ML18032A686

Environ Radioactivity Levels Browns Ferry Nuclear Plant Annual Rept - 1985. W/860422 Ltr

ML18032A686
Person / Time
Site:	Browns Ferry
Issue date:	12/31/1985
From:	Gridley R TENNESSEE VALLEY AUTHORITY
To:	Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
NUDOCS 8712310150
Download: ML18032A686 (66)

Text

s REGULA. Y INFORMATION DISTRIBUTI SYSTEM (RIDS)

ACCESSION NBR:8712310150 DOC. DATE: 85/12/31 NOTARIZED: NO DOCKET FACIL: 50-259 Browns Ferry Nuclear Power Station> Unit 1> Tennessee 05000259 50-260 Browns Ferry Nuclear Power Station> Unit 2. Tennessee 05000260 50-296 Browns Ferrg Nuclear Power Station> Unit 3> Tennessee 05000296 AUTH. NAME AUTHOR AFFILIATION GRIDLEY> R. L. Tennessee Valley Authority REClP. NAME RECIPIENT AFFILIATION GRACE> J. N. Region 2> Ofc oF the Director

SUBJECT:

"Environ Radioactivitg Levels> Annual Rept for 1985. "

IrJ/860422 1 tr.

DISTRIBUTION CODE: IE48D COPIES RECEIVED: LTR TITLE: 50. 36a(a) (2) Semiannua'1 Effluent Release

+Reports ENCL Q SIZE:

NOTES: Q. Zech 3 cg. 1 cg. ea to: Ebneter> Axelrad> S. Richardson 05000259 B. D. Liaw> K. Barr> Donohew> OI.

Q. Zech 3 cg. 1 cg. ea to: Ebneter> Axelrad> S. Richardson> 05000260 B. D. Liaw> K. Barr> Donohew> OI.

Q. Zech 3 cg. 1 cg. ea to: Ebneter> Axelrad> S. Richardson> 05000296 B. D. Liaw> K. Barr> Donohew> OI.

RECIPIENT COPIES REC IP I ENT COP I ES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL JAMERSON. C 0 PD 5 5 GEARS> Q 1 STANG> J 1 lNTERN*L: ACRS AEOD/DOA 1 1 AEOD/DSP/TPAB ARM TECH ADV 1 NRR/DEST/PSB P/RPB 4 NRR/PMAS/ lLRB REG F LE 01 1 RGN2 FILE 02 RGN2/DRSS/EPRPB 1 1 EXTERNAL: BNL TICHLER> J03 LPDR 1 1 NRC PDR NOTES: 10 10 TOTAL NUMBER OF COPIES REQUIRED: LTTR 34 ENCL 33

gk

,i

TENNESSEE VALLEY AUTHORITY 5N 157B Lookout Place April 22, 1986 U.S. Nuclear Regulatory Commission Region II ATTN: Dr. J. Nelson Grace, Regional Administrator 101 Mari et ta Street, NW, Suite 2900 Atlanta, Georgia 30323

Dear Dr. Grace:

BROWNS FERRY NUCLEAR PLANT UNITS 1, 2, AND 3 ENVIRONMENTAL RADIOACTIVITY LEVELS ANNUAL REPORT 1985 Enclosed is a copy of the subject report prepared by the Tennessee Valley Authority pertaining to environmental monitoring at the Browns Ferry Nuclear Plant. This monitoring program is specifically responsive to the recommendations and requests of the U.S. Fish and Wildlife Service. We understand that NRC-NRR will transmit five copies of the report to the Secretary of the Interior.

Very truly yours, TENNESSEE V LE A HORITY R. L. Gridley, Director Nuclear Safety and Licensing Enclosure cc: Director of Nuclear Reactor Regulation (

Enclosure:

20)

Attn: Mr. R. M. Bernero, Director Division of BWR Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555 An Equal Oppartunity Employer

I ENVIRONMENTAL RADIOACTIVITY LEVELS BROWNS FERRY NUCLEAR PLANT ANNUAL REPORT " 1985 TVA/NUC SVS/RH 8712310150 851231 PDR ADQCK 05000259' PDR April 1986

-t

'k

CONTENTS List of Tables i11 List of .Figures. iv Introduction .

Atmospheric Monitoring ll Terrestrial Monitoring . ~ ~ ~ ~ 23 Reservoir Monitoring . 43 equality Control. 57 Data Analysis. 57 Conclusions. 58

LIST OF TABLES Table 1 Environmental Radioactivity Sampling Schedule . ~ ~ ~

Table 2 Atmospheric and Terrestrial Monitoring Station I,ocations - Browns Ferry Nuclear Plant .

Table 3 Detection Capabilities for Environmental Sample Analysis 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 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 Green Beans 34 Table 19 Radioactivity in Apples 35.

Table 20 Radioactivity in Potatoes 36 Table 21 Radioactivity in Beef . 37 Table 22 Radioactivity in Tomatoes 38 Table 23 Sampling Schedule - Reservoir Monitoring 45 Table 24 Radioactivity in Surface Water 46 Table 25 Radioactivity in White Crappie (Flesh) 47 Table 26 Radioactivity in Smallmouth Buffalo (Flesh) 48 Table 27 Radioactivity in Smallmouth Buffalo (Whole) 49 Table 28 Radioactivity in Sediment . 50 Table 29 Radioactivity in Plankton . 51 Table 30 Radioactivity in Clam Flesh . 52 Table 31 Radioactivity in Clam Shell . 53 111

LIST OF FIGURES Figure l - Tennessee Valley Region . 9 Figure 2 - Atmospheric and Terrestrial Monitoring Network 18 Figure 3 - Local Monitoring Stations 19 Figure 4 - TLD Locations, BFN 20 Figure 5 - Annual Average Gross Beta Activity in Air Filters, Browns Ferry Nuclear Plant 21 Figure 6 - Annual Average Gross Beta Activity in Drinking Water, Browns Ferry Nuclear Plant 39 Figure 7 - Direct Radiation Levels, BFN 40 Figure 8 - Direct Radiation Ievels, BFN (4-Quarter Moving Average) 40 Figure 9 - Direct Radiation Levels, WBN 41 Figure 10 - Direct Radiation Levels, WBN (4-Quarter Moving Average) 41 Figure ll - Reservoir Monitoring Network 54 Figure 12 - Annual Average Gross Beta Activity in Surface Water 55

ENVIRONMENTAL RADIOACTIVITY LEVELS BROWNS FERRY NUCLEAR PLANT ANNUAL REPORT 1985 Introduction The Browns Ferry Nuclear Plant (BFN), operated by the Tennessee Valley Authority, is located on a site owned by TVA containing 840 acres of land in Limestone County, Alabama, bounded on the west and south by Wheeler Reservoir (see figure 1). The site is 10 miles southwest of Athens, Alabama, and 10 miles northwest of Decatur, Alabama.

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

Unit 2 began commercial operation on March 1, 1975. However, a fire in the cable trays on March 22, 1975, forced the shutdown of both reactors. Units 1 and 2 resumed operation and Unit 3 began testing in August 1976. Unit 3 began commercial operation in January 1977. The plant has been shutdown since March 1985.

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

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

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 Area Radiological Laboratory (WARL) located in Muscle Shoals, Alabama.

Alpha and beta analyses were performed on Beckman Low Beta II, low background proportional counter or a Tennelec LB-5100. Nuclear Data (ND) Model 6700 system, in conjunction with germanium detection systems, were used to analyze the samples for specific gamma-emitting radionuclides. Specific analysis for iodine-131 in charcoal filters was performed using NaI(Tl) well detector systems attached to single channel analyzers. A TVA fabricated beta-gamma coincidence counting system was utilized for the determination of iodine-131 concentrations in milk. Analysis for low-energy beta emitters such as tritium was performed using Packard Tri-Carb Model 3255 and 4000 series liquid scintillation systems.

Data were entered in computer storage for processing specific to the analysis conducted. The 'data obtained by germanium detectors were resolved by the appropriate analyzer softwar'e 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 fo'und in germanium spectra were identified and quantified. Many of the isotopes identified by germanium spectral analysis are naturally occurring or naturally yroduced radioisotopes, such as Be, K, 212Bi 214Bi 212Pb, Pb '226Ra etc. LLDs for radionuclides identified by Ge(Li) an'alysis were calculated for each analysis and'nominal values are listed in table 3B. In the instance

'where an LLD h'as not 'been est'ablished', an LLD value of zero was assumed.

A notation in a t'able of " "values <LLD" for an 'isotope with no established XLD does not imply 'a value less than 0; rather it indicates that "th'e isotope was 'not identified in that spec'itic 'group o'f samples.

For each sample type, 'o'nly the radionuclides 'for which values greater

'than 'the LLD we'e reported are li'sted in the data, tables.

TVA's WARL participates in the Environmental Radioactivity Laboratory Inte;comparison Studies 'Prog'ram 'c'onducted by 'EPA-Las Vegas.

This program 'provides per'iodic cr'oss-checks on samples of the type and

'radionuclide composi'tion normally analyzed in an 'environmental radio-logical monitoring p'rogram; Route'ne sample handling and analysis p"

cedures were employed in the 'eval'ua'tion o'f 'the's'e 'sa'mples. The results received during calendar year 1985 are shown 'in table 4. The based on one 'measurement, were d'i'vided 'by the 'square roo't of 3

+3o'imits to correct for 'triplicate determinati'o'ns.

Table 1 EWIRONMENTAL RADIOACTIVITYSA!IPLIVC SCHEDLLE Station Location Air pygmy Charcoal rilt e ill Rain- Heavy P~rticle c s il~VDci River Mell Public Aquatic Life Milk I:c l4a 4 asdi I 1 di Huscle Shoals M ~ M II Lavrenceburg Rogersville Athens Decatur Courtland Site 1 (H)

Site 2 (NNE)

Site 3 (ENE)

Site 4'NNV) A Site 5 ('WSM)

Farm B M M Farm Bn+ M M Farm Poo M 'V Farm L M Farm E Farm V Control Farms M V Onsite Mell Wheeler Dam Elk River Tennessee River Champion Paper Co.

Various Local Farms M - Veekly H - Monthly (every 4 veeks) Q

- Quarterly S - Semiannually A - Annually

• Sampling commenced November 1985

<<eDiscontinued operation October 1985

)

0 Table 2 Atmospheric and Terrestrial Monitoring Station Locations Browns Ferry Nuclear Plant Sam le Station Approximate Distance and Direction from Plant LM-1 BF, North 1.0 Mile (1.6 kilometers) N LM-2 BF., North-Northeast 0.9 Mile (1.4 kilometers) NNE LM-3 BF, East-Northeast 1.0 Mile (1.4 kilometers) ENE LM-4 BF, North-Northwest 1.7 Miles (2.7 kilometers) NNW LM-5 BF, West-Southwest 2.5 Miles (4.0 kilometers) WkW PM-1 BF, Rogersville, AL 13.8 Miles (22,2 kilometers) NW PM-2 BF, Athens, AL 10.9 Miles (17.5 kilometers) NE PM-3 BF, Decatur (Trinity), AL 8' Miles (13.2 kilometers) SSE PM-4 BF, Couri.land, 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, 'awrenceburg, TN 40.5 Miles (65.2 kilometers) NNW (Control)

Farm Bn> 4.g5 Miles (7.6 kilometers) N Farm B 7.0 Miles (11.3 kilometers) NW Farm L 5.0 Miles (7.0 kilometers) NE Farm P-'~ 8.8 Miles (14.1 kilometers) E Farm E 6.1 Miles ( 9.8 kilometers) NE Farm W 6.9 Miles (11.0 kilometers) NE Farm N (Control) 27.0 Miles (43.4 kilometers) NW Farm J (Control) 40.0 Miles (64.4 kilometers) NNW Farm C (Control) 32.0 Miles (51.5 kilometers) N Farm Ca (Control) 32 ' Miles (51.5 kilometers) W Farm Cb (Control) 22,5 Miles (36.2 kilometers) E Farm M (Control) 22.5 Miles (36,2 kilometers) ENE

>> Sampling commenced November 1985

>+"Discontinued operations October 1985

Table 3 DETECTION CAPABILITIES FOR ENVIRONHENTAL SAHPLE ANALVSIS A. S ecific Anal ses NOMINAL LOWER LIHIT OF DETECTION (LLD)*

Fish, Air Vegetation Soil and Clam Flesh, Foods, Heat, Particulates Charcoal Fal lout Water and Grain Sediment Plankton, Clam Shells Poultry, Hilk pCi/m ~Ci/n mCi/K pCI/i pCi/<i, Dry ~CI/ ~Dr ~C'/ De ~Ci/ De ~Ci/K m Wee KClll Gross a 0.005 2 0.05 0 '5 0.1 0.1 0.7 0.7 25 Gross B 0.01 0.05 2 0.20 0.70 H-3 330 1-131 0.01 0.5 Sr-89 0.005 10 0.25 1.5 0.5 5.0 40 10 Sr-90 0.001 2 0.05 0. 15 0.1 1.0 8 2

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

factors such as sample size, decay time, chemical yield, and counting efficiency may varyareforanalyzed a given sample; these variations The assumption Is made that all samples within one week of the

~

may change the LLD value for the given sample. z collection date. Conversion factors: I pCi mm 3.7 x 10 Bq; 1 mCi mm 3.7 x 10 Bq.

