1975 1976 19 7 1978 1979 1980 1981 1 82 1983 1984 1 968 1969 19 70

23 Terrestrial Monitorin Terrestrial monitoring is accomplished by collecting environ-mental media within the general area of the plant for indicator locations, and at remote locations for controls. These media sampled include milk, vegetation, soil, ground water, drinking water, and food crops.

In addition, environmental gamma radiation levels are determined by s'trategic placement of thermoluminescent dosimeters. Twice each year a land use survey is conducted to determine milk producing animal census and location.

Land Use Surve The land use surveys were conducted in June and September of 1984. Milk animal census and locations were unchanged from the previous survey. Projected doses to individuals in the area were not significantly different from those calculated for 1983. It was determined that the "

current environmental monitoring program is adequate.

Milk Milk is collected from four farms within a l0-mile radius of the plant (see figure 3), and from at least one of six control farms.

During this reporting period, one indicator dairy farm disposed of all milk animals and ceased operations (November 1984). Information provided by the latest land use survey indicated that there are no replacement dairies in the vicinity of the plant. In compliance with plant technical specifications, a Special Report was submitted to the Nuclear Regulatory Commission on December 13, 1984.

Raw milk samples are collected from indicator and control farms, and are analyzed weekly for iodine-131 and monthly for gamma-emitting isotopes and radiostrontium. Analytical results are summarized in table 10. During the 1984 reporting period, 13 samples were not available for collection. Four samples spoiled and could not be analyzed.

V~e etation Vegetation is sampled monthly at six indicator farms (four dairies and two farms with one milk-producing animal), and at each air monitoring station. quarterly vegetation samples are collected at four control farms. The monthly samples are analyzed for iodine-131 and gamma-emitting isotopes with analysis for radiostrontium performed on the last monthly sample of each quarter. Samples collected quarterly are analyzed for gamma-emitting isotopes. Table 11 summarizes analytical results. During this reporting period, one monthly sample was not collected because of severe weather conditions, one sample spoiled before a gamma scan could be performed, and one set of samples for March were "lost" prior to strontium analysis because of analytical difficulties. Laboratory procedures were revised to prevent reoccurrence.

24 Soil Soil samples are collected annually near each monitoring station to provide an indication of long-term buildup of radioactivity in the environment. An auger or "cookie cutter" type sampler is used to obtain samples of the top. two inches (5 cm) of soil. These, samples are analyzed for gamma-emitting radionuclides, strontium-89, and strontium-90. The results are given in table l2.

Ground Mater An automatic sequential-type sampling device collects groun'dwater from a well downgradient from BFN. A composite sample from this well is analyzed for gamma'-emitting radionuclides monthly and composited quarterly for determination of tritium. A grab sample is also taken monthly from a control well upgradient from the plant. The results 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: Sr analyses. The first potable water supply downstream from the plant is equipped with an automatic sampler with samples collected and analyze'd weekly. The sampler is located on the -water intake structure and takes the sample from the riper as the raw water is drawn into the water treatment facility. Two additional supplies downstream and water supply upstream are sampled by taking monthly grab samples one'ublic of treated water at user points. Table 14 indicates the results from'he analysis of drinking water samples. During this reporting period, gross beta of one of the weekly samples was not determined because of insufficient sample size caused by the malfunction of automatic sampling equipment. t.

Figure 6 shows the trends in gross beta activity in drinkin'g water from 1968 through 1984. The annual average level from the raw water samples tends to run slightly higher than the average for treat'ed water samples; however, the levels are consistent with the in surface water samples taken upstream- from BFN (figure 12) activities'eported and in samples taken from the Tennessee River in preoperational monitoring programs conducted by TVA at other sites.

Environmental Gamma Radiation Levels Bulb-type Victoreen manganese-activated calcium fluoride (CazF: Mn) thermoluminescent dosimeters (TLDs) are placed at sixteen stations around the plant near the site boundary, at the perimeter and remote air monitors, and at nineteen additional stations out to approx-imately five miles from the site to determine the gamma exposure rates at these locations. The dosimeters, located inside energy compensating shields to correct, for energy dependence, are placed at approxi'mately one meter above the ground, with three TLDs at each station. They aie

25 annealed and read with a Victoreen model 2810 TLD reader. The values are corrected for gamma response, self-irradiation, and fading, with individual gamma response calibrations and self-irradiation factors determined for each TLD. The TLDs are exchanged every three months.

The quarterly gamma radiation levels determined from these TLDs are given in table 15, which indicates that average levels at onsite stations are approximately 2-4 mR/quarter higher than levels at offsite stations. This is consistent with levels reported at TVA's nonoperating nuclear power plant construction sites where the average radiation levels onsite are generally 2-6 mR/quarter higher than levels offsite.

The causes of these differences have not been completely isolated; however, it is postulated that the differences are probably attributable to combinations of influences, such as natural variations in environmental radiation levels, earth moving activities onsite, the mass of concrete employed in the construction of the plant, and other undetermined influences.

Figure 7 compares plots of the data from the onsite or site boundary stations with those from the offsite stations over the period from 1976 through 1984. To reduce the variations present'in the data sets, a four-quarter moving average was constructed for each set.

Figure 8 presents a trend plot of the direct radiation levels as defined by the moving averages. The data follow the same general >

trend as the raw data, but the curves are smoothed considerably.

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

,offsite stations.

Food Products Food products raised in the vicinity of BFN and at control locations are sampled as they become available during the growing season, and analyzed for gross beta activity and for gamma-emitting radionuclides. During this sampling period, samples of cabbage, corn, peaches, peas, potatoes, poultry, and tomatoes were collected and analyzed for specific gamma-emitting radionuclides. The results are given in tables 16 through 22.

TABLE 10 RADIOACTIVITY IN HILK PCI/L - 0 ~ 037 SQ/L NAHE OF FACILITY EBQBJE fEBBI 00'CKET NO ~ EQ=222c24Qc?25==

c LOCATION OF FACILITY LIQEEIQQE REPORTIHG PERICO TYPE AND LOWER LIHIT ALL CONTROL NUMBER OF TOTAL NUHBER CF INDICATOR LOCATIONS LQEkIIQb ltIIU UIQUEEI hhUQBL LEST~ LOCATIONS NONROUTINE OF ANALYSIS DETECTION a HEAN (F) NAPE MEAN (() MEAN (f)b RcPORTEO b .B85QE VESEQBE"=BRIE fEBfQB5EQ Ll LQX BSUQE QIEIhHQE 85Q QIBEQIIQU BhHQE IODINE-131 0.500 195 VALUES <LLO .302 VALUES <LLG 497 ANALYSIS PERFORMED GAMMA (GELI) 124 7/ 48) 4/ 67( 1/ 76)

'112) 5.000 7.55( - 8 ~ 20(

CS-1 37 5.15-11 01 PAGE FARM 8 75 HILES E 5 15- 11 5

5 '7- 5.67 K-40 HOT ESTAB 1271 95(

'9- 48/ . 48) SMITH FARH 4~75 MILES 1337 '3(

~

10/

1155 ~ 58- 1787 10)

'912) 1270 05(

789 '9-76/ 76) 1839 06 881 17o7 ~ 99 N BI-214 HOT ESTAB 11 '5(

47-27/

126 67

48) PAGE FARM 8 75 HILES 19 ~ 15( 10/

11- 126 '7 7 43(

0 '6 55/

19 '7 76)

PB-214 HCT ESTAB 0

19 '5(

00'-

13/ 48) PAGE FARH E 1 ~

39 86( 4/ 12) 0 00- 140 '0

~ 6 '6(

0 72-38/ 76) 25 '4 140 ~ 10. 8 ~ 75 HILES E ~

PB-212 NCT ESTAB C

2~ 21( 10/ 48) PAGE FARM 2 '3(

~1-2/ 12) 1 59(

02" 22/ 76) 0 ~ 80- 3 ~ 80 8~75 HILES 2 2+74 0 4 51 TL-208 NOT ESTAB 0 ~ 81( 11/ 48) SMITH FARH E

1 ~ 22( 5/ 10) '3(

0 '3" 1 20/

'9 76) 0 '2- 3+31 4%75 HILES N 0 ~ 37-1/

3 ~ 31 5 '9(

2 7/ 76) 21( 5/ 48) 13 ~ 36( 13) 0 '2-AC-228 LCCNEY FARF 25 '2 NOT ESTAB 2 ~ 53 13 ~ 36 5 75 HILES ENE 13'6- 13 36 SR 89 10 F 000 46 VALUES <LLO 76 VALUES <LLO 122 ANALYSIS PERFORMED 5 ~ 10( 10/ 71/ 76)

SR 90.