Table 3 DETECTION CAPABILITIES FOR ENVIRONHENTAL SAHPLE ANALYSIS B. Gamma Anal ses NOHINAL LOWER LIHIT OF DETECTION (LLDl Air Water Vegetation Soll and Clam flesh Foods, (tomatoes Heat and particujates and milk and grain sediment Fish and plankton Clam shells potatoes, etc.) poultry

~CI/

I ~pCI/ dr pCi/c dr pCi/< dry g>C I / i dr)/ pCi/< dr~ Cl/K , wet Ci/K wet Ge LI

• Ge Li Ge Li GeYL~I ~Ge L~I ~Ge L~i Ge I~LI Ge Li Ge Li Ce-144 0.02 33 0.22 o.o6 o.o6 0 35

~ 0.06 33 40 Cr-51 0.03 44 o.47 0.10 0. 10 o.56 0.10 44 90 I-131 0.01 8 0.09 0.02 0.02 0.07 0.02 8 20 Ru-106 0.03 30 0.5I 0.11 0.11 0.74 0. 11 4o 90 Cs-134 0.01 5 0.33 o.o8 0.07 o.48 o:o8 26 40 Cs-137 0.01 5 o.o6 0.02 0.02 o.o8 0.02 5 15 Zr-95 O.OI 10 0.11 0.03 0.03 0.15 0.03 10 20 Nb-95 0.01 5 0.05 0.01 0.01 0.07 0.01 5 15 Co-58 0.01 5 0.05 0.01 0.01 0.07 0.01 5 15 Hn-54 0.01 5 0.05 0.01 0.01 o.o8 0.01 5 15 Zn-65 0.01 9 0.11 0.02 0.02 0.17 0.02 9 20 Co-60 0.01 5 o.o6 0.01 0.01 o.o8 0.01 5 I5 Fe-59 5 0. 10 Ba-140 0.02 25 o.34 0.07 0.07 0.30 0.07 25 50 La-14O 0.01 7 0.08 0.02. 0.02 0.10 0.02 7 15

< The Ge(Li) LLD values are calculated by the method developed by Pasternack and Harley as described in-HASL-300. These LLO 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-L Harinelli beaker as dry weight. The average dry weight is 400-500 grams. Air filters and very small volume samples are counted in petri dishes centered on the detector endcap. The counting system consists of a ND-6700 multichannel analyzer and germanium detector having an efficiency of 20 percent. The counting time is normally 4-15 hours. All spectral analyses are performed using the software program HYPERHET. 2The assumption is made that all samples are analyzed within one week of the collection date.

Conversion factor: I pCI ~ 3.7 x 10 Bq.

Table 4 RESL'LTS OBTAINED IN INTERLABCFA.OPY COMPARISON PROGRAM A. Air Filter (pCi/Filter)

'Gross Alpha Gross Beta Strontium-90 Cesium-137 EPA value TVA EPA value TVA EPA value TVA EPA value TVA Date (+3c) Avg. (+3(r) Avg. (+3a) Avcv. ~(t e) Avc).

11/84 15+9 15 52+9 61 21+3 21 10+9 10 3/85 10+9 ]1 36+9 40 15+3 16 6+9 6 8/85 13+9 12 44+9 45 18+3 16 8+3 9 B. Tritium in Urine (pCI/R)

Date EPA value (+3a) TVA AvcV.

4/85 3056+622 2687 7/85 2444+610 2280 C. Radiochemical Analysis of Water (pCi/R)

Gross Alpha Gross Beta Strontium-89 Stronium-90 Tri tium Iodine-131 EPA value TVA EPA value TVA EPA value TVA EPA value TVA EPA value TVA EPA value TVA

(+3a) ~Av . (+3a) Av(V. (+3a) ~Av . (+3a) AvcV ~ (t3e) ~Av 4/84 23+9 22b 26+3 26 1/85 5+9 15+9 19 3+9 30+3 29 2/85 3796+634 3817 3/85 6+9 6 15+9 17 4/85 355"+630 3347 7.5+1.4 7.3 72+9 69 10+9 9d 15+3 16 4/85'/85 12+9 9 11+9 14 39+9 49 15+3 13 6/85 2416+608 2257 7/85 11+9 12 8+9 8/85 4480+776 4127 33. +10 29 9/85 8+9 8 8+9 12 20+9 26 7+3 10/85 1974+598 1880

Table 4 (Continued)

RESULTS OBTAINED IN INTERLABORATORY COMPARISON PROGRAM (Continued)

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

Chromium-51 Cobalt-60 Zinc-65 Ruthenium-106 Cesium=l 4 Cesium-13>

EPA value TVA EPA value TVA EPA value TVA EPA value TVA Ep!'alue TVA Date (+3a) ~Av ~ (+3a) ~Av ~ (+3a) Av(V a (-3a) AvcV (+3a) ~Av . (+3a) Ave ~

4/84 3%9 30 3%9 2/ 26+9 27 2/85 48a9 45 2%9 20 5R5 53 2%9 40b 35+9 32 25+9 25 4/85 15+9 16 15 9 15 12+9 13 6/Sc 4ir+9 IIOb 14-9 14 47 9 48 62='9 53 35+-9 34 20+9 19 10/85 21+9 40 2%9 21 19+9 20 20 9 25 20+9 18 20+9 20 E. Food (pC i/Kg; Wot We r ght)

Strontium-89 Strontium-90 Iodine-131 Cesium-137 Potassium-40 value TVA value TVA EPA value TVA Date EPA

(+3a} ~Av . (+ 3a) Avg.

EPA

(+3 ) AvcV a (+3a) Ava. ~ta ~Av 1/85 34+9 37 26+3 37 35+10 33 29+9 28 1382+208 1270 7/85 34 26+3 34 f 35+10 36 29+9 31 1514+132 1567 F. Mi 1 k (pC I/vE!

Strontium-89 Strontium-90 Iodine-131 Cesium-137 Potassium-40g tW ~ ~ EPA value TVA EPA value TVA EPA value TVA EPA value TVA Date (+3a) AvcV (+3a) AvcVe (+3a) Avg. (+-3a) I'vg. (+-3a) ~Av .

3/85 9+1 ~ 6 llh 6/85 11+9 13 11+3 11 11+10 11 11+9 12 1525+132 1680 t

a ~ Laboratory perfcrmance evaluation study. Results received from EPA ir April '1985.

b. Below LLD ~

c. Labortory performance evaluation study.

d. The analysis was reviewed. Cause for high results could not be identified.

e. Values reported as mg K/kgb

f. Possible error due to nonhomogeneity of sample. EPA used dog food ccntaining bone

!real in the preparation of the food cross-check.

g. Values reported as mg K/II Results were investigated'o source of error, was determined..

i'Igh bias on result due to broader ing of the peak used for identifying K-40. The low abundance and low court'.-!"tt eff1ciency for the 1460 Kev line inflated th<< small. positive bias'aused by temperature-variations. ~

V ~

M

~~ las 5 O.-

}~

~

5'.J r

~

I

.-= 50"C L

~ aoVCui%'

l

/

L

/

~

(

(

/+T)

I

)

A',Il.:

l

~ 'Q N~iN IND

..~

80wUIIG

-'~c

-~c K

GREEN l5HVILI.

E E

N LOUI5VC.LE T

(~z I

so TENNESSEE VALLEY REGION P

(TVA NUCI EAR PLANT SITES)

/

Ei U

/

~/"V C

~

04K A!0GCp y

K Y v

@5M i

V'~

J jl

)

~

W I

..iC VA.

r "p-.

A R.

l

\

I CHATYJN00GA~ ~

~

~)

\ QHWT5vkLC \ a J ~ S C 4 R.

lg / J

~ Qfll $

NV5CI.E 5~L5 I/ LEGEND I -- .<~b /

M I S S.

A L A 8 A

/J M A GEORG I A

~-

ZS

-WaTTs enR NucLEaR PLaNT

-sEouoYAN Nucl.EAR PLANT BELLEFONTE NUCLEAR PLANT

.-. QROWNS FERRY NUCLEAR PLANT

Atmos heric Monitorin The atmospheric monitoring network is divided into three groups. Four local air monitors are located on or adjacent to the plant site in the general areas of greatest wind frequency. One additional station is located at the point of maximum predicted off-site concentration of radionuclides based on preoperational meteorological data (see figures 3 and 4). Four perimeter air monitors are located in communities out to about 13 miles from the plant, and two remote air monitors are located at distances out to 45 miles. These monitoring stations are shown in figure 2. The remote monitors are used as control or baseline stations. At each local monitor, air is continuously pulled through a Hollingsworth and Voss LB5211 glass fiber particulate filter at a flow rate of about 3 fthm/min. At perimeter and remote monitors the system has been modified so that air is continuously pulled through a 1-7/8 diameter glass fiber particulate filter at a flow rate of about 2 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.

T Each of the local air'onitors is fitted with a GM tube that continuously scans the particulate filter, The disintegration rate of the atmospheric radioactivity is continuously recorded at each station and radiotelemetered into the plant.

Air Filters Air filters are collected weekly and analyzed for gross beta activity. Adequate time is allowed for decay of radon daughters between collection and analysis of samples. This time is typically three days.

The samples are composited monthly for analysis of specific gamma-emitting radionuclides and quarterly for Sr and Sr analysis. The results are combined for each station to obtain an annual average.

These data are presented in table 6. During this reporting period, two samples were not obtained because of equipment malfunction, two samples were damaged beyond use, one sample was destroyed during analysis, and one sample was lost during sample change.

The annual averages of the gross beta activity in the air particulate filters at the indicator stations (local and perimeter monitors) and at the control stations (remote monitors) for the years 1968-1985 are presented in figure 5. Increased levels due to fallout from atmospheric nuclear weapons testing are evident, especially in 1969, 1970, 1971, 1977, 1978, and 1981. These patterns are consistent with data from monitoring programs conducted by TVA at nonoperating nuclear power plant construction sites. Table 5 presents the maximum permissible concentrations (MPC) specified in 10 CFR 20 for nonoccupa-tional exposure.

12 Rainwater Rainwater is collected monthly and a 3.5-liter sample analyzed for specific gamma-emitting radioisotopes and tritium. The results are shown in table 7. During this reporting period, four samples were hot available due to insufficient rainfall and three samples were not'.

collected due to human error.

Fallout The gummed acetate that is used to collect heavy particle fallout is changed monthly. The samples are ashed and counted for gross beta activity. The results are given in table 8.

Charcoal Filters Charcoal filters are collected and analyzed for radioiodine, The filter is counted in a single channel analyzer system. The results are shown in table 9. During this reporting period, five samples were not taken because of equipment malfunction or filter damage and one sample was destroyed during analysis.

13 Table 5 tMXIMUM PERMISS IBLE CONCENTRATIONS FOR NONOCCUPATIONAL EXPOSURE In Water In Air

~Ci/1* ~Ci/m'*

Alpha 30 Nonvolatile beta 3,000 100 Tritium 3,000,000 200,000 1 37Cs 20,000 500 10 3 106Ru

~

10,000 200 144( 10,000 200 "Zr-"Nb 60,000 1,000 Ba- La 20,000 1,000 131I 300 . 100 6SZ 100-,000 2,000 4Mn 100,000 1,000 6 OCo 30,000 300 "Sr 3,000 300 90Sr 300 30 51(.r 2,000,000 80,000 "4C 9,000 400 "Co 90,000 2,000

• 1 pCi ~ 3.7 x 10 Bq.

TABLE 6 RADIOACTIVITY IH AIR FILTER PCI/H(3)' 0 ~ 037 BQ/H(3)

NAME OF FACILITY989955 EEBBI DOCKET NO 59=222/2(IQc2.R LOCATION DF. FACILITY LIUESIQUE REPORTI IG PERIOD

~

TYPE AHD LOsIER LIMIT ALL CONTROL NUMBER OF

'OTAL NUMBER OF INDICATOR LOCATIONS L996IIQB III'IQUESI 65596l. 5E65 LOCATIONS NONROUTINE

)F AHAlYSIS DETECTIOH MEAH (F) NAME MEAN (F) McAN (F) REPORTED PERFORMED (LLD) RANGE DISTAHCE ANO DIRECTION RANGE RANGE MEASUREMEHTS XEE UQIE 1 EE gQIE BEE DQXE 2 Kfi hQIE 2

'GSS ALPHA 5.00E-03 6.73E-03( 1/ 52) 52 6i?3E 5.738-03 1.0GE-02 '4E-GZ( 44 9/ 46Z). 2i09E"02( 103/ 1~~~)

- 50/

!OSS SETA 1 OECATURr AL 2 13E-02 ( 52)

'0E ~

566 OOE 02 4 33E 02 8 ~ 2 MILES SSE 1 .18E-02 5.o9E-02 1 3 64E-02 1HHA (GELI) 145

'"40 NOT ESTAB 1 ~ 51c-02( 43/ 117) LH1 SF NORTHMEST 2 42E"02( 7/ 13) Bo18E-03( 11/ 25) 4 'Gc 3 '3E-OZ 1 ~ 0 MILE N 9 '0c 5 '6E"02 1 '08-03 1 '38-02 sI-214 2.00E-02 2.428-02( 2/ 117) I.H3 SF NORTHEAST' Zo68E-02( 1/ 13) 25 VALUES <LLO 2 '6E-02. - 2 '8E-02 ~ 0 HILE ENE 2.68E-02 2.68E-02 sI-212 HOT 1+4?E-OZ( 1/ 117) LM3 SF NORTHEAST 1 '7E-02( 1/ 13) 25 VALUES <I.LD ESTAB'.GGE-GZ 1 '?E 1 47E-02 1 ~ 0 MILE ENE 1.47E-02 1 '7E-02

>8-214 2/ 1'17) '3E-02(

- 1/

2 72E-02( LM3 BF NORTHEAST 3 1'3) 26 VALUES <LLD 2+36E-OZ - 3.08E-OZ 1 ~ 0 HILE ENE 3.08E-02 3.083-02

)8-21 '6E-04( - 19/ 117) 5.008-04( 3/

2, HOT EST'AS 3 1.00E-04 1eOOE-03 LM3 BF NORTIiEAST 1 ~ 0 HIL'E ENE 5.00E-04. - 51/'OE-04

13) 3oGOE-04 (

2 'OE-04 5 DG 26)

-04

)E-7 8 '9E-02.( 94/ 117) DECATURr Al 1.02E"01( '1E-01 ( 22/ 25)

- 11/

SPODE-02 15) 1 5 '0E 02 1 '5E 01 8 ~ 2 HIlES SSE 5.76E-02 1.34E-01 oo31c-'02 -'.43c-"1 rl-208 NOT CSTAB 1 SGE-04( 5/ 117) ROGERSVILLEr AL 2.00E-04( 1/ 13) g.OCE-04 ( 2/ 25)

'0c 2 'OE-04 -

~

1 13 ~ 8 MIlcS NSI 2 'OE-04 2.00E-04 1 'GE-04  ?.OOE-04 XC-228 rIOT- ESTAB 2.72E-05( 12/ 117) ATHENSr AL SoOGE-05( 1/ 15) 9o5CE-04 2/ 26)

? OOE 7.50E-03

~ 10 ~ 9 MILES NE 5 ~ GOE-03 -. 5 ~ ODE-03 9 ~ GOE-04 1.0GE-G3 89 5.00E-03 36 VALUES <LLD 8 VALUES <I.LD 44 ANALYSIS PERFORHED R 90 1 ~ DOE-03 36 VALUES <LLO VAlUES <LLO 44 ANALYSIS PERFORHED MOTE: 1 ~ NOHINAL LOSIER LIMIT OF DETECTION (LI.D) AS 0 SCRIBED IN TABLE 3 ~

NOTE: 2 ~ MEAN ANO RANGE BASED UPON DETECTABLE HEASUREMENTS ONLY ~ FRACTION OF DETECTABLE MEASUREMEIITS AT Sc CIFI 0 LOCATIONS IS INOICATEO IH PARENTHES "S (F) ~

TABLE 7 RADIOACTIVITY IN RAINwATER PCI/L " 0.037 80/L NaHE OF FACILITY $ $ QUU5 EEBttI DOCt(ET ttO ~ NQ:252c2094226 LOCATION OF FACILITY l IttHIQUE REPORTING cERIOD 19tih TYPE ANO l.OWER LIMIT ALL CONTROL NUMBER OF TOTAL "tUHSCR OF I'tOICATOR LOCATIONS IQQRIIQU BIIU UIQUEXI hUUQ&L, BEAU LOCATIONS NONROUTINE OF ANALYSIS OETcCTION HEAlt (F) NAME MEAN (F) MEAN (F) RcPORTEO PERFORMED (LLO) RANGE DISTANCE ANO DIRECTION RattGE RANGc HcASUREcHEVTS Xff UQIE 1 Gff UQIE 2 Gff UQIE 2 Sff UQIc 2 GAM"ta (GcLI) 136 t("40 20.64( 15/ 112) ATHENS'L 35.62( 2/ 12) 2m 1 8 ( 2/ 24)

NOT ESTAB'OT 4 '2 - os 94 10 ~ 9 HILES NE 5

'3(

~ 30- 65.94 0 '9 - 3.67 8I-214 ESTAo 5 '2(

0 56 - 59/ 112) 29eSB LHS BF OA VIS F 2 5 HILES 9

0 '5 o/ 13)

29. 58 bI60(

Oe04 - 12/

20 24)

'2

'4(

~

3/ 5.58( 4/

WSW'H5

>8-21 35/ 112) BF DAVIS F 9 ~ 10( 13) 24) 7 '4 NOT ESTAB 4 5 0 33 "

'0(

21 '5 2 ~ 5 HILES WSW 1 ~ 58- 21 05 0 '1 -

P8-21 2 NOT ESTAB 1 0.01 -

29/ 112) 6.05 LH5 8F OA VIS F 2 ' MILES WSW 2.83(

0.43 4/ 13) o.05 2.39(

0.05 - 7/ 24) 5.97 3E-7 NOT =STAB 58.12( 24/ 112) LH1 SF NORTHWEST 78 '6( 6/ 13) 54o56(

'2 8/

- 106 24)'5 24.G9 - 197 7o 1 ~ 0 MILE N 37 82 197 75 31 TRITIUM S30+00 1'l2 VALUES <LLO VALUES <LLO 136 ANALYSIS PcRFDR.'IED NOTE: 1 ~ NOMINAL LOWER LIHIT OF DETECTION (LLO) AS DcSCRIBED Itl TABLE 3 ~

VOTE: 2. HEAN ANO RA'VGE BASED UPON DcTECTASLE MEASUREMENTS ONLY. FRACTION OF DETECTABLE MEASUREt ENTS aT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) ~

TABLE 8 RADIOACTIVITY IN HEAVY PARTICLE FALLOUT HCI/KH(2) - 37000000 F 00 BQ/KH(2)

NAHE OF FACILITY !!gQ!!g$ f f!!!!g DOCKET NO.

LOCATION OF FACILITYl,j!!g5XQHg Ai!!!!!!!! 8 2{i=202cRCQc'if'EPORTING PERIOD -gP!!$

TYPE AND LOMER LIHIT ALL C04TROL NUHBcR OF (OTAL NUHBER OF INDICATOR LOCATIONS  ! 964IIQU !!I15 VIQ!!ESI hU!!!!6! 5ESU LOCATIONS NONROUTI4E

)F ANALYSIS DETECTION HEAN (F) NAHE HEAN (F) HEAN (F) REPORTED PERFORHED (LLD) RANGe DISTANCE ANO DIRECTION RANGE RANGE HEASURE<EMTS Gff (!QEf 1 See 8QIE 2 GPE 5Q..R  ? RER 5QIE 2 0 16( 108/ 117) 0.31( '.11 ( - 25/

0 ~ 05

- 13/ 13) 26)

ROSS BETA LH4 BF TRAILER P 143 0.06 - 0 F 88 1 ~ 7 HILcS NtlM 0.06 0.88 0 F 05 0.20 NOTE 1 ~ NOHINAL LONER LIMIT OF DETECTION (LLO) AS DESCRIBED IN TABLE 3 ~

NOTE: 2 ~ H AN AND RANGE BASED UPON DETECTABLE HEASUREHENTS ONLY FRACTION OF DETECTABLE H EASUREHENTS AT SPECIFI D LOCATIONS IS INOICATEO IN PARENTHESES (F) ~

TASLE 9 RADIOACTIVITY It( CHARCOAL FILTERS PCI/H(3) - 0 ~ 037 8Q/H(3)

NAHE OF FACILITY ilgQWlig EfililI DOC!(ET "lO 2Q:222'?(tQc?2E LOCATIOtl OF FACILITY l.Il)EKIQHE 8! 8EhL8 RcPORTING PERIOD gPgS TYPE A!lO LONER LIMIT ALL CONTROL NVHSER OF TOTAL NUMBER OF IhOICATOR LOCATIOtlS  !.QQAIIQB ttIIl! ~I%i)EKI 8(tt!M8!. 5=!!L3 LOCATIONS NONROUTINE OF ANALYSIS OcTECTION HE Atl (F ) NAME HEAtl (c) MEAN (F) REPORTED PERFORHEO (LLD) RAttGc DISTANCE AND DIRECTION RANGE RAtlGE EASUREHcNTS gfc iiQIE 1 EEE tiQIE 2 REE ilQIE ? SEE 5QIE 2 68/ 0.02(

IODINE-1 31 566 0.01 0 02(

0.01 - 452) 0 '3* LF1 dF NORTHNEST 1.0 MILE N 0.01 - 12/ 0.13"

52) 0 ~ 01(

0.01 - 15/ 104) 0 ~ 02 NOTE: 1 ~ tlOHINAL LONE'R LIHIT OF DETECTION (LLD) AS OCSCRIEEO It( TA8LE 3 ~

NOTE: 2 ~ MEAN ANO RANGc BASED UPON OETECTASLc HcASURcHENTS ONLY'RACTION OF DETECTASLE MEASUREMENTS AT SP CIFI 0 LOCATIONS IS INDICATEO IN PARENTHESES (F) ~

• This valve is inflated because of radon interference.