122 2 ~ GOO 4 2

~ 26(

'3- 41/

7 '946) SMITH FARM 4a75 MILES'N 3 '9- 7 '910) 3 ~ 88 (

2 ~ 07- 8 ~ 79

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

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

TABLE ll RADIOACTIVITY IN VEGETATION PCI/G - 0 ~ 037 BC/G (DRY %EIGHT)

NAME GF FACILITY ggQggg gggQZ DOCKET NO ~ GQ=25$ cggQAPff LOCATION OF FACILITY gJQg$ g{}gg ILLBOhBh REPORTING PERIOD TYPc AND LONER LIHIT ALL CONTROL NUMBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LQCIIIQh HJIU UlQUESI hhBQhL HEST LOCATIONS NCNROUT INE OF ANALYSIS DETECTION a McAN (F) NAME MEAN (F) 8 MEAN (F)b REPORTcD EEBEQBHPQ SLLQ? QIBIBHQE 85Q QIBEQIKQU b BBUQE HBUQC 888QE 5E85QEEEf BIK GROSS ALPHA 0 '50 0%05( 1/ 1) SHITH FARM 0 ~ C5( 1/ 1)

GROSS BETA 1

0 '00 C

7

~ 05-

'4( 0 1/

05 1) 4 ~ 75 HILES N SMITH FARH 0 '5 7 ~ 94( 1/

0 F 05 1)

IODINE-131 1 7 '4- 7 94 4 75 MILES N 7 ~ 94- '7 ~ 94 00( 161/ 194) 13/ 0 F 00( 19/

'113)

NOT FSTAB

'126) 0 LH1 BF NORTHWEST 0 ~ CO(

220 0 00- 0%01 1%0 MILE N 0 ~ CO- 0 0 F 00- 0 GAHHA (GELI) 235 C0-60 0 '60 0 ~ 14( 1/ 193) LH1 BF NORTHMEST 0 ~ 14( 1/ 13) 42 VALUES <LLO 0 ~ 14- 0 ~ 14 1 ' MILE N 0 ~ 14- 0 ~ 14 CS-137 0 '60 0 ~ 08(

0 ~ G6-11/ 193) 0 ~ 15 SMITH FARH 4 ~ 75 HILES N 0 ~ 15(

0 ~ 15-1/

0 ~ 15

13) 0 0

'2(

07-5/

0 F 25 42)

K 40 NOT ESTAB 10 ~ 75( 193/ 193) LH2 BF NORTH 14 ~ 35( 13/ 13) 13 '2( 42/ 42) 0%46- 40 10 0 ~ 9 HILE NNE 1 ~ 25- 34 ~ 03 0 '2- 39 '4 BI-214 0 '00 0 ~ 17( 57/ 193) ATHENSr AL 0 25( 1/ 13) 0%19( 14/ 42)

BI-212 NOT ESTAB 0

0

~ 10" 0%43 27( 10/ 193) 10 ~ 9 HILES NE MISER FARM 0 ~ 25-0'%37(

0 '5 1/ 13) 0 11-0 '7(

0 '8 3/ 42) 0 ~ 06- 0 ~ 38 6%9 HZLES NE 0 ~ 37- 0 37 0 '5- 0 '8 PB-214 NOT ESTAB G ~ 08( 167/ 193) EVANS FARM 0 ~ 11( 13/ 13) 0 10( 35/ 42)

PB-212 NOT ESTAB 0 ~ 00-0 '4( 0 40 136/ 193) 6%1 MILES NE LH4 BF TRAILER. P 0 ~ G1-0%C(

0 '0 12/ 13) 0 00-0 '6(

F 0 '2 25/ 42) 0 00 0 ~ 27 1 ~ 7 MILES NNX 0 ~ 02- 0 ~ 16 0F 00- 0 27 0 '2(

F RA-223 NOT ESTAB 1/ 193) LH5 BF DAVIS F 0 ~ 12( 1/ 13) 42 VALUES <LLD BE-7 NOT ESTAB 0 12-5 F 0 ~ 12 88( 192/ 193) 2 ' MILES bSll ROGERSVILLEr AL 0 ~ 12 9 ~ 71( 12/

0 '212) 6 53( 42/ 42)

TL-208 NOT ESTAB 0 ~ 21-0 '2( 25%72 114/ 193) 13 ~ 8 MILES NN LH3 BF NORTHEAST 1 ~

0 23-

'4( 25 ~ 72 6/ 13) 0 88-0 02(

17 '3 21/ 42) 0 ~ GO- 0 ~ 10 1%G HILE ENE 0 CO" 0 10 0 00- 0 ~ 1G AC-228 NOT ESTAB 0 ~ 11( 111/ 193) ATHENSr AL 0%31( 4/ 13) 0%11 ( 18/ 42)

C 00- 1 ~ 15 10 ~ 9 HILES NE 0 ~ CO- 15 0%00- 0 ~ 33 PA-234H NOT ESTAB 3 '4(

78-4/ 193) LH1 BF NORTHNEST 4 ~ 96( 1/

1 ~

13) 2 ~ 03( 1/ 42) 2 ~ 4 ~ 96 1 C MILE N 4 ~ 96- 4 96 2 03- 2 ~ 03 SR 89 0 '50 48( 5/ 46) LP4 BF TRAILER P 0 ~ EO( 1/ 3) 6 VALUES <LLC 0 '9" CD 52 0 ~ 80 1 ~ 7 HILES NNM 0 EO- 0 80 SR 90 0 '50 0 '6( 45/ 46) ROGERSVZLLEr AL 0 ~ 75( 3/ 3) 0 46( 6/ 6) 52 0 ~ 05- F 05 13 8 MILES NW 0 ~ 63- 0 ~ 86 0 26- CD 91

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

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

TABLE 12 RADIOACTIVITY IN SCIL PCI/G - C.037 BC/G (CRY I EIGHT)

NAME CF FACILITY ggQii55 EEBBI DOCKET NO. gg-252c25Qc225 LOCATION OF FACILITY I,?5ESIQBE REPORTING PERIOD 1255 TYPE AND LONER LIMIT ALL CONTROL NUMBER OF TOTAL NUMBER CF, INDICATOR LOCATIONS I.QQEIIQh'LIU UKQUfhI hhBQBL t)ach8 NCNROUTINE OF ANALYSIS DETECTION MEAN (F) NAME MEAN (F) ~ LOCATION(

MEAN (F) REPORTED RRBEQ85EQ LLLQ? 8889K QISI68QE hHQ QIEEQIIQ5 88UQE 885QE lEBKQBEEEUI5 GAHHA (GELI) 11 1/ 0%16( 1/ 1) 2 VALUES <LLC CS-134 CS-137 0 080 O.C20 CD C ~

16(

16-39(

0 9/

'6 9)9) LH1 SF NORTHMEST 1 ~C MILE N LM5 SF DAVIS F 0 ~ 16-1 ~ C3( 1/

0 16

1) 0 51( 2/ 2)

CD C 06- 1 '3 9/ 9) 2 ~ 5 MILES 'IISM 1 C3-7.29( 1/

1 ~ 03 1) 0%26-4 63(

0 2/

'76 2)

K 40 0.250 5.28( LH4 BF TRAILER P 3 32- 7 29 1 ~ 7 HILES NNM 7 29- 7 29 4 ~ 15" 5 ~ 11 BI-214 0 050 1 00( 9/ 9) LM1 SF NORTHMEST 1 ~ 30( 1/ 1) 1 06( 2/ 2)

. G ~ 61- 1 30 1 ~C HILE N 1 30- 1 $0 0 90- 1 ~ 21 BI-212 9/ 1 89( 1/ 1) 1 30( 2/ 2) 0 100 1 24(

C%75 1 '9 9) LM1 BF NORTHMEST 1 ~C HILE N 1 ~ 89- 1 ~ 89 1 ~ 25- 1 35 PB-214 0 '50 10( 9/ 9) LH1 BF NORTHMEST 1 ~ 47( 1/ 1) 1%13 ( 2/ 2)

PB-212 NOT ESTAB

4. 1 ~

G~

F 08(

68- 1 9/

'7 9) 1 0 HILE N LM1 BF NORTHMEST 1 ~ 47-1%60(

1 ~ 47 1/ 1) 0 98-1 ~ 16(

1 ~

2/

28 2)

G 57- 1 60 1 ~0 MILE N 1 ~ 60- 1 60 1 ~ 15 1 ~ 17 1/ 2/

RA-226 0 050 F 00(

0 ~ 61-9/

1 ~ 30

9) LH1 SF NORTHMEST 1%C HILE 1 ~ 30(

1 ~ 30- 1%30

1) 1 0

06(

90- 1 '1 2)2)

RA-223 NOT ESTAB 0 ~ 35( 4/ 9) ATHENSr AL N

0 ~ 43( 1/ 1) 0 '9(

'9" 1/

0 ~ 28- 0 ~ 43 10 9 HILES NE 0%43- 0%43 0 0 29 RA-224 NOT ESTAB 1 09( 6/ 9) OECATURr AL 1 ~ 47( 1/ 1) 2 VALUES <LLD 0 ~ 67- F 47 8~2 HILES SSE 1 ~ 47 1%4?