18 Figure 2 ATMOSPHERIC AND TERRESTRIAL MONITORING NETWORK RM.2BF LAWRENCEBURG yPULASKI FAYETTEVILLE WII.SON PM-IBF WHEELER ROBE SVIL FLORENCE OAM ATHENS PM-28F FFIEL MUSCLE SHOALS BROWNS FERRY HUNTSVILLE RM-IBF NUCLEAR PL LEIGHTON TUSCUMBIA COURTLANO PM-4 F OECAT PM-38F 0 IO MILES pRUSSELLVILLE GUN T SVIL HARTSELLE OAM 4

25 HALEYVILLE

~CULLMAN 45 MILES O- ENVIRONMENTAL MONITORING STATION NOTE: THE FOLLOWING SAMPLES ARE COLLECTED FROM EACH STATION:

AIR PARTICULATES RAINWATER RADIOIODINE SOIL HEAVY PARTjCLE FALI OUT

LOLL MONITORING RATIONS 19,I BROWNS FERRY NUCLEAR PLANT ATHENS US HWY 72 C3 0

BFN ALA. HWY 20 Legend h

Air Monitor DECATUR AUtomatic Well Sampler Dairy Farm Other Fnrms Scale 0 I 2 3 4 6 Miles

-~ %e-~=~M

'kN.".',.- @e5Ãw.-,.

Yi Vi

-:, P pj's'~i "4

~t

~ >X

~  %@@le .

~~~w~~-

~ ~8

, ~

~is --~

~ma~a  !&~~

"-=

~~~IBeseei'a= ~aRR,"

'Ill

Figure 5 AQANL AVERAGE

.30 GROSS BETA ACTIVITY III AIR FILTERS HRGWS FERRV Hmae Purr Preoperational Phase Operational Phase 25 o tÃt C

Jl o

.20 1J iJ v'

4J V5 ilC

.15 Avcrafm: Preonerational Phase

.10

.05 1968 1969 1970 1 971 1972 1973P 19730 1974 1975 1976 1977 1978 1979 1980 1981 1 82 1983 1984 Io85

I 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'ddition, environmental gamma radiation levels are determined by strategic placement of thermoluminescent dosimeters.'wice each year a land use survey is conducted'to determine milk producing animal census and location.

Land Use Surve The land use surveys were 'conducted in June and September of 1985. The fall survey revealed that a dairy operation had resumed at a location previously used as a milk sampling point. This location was added to the environmental sampling program.

After the land use survey was completed and during routine sample collection run, a dairy operation from which samples had routinely been collected ceased operation. This location was removed from the sampling schedule. In compliance with plant technical

,specifications, a Special Report was submitted to the Nuclear Regulatory Commission on November 26, 1985.

Milk Milk was collected from three farms within a 10-mile radius of the plant (see figure 3), and from at least one of six control farms.

During this report period, one indicator dairy farm ceased operation with the last sample being collected October 28, 1985., At about the same time, operations were resumed at a dairy formerly used as an indicator location. This location was added to the milk sampling program with the first sample collected on November 4, 1985.

Raw milk samples are collected from indicator and control farms, and are analyzed weekly for iodine-131 and monthly for gamma-emitting isotopes and radiostrontium. Analytical results are summarized in table 10. During the 1985 reporting period, 7 samples were not .

available for collection, and one sample was inadvertently destroyed prior to analysis for radiostrontium.

V~e etation Vegetation is sampled monthly at five indicator farms (three dairies and two farms with one milk-producing animal), and at each air monitoring station, quarterly vegetation samples are collected at four control farms (one control farm ceased operation in August). The monthly samples are analyzed for iodine-131 and gamma-emitting isotopes with analysis for radiostrontium performed on the last monthly sample of each quarter. Samples collected quarterly are analyzed for gamma-emitting isotopes. Table ll summarizes analytical results.

this reporting period, three samples were inadvertently 'uring destroyed before iodine analysis was done.

Soil Soil samples are collected annually near each monitoring station to provide an indication of long-term buildup of radioactivity in the environment. An auger or a "cookie cutter" type sampler is used to obtain samples of the top two inches (5 cm) of soil. These samples are analyzed for gamma-emitting radionuclides, strontium-89, and strontium-90. The results are given in table 12.

Ground Water An automatic sequential-type sampling device collects groundwater from a well downgradient from BFN. A composite sample from this weli is 'analyzed for gam'ma-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. During this report period one sample was not available for gamma analysis.

Potable water supplies taken from the Tennessee River in the vicinity of BFN are sampled and analyzed for gross beta and gamma-emitting radionuclides, and composited quarterly for tritium, Sr, and Sr analyses. The first potable water supply downstream from the plant is equipped with an automatic sampler with samples collected and analyzed weekly. The sampler is located on the water intake structure and takes the sample 'from the river as the raw water is drawn into the water treatment facility. Two additional supplies downstream and one public water supply upstream are sampled by taking monthly grab samples of treated water at user points. In addition, the surface water sample collected by an automatic water sampler upstream from the plant is included as a control for drinking water. Table 14 indicates.

the results from the analysis of drinking water samples. During this reporting period, two weekly samples were not collected because of automatic sampling equipment malfunction.

Figure 6 shows the trends in gross beta activity in drinking water from 1968 through 1985. The annual average level from the raw water samples tends to run slightly higher than the average for treated water samples; however, the levels are consistent with the activities reported in surface water samples taken upstream from Bl'N (figure 12) and in samples taken from the Tennessee River in preoperational monitoring programs conducted by TVA at other sites.

Environmental Gamma Radiation Ievels N

Bulb-type Victoreen manganese-activated calcium fluoride (Ca~F: Mn) thermoluminescent dosimeters (TLDs) are placed at sixteen stations around the plant near the site boundary,"at the perimeter and remote air monitors, and at nineteen additional stations out to approx~

imately five miles from the site to determine the gamma exposure rates at these locations, The dosimeters, located inside energy compensating shields to correct for energy dependence, are placed at approximately one meter above the ground, with three TLDs at each station. They are

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

The quarterly gamma radiation levels determined from these TLDs are given in table 15, which indicates that average levels at onsite stations are approximately 2-5 mR/quarter higher than levels at offsite stations. This is consistent with levels reported at TVA's nonoperating nuclear power plant construction sites where the average radiation levels onsite are generally 2-6 mR/quarter higher than levels offsite.

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

Figure 7 compares plots of the data from the onsite or site boundary stations with those from the offsite stations over the period from 1976 through 1985. To reduce the variations present in the data sets, a four-quarter moving average was constructed for each set.

Figure 8 presents a trend plot of the direct radiation levels as defined by the moving averages. The data, follow the same general trend as the raw data, but the curves are smoothed considerably.

Prior to 1976 measurements were made with less sensitive dosimeters, and consequently the levels reported in the preoperational phase of the monitoring program are up to 2 times the levels reported herein. Those data are not included in this report. Therefore, for comparison purposes, figures 9 and 10 depict the environmental gamma radiation levels measured during 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 apples, cabbage, corn, green beans, potatoes, beef, and tomatoes were collected-and analyzed for specific gamma-emitting radionuclides. The results are given in 'tables 16 through 22.

TABLE 10 RADIOACTIVITY IN HILK PCI/L - 0 ~ 037 BQ/L NAME OF FACILITY QQQltgg EEEEI DOCKET NO 29=252c20Qc225 LOCATION -OF FACILITY LZHESIQHE 8l89858 REPORTING PERIOD 1252 TYPE ANO LONER LIHIT ALL CONTROL NUMBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LQG8IIQU lllIU UIQUEGI 855081-df 88------ LOCATIONS NONROUTINE OF ANALYSIS OETEC. ION MEAN (F) NAHE MEAN (F) MEAN (F) REPORTED PERFORMED (LLD) RANGE DISTANCE AND DIRECTION RANGE RANGc MEASUREMENTS 5QIE 1 Sff ODIN E-1 31 434 SEE 0 '0 SEE UQIE 2 156 VALUES <L'LO ANAL'YSIS PERFORMED 9Q'lE 2 E HQIE 2 278 VALUES <LLO AHHA (GELI) 108 CS-137 5.00 8 6 '941(

- 6/ 39) 9 '8 PAGE FARH 8 75 HILES 8 41(

6e29 6/ 11) 9+98 8

5

'9(

'4 2/

11 69)

'4 1193 '9( 39/ 59)

E K-40 NOT ESTAB 768.95 - 1686 '7 LOONEY FARM 1264 '3( 13/ 15) 1297 44( 69/ 69)

BI-214 NOT ESTAB  ? ~ 41 ( 31/ 39) 5 ?5 MILES ENE SMITH/BENNETT FA 1058.34 9 98(

1435o68 2/ 2) 781 '3 -

6.93(

1925.94 38/ 69) 0+59 - 35e98 4 ~ 75 HILES N 8 '1 11 '5 0 '2 - 21 87 7 '8(

F PB-214 NOT ESTAB 7.65( 13/ 39) LOONEY FARM 10 02( 4/ 13) 27/ 69) 1 '6 " 26 '5 5 ~ 75 MILES ENE 1 ~ 36 26 '5 0 '4 - 29 05 PB-212 NOT ESTAB 2.00(

0 39 -

8/

3 39)

'0 LOONEY FARM 5~ 75 NIL ES ENE F 00(

3.00 1/ 13) 3 ~ 00

'8(

0 '6 -

1 12/ 69)

F 6+27 TL-ZOB NOT ESTAB '5(

0 12 -

1 6/ 39) PAGE FARM 2 '5( 2/ 11) 0.97( 13/ 69) 3 63 8 ?5 MILES E 0.87 3ob3 0.01 - 2.78 AC-228 NOT ESTAB 8 '2( 3/ 39) PAGE FARH 10 '3( 2/ 11) 5 20( 9/ 69)

R 89 10 00 5 08 -

39 VALUES <LLD 13 26 8 ~ 75 MILES E 7.21 13 '6 68 0 '2 -

VALUES <LLO 11 '6 107 ANALYSIS PERFORHEO R 90 Z.OO 3 '0( - 38/ 39)

'4 SMITH/8 ENNETT FA 4 ~ 12( 2/ 2) 3.?0(

- 56/ 68) 107 2.05 5 4 ~ 75 MILES N 3 77- 4 ~ 48 F 00 6 '1 NOTE: 1 ~ NOHINAL LONER LIHIT OF DETECTION (LLO) AS DESCRIBED IN TABLE 3 ~

NOTE: 2 ~ MEAN AND RANGE BASED UPON DETECTABLE MEASUREHENTS ONLY ~ FRACTION OF DETECTABLE MsASUREHcNTS AT SPECIFIcD LOCATIONS IS INDICATEO IN PARENTHESES (F) ~

TABLE 11 RADIOACTIVITY IN VEGETATION PCI/G -'

~ 037 BQ/G (ORY MEIGHT)

NAME OF FACILITY EBQHUX EEBBI DOCKET NO ~ gg:2$ Pc2$ QA2$ 0 LOCATION OF FACILITY l,I5EBIQBE ---- BLBEBLB REPORTING PERIOD TYPE ANO LONER LIMIT ALL COhTROL NUMBER OF TOTAL NUHBER OF INDICATOR LOCATIONS  !.QQBIIQU liIIU UIQUEBI BUUDBL ZEBU LOCATIONS NONROUTINE OF ANALYSIS DETECTION HEAN (F) NAME HEAN (F) HEAN (F) REPORTED PERFORMED (LLO) RANGE DISTANCE ANO DIRECTION RANGE RANGE MEASUREMENTS BEE UQIE 1 GEE BQIE 2 GEE BQIE 2 5EE BQIE 2 IODINE-131 NOT ESTAB 0 00( 85/ 183) 0 ~ 01( 6/ 12) 0 F 00( 10/ 25) 208 0.00 - Oe02 0 F 00 - 0 02 0 ~ 00 - -0 ~ 01 GAMMA (GELI) 226 C0-60 0 '6 0 0

'9(

'9 - 1/ 185) 0 F 49 LH1 BF NORTHllEST 0 MILE ti Oo49(

0 '9 1/ 13) 0 49 41 VALUES <LLD 1 (Note 3)

CS-137 0 06 '3( - 14/ 185) 1 ~

PAGE FARH

' '7( 1/ 11) 0 12( 3/ 41) 0 0 07 0 '7 8~ 75 MILES E 0.27 25.86( 11/

0 '7 0 '6 15 '7(

40/

0 '5 41)

K-40 NOT ESTAB 15+56( 182/ 185) PAGE FARH 11) 1 '4

'2(

- 43 '1 93/ 185) 8 ~ 75 MILES E 5 '6

'9( 4/

43 ~ 21 11) 1 43 0 ~ 20(

14/

40 34 41)

BI-214 PAGE FARM 0 0 '6 0 ~ 10 0 0 '0 - 0 '0 8 75 MILES E 0 13

~ 0.60 0 '1 -

BI-212 0 '8( 2/ 185) PAGE FARH 0.50( 1/ 11) 41 VALUES <LLO PB-214 NOT ESTAB 0 '7 -

0.16( 167/ 185) 0 '0 8 ~ 75 HILES E EVANS FARH '0 0 '0 21( 12/

0 F 50

13) 0.12( 33/ 41)

NOT ESTAB 0 00 -

F 0 '6 6 ~ 1 MILES NE 0 ~ 06

'3( 9/

0 '2 13) 0 ~ 01 0 ~ 04(

18/

0 ~ 40 41)

PB-212 NOT ESTAB 0 07( 126/ 185) EVANS FARH 0 0.00 - 0 '3 6 ~ 1 HILES NE 0 01 0+30 0 ~ 01 - 0 ~ 11 BE-7 13( 184/ 185) SMITH/BENNETT FA 10 '8( 5/ 5) 7 44 ( 41/ 41) 6 '7 NOT ESTAB 7 ~

0 61 - 25 22 4 75 MILES N 15 ~ 56 0.97 - 18.75 TL-208 NOT ESTAB 0+04( 78/ 185) EVANS FARM 0 07( 6/ 13) 0.02( 11/ 41) 0 '1 0 00 -

F 0 00 - 0 ~ 14 6.1 MILES NE 0 ~ 11 0.05 AC-228 '0(

~

73/ 185) PAGE FARM 0 '9( 2/ 11) 0 '6( -

F 12/ 41)

'0 NOT ESTAB 0 0 '2 - 0 79 8 '5 MZLES E 0 '3 0 '5 0 F 05 0 SR 89 65 0 '5 5? VALUES <LLD ANALYSIS PERFORHED 8 VALUES <LLD SR 90 0~05 0 '0( - 53/ 57)

'6 ROGERSVILLEr AL 0~ 35( 4/ 4) 0.21(

'9 8/

'1 S) 65 0 '6 0 13 ~ 8 MILES NN 0 ~ 16 - 0 ~ 56 0 - 0 NOTE: 1 ~ tiOMINAL LOttER LIMIT OF DETECTION (LLD) AS DESCRIBED IN TABLE 3 ~

NOTE 2a HEAN AND RANGE BASED UPON DETECTABLE HEASUREHENTS ONLY'RACTION OF DETECTABLE MEASUREMENTS AT SPECIFIEO LOCATIONS IS INDICATEO IN PARENTHESES (F) ~

Note: 3. A report was submitted to the Nuclear Regulatory Commission on June 14, 1985, outlining the high value. The single, tsolatect occurrence of cobalt-60 in vegetation, the absence of other fission and activation products in the sample, and the lack of an Increase in cobalt-60 releases from the plant prevented an identification of the causes for the presence of the isotope in the sample. Subsequent samples showed no indication of the presence of cobalt-60.

TABLE 12 RADIOACTIVITY IN SOIL PCI/G - 0 ~ 037 BQ/G (DRY HEIGHT)

NAME OF FACILITY gggjfgg fggQJ DOCl(ET ND ~ 29=?22c?09c?2k LOG ATION OF FACILITY ggggggggg $ gQg$ Q$ REPORTING PERIOD TYPE AND LONER L IHIT ALL CONTROL NUHBER OF TOTAL NUHBER OF INDICATOR LOCATIONS. Lgga?LOB IZING UIGUEII hUBLthl, BEh5 NONROUTINE OF ANALYSIS DCT ECTION MEAN (F) NAHE MEAN (F) MEAN (F) REPORTED (LLD)

PERFORMED AMHA (GELI)

RfE 5QIC 1 5EE RANGE UQIf  ?

DISTANCE ANO DIRECTION RANGE GEE SCIL ? 'EE RANGE hQIE 2 MEASUREHENTS 11 CS-137 0 ~ 02 0.46( 9/ 9) LH5 Bf DAVIS F 43( 1/ 1) 0.38( 2/ 2)

K-40 '5 0 02

'8( 9/

1 ~ 43 9) 2 ~ 5 MILES HSW 1

1 7 '4(

'3 1/

1 ~ 43 020-4 ~ 03( 2/

0 57 BI-214 0

0 F 05 5

2.89-1 '8( 9/

7.24 9)

LM1 BF NORTHNEST 1 ~ 0 MILE LH2 BF NORTH N 7 24 1.43( 1/

1) 7 ~ 24 1 )

3 ~ 17 0 ~ 90( 2/

4 '92)2)

BI-212 0.10 0.63-9/

1 ~ 43 0 ' MILE NNE 1 ~ 43 1 '3 0. 87 2/

0 '42) 21( 9) LH2 BF ;lORTH 55( 1/ 1) 0 91(

PB" 214 0 '5 1 ~

0.62 1 ~ 17( 9/

1 ~ 55 9) 0 9 HILE NNE LK1 BF HORTHHEST 1 ~

1 ~ 55 48( 1/

1 ~

1) 55 0 0

'9

'6( 2/

0,04 2)

PB-212 NOT ESTAB 0.67 1 '4( 9/

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

1 ~ 48 35( 1/

1 ~ 48 1) 0 88 0 85( 2/

1,04 2)

RA-226 0 F 05 052-1 ~ 08( 9/

35 9)

Be 2 MILES SSE LH2 BF NORTH 1 ~

1 1

'3('5 1/

1 1) 35 0 ~ 83 0.90( 2/

0.87 2) 0~ 63- 1 ~ 43 0 ~ 9 HIl.E NNE 1.43 1 ~ 43 Oe87 0.94 RA-224 NOT ESTAB 11( 7/ 9) LH3 BF NORTHEAST 1.47( 1/ 1) 0.8?( 2/ 2)

BE-7 0.16 1

0 62 0 '1( 2/

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

0.24(

'7 1/

1 ~

1) 47 0.80 0.22( 1/

0.93 2) 0.18 0 24 8~2 MILES SSE 0 24 0.24 0.22 0.22 TH-227 NOT ESTAB 9 VALUES <LLD 0 11( 1/ 2) 0 11 0 11 TL-208 0.02 0 36( 9/ 9) DECATURr AL 0 ~ 47( 1/ 1) 28( 2/ 2)

AC-228 0 ~ Oo 0.19 -

'6( 9/ '89) 0 '7 8 ~ 2 HILES SSE OECATURr AL 0.47-1 38( 1/

0. 47 1)

Oe 0 27 0.85( 2/

0.29 2) 1 0,55 -

2.18(

1 8.2 MILES SSE 1 ~

2.74(

38- 1 '8 0.83 0 F 87

- 4/ '4 1/ 2.69( 2/

PA-234M NOT ESTAB 9) ROGERSVILLEr AL 1) 2)

R 89 1e50 9 1 '3 VALUES <LLD

. 2 13.8 MILES NH 2.74- 2 '4 2 1 ~ 44 VALUES <LLD 3 33 ANALYSIS PERFORMED 4/

R 90 0 ~ 15 0 0 20 24(

- 0 '89) LMS BF DAVIS F 2 ~ 5 MILES HSH 0~ 28(

0.28 - 1/ 1) 0.28 2 VALUES <LLD NOTE: 1 ~ NOHINAL LOWER LIHIT OF DETECTION (LLO) AS DESCRIBED IN TABLE 3 ~

NOTE: 2 ~ MEAN,ANO RANGE BASED UPON DETECTABLE HEASUREHENTS ONLY ~ FRACTION OF DETECTABLE MEASUREMENTS AT SPECIfIED LOCATIONS IS INOICATEO IN PARENTHESES (F)

TABLE 13 RADIOACTIVITY IN WELL WATER PCI/L - 0 037 SO/L NAtlE OF FACILITY ERQHUX EEEBI DOCKET NO ~ 1Q=222c25QA22!)

LOCATION OF FACILITYLIUESIQUE hLM8U6 REPORTING PERIOD TYPL. ANO LOWER LIMIT ALL CONTROL NUMBER OF TOTAL NUMBER OF INDICATOR LOCATIONS  !,QQGIIQU hIIU UIQUEKI BUUQSL UWU LOCATIONS NONROUTINE OF ANALYSIS DETECTION HEAN (F) NAHE MEAN (F) tlEAN (F) REPORTED PERFORHEO (LLO) RANGE DISTANCE ANO DIRECTION RANGE RANGE MEASUREMENTS kEE UQIE 1 REE UQIE 2 GEE UQIE 2 SEE UQIE 2 GAHHA (GELI) 25 K-40 NOT cSTAB 8,92 ( 1/ 13) BFN WELL %6 8.92( 1/ 13) F 57( 2/ 12)

BZ-214 NOT ESTAB 8

9

'2

'6(

- 8 12/ 15)

'2 0 ~ 02 MILES k BFN 'WELL tt6 8.92 9.36( 12/

8 13) 92 F 06 175 22(

12/

8.09 12) 1 <<3 - 17 '2 0 ~ 02 HILES X 1~43 17 '2 40 F 97 - 680 '5 PS-214 NOT ESTAB 12 08( 9/ 13) BFN WE!.L ttb 12 08( 9/ 13) 177 10( 12/ 12)

PS-212 NOT ESTAB 2 '7 4/ 18 15)

F F 80(

- '7 0 BFN

'2 MILES W WELL tt6 2 2 '7 80( 4/

18 ~ 27 13) 43 '4 3/682 12) 3.77(

'2 TL-208 NOT ESTAB 0 '1 13 VALUES <LLO 4 '4 0 ~ 02 MILES le Oe71 4 '4 1 '3 - 2/ 12) 0 '3(

6 '6 0.28 - 0 '8 AC-228 NOT ESTAB 7 7

'9(

'9 - 1/

7 15)

'9 BFN WELL tt6 0 ~ 02 MI!.ES W 7 ~ 09(

7 '9 - 1/ 13) 7 F 09 12 VALUES <LLD TRITIUH 550.00 4 VALUES <LLO 4 VALUES <LLO ANALTSIS PERFORHEO NOTE: 1 ~ NOMINAL LOWER LIMIT OF DETECTION (LLO) AS OESCRIBEO IN TABLE 5 ~

NOTE: 2 ~ MEAN AND RANGE BASED UPON DETECTABLE HEASUREHENTS ONLY ~ FRACTION OF DETcCTASLE HEASUREMENTS AT SPECIFIEO LOCATIONS IS INOICATEO IN PARENTHESES (F) ~