BE-?. 0%160 9 VALUES <LLO 0 19( 1/ 2) 0%19- 0 ~ 19 TL-208 0 '20 0 '8(

20-9/ 9) LH1 BF NORTHMEST 0 '3(

53-1/

0 53

1) 0 F 42(

0 '2- 2/

0 '2 2) 0 0 53 1%C MILE N 0 AC-228 0 '60 13( 9/ 9) LH1 BF NORTHMEST 1.68( 1/ 1) 1%18( 2/ 2)

PA-234H NOT ESTAB 1

G~

2 60-34( 5/

1 '8 9) 1%C MILE N LH1 BF NORTH'MEST 1 ~ 68-3 ~ 64(

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

1 ~ 22 2) 1 '0- 3 64 1 ~C HILE N 3 64- 3%64 2 ~ 19- 2 ~ 19 SR 89 1 '00 9 VALUES <LLO 2 VALUES <LI.D ANALYSIS "PERFORMED 1/

SR 90 0 300 9 VALUFS <LLO 0 34(

0%34- 0 '4 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 at specified locations 'is indicated in parentheses (F).

TABLE 13 RACIOACTIVZTY IX MELL MATER PCI/L - 0 ~ 037 BC/L NAME CF FACILITY EBQB5B Ef BBZ DOCKET NO ~ EQ=222c25Qc226 LOCATION OF FACILITY LI5EJIQ5E 8L8E858 REPORTING PERICD gBB8 TYPE AND LO'NE R LIMIT ALL CONTROL NUMBER OF TOTAL NUHBER CF INDICATOR LOCATIONS  ! QQ8IIQ5 )lII5 5IQUEBI 855!l8L 5E85 ~ LOCATION[

NGNROUTINE OF ANALYSIS DETECTION a MEAN (F) n NAYE MEAN (F) MEAN (F) RcPORTED BEBEQB5EQ SL.LQ2 B85QE QLBI85QE 85K QIBEQIIQ5 B85Q B85QE f 5E8EQBE 5 5IB GAHHA (GELI) 26 K-40 NOT ESTAB 21 ~ 78(

78-1/ 13) BFN MELL 06 0 ~ C2 MILES 21 ~ 78(

21%i 8-1/ 13) 78 15 '8(

12 F 05-2/

19 '1 13) 21 21 78 21 SI-214 NOT ESTAB

~

7 ~ 23(

C 12-11/

14 '0 13) SFN MELL A6 0 ~ 02 HILES M 7 ~ 23(

0 ~ 12 11/ 13) 14 ~ 30 187 '4(

14% 57 13/ 13) 344 ~ 52 PB-214 NOT ESTAB

'4- 7/13 '613) 7%50(

BFN MELL A6 0 C2 HILES M 7 '0(

2 74-7/

13 26

13) 186 72(

28 '2- 13/ 13) 367 F 80 3 '9(

~

PB-212 NOT ESTAS 1 '7(

07-3/ 13) 2 32 BFN MELL P6 0 C2 HILES 1 C7(

0 ~ C 7-3/

2%32 13) 3 '0- 3/

5 '1 13)

TL-208 NOT ESTAB C~

1 0

'3(

'9-

~

2/ 13)

'8 SFN 'MELL N6 0 ~ C2 MILES M 1 ~ 03(

0 ~ 39-2/

1%68

13) 0%64(

0 '1-3/ 13) 0 '613)

AC-228 NOT ESTAS 13 VALUES <LLD 1

4 2

'9(

47-2/

6 '0 TRITIUM 330 F 000 4 VALUES <LLD 4 VALUES <LLC 8 ANALYSIS PERFORMED

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

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

TABLE 14 RADIOACTIVITY ZN PUBLIC WATER SUPPLY PCI/L - 0 037 BO/L NAME OF FACZLITY j}BQQ{ig EEBBI DOCKET NO ~ KQ=222c2{lQA225 LOCATZON OF FACILITY LI((EEIQBE 8L8E858 REPORTING PERIOD TYPE ANO LOWER LIMIT ALL CONTROL NUHBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LQQ8IIQh HLIU l{IQUEEI 8ht{U8L 5E88 8 LOCATIONS NONROUT INE OF ANALYSIS DETECTION a MEAN (F) b NAME HEAN (F) HEAN (F)b REPORTED b

B85{ij b QISI8BQE 85Q QIBEQIIQB B8U{ijb B8UQE BE8lMBElEBIE BEBEQBBEQ SLLQK

'00 00( 46/ '2( 40/

'052) 3 ~ 06( 5/ 13)

'077) CHAHPICN PAPER 3 GROSS BETA 90 2 3 2 '1- 5 TRH 282 ' 2 '6- 5 2 55" 3 ~ 51 GAHHA (GELI) 91 K-40 88( 6/ ?8) 18 ~ 62( 5/ 52) 28~73( 1/ 13)

NOT ESTAB 17 9

~

70- 33 '6 CHAHPION PAPER TRH 282 6 9 ~ 70 33 96 28 '3-6 '3(

28 '3 9/ 13)

BI-214 64( 46/ 78) WHEELER OAHr AL 6+86( 9/ 13)

'8 3 '9" '?

NOT ESTAB 5 Ce14" 24 79 TRH 274 ' 2 85-17(

12 14/ 52) 50(

8 6/ 13) 28( 26/ 78)

PB-214 NOT ESTAB 4 Ce35- 19+47 CHAMPION PAPER TRH 282 '

5 0 ~ 41 19 ~ 47 5

1 84- 11 '6 PB-212 NOT cSTAB '9(

-0 '5-1 23/

4 78)

'078) SHEFFIELDiAL TRV 254 '

ROB 2 ~ 38(

0 ~ 58-4/

4 13)

'013) 1 95(

0 '7-6/ 13) 4 '4 TL-208 18( 11/ WHEELER DAHr AL 37( 2/ 65( 5/ 13) 0 '3- '2

~ 1 ~

NOT ESTAB Oa28-19(

3 '8 7/ 78)

TRH 274 ~ 9 1

1 ~ 22-

?e?3(

1 '2 4/ 52) 1 0 '6(

2 1/ 13) 0 '6-AC-228 NOT ESTAB 1+08- 17 '9 CHAHPION PAPER TRH 282 ' 1 ~ 08- 17 ~ 19 4

0 '6 VALUES <LLO SR 89 10 F 000 12 VALUES <LLO 16 ANALYSZS PERFORHEO SR 90 F 000 12 VALUES <LLO .4 VALUES <LLD 16 ANALYSIS PERFORMED TRITIUM 330 F 000 12 VALUES <LLO 4 VALUES <LLC 16 ANALYSIS PERFORMED

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

b. Mean and range based upon detectable measurenents only. Fraction of'detectable neasurements at specified locations "is indicated in parentheses (P).