TAB!.E 14 RADIOACTIVITY IN PUBLIC WATER SUPPLY PGI/L - 0+037 8(t/L NAME OF FACILITY EEQ$ 55 EEBBX DOCKET NO 2Q"22212{iQc22B LOCATION OF FACILITYL,?5i~5IQUE BLBE858 REPORTING PERIOD TYPE AND LOWER LIHIT ALL CONTROL NUMBER OF TOTAL NUHBER OF INDICATOR LOCATIONS LQQBI?QU t(IIU UIQUEEI BUUllBL HEBE I.OCATIONS NONROUTINE OF ANALYSIS DETECTION tlEAN (F) NAHE HEAN (F) MEAN (F) REPORTED PERFORHEO (LLD) RANGE DISTANCE ANO DIRECTION RANGE RANGE MEASUREMENTS HE HQIE 1 SEE MIE 2 SEE UQIE 2 5EE HQIE 2 ROSS BETA 102 F 00 3 23(

2.05 - 55/ 76) 6.58 CHAHPION PAPcR TRH 282 6 3 '8(

F 08 - 40/ 50) 6 '8 2 ~ 93 (

F 04 - 22/ 26) 5.62 AHHA (GELI) 102 t(-40 NOT ESTAB 14 '2( 12/ 76) wHEELER DAMr AL 23 '6( 3/ 13) 0 ~ 47( 1/ 26) 2 '2 -

'5( 42 '6 TRH 274 ' 11 '0 42 16 0 47 - 0.47 BI-214 NOT ESTAB 5 0 '7 -

39/ 76) 19 '3 WHEcLER DAFr AL TRM 274 '

7 '9(

'1 7/ 13) 14 '2 9 '2( - 12/ 26) 47 ~ 47 0 ~ 13 4 '6(

1 PB-214 NOT ESTAB 0 '8 -

24/ 76) 17 '9 SHEFFIELDr AL TRH 254 '

ROB 7 29(

0 '6 3/ 13) 17 '9 5 '2(

0 '7 -

7/

18 26)

'0 PB-212 NOT ESTAB 76(

Oe01 -

15/ 76) WHEELER OAHr AL 4 '0( 1/ 13) 1.49(

- 6/ 26)

TL-208 NOT ESTAB '2( 12/

8 F 28 76)

TRM 274 '

CHAHPION PAPER 4 10

~

05( 8/

4 ~ 10 0+29 2 '2 1

0 00 - 2 '8 TRH 282+6 1 ~

0 F 00 50) 2.38 26 VALUES <LLD AC-228 NOT ESTAB 5.46(

Os13 - 9/ 76) 11.59 SHEFFIELDr AL ROB TRH 254 '

9 '9(

9 '9 1/ 13) 8 '8( - 4/ 26) 9 ~ 49 0.93 27.49 R 89 10 F 00 12 VALUES <LLD 8 VALUES <LLO 20 ANALYSIS PERFORMED iR 90 F 00 12 VALUES <LLO 8 VALUES <LLO 20 ANALYSIS PERFORMED

'RITIUH 330 F 00 12 VALUES <LLD 333o48( 1/ 8) 20 333 '8 333.48 NOTE: 1 ~ NOMINAL LOWER LIMIT OF DETECTION (LLO) AS OESCRIBEO IN TABLE 3 ~

NOTE: 2 ~ MEAN AHO RANGE BASED UPON DETECTABLE tlEASUREHcNTS ONLY FRACTIOtt OF OcTECTABLE MEASUREMENTS AT SPECIFIcO LOCATIONS IS INOICATEO IN PARENTHESES (F) ~

31 Table 15 FNVIRONMENTAL GAHHA RADIATION LEVELS Average External Gamma Radiation Levels at. Various Distances from Browns Ferry Nuclear Plant for Each Quarter - 1985 mR/Quarter Distance Avera e External Gamma Radiation Ievels b miles 1st Quarter 0-1 18.0 + 2.5 19.4 + 0.8 21.8 + 3.7 21.0 + 2.1 1-2 16.2 + 2.6 17.7 + 1.8 17.9 + 3.8 18.1 + 2.4 2-4 15.1 + 1.4 15.9 + 1.5 16.1 + 3.0 18.2 + 2.7 4-6 14.8 + 1,3 16.1 + 1.7 16.5 + 3.2 17.6 + 2.2

>6 14.4 + 1.3 15.8 + 1.5 15.2 + 2.4 17.4 + 1,9

Average, 0-2 miles (Onsite) 17.6 + 2.5 18.9 + 1.3 20.8 + 4.0 20.3 + 2.4

Average,

>2 miles (Offsite) 14.8 + 1.3 15.9 + 1.5 16.0 + 2.9 17.6 + 2;2

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

b. All averages reported +l(r (68 percent confidence level).

TABLE 16 RADIOACTIVITY IN CABBAGE PCI'/KG' 0.03'7 BQ/KG- (ilET HEIGHT).

NAHE OF FACILITY QBQUU5 EEBBI DOCKET NO ~ 29=222c2ftQA29O LOCATION OF FACILITY l,IUxgIQUE REPORTING PERIOD 125>

TYPE AND LONER LIMIT ALL CONTROL NUMBER OF

'OTAL NUHBER OF INDICATOR LOCATIONS l QQ8IIQU ViIIU UIQUE51 8UUll8l UE88 LOCATIONS NONROUT INE iF ANALYSIS DETECTION MEAN (F) NAME HEAN (F) MEAN (F) REPORTED PERFORMED <LLO) RANGE DISTANCE AND DIRECTION RAilGE RANGE MEASUREMENTS SEE UQIE I SEE UQIE 4 1/

SEE UQIE 2 $ EE hQIE 2 ---

OSS BETA 25 F 00 3764 15( 1) PAGE FARH S764 ~ 15( 1/ 1) 3440.65<

iHHA (GELI) 2 3764 '5 - 3764 '5 B.75 MILES E 3764.15 - 3?64.15 3440.65 - 3440.65 2

-40 1/ 1/

- 1/1652.64 NOT ESTAB 1652 ~ 64( 1) PAGE FARM 1652 ~ 64( 1) 1559.45( 1) 1652.64 - 1652 ~ 64 B 75 HIt.ES E 1652 64 1569.45 15"9-45 lOTE: 1 ~ NOHINAL LOllER LIMIT OF DETECTION (LLO) AS DESCRIBED IN TABLE 3 ~

lOTE 2 ~ MEAN ANO RANGE BASED UPON DETECTABLE l EASUREHENTS ONLY~ FRACTION OF DETECTABLE HEASUREHENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) ~

TABLE 17 RADIOACTIVITY Ih CORtt PCI/KG - 0 ~ 037 BQ/KG (wET 4'EIGHT)

NAME OF FACILITY ggQggg PgllRI '

DOCKET NO ~ 2{}=222cRt)Q422(t--------

LOCATION OF FACILITY l,gg~cggQltf El,ggggg RcPORTING PERIOD TYPc AND LOitER LIMIT ALL CONTROL NUMBER OF TOTAL NUMBER OF INDICATOR LOCATIONS lLQQhlIQ9 h?ill UiQUZKI 68Ullhl LOCATIONS NONROUT INE OF ANALYSIS DETECTION MEAN (F) NAME HEAN (F) MEAN (F) RcPORTED ccRFORHED (LLO) RANGE DISTANCE ANO DIRcCTION RAttGE RANGC HEASUREHENTS 5aE BQI~ 1 0EE 8QIR 2 XcR UQX: 2 KEc UQIC 2 4152.67( 1/ 1) 7 HILES NNW 4152 ~ 67( 1/ 3807 94( 1/

1)

'41)

GROSS BETA 25 F 00 GAHca (GELI) 2 41 52 ~ 67 41 52 ~ 67 4152 '7 - 4152.67 3507 '4 - 3807 2

K-40 NOT FSTAB 2518 ~ 86( 1/ 1) 7 MILES NNM 2518 86( 1/ 1) 2163 ~ 31( 1/ 1)

PB-214 NOT ESTAB 2518 '6 10.58(

- 2518 F 86 1/ 1) 7 WILES NNW 251 Bo 86 10 58(

251 8 ~ 86 1/ 1) 2163 ~ 31 21 63 ~ 31 VALUES <LLD 10 ~ 58 " 10 ~ 58 10 'o - 10 F 58 1

'ROTC 1 ~ NOHIiVAL LOWER LIMIT OF OETE CT ION (LLO) AS DESC RI 8 0 IN TABLE 3 ~

NOTE: 2 ~ MEAN ANO RANGE BASED UPON DETECTABLE M ASUREHENTS ONLY ~ FRACTION OF DETECTABLE MEASUREMENTS AT SPcCIFIEO LOCATIONS IS. INOICATEO IN PARENTHESES (F) ~

TABLE 18 RADIOACTIVITY IN GREEN BEANS PCI/KG - 0 037 8Q/KG (MET it EIGHT)

NAME OF FACILITY EBQl(55 fEBBI DOCKET NO ~ fg 22B4259c225 LOCATION 'OF FACILITY l,jgESIOUE --- - -Al 8ll858 REPORTING PERIOD 1255 TYPE AND LONER LIMIT ALL CONTROL NUMBER OF

'OTAL NUHBER OF INDICATOR LOCATIONS l 9GAIIQU llII" QIGUERI 8BHQEL BEBOP MEAN (F)

LOCATIONS HcAN (F)

NONROUTINE IF ANALYSIS DETECTION HEAN (F) NAHE REPORTED PERFORMED (LLO) RANGE DISTANCE ANO DIRECTION RANGE RANGE MEASURcHENTS EE gQIE KEE UQIE 2 SEE 991E 2 GEE QQIE 2

'OSS SETA 2

25+00 3823 3823

'7(

'7 1/

3823 '71) 7 MILES NNN 3823.47(

3823 ~ 47 - 1/SB23 47 1)

~

5150 ~ 78(

5150 78 -

1/

5150.73 1)

<MHA (GELI) 2

- 1/1659.47

-40 NOT ESTAB 1659 ~ 47( 1/ 1) 7 MILES NNH 1659 ~ 47( 1) 2003.71 ( 1/ 1) sI-214 NOT ESTAB 1659 1

'7 - 1659 47 VALUES <LLD

~ 1659 47 20G3.71 3.70(

2003o71 1/ 1) 3 70 3 ~ 70

'8-214 NOT cSTAB 1 VALUES <LLD 2.14( 1 / 1) 2.14 2+14 lOTE: 1 ~ NOHINAL LONER LIMIT OF 0 TECTION (LLO) AS DcSCRISEO IN TABLc 3 ~

IOTE: 2 ~ MEAN ANO RANGE BASED UPON DETECTABLE HEASUREMENTS ONLY ~ FRACTION OF OETECTASLE MEASUREMENTS AT ScECIFIEO LOCATIONS IS INDICATED IN PARENTHESES (F) ~

TABLE 19 RAOIOACTIVIT Y IH APPLES PCI/KG 0 '57 BO/KG ('AET HT)

NAME OF FACILITY QEQH55 EERBY oOCKET NO ~ 20=212A21)QA220 LOCATION OF FACILITY gjgE/IQt1E ---- - 8L85858 REPORTIHG PERIOD TYPc ANO LONER LIMIJ ALL CONTROL NUMBER OF TOTAL HUHBER OF INDICATOR LOCATIONS MEAN (F)

LQQBIIQB III'IQdEDI 85UQEL PERU MEAN (F)

LOCATIONS (F)

NONROUTINE OF ANALYSIS OcTECTION NAME HEAN REPO'RTED PERFORMED (LLD) RANGE DISTANCE ANO DIRECTION RANGE RANGE MEASUREMcNTS SEE UQIE I GEE 9QIE 2

'2( EE 8QIE

'2( " 2 Sic BQIE 2 GROSS AHHA BETA (GcLI) 2 25 ~ 00 1695 1695.72 -

1/

1 695 1)

'2 PAGE FARM 8.75 WILES E 1695 1695.72 - 1/1695.72 1) 1618 '9 -

1618.79( 1/

1618 '91) 2 K-40 NOT ESTAB 1080.23(

1080 ~ Z3 - 1/

1080 23

1) PAGE FARH 8.75 MILES E 1080 ~ 23 (

1080 23 - 1/1080 1

~

)

23 862 ~ 72 (

862 AD ?2 1/

862 '21)1)

SI-214 NOT ESTAB 1 VALUES <LLD 8 8

'7(

'7 1/

Be47

'2( 1/

PS-214 AC-228 HOT ESTAB NOT ESTAB 1 VALUES <LLD VALUES <LLO 3

5 '2 2.70( 1/

3 '21)1) 1 Zo?0- 2 '0 NOTE: 1 ~ NOMINAL LOiiER LIHIT OF DETECTION (LLO) AS OESCRIBEO IN TABLE 3 ~

NOTE: 2 ~ MEAN ANO RANGE BASED UPON DETECTABLE HEASUREHENTS ONLY'RACTION OF OETcCTABLE HEASUREHEHTS AT SPECIFIEO 1.OCATIONS IS INOICATEO IN PARENTHESES (F) ~

TABLE 20 RADIOACTIVITY IN POTATOES PCI/KG - 0 ~ 03l BQ/KG. ('AET. )(EIGHT,).