31 Table 15 ENVIRONMENTAL GAMMA RADIATION LEVELS Average External Gamma Radiation Levels at Various Distances from Browns Ferry Nuclear Plant for Each Quarter - 1984 mR/Quarter Distance Avera e External Gamma Radiation Levels-b Miles 1st uarter 2nd uarter 3rd uarter 4th uarter 0-1 19.4+1.7 19.9+1.4 21.9+3.0 20.5+1.5 1-2 18.5+2.0 17.5+1.7 19.2+3.7 19.4+2.2 2-4 17.5+1.5 17.8+1.9 17.7+3.5 17.8+2.1 4-6 16.9+1.3 17.5+1.7 17.2+2.7 17.9+1.4

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

Average, 0-2 miles (Onsite) 19.5+1.8 19.3+1.7 21.2+3.2 20.2+1.7

Average,

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

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

TABLE 16 RAOIOACTIVITT IN CABBAGE PCI/KG 0 ~ 037 BQ/KG (IIET liEIGI'.T)

NAME OF FACILITT BB{}HHS f EEBI DOCKET NO ~ >Q=2S2c24Qc228 q LOCATION OF FACILITT LIBESIQhE TTPE ANO LONER LIHIT ALL CONTROL NUMBER OF TOTAL NUHBER OF INDICATOR LOCATIONS LQC8IIQb 'HJIU LZQUESI 8htlll8L UE88 > LOCATIONS NCNROUTINE OF ANALTSIS DETECTION a MEAN (F) b NAME MEAN (F) MEAN (F) b REPORTED E8uar. b QISI8tllf, 8tlQ QIBfQIIQH B88QE E859f 5C8SUBfBCUIS BEBEQEBEQ GROSS BETA SLLQ}

25 F 000 3903 25( 1/ 1) 7 RILES NNli 3903 25( 1/

'5 1) 3687 '8( 1/ 1)

GAMMA (GELI) 2 3903 '5 3903 '5 3903 ~ 25- 3903 3687 18- 3687 18 K-40 2

NOT ESTAB 1557 05( 1/ 1) 1557 05- 155? ~ 05 7 PILES NNIi 1557 '5( 1/

155?~05- 1557 F 05

1) 2257~49(

225? ~ 49- 2257 1/

'9 1)

BI-214 4 '6( 1/ 1)

NOT ESTAB 1 VALUES <LLO 4

5 96-

'3( 1/

4 '6 1)

PB-21.4 NOT ESTAB 1 VALUES <LLO 13-PB-212 NOT ESTAB 2 24(

2 ~ 24-1/

i2 24

1) 7 FILES NNIi 2~

2 24('/2a24 1)

'4-5 0 '1(

0 91-1/

5~ 13 0 '1 1)

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

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

TABLE 17 RADIOACTIVITY IN CORN PCI/KG - 0 ~ 037 BC/KG (NET 'NEIGHT)

NAHE CF FACILITY EBQBBQ EEBBI DOCKET NO ~ 2Q=222c28Qc228 LOCATION OF FACILITY LIBEgIQBE 8L8E8$ 8 REPORTING PERICD TYPE AND LONER LIHIT ALL CONTROL NUHBER OF TOTAL NUHBER OF INDICATOR LOCATIONS LQQ8IIQh HJIll llIQUESI 8hUll8L UE88 LOCATIONS NONROUTZNE OF ANALYSIS DETECTION HEAN ([) NAHE HEAN (F% HEAN (FP REPORTED EEBEQBHEQ SLLQ? B8hQE QIBI8UQE 85'IBEQIIQ5 B85QE B8KiP BE85MBELEUIG GROSS BETA 25.000 3551 07( 1/ 1) 7 HILES NNN 3551 ~ 07( 1/ 1) 2172+74( 1/ 1)

GAHHA (GELI) 2 3551 '7- 3551 F 07 3551 '7- 3551 07 2172 74- 2172 ~ 74 2

K-40 2254 ~ 39( 1/ 1) 2254 ~ 39( 1/ 1/

BZ-214 NOT ESTAB NOT ESTAB 2254 '9- 2254 39 VALUES <LLO 7 HILES NNN 2254 39- 2254 '9 1) 2094%54(

2094 '4-

'6( 2094 '4 1/ 1) 1)

PB-214 1 3 3 '6- ~

3 '6 1)

NOT ESTAB VALUES <LLO 0048(. 1/

0 '8-1 0 F 48 PB-212 NOT ESTAB 1 '4(

1 ~ 44-1/

1 '4 1)- 7 PILES NMN- 1 ~

1 ~

44(

44-1/

1 ~ 44

1) 1 VALUES <LLD

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 (P).

TABLE lg RADIOACTIVITY IN PEACHES PCI/KG - 0 ~ 037 BQ/KG (WET WEIGHT)

NAHE OF FACILITY EBQ555 EEBBI DOCKET NO ~ XQ=212c20Qc225 LOCATION OF .FACILITY LI5EBIQ5E hl.hea5h REPORTING PERIOD TYPE AND LOWER LIHIT ALL CONTROL NUFBER OF TOTAL NUHBER OF INDICATOR LOCATIONS l QChISQh HIIU UI{iUEEI h555hl 5Eh5 8 LOCATIONS NONROVT INE OF ANAL'ISI 5 DETECTION a PEAN (F) b NAME MEAN (F) MEAN (F) REPORTED b QIEIh5CE h5Q QIBEQIIQ5 Bh5QE Bh5QE 5EhEQBEBE5I5--

BEBEQB5EQ SLLQl Bh5QE 2273 65( 1/ 1) 4 PILES N 2273 ~ 65( 1/ 1) 2772 95( 1/ 1)

GROSS BETA 2

25 F 000 2273 '5- 2273 '5 2273 65- 2273 '5 2772 '5 2?72 '5 GAHHA (GELI) 2 K-40 1955 '0( 1/ 1) 4 FILES 1955 30( 1/ 1) 1595 08( 1/ 1)

NOT ESTAB 1955 30-

~ 1955 '0 N 1955 ~ 30- 1955 '0

'9( 1/Oe?9 1) 1595 ~ 08- 1595 F 08 5 79( 1/ 1)

BI-214 Co?9( 1/ 1) HILES 0 NOT ESTAB 0 79- Oe?9 4 N 0 79- 5 ~ 79- 5 '9 PB-214 NOT ESTAB 9 '7(

9e47-1/ 1) 4'ILES N 9 9~

'7(

~

47-1/

9 '7 1) 2 46(

2 46-1/

F 46 1) 9 47 PB-212 NOT ESTAB 0.98( 1/ 1) 4 HILES N 0 '8(

'8 1/ '8 1) 1 ~ 68(

1 ~ 68-1/ 1)

'8 0 ~ 98- 0 ~ 98 0 0 1

a. Noninal Lower binit 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 19

.RADIOACTIVITY IN PEAS PCI/KG - Ce037 BZ/KG (NET HEIGHT)

NAME OF FACILITY BBQljUE EEBBI DOCKET NO ~ 5Q=222c25Qc226 LOCATION OF FACILITY LJUE5IQUg 6L8BBU8"---- REPORTING PERICD TYPE AND LONER LIHIT ALL CONTROL NUHBER OF TOTAL NUHBER OF INDICATOR LOCATIONS LQQhIIQb UJIU UIQUEEI 8UUllhL UfhU~ NONRCUTINE OF ANALYSIS DETECTION HEAN (F) NAVE HEAN ($ )

LOCATIONS

-b HE AN (g) REPORTED PEBEQBUEQ SLLQ? BGUQs QZKISUQa EUQ QIEHIZQU EaUQE BEUQE UBSEQEf PBUIK GROSS BETA 2

25 000 6965 6965

'6(

'6- 1/

6965 66

1) 4 PILES N 6965 ~ 66(

6965 '6 1/

6965 '6 1) 5614 ~ 87(

561 4 ~ 87 1/

561 4 ~ 87 1)

GAMMA (GELI) 2 K-40 NOT ESTAB 3461 ~ 39( 1/ 1) 4 VILES N 3461 ~ 39.( 1/ 1) 3651 ~ 65 ( 1/ 1) 3461 ~ 39- 3461 ~ 39 3461 ~ 39- 3461~39 3651 ~ 65- 3651 ~ 65 BI-214 NOT ESTAB 6 '3(

6 ~ 03-1/

6 03

1) 4 PILES N 6 6

'3(

'3 1/

6~03

1) 1 VALUES <LLO PB-214 NOT ESTAB 5 '3(

03-1/

5+03

1) 4 FILES N 5 5

'3(

'3" 1/

5 03

1) 1 VALUES <LLO 5

5

~

~ 03- 5 '3 5 ~ C3- 5 '3

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

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

TABLE 20 RADIOACTIVITY IN POTATOES PCI/KG - 0 ~ 037 BC/KG (MET MEIGHT)

NAME OF FACILITY EPQg~t.g fEEP OOCKFT NO. SQ-222c25QA225 LOCATION .OF. FACILITY LILVE)IQJE BLBEB5B REPORTING PcRIOD S'IL TYPE AND LONER LIMIT ALL CONTROL NUHBcR OF TOTAL NUHBER OF INDICATOR LOCATIONS LQC>IIQh HIIU VIQUEEI BDHQBL 5EB5~ LOCATIONS NON ROUTINE I MEAN (~)b HEAN (g) REPORTED OF ANALYSIS 0 E T 5 C T 0 lP NAME MEAN ($ )