NAHE OF FACILLTY $ 3Q)l55 OF FACILITY l,Illa'IQ(lC ELBRBllk EEBBX'OCATION DOCKET NO ~ 59:?0 c?5QA225 REPORTING PERIOD 12llk TYPE ANO LONER LIMIT ALL CONTROL NUHBER OF (OTAL NUHBER OF INDICATOR LOCATIONS l QfchIIQ8 lfIIll UIQU~DI hUllllhl. 5PBU LOCATIONS NONROUTINE

)F ANALYSIS DETECTION MEAN (F) NAME MEAN (F) MEAN (F) RcPPRTEP PERFORHEO (LLD) RANGE DISTANCc AND DIRECTION RANGE RANGE MEASUREMENTS 5:E llQIi 1 SEE UQIc 2 BEf UQ) E 2----- KfE UQXE ?

LOSS BETA 2

25 F 00 6048 46(

6048.46 - 604e.,46 1/ 1) PAGE FARH 8 ~ 75 MILES c 6048 '6(

6048.46 1/ 1) 6048.46 6564 '8( -

6564.38 1/ 1) 6564.38 LHHA (GELI) 2

-40 1/ 3408.85(, .1/

3408 F 85( 3694.61(

- 1/

NOT ESTAB 1) PAGE FARM 1) 1) 3408 ~ 85 - 3408 ~ 85 8 ~ 75 MILES 3408.85 - 3408.85 3694 ~ 61 3694+61 IOTE: . 1 ~ NOHINAL LONER LIMIT OF DETECTION (LLD) AS OESCRIBEO IN TABLE 3 ~

<OTE P ~ MEAN AND RANGE BASED UPON DETECTABLE HEASUREMENTS ONLY ~ FRACTION OF DETECTABLE- HEASURcHENTS AT SPECIFIcD LOCATIONS IS INDICATcO IN PARENTHESES (F) ~

TABLE RADIOACTIVITY IN BEEF PCI/KG - 0 037 BO/KG (PET HEIGHT)

NAME oF FAGILITY EEQUU5 EEEBI DOCKET NO ~ 09=222c26Q4225 LOCATION OF F AC ILITY I.IUEPIQUE Bl BfBUB TYPE ANO LOAER LIMIT ALL CONTROL NUHBER OF TOTAL NUMBER PF INDICATOR LOCATIONS LQQBIIQU uIIU UIQUEGI BUU!lBl UEBU LOCATIONS NON ROUTINE OF ANALYSIS OETcCTION MEAN (F) NAHE HcAN (F) HcAN (F) REPORTED PERFORHcD (LLD) RANGE DISTANCE ANO DIRECTION RANGE RANGE MEASUREMENTS SEE UQXE 1 Kff UQIE 2 UQjs 2 Kff UQIE 2 GROSS BETA 25.00 4397. 55 ( 1/ 1) LOONEY FARM

'5 4397 '5(

'5 - 1/4397 1)55 3768 57( 1/ 1)

GAHHA (GELI) 2 4397 F 55 - 4397.55 5 MILES ENE 4397 3768 '7 '3768 ~ 67 2

K-4O ESTAB 1838.92( 1/ 1) LOONcY FARH 1838.92( 1/ 1) 1384 55( 1/

'51)1)

NOT PB-21 1838 '2 0 10(

1838 92 1/ 1) 5 75 MILES ENE 1838 '2 0 10( '1/

1838 92

~ 1384 55 1384 4 NOT ESTAB LOONEY FARH 1) 21( 1/

0 '0

~ ~ 1 ~

0 ~ 10 5 ~ 75 MILES ENE 0 10

~ 0.10 ~ 21 1 ~ 21 PB-212 NOT cSTAB 0 33( 1/ 1) LOONEY FARH 0.33( 1/ 1) 0.77( 1/ 1) 0.33 0.33 5 ~ 75 MILES ENE 0 '3 0 33

~ 0 ~ 77 0.77 NOTE: 1 ~ NOHINAL LONER LIMIT OF DETECTION (LLO) AS DESCRIBED IN TABLE 3 NOTE~e2 ~ MEAN ANO R4NGE BASED UPON DETECTABLE MEASUREMENTS ONLY ~

IS INDICATED IN PARENTHESES (F) ~

~

FRACTION OF DETECTABLE HEASUR MENTS 4T SPECIFIEO LOCATIONS

TABLE 22 RADIOACTIVITY IN TOHATOES PCI/KG '037 BO/KG -(McT -MEIGHT)

NAHE OF FACILITY EllQlfUK CE HEI DOCKET No ~ NQ=?22c?(tQc2Rtt LOCATION Or. FACILITY l,ZIEEIQUE hl SE658 REPORTING PERIOD 1252 TYPE ANO LOMER LIHIT AI.L CONTROL;. NUMBER OF foTAL NUHBER OF INDICATOR LOCATIONS I QChIIQ5 hII'll llIGUEEI 658!tel JE65 'OCATIONS NONROUTINE

)F ANALYSIS DETECTION HEAN (F) NAHE HEAN (F) HcAN (F) REPORTED PERFORHEO (LLD) RANGE DISTANCE ANO OIRcCTION RANGc RANGE HEASUREHENTS OEE UQIE 1 SEE 8QIE 2 Eff 5Q:E? SEE UQIE 2------

BcTA 25 F 00 4228 87( 1/ 1) 7 HILES NNM 4228 ~ 87 ( 1/ 1) 3786.61( 1/ 1)

ROSS 2 4228 '7 - 4228 F 87 4228.87 - 4228.87 3786.61 - 3785 61 AHHA (GELI) 2 K-40 NOT ESTAB 2103.35( 1/ 1) 7 HILES NNM 2103 35( 1/ 1) 2103. 69 ( 1/ 1) 2103 '5 2103.35 1/

2103 '5 2103. 35 1/

2103. 69 8.97(

2103.69 1/ 1) 8 I'-21 4 NOT ESTAB 6.31 ( 1) 7 MILES NNM 5 31( 1) 6.31 " 6 ~ 31 6 ~ 31 6. 31 8 97 8 97 PB-214 2.20( 1/ 1) 7 HILES NNk 2 20( 1/ 3+10( 1/ 1)

NOT ESTAB 2 20 2 '0 2 '0 1)'.20 3 ~ 10 3.10 NOTE: 1 ~ NOHINAL LokER LIHIT OF DETECTION (LLD) AS DESCRIBED IN TABLE 3 ~

NOTE 2 ~ HEAN AND RANGE BASED UPott DETECTABLE HEASURCHENTS ONLY ~ FRACTION OF OcTECTABLE HEASUREHENTS AT SPECIFIED LOCATIONS IS INDICATED =IN PARENTHESES (F) ~

Figure 6 Cl CC CJ

'0 4J CJ 4J 0

CC Cl '0 A VNIAL AVERAGE Cl 4J C

44 0 Preoperational Operational 6ROSS HElA kTIVITY 0LI Phase Phase IN 8RI N<1t6 MATER SUPPLIES C BmWrS FERRY NuCLEAR RP hT 0 tA C

CJ 0 4J 4J M 0 4J M

0 JJ 0

0 4J C

C 0 CJ Averacrec Preonerational Phase 3

0 r

C 1

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 )985

40 Fl uro

24. 7 Oneito Direot Radiation Levels ~ Offsets Browns Ferry Nuolear Plant 22.

14; 12' 976 1 977 1 978, 1 979 1 980 1981 1 982 1 983 1 984. 1 985. 1 986.

Figure 8

+ Onomato Dir eat Radiation Levels D Offsets Browne Ferry Nuolear Plant

22. 4-Quarter Hovine Averase 14.

12.

1 9 16 1 977 1 978. 1 979. 1 980 1 98 1 1 982 1 983 1 984 1 985. 1 986.

4i FlguFe 9 26 Direct Radiation Levels Watts Bar Nuolear Plant 24.

Onoito p Offoito 22.

20.

8 1 B.

16.

14 12.

1976. 1977. 1978. 1979 1980. 1981. 1982. 1983. 1984. 1985. 1986.

Flguro j0 26 Direct Radiation Levels Watts Bar Nuclear Plant

24. 4-Quarter Moving Average Onomato p Offoit 22m 16.

14.

12.

1976. 1977. 1978. 1979 1980 1981 1982 1983. 1984. 1985. 1986.

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

Mater Mater 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 required samples, grab samples were also collected monthly from the vicinity of the plant discharge to the Tennessee River, and at a point on the Elk River, and analyzed for gross beta, gamma-emitting radionuclides, and strontium. Results are displayed in table 24.

Figure 12 presents a plot of the gross beta activity in surface water from 1968 through 1985. No gross beta measurements were made in surface water samples in 1978. The levels reported are consistent with gross beta levels measured in surface water samples taken from the Tennessee River in preoperational monitoring programs conducted by TVA at other sites.

Fish Radiological monitoring for fish is accomplished by analysis of composite samples of adult fish taken from each of three contiguous reservoirs--Wilson, Wheeler, and Guntersville. No permanent sampling stations have been established within each reservoir; this reElects the movement of fish species within reservoirs as determined by TVA data from BFN preoperational monitoring program. Two species, white crappie and

'he smallmouth buffalo, are collected representing both commercial and game species. Sufficient fish are collected in each reservoir to yield 250 to 300 grams oven-dry weight for analytical purposes. All samples are collected semiannually and analyzed for gamma-emitting radionuclides. The composite samples contain approximately the same quantity of flesh from each fish. For each composite a subsample of material is drawn for counting. Results are given in tables 25, 26, and 27.

Sediment Sediment samples are collected semiannually from Ponar dredge hauls made for bottom fauna. Gamma radioactivity and Sr and Sr content are determined in composite samples collected Erom each of four stations..

Locations of these stations are shown in table 23. Results are shown in

'table 28. I

44 Plankton Net plankton (all phytoplankton and zooplankton caught with a l00 p mesh net) is collected for radiological analyses at each of three stations by vertical tows with a 1/2-meter net. At least 50 grams (wet weight) of mate'rial is necessary for analytical accuracy. Samples are collected semiannually and submitted for gross beta analysis, and when quantities are sufficient, forI 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, sufficient quantities of plankton were collected for only one gross beta analysis.

Results're presented in table 29.