QIEIBHCE MQ QIEEGIIM BB5QE EBBQE UEBEllEEKEUIE PEEPQEUEQ GROSS BETA QI 25 ~ COO 7312+07(

RBZQE 1/ 1) 7 PILES NNM 7312.07( 1/ 1) 6571 '0( 1/

'0 1) 2 731 2 ~ 07 731 2 ~ 07 7312 ~ 07- 7312 ~ 07 6571+60- 6571 GAHHA (GELI) 2 K-40 NOT ESTAB 3287 97( 1/ 1) 7 PILES NNM. 3287.97( 1/ 1) 3924 ~ 85( 1/ 1)

'7 3924 85- 3924 F 85 BI-214 PB-214 PB-212 NOT ESTAB NOT ESTAB NGT ESTAB 3287.97" 3287 2o73(

2.73-C.78(

0.78-CD 83(

1/

2 1/

Oo78 1/

73 1) 1)

1) 7 H ILES PILbS 7 PILES NNM NNM NNM 3287 ~ 97- 5287 97 2 '3(

2 73-0 78(

0 '8" 0 '3(

1/

1/

0 1/

2 F 73

'8 1) 1)

1) 3 3

'9(

'9" 12 44(

12 '4-1 F '/ 1/

3 29 12 44 VALUES <LLD 1) 1)

0 ~ 83- 0 83 0 83-

~ 0.83

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

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

TABLE 21, RADIOACTIVITY IN POULTRY PCI/KG - 0 037 BQ/KG (NET 'HEIGl T)

NAHE OF FACILITY fgQQgl ffggg OOCKcT NO. NQ=212A25QA225 LOCATION OF FACILITY gjgfgfQgf TYPE ANO LONER LIMIT ALL CONTROL NUMBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LQt'BIZQh HJIU VIQUfXI hhUQhl lfhH LOCATIONS NONROUTINE OF ANALYSIS DETECTION MEAN ($ ) NAHE HEAN MEAN gF REPORTED 650 QIBrQIIQH 868QE j'hhQ 5f 85UEf LfHIS Ef BEQBHf Q Su.QZ B85Qf

'4(

(F7'ISI65QE GROSS BETA 25 F 000 5016 '7(

'7- 50161/ '7 1) PAGE FARM 8 ~ 75 HILES E 5016 ~ 47( 1/

5016 ~ 47- 5016 ~ 47

1) 4902 4902 '4- 4902 1/

'4 1) 2 5016 GAMMA (GELI) 2317 '0(

2 1/ 2511 67( 1/ 1/ 1)

K-40 NOT ESTAB 2511 67(

2511 ~ 67- 2511 '7 1) PAGE FARH 8 ~ 75 MILES E 2511 '7-12 ~ 62(

2511 1/

'7 1)1) 2317 20-41(

2317 20 1/ 1)

BI-214 12.62( 1/ 1) PAGE 'FARH 8 NOT ESTAB 12 ~ 62- 12 '2 8 ~ 75 HILES E 12 '2-8 '1(

12 1/

'2 1) 8. 41-8 ~ 90(

8 41 1/ 1)

PB-214 61( 1/ 1) PAGE FARH NOT ESTAB 8 8 ~ 61- 8 ~ 61 8 ~ 75 HILES E Saki- 8 '1 8>> 90- 8 ~ 90

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

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

TASL E 22 RACIOACTIVITY IN TOHATCES PCI/KG - 0 ~ 03? SQ/KG (NET NEIGVT)

NAME OF FACILITY BQ'gB$ EEBBI .. DOCKET NO ~ 59222c2kQs22fi LOCATION OF. FACILITY LItlfgIQBE BLllEBllB R PORTING PERIOD 1255 TYPE ANO LONER LIHIT ALL CONTROL NUVSER OF TOTAL NVHSER CF INCICATOR LCCATIONS LQLEIIQh HIIll UIQUESI BhUQBL BEBOP~

LOCATIONS NONROUTINE OF ANALYSIS DETECTION HEAN (F) HAVE MEAN (F) HEAN (F) REPORTED BEBEQB5EQ fLLQ? QIEIBBQE SBQ QIBEGIIQB BOUSE BOUGE b

UfhfQBEEEUIE GROSS SETA 2

25 F 000 91(

BaBQE'617 1617 ~ 91- 1617 ~ 91 1/ 1) 7 VILES NNX 1617 ~ 91( 1/

161? ~ 91- 1617 91

1) 3007 3007

'6(

'6- 1/

3007~66 1)

GAHHA (GELI) 2 K-40 NOT ESTAS 2161 ~ 25( 1/ 1) 7 VILES NNN 2161+25( 1/ 1) 2552 92( 1/ 1) 2161 ~ 25- 2161+25 21 61 ~ 25 2161 ~ 25 2552 ~ 92 2652 ~ 92

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

b. Mean and range based upon detectable measurements only. rpraction of detectable measurements;at specified locations's dndicated in:parentheses,,(F).

Figure 6 0

a~

JJ Q

'o JJ Q C JJ C ANNIAL AVERAGE 0 'o JJ C C CJ JJ Preoperational Operational 6ROSS HEfA kT IVITY Q

SJ Phase Phase I N HRI tKI % HATER SUPPLIES C Prem FERRY ihCLEAR l&NT o N C

o C

JJ JJ cJJ rJ JJ Sl Vl o

JJ C O V

JJ C

C Q

O Averao,e: Preooerational Phase 4

Iri

. J r"+

I-'

,I

~

'J~

Irl

'I i~(.

G 'hl.

a !1-., !X 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 19 9 19 0 1 1 82 1 83 1 4

~f, (I 0 PIguru 7 W

4 Olrecl Rod(orion Levels 6rowns Ferry Nucleor Plonl 22 28 O((s I (e

\

I I'1 0

0 I i I,h,.~i I

i lI'I'1 /

0 I 18 I P.

0 I b 1 0

C

/ I 1

~

l (xg

~ + 0-g I (t I I 1 b \

I I I I I '1 I

Orrslie 'll It 12 1976 1977 1978 1979 1988 1981 1982 1983 1981 FIPure 8 2N Oirecl Rodioilon Levels groans Ferry Nucleor Plonl H-guorier, Moving Averoge

(. O((s((e 0

(. 0'0. (('A

18 ~ s 0

Pw~

/(/ /

16 0 '0'"'~

Offs(ie 12 1976 l977 1978 1979 1988 1981 1982 1983 198N

o 41 I'lluirr 9 24 Olrec I Radial Ion Levels Mails 8o( Nuclear Plan>

22 ll 4

(I e Ons>>e l 0

18 (

I e e,

'0~

i 0

i!!

I Ol I s>>eo o-e

('~

e I (

( (

'd 16 I ~ ( \ ('

0

(

'I( I ~

'e (

'o w

'l2 1976 1977 978 1979, 1988 1981 1982 1983 I 984 I'Igurv 10 2l 0 (reel Rod ol I on Levels 1

Valls 8or Nuclear Plonl 1-Ouorler Hov!ng Average 22 28 One( le 0

0.$

s 18 0 / ~ /e-on

'e. ~ e-~g'e ,O-.o i7(

e ~

elis>>e o-e~ e d

( 0 16 12 "

1976 1977 1978 I g7g 1988 Iggl 1982 I g83 1981

n o 43 Reservoir Monitorin Samples are collected from various Tennessee River cross sections as detailed. in table 23. Samples collected for radiological analysis include plankton from three of these 'cross sections and bottom fauna and sediment from four cross sections. The locations of these cross sections are shown on the accompanying map (figure 11) 'and conform to sediment ranges estabiishcd and surveyed by TVA.

Wa ter.

Water samples are collected automatically by sequential type sampling devices at three cross sections and composite samples analyzed monthly for gross beta and gamma-emitting radionuclides. Further composites are made quarterly for strontium and tritium analyses. In addition to these'equired samples, grab samples were also collected monthly from the vicinity of the plant discharge to the Tennessee River, and at a point on the Elk River, and analyzed for gross beta, gamma-emitting radionuclides, and strontium. Results are displayed in table 24. Figure 12 presents a plot of the gross beta activity in surface water from 1968 through 1984. No gross beta measurements were made in surface water samples in 1978. The levels reported are consistent with gross beta levels measured in surface water samples taken from the Tennessee River in preoperational 'monitoring programs conducted by TVA at other sites.

Fish Radiological monitoring for fish is accomplished by analysis of composite samples of adult fish taken from each of three contiguous reservoirs--

Wilson, Wheeler, and 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 25, 26, and 27.

Plankton Net plankton (all phytoplankton and zooplankton caught with a 100 ij mesh net) is collected for radiological analyses at each of three stations by vertical tows with a 1/2-meter net. At least 50 grams, (wet weight) of material is necessary for analytical accuracy. Samples are collected semiannually and submitted for gross beta analysis, and when quantities are sufficient, for gamma activity and Sr and Sr content. During this reporting period, samples collected during the first half of the year contained insufficient volume for any analysis. During the second half of the year, plankton could not be located in sufficient quantities to be collected.

~ rt a 44 Sediment Sediment samples are collected semianhually from Ponar dredge hauls made for bottom fauna. Gamma radioactivity and Sr and Sr content are.

determined in composite samples collected from each of four stations. Locations oE these stations are shown in table 23. Results are shown in table 28.

1 Bottom Fauna The flesh and shells of Asiatic clams collected semiannually'rom the cross sections at four stations (table 23) are analyzed for gamma-emitting radionuclides. Levels of Sr and Sr are "determined on the shells, and on the flesh when sufficient amounts were available. A 50-gram (wet weight) sample provides sufficient activity for counting. Results are given in tables 29 and 30. Clams from one location were not available; and from two locations, insufficient quantities were collected to permit analysis of clam flesh.

Table 23 SAMPLING SCHEDULE - RESERVOIR MONITORING Biolo ical sam les (collected semiannuall )

Zooplankton, chlorophyll, Benthic Water Samples River/river mile phytoplankton fauna Sediment Fish (collected monthly' Tennessee 277.9 X Tennessee 285.2 Tennessee 288.7 X Tennessee 291.7 Tennessee 293.5 Tennessee 293.7 (discharge area)

Tennessee 305.0 b

.(Control)

Tennessee 307.5 (Control)

Elk 20.5 (Control)

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

b. Automatic sampler.

c. Grab sample.

T ABt. c .24 RACiOACTiVITY IN SURFACE hATER TOTAL ssCI/L - 0 ~ 037 BO/L hAPl= CF FACILITY zoBtttth~z DOCKET NO ~ 's"=c22ciPstcZ R LOCATICN OF FACILITY t,jHggI('thy kcPORTzHu P>>RICO TYPE AHO LOwcR LIHIT ALL COHTRCL . HUYB R CF TOTAL HUHBcR CF IHCICATOR LCC 'ICtiS l QtiAIIOh ALIT LIt'ttt'0I AhltlAI LOCATIONS tiChROUT INE OF AHALYSIS OETECTIOh a EAM (F) b FAYE YEAh (F)S Yc AN <~>b REPORTEO b 2ISIntttif, >ht'IB=CII9h ~~hGhGj "=82QBEYghIK

~

4ycpsnc BA5<ta HG 2RBr()BE =9 IJ4$

GROSS ALPHA 2.COO C VALUCS <LLC 1 VALLES <LLC ANALYSIS P RFORY.ED GROSS BETA 1

2 '00 3 '2(

'4- 27/ 39) TRY 293 ' 3.31(

2.54-8/

4.25 13> 3.62(

43-20/ 25) 12.06 65 2 5.18 2 GAHHA (GELI) 6c hCT ESTAB 21.09( 5/ 39) TRY 285 ' 23 C5( 1/ 13) 23 43( 2/ 25)

K 4C C ~ 59-, 38 69 23 '5" 23 F 05 19 74- 27 ~ 12 BI-214 '<CT cSTA3 5.56( 14/ 39) TRY 293 ' 8.39( 5/ 13) 8 ~ 57( 15/ 26)

C.61- 18 71 BFh OIS CHARGE 2 ~ 18 18 ~ 71 0.72- 25 ~ 47 PB-214 HCT cSTA3 3.06< 7/ 39) TRY 293 ' 3 ~ 95( 4/ 13) 6.71( 14/ 25>

C.01.-.. 7 14>>. oFh- OISCI:ARGE 0 ~ 72- 7 ~ 14 0F 59- 18 'C PB-212 HCT cSTAB 1'1( 20/ 39) TRY 285 ' 2 '4( 5/ 13). 2 64(

'd- 7/

'5 26).

SR d9 10 COO 12 0 '0-VALUES <LLO 4 '2 0 99- 4. 52 0 8

5 VALUES <LLG 2C ANALYSIS PERFORYEO SR 9C 2 'Gv 12 VALUES <LLC 8 VALUES <LLC Zu ANALYSIS PERFORNEO TRIT IUH 330.COO 387 92( 2/ 12) TRY 29z ~ 5 416>>31( 1/ 4) 8 VALUES <LLO 2C 359 53- 416 ' 416 ~ 31- 416 ~ 31

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

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

TABLE 25 RADIOACTIVITY IN MHITE CRAPFI= (FLESM)

PCI/O - C.C37 BC/6 (CRY ~EIGl T) hAME CF FACILITY g(Q)lhA" fjggg 0GCl(ET NG. 'Q=i~2ciRQc2ZO LOCATICt'F FACILITY Lig~gJQgf h! ARnYik REPORTING FE RICO ()~<4 TYPE ANO LONER LIMIT ALL CONTROL NLvBER GF TOTAL NbMBER CF IllCICATOR LCCATIONS  ! QQiKEQl'iIL tIQL!ca'I Ahl s!A!. LcA4 LOCATIONS NC'iROUTILE (F)b

'( PEAN (F) (F)

OF ANALYSIS DETECTION a N NAPE MEAN REPCRTE" nANnc b P.ABQcb -b 5a cSQB~t'ghT 5 PE!!EQR" EQ KLI Q? Sl Q+5IBBQi She QIRLScQIIQ5 EBhQc

0. 100 e19( 4/ 4) hHE LcR 29 2/ 2) Zc ~ B9( 2/ 2)

GROSS BETA 2E 21 ~ 10 3 ~ 50 R

275-349 S

25 '9- 32.93 20.46- 37.33 GAMMA (GELI)

CS-137 0 ~ 020 C C9( / 4) WILSON RESERVCIR 0~ 11( 1/ 2) 0.09(

07-Z/ 2)

CE- 0 ~ 11 TRP Z55-275 11 C 11 0 C ~ 11 l(-4C NCT ESTAB C

15 'C( 4/ 4) NMEELER RES C

16

~

~ 14( 2/

~

2) 14 '9( 2/ 2) 12 'C- 17.51 TRP 275-349 14 ~ 77- 17 ~ 51 11 72- 1E.85 1/

BI-214 OsC20 C ~ C4( 1/ 4) ill.EELER RcS C.e4( 1/ 2) 0 02( 2) 04- O.C4 TRP 275-349 C.C4- ".. 04 C.02- C ~ 02

'.2-CD PB-214 NCT ESTAB CD 17( 2/ 4) wILSON REScMVCIR C.ZB( 1/ 2) . 0.03( 1/ 2)

C 05- O.ZB TRl'59-275 C ~ 28 0.03- 0.03 1/ 1/ 1/ 2)

PB-212 NCT STAB C 01(

C ~ 01- 0 ~ 61

4) Ql'EELER RES TRP 275-349 0 ~ C1(

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

0.00- 0 OC SR 89. 0 '00 2 VALUES <LLD 1 VALLES <LLC ANALYSIS P ERFORMCO SR 9C 0 ~ 100 2 VALUES <LLD 1 VALl:ES <LLC ANALYSIS PERFORMED 4

a. Foninal Lover Linit of Detection (LLD) as described in'able 3.

b. )lean and range based upon detectable neasurectents only. Fraction of detectable neasure=ents at specified locations is indicated in parentheses (F).

TABLE 26 RADIOACTIVITY IN SrALLMOUTt ELFFALC (FLESt)

PCI/G - C~ 037 BC/0 <CRY hEIGFT) h'NE FACILI CF LOCATICN OF FACILITY Y gBgBb5 gip2$ IliEs33I- ag fc2c45QL42a REFORTING PcRIOG TYP= ANO LQ~ER LI."IT ALL CONTROL NLrBER DF TOTAL NUNBER CF INCICATCR LCCATICNS LGHIiQh yiIU hi9gtSI Ahullkl vEE LCCATIONS NChRCUT ihc OF ANALYSIS CETCCT Ch a r EAU ( ) NAr 5 ~ REAh'F) RcPCRTcD Ef BFQBCRQ ELLE 8659= hi5IhbQ=.hbC OiB=GIIQh RAbkE an Bsa l.h94L/Ks ABi5 GROSS SETA 0.100 2' 1 2 56(

'2- 4/

39 '8

<<) htEELER RES TRr 275-345 32 'c(

25.'9-2/

39 1d

2) 20 ~ 42(

19 '6- 2/

20 'o GAHHA (GELI)

CS-137 Goi23 05( 3/ 4) Hgc L REc C.C6( 2/ 2) 0.06< 1/ 2)

C ~

CeG4- G.C7 R

TRr 275-349 C C4- 0.07 0 '6- C.06 j<-40 NCT ESTAB 12 '6( 4/ 4) 'Al EELER RES 15 ~ 44( 2/ 2) 12.11(

'4- 2/ 2)

BI-214 0 '20 2 '6" C ~ C4(

15.33 2/ 4)

TRr 275-349 hILSON RESERVCIR 12.55-G.C5(

15 1/

'3 2) 9 14 F 58 2 VALUES <LLC CeG4.- G.GS TRR 259-275 Ge(5" 0 F 05 PB 214 NCT ESTAB C.G4( 3/ 4) WILSON RES RVCIR Coi6( 1/ 2) 0.02( 2/ 2)

~ "C ~ 02 0 ~ Go ~TRR'59-275 C ~ C6- G~ 06 0 '1- GAG PB-212 NCT ESTAB e'o01( 1/ 4) MHEELER RES G C1( 1/ 2) 0 01( 2/ 2),

C.C1" G ~ 01 TRr 275-349 0 01 0 ~ 00" C ~ 01 SR 89 0.5GG 3.VALUES <LLC 1 VALLcS <LLC 4 'LYSIS PcRFORNEO SR 9C 0.100 VALUES <LLC 1 VALUES <LLC ANALYSIS PERFORNEO

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

b. Nean and ".ange based 'upon detectable =easurenents only. Fraction of 'detectable neasu'renents at specifieded locar.ions .is indicated in parentheses arentheses (F)

F .

TAEL3 27 RADIOACTIVITY IN SrALLMOOT.- 3lFFALC (VMGLE)

PC /C - C ~ 0 7 3 /G ("RY FE Gl T)

NAME cF FAcILITY  ! orb~'5 f!Eric NO ~ 2Q:222c262c22~

LO CATION OF FACILITY LgH!$ggQ!

TYPc Att5 LDa R a. PIT ALL CONTRCL Nb"" -R Oc TOTAL hGM3 ER CF ItiCIC>>TCR LCC>> TICitS LQCBI:91 dII(I Like!;I c'huuAl..".!AS LCCATIOi'IS h'CNR CL 1 I NE OF ANALYSI 0 T CTICh ÃE/N (F) hAYE BEAN (F) MEAN (F) RFPC=TEG o! ItfQR."! 2 SL,hu? aiNn% 4 b QL~<IBDC! Eh'IB!GIiIt5 868k! L'9 E b W!SKMoc"chloe GROSS SETA 6

0 ~ 10C 2'2(

13o60-

>>N 4/

33.71

4) WILSON RESERVCIR TRt'59-2?5 23ito( 2/ 2) 13.cO- 33 '1 15 '0(

15.55-2/

16.25 2)

GAtlNA (G=LI) 6 CS-1 37 0.020 C 04( 2/ 4) NILSON REScRVCIR 0 ~ C4( 2/ 2) .0.02( "

1/ 2)

C3- O.C4 TRt'59-2?5 O.C3- G.G4 0 02- 02 I(-4 C NCT ESTA3 C ~

E.56( /) )IILSDtt RESERVCIR TRI'59-275 9.65( 2/ 2) 7 '1(

7.61-G~

2/ 2) 7 ~ 27- 10.79 8 c1 10m?9  ? 62 0 '5(

~

bi-214 0 '20 C.03( 2/ 4) NILSON RESERVCIR 0 ~ C4( 1/ 2) 1/ 2)

PB Z14 NCT ESTA3 C ~ G2-C.04( 2/

0 '4 4)

TRt 259-275 IttIEELER RES O.C4" OeC5( 1/

0 '4 2) 0 05-0,04(

C~

=1/

05 2)

C.G3- Oo05 TRP 275-349 0 ~ CS- G.05 0 04- 0 04 PS-212 NGT ESTA3 Co01( 1/ 4) Itt'EELER RcS G.C1 ( 1/ 2) 0 ~ 01( 1/ 2)

C.C1- 0.01 TRY 275-349 0 ~ C1- 0.01 0 ~ 01- C.51 RA-223 NCT cSTA8 C ~ 26( 1/ 4) NILSON RESERVOIR 0 ~ 26( 1/ 2) 2 VAlUES <LlC AC-228 C ~ 26-CD Od( 1/

0 ~ co 4)

TRF 259-275 leILSON P.ESERVCIR 0 '0 0 Co( 1/

G~ 2o

2) 2 VALUcS <LLC C.CE- 0.08 TRP 259-275 Go(3- O.OS SR 89 0 ~ 500 2 VALUES <LLD 1 VALlES <LLC ANALYSIS PERFD>BED SR 9C 0 ~ 100 2-VALVES <LLD 0 0

'3(

'3- 1/

Co23 1)

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

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

TABLE 28 RADIOACTIVITY Ih'EC IFchT PCI/O - 0 '37 BQ/G (ORY )/EIGHT)

NE CF FACILITY ~~gg)lb) jn3$ $ O<<KET NO. RC=KZoc249422O LOCATICN OF FACILITY .I4E<<e5jgha REPORTING PERIOD TYPE ANO LQ~ER LIMIT ALL CONTRCl. NL'NSER CF TOTAl. NURSE R CF I!s 0 I C ATOR LOCA(IONS LCCAT IONS NGNRCL'TINE OF ANALYSIS "ETECTIOh PEAN (F) ..EAN (F) r At( (F)b REPORTED b

22EE9Rh=2 SI.L0} 8459E (ii'IA56i 65K 'dIBRCiTQB RANGE 8 !luC 5EAkl!R=rCNKS GANJA (GELI)

CO"60 0. C10 C ~ 31( <</ 5) Tgl'77.98 C'32( 1/ 2) 0 02( 1/ 2)

C.27- 0'36 0 ~Z- 0.32 OIGZ- C.02 CS 134c 0.060 C.14( 2/ o) TRY 293 ' G.1.7( 1/ 2) 2 VALUES <LLC C.1C- 0 17 SFh OISChARGE 0 ~ 17- 0 ~ 17 CS-137 O.C20 C.90( / 6) TRr 277 '8 0 ~ 95(

GI?d-2/ 2) Go48(

0.30-2/ '2)

C 7o- 1 ~ 12 1 ~1 2 C ~ 65 K-4C lCT ESTAB 14 ~ G2( 6/ o) Tpr 277 ~ 98 15i54( 2/ 2) 10 F 54( 2/ 2) 11.?B- 1o EZ 14 ~ Zo- 16 BZ 7 91- 13 ~ 38 Trr 277.98 2/ 11( 2/

BI-214 OoCZO 1.37(

0.94; 6/

1'2 o) 1 49(

1 ~ 44- 1 '4 2) 1 ~

1.01- 1 '1 2)

BI-212 0+ 100 2'01 ( 4/ 6) TRr'77 98- 2 ~ C6( 2/ 2) 1 ~ 45(. 2/ 2)

'B 1 86- 2 05 2 Co- 2.05 1 ~d 1 ~ 53 1 55( 6/ 5) TRr 288 ~ 78 1 ~ 64( 2/ 2) 25( 2/ 2) 214 NCT CSTAB 1 ~ 21" F 68 1 ~ c1 1.68 1

1 ~ 16-2/

1 '4 2)

PB-212 1<<49( 5/ 5). TRP 277.98 60( 2/ 2) 1 21(

VCT ESTAB 33-. '1 1 ~

~8 81 1 ~ 1d- '4 RA 225 NCT ESTAB 1 ~

1 ~

1 52(

~ 51-1 2/

1 '4 o)o) TR<< 277 '8 1 ~

1.54(

1 <4-1/

1 ~

1 ~ 54

2) 1 11(

1 01-2/

1 1 ~ 21 2)

RA-224 NCT ESTAB 1 '9(

1.69-1/

69 TRP BFh -

DISCHARGE

,1 e 69( 1/

'9 2)2) 1.28(

1. 28-1/

ZB 2)

TL-203 G.C20 C.53(

C ~ 33-1 6/

0 "1 o) TRr 277 '8 G~

0 56(

'2- 2/

1 0 '1 0.41 (

0.3"-

2/

1 ~

CD 44 2)

AC-228 0 C50 1+50( 6/ 5) TRr 2?7.98 1 ~ 73( 2/ 2) 1 ~ 22( 2/ 2) 1.17- 1.94 1 ~ 52 1 94 1 ~ 15- 1 28 PA-2348 1/ 40( 1/ VALLES <LLC SR 89 NCT ESTAB 1 '00 3eCC(

40" 3.40 VALUES <LLO o) TRY 277 98 3 3

~

~ CO- 3 '0 2) Z 2 VALLcS <LLC ANALYSIS PER FORHEO SR 9C 0.3GO 6 VALUES <LLC 2 VALLES <LLC c ANALYSIS PER FQRrgo

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

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

c. The distribution of 6 Co and Cs becween indicator and control locations reported herein is conparable13<to the distribution reported in the preoperational monitoring program from 1963 to nid-19?3. The levels reported for the isotopes and for Cs are also comparable with levels reported in sanples from the Tennessee River in preoperational monitoring prograns conducted, by TVA at other sites.

TABL F 29 RACIOACTIVITY It CLAII FLESI.

PCI/C C ~ 0 7 BC/0 (CRY W=IGI T) hAIIE CF FACILITY vc~ogbbg tc3ttg QCi(CT NO ~ cscr CRXLCswcZ os,p g LOCATION OF FACILITY {,AMggjggf,

• cAH'ike RcFORTING P=Rs"0 T'YPE ANO LOWE R LivIT AI.L CO NTROL Nl.i" " R TOTAL NUBBER c Iii'CICATCR LCCAbTICNS LGSAIIQh III'IMIICSI ~hbQhl 52c5 LCC AT IBNS NQh R O'. 1 I tl =

OF A IALYSIS 0"TECTION HE'N (F) NAPE vcAN (() < N ([)

2A iin r REFCRTc PCRF935=2 ELLil ~ is 59 ~ Q 528hCS 65K BLED:GIi9d 6~99r. Hs c 0AIIN'GEI.I) 5 K-40 NOT ESTAB VAI UcS <I 2.06( 2/ 2)

BI"214 3/

I 9r '0( 1/

1og5-1 ~ 32(

2 2/

'7 EST'6 2.47( 3) TRv 2?7 1) 2)

PB-214 NCT NOT ESTAB 1 '6-33(

3<<60 3/ 3) TRY 277

~

9E 3

3ocG-2.75( 1/

3 '0 1) OoE5(

2 2/

~ 2 2)

PB 212 NGT cSTAB 2

1 58-C.26(

2.75 1/ 3) TRP

~

2c= ~ 7E 2 75-0 26( 1/

2 75 1) 0 6~-

G.15(

1 1/

'7 2)

'TL-205 =STAB 0 '6- 0 'o 0 ~ 25- 0. 26. Go15-0.07(

C 2/

~ 15 2)

NCT 3 VALUES <LLQ 0 ~ 03- C ~ 1G AC-228 flOT EST'B 3 VALUES <LLG 1 ~ 39( 1/ 2) 1 ~ 39- 1 ~ 39

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

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

'TA'BL c 30 AO 0 CTIVITY I" LAP eHcLL oCI/O - 0 ~ 0'7 8>>/G (ORY HEI hT) ~

hAWE CF FACILITY 2pg'ctbg calif No. RE=2)2r2RCc2o" LOC'TICh OF FACILITY LJLtc~IIQJt ALAcP~A REPORTING PERICC TYP:'ND 'C>>ER LIM T ALL NQPBCR vc TOTAL NU4BER OF AtiALYSIS CF ETcCTION INQIC>>TOR LCCATICNS t',EAti (F)

LQCEII9h aIId NAPE CItt"~cSI Ehdhl EAbi'ONTRCL L>>chal tcEAh (FT LCCAT IOIJS HEcAN (F NChRCLT INE RcPCRTt>>

PRAEQBL'2 It!.RI Pl Qka JIHAD(I2 455 9IB=tcTIQlt 8BLANC+

~ lhTS Mgk~cliELZc "Lc GAUM'GELI) 7 K-4C "<CT 8 ST AB C.OG( 1/ 5) TRP :c.78 C ~ CO( 1/ 2) CD 13( 1/ 2)

CoCO- v ~ ~V C. CO- 0.00 0.13- C 13 BI-214 0+C50 ~ 22( 3/ 5) TRt'93.7 C.30( 2/ 2) C.15( 2/ 2)

C G.C7- 0 ~ 42 5/

BFh CISCMARGE 0.17-50( 1/

3 '2 1) 0.06-0.18(

CD 2/

23 2)

PB" 214 0 ~ C50 C ~ 28( 5) TRF 277 ~ 98 0F G.08- C.SC c0- 50 29 PB-212 ttCT ESTAB C.06( 3/ 5) TRP 288.78 C

C.C6( 2/

G~

2) 0 '?( CD 1/ 2)

C.C4- 0 ~ i7 G.C4- 0 F 07 Qe02- C.02 RA-226 Co050 C.C7( 1/ 5) TRP 288.78 0 ~ C7( 1/ 2) Go06( 1/ 2)

C C7- C C7- 0 07 C ~ Oo- 0.06 AC-228- Q.CoQ C.G7( 1/ 5) TRP 288 F 78 0. 7( 1/ 2) C 07( 1/ 2)

C.C7- O.C7 0. C7- 07 C.07- C.07 6.24( 1/ 5) TRP 293 F 7 6.24( 1/ 2) 2 VALLcS <LLC' SR 89 5 ~ COC 6.24- 6 F 24 bFh 0 I SCHA RG 8 o ~ c4.

2/

6 '4 2) '6( 1/  ?)

14( 4/ 5) TRP 288 7c 1+23(

SR 9C 1 COO 1 ~

1.01- F 24 1 ~ 21- 1 '4 1 ~ 16" 1>>16

a. Noninal Lo er Linit of Detection (LLD) as described in Table 3. (F).

b. Mean and =ange based upon detectable tceasurercents only. Fraction of detectable tceasurenents at specified locations is indicated in parentheses

Figure ll 53 R ESERVOI R MONITORING NETV/ORK N

Elk River WHEELER DAlVI mile 274.99 mile 277.98 Rogersville 0

mile 29I.76 Athens mile 282.6

,0

~mile 285.2 B.F. NUCLEAR PLANT

(

II Champion Paper Co.

ile 288.78 mite 293.50 mile 305.0

,,0 Cour tland rnite 295.TO 0

Decatur mile 307.52 Scale of Miles

~ - Automatic Sam ler 0

Pigure 12 Areeu AVERAGE e 6ROSS HETA ACTIVITY n Preoperational Operational o w Phase Phase IN SURFACE HATER n

4J o W

4l 4J HNMS FERRY NUCLEAR PLANT cc e Lr M o

o V

'o n n 0 Average:

't Preoperational Phase V

T kCI 1968 1969 1970 1 971 1972 1973P 19730 1974 1975 1976 1977 1 /8 1979 1980 " 1 $ 1 19 2 19 14

a. No gross beta neasuzements nade in 1978.

55 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. Me can expect that background concentrations would be distributed within these. limits. This provides us the basis for comparing control and indicator data. If the indicator data fall within the limits defined for control data, we conclude that the indicator data were not significantly affected by the nuclear plant.

If the data do not fall within the limits, we will perform further analyses to determine if the difference is attributable to the nuclear plant.

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

Dose estimates were made from concentrations of radioactivity found in samples of environmental media. Media sampled include, but are not limited to, air, milk, meat, vegetation, drinking water, and fish. Inhalation and ingestion doses estimated for persons at the indicator. locations were essentially identical to those determined for persons at control locations. Greater than 99 percent of those doses were contributed by the naturally occurring radionuclide potassium-40, and by strontium-90 and cesium-l37 which are long-lived radioisotopes found in fallout from nuclear weapons testing.

56 It is concluded from the above a'nalysis of the data and fr'om the trend plots presented earlier that there were. no,measurable increases in'he exposure to members of the general public attributable to the operation o'

,BFN. Indications of the presence of small quantities of fission products have been seen in aquatic media (for example, sediment). The levels measured were, similar to levels reported'n upstream samples collected in conjunction with preoperational monitoring pr'ograms being conducted by TVA at nuclear plant construction sites.