II Bottom Fauna The flesh and shells. of Asiatic clams collected semiannual.).y from the cross sections at four stations ]table 23) are analyzed for gamma-emitting radionuclides. levels of Sr and Sr are determined on the shells', and on the flesh when sufficient amounts were available. A 50-gram (wet weight) sample provides sufficient activity for counting. Results are given in tables 30 and 34. 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 X Tennessee 285.2 b Tennessee 288.7 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 24 RADIOACTIVITY IN SURFACE 'WATER TOTAL PCI/L - 0 ~ 03? BO/L NAKE OF FACILITY EEQ}tUE EERILY DOCKET NO. )Q:252c25Qc22O LOCATION OF FACILITY LIQEGIQQE REPORTING PERIOD 1255 TYPE AND LOWER LIMIT ALL CONTROL NUNBcR OF TOTAL NUMBER pc INDICATOR LOCATIONS l.Qt'BIIQS hIIU UIQt!EKI AiBUQht 5E65 LOCATIONS NONROUTINE OF ANALYSIS DETECTION MEAN (F) NAHc HEAN (F) MEAN (F) REPORTED PERFORHED (LLO) RANGE DISTANCE ANO DIRECTION RANGE RANGE HEASUREHENTS Eff UQIE 1. f Ef UQIE 2 GEE UNTIE 2 SEE 9QIE 2 VALUES <LLO

ROSS ALPHA F 00 0 VALUES <LLD 1 ANALYSIS PERFORHED BETA 1

2 ~ 00 3.13( 35/ 39) TRN 293.5 3. 27 (

- 12/ 13) 3 '4( - 22/ 26)

'9 ACROSS iAMMA (GELI) 65 2 '3 - 4 3? 2.37 4.31 F 07 5 65 K-40 NOT ESTAB 11 '2( -

11.52 1/

11 39) 52 TRH Z93 F 7 BFN DISCHARGE 11 '2(

11.52 1/ 13) 11.52 27 20.68 -

04( 3/ 26) 39~53 BI-214 NOT ESTAB 7 '2( 11/ 39> TRH 285 ' 9 '7( 3/ 13) 10.36( 17/ 26)

PS-214 0.34 -

3.08(

23.29 6/ 39) TRH 293.7 0 34 4 '6( 3/

22,93 13) 0

'?

'329( - 15/

44 '9 26)

NOT ESTAB Oe?8 - 6 '0 BFN DISCHARGE 2. 07 6 30 0 '7 - 18 '0 PS-212 NOT ESTAB '4( 6/ 39) TRH 285 ' 3 47( 1 / 13) '7(

0 '9 1 10/ 26)

'1 0 12 -

1 3.47 3.47 3.47 3 AC-228 15e00 39 VALUcS <LLO 27.49( 1/ 26)

27. 49 -

VALUES <LLO 27 '9

>R 89 10 F 00 12 VALUES <LLD 8 20 ANALYSIS PERFORHED 1R 90 2.00 12 VALUES <LLO 8 VALUES <LLD 20 ANALYSIS PERFORMED TRITIUM 330. 00 334 '1( 1/ 12) TRN 285 ' 334. 51 (

- 1/ 4) 333 '8( - 1/ 8) 20 334 '1 334 ~ 51 334.51 334 ~ 51 333.48 333.48 NOTE: 1 ~ NOMINAL LOWER LINIT OF DETECTION (LLO) AS OESCRIBEO IN TABLE 3 ~

NOTE 2 ~ HEAN AND RANGE SASEO UPON DETECTABLE MEASUREMENTS ONLY ~ FRACTION OF DETECTABLE MEASUREN NTS AT SPECIFI D LOCATIONS IS INDICATED IN PARENTHESES (F) ~

TABLE 25 RADIOACTIVITY IN @HITE CRAPPIE (FLESH)

PCI/G - 0 ~ 03? BG/G (ORY HEIGHT)

NAHE OF FACILITY QEQli85 Ef EBI DOCKET NO ZQ=252c2i)Qc225 LOCATION OF FACILITY l,ICE PIQUE ------- - -- ki BtlMk REPORTING PERIOD TYPE ANO LOMER LIHIT ALL CONTROL NUHBER OF TOTAL NUHBER OF INDICATOR LOCATIONS lQQSIIQ5 liIIU UIGUEGI 6UUMhl HEST LOCATIONS NONROUT INE OF ANALYSIS DETECTION HEAN (F) hAHE HEAN (F HEAR (F) REPORTED PERFORHED (LLD) ,RANGE DISTANCE ANO DIRECTION RANGE RANGE HEASUREHENTS Bff UQIE I SEE 5QIE 2

'6( 4/

SEE 5QIE 2 32 ~ 67( 2/

SEE hQIE ?

2/

0.10 4) 2) 29+20(

32

'52)

BETA WILSON RESERVOIR GROSS 6 27 58 37 '5 TRH 259-275 27.58 - 37.75 28 '7 - 29 GAHHA (GELI) 6 CS-13? 0 '2 0 '8(

0 F 06 4/ 4) 0 ~ 11 WILSON RESERVOIR TRH 259-275 0

0 09(

'? - 2/

0 2)

'1 Oe09(

0 '9 2/

0 '02)2)

K-40 NOT ESTAB 14 03( 4/ 4) WILSON RESERVOIR 14 25( 2/ 2) 15 ~ 15( 2/

10 ~ 81 16 ~ 81 TRH 259-275 13 F 88 14 '2 14 ~ 59

'2( 1/

15 71 BI-214 0. 02 4 VALUES <LLD 0 ~ 02( 1/ 4) RHEELER RES 0 ~ 02( 1/ 2) 0 0 '2 0 '1( 1/

0 '22)2)

PB-214 NOT ESTAB 0~ 02- 0 F 02 TRH 2?5-649 0 F 02 " 0 02 0~ 01 0 ~ 01 PB"212 NOT ESTAB 0 F 00( 1/ 4) MHEELER RES Oo00( 1/ 2) 2 VALUES <LLO 0 ~ OG- Oo00 TRH 275-349 0.00 - 0.00 NOTF: 1 ~ NOHINAL LOAMIER LIHIT OF DETECTION (LLO) AS DESCRIBED IN TABLE 3 ~

2. HEAN AND RANGE BASED UPON DETECTABLE HEASUREHENTS ONLY. FRACTION OF DETECTABLE HEASUREHENTS AT SPECIFIED LOCATIONS IS INDICATEO IN PARENTHESES (F) ~

TABLE 26 RADIOACTIVITY IN SHALLMOUTH BUFFALO (FLESH)

PCI/G - 0 ~ 037 81/G (ORY WEIGHT)

NAME OF FACILITYEEQUUE EEE$ 7 DOCKET NO. Eg:2$ $ c2ggc2$ ('t LOCATION OF FACILITY L,IUEEIQUE--- ----- -----BLBEBUB --- ------------ REPORTING PERIOD-1/55 TYPE AND LOWER LIMIT ALL CONTROL NUHSER OF TOTAL NUHBER OF INDICATOR LOCATIONS LQQBIiQU ttIIU UIQUESI BUUUBL UEBU LOCATIONS NONROUTINE OF ANALYSIS DETECTION HEAN (F) NAME MEAN (F) HEAtl (F) REPORTED PERFORMED (LLO) RANGE DISTANCE AND DIRECTION RANGE RAttGE HEASUREHENTS SEE UQIE 1 SEE UQIE 2 GROSS BETA 0 ~ 10 19 '3(

'2 - 4/ 4) WHEELER RES SEE UQIE 2 20 ~ 16(

- 2/ 2)

EEE HQIE 2 20.06(

- 2/ 21 2)

SAHMA (GELI) 6 16 20 38 TRH 275-349 ZO F 07 20 '5 18 '9 22 6

C$ -137 0 '2 0 '3( - 2/ 4) WILSON RESERVOIR 0.03(

- 1/ 2) 03( /

0 '3 0 2)

K-40 NOT ESTAB 0.03 9 '5( 4/ 4)

TRH 259-275 0 '3 0 03 Oe03-1 0 '3 64(

- 2/ 2) 9.20( 2/

WHEELER RES 11 '0 2)

BI-214 0 F 02 4 8 '5 -

VALUES <LLO TRH 275-349 10 9e37 11 90 7.49 1'0 0 07( 2/ 2) 0.10 0 '4(

0 ~ 04 PS-214 NOT ESTAB 0F 04 -

1/ 4) 0 F 04 WILSON RESERVOIR TRM 259-275 0

0~

04(

04-1/ 2) 0 04 0 '6(

0 '4 2/ 2) 0+08 PB-212 NOT ESTAB 0 F 00(

0.00 - 2/

0 '14) WHEELER RES 275-349 0 '1(

'1 1/ 2)

0. 01 0%00(

D.OC-1/ 2) 89 TRH 0 0.00 SR 0 50 2 VALUES <LLD 0 VALUES <LLD ANALYSIS PERFORMED SR 90 Oe10 2 VALUES <LLO 0 VALUES <LLD ANALYSIS PERFORHED NOTE. 1 ~ tiOHZNAL LOWER LZHIT OF DETECTION (LLD) AS DESCRIBED IN TABLE 3 ~

NOTE: 2 ~ HEAN ANO RANGE BASED UPON OETCCTABLE MEASUREMENTS ONLY ~ FRACTION OF DETECTABLE MEASUREMENTS AT SPECI"IED LOCATIONS ZS INOICATEO IN PARENTHcSES (F) ~

TABLE 27 RADIOACTIVITY IN SHALLHOUTH BUFFALO (WHOLE)

PCI/G - 0 ~ 037 BQ/G (ORY WEIGHT)

NAHc OF FACILITY EgQggg f DOCKET NO. $ Q-7$ Pc2QQ! 2$ {j OF FACILITY L,J5EJIQUE EBB'OCATION 8l 80858 REPORTING PERIOD TYPE AND LOWER LIMIT ALL i CONTROL NUHBER OF TOTAL NUHBER OF INDICATOR LOCATIONS LQQ8I?QU BIIU 5IQUEKI 8HBQ8L 5E85 LOCATIONS NONROUTINE OF ANALYSIS DETECTION HEAN (F) NAHE MEAN (F) HEAN (F) REPORTED PERFORMED (LLO) RANGE DISTANCE ANO DIRECTION RANGE RANGE MEASUREMENTS 5 E HQIE 1 Hf'9( UQIE ? SEE 5QIE 2 Kff BQIE 2 GROSS SETA 6

0 ~ 10 17 14.48 - 4/ 20 4) 02 WHEELER RES TRM 275-349 17.95(

17 35 - 2/

18 2)

'2 19e59(

17 '4 - 2/ 21,642)

GAHHA (GcLI 6

CS-137 0.02 0 0

'3(

'2 2/

0 03

4) WILSON RESERVOIR TRH 259-275 0 ~ 05(

0 '2 2/ 2)

Oa03 2 VALUES <LLD K-40 NOT ESTAB 7 08( 4/ 4) WHEELER RES 7 49( 2/ 2) 11.04( 2/ 2) 6 '5 F

F 00 TRM 275-349 6 ~ 97 8.00 7.37 14.70 SI-214 '2 0 '4( 1/ 4) WHEELER RES 0 04( 1/ 2) 0 '4( 1/ 2) 0 0 '4 0.04 TRM 275-349 0 '4 0.04 0 04- 0 04 PB-214 0 '3( 4/ 4) WHEELER RES 0 05( 2/ 2) 2 VALUES <LLD NOT ESTAB 0.01 0 '44) TRH 275-349 0 '3 0.01( 1/

0 '4 2 VALUES <LLO PB-212 0.01( 3/ WILSON RESERVOIR 2)

NOT ESTAB 0.00 0 '1 TRH 259-275 Oe01 0 '1 NOTc-. 1 ~ NOMINAL LOWER LIMIT OF DETECTION (LLO) AS DESCRIBED IN TASLE 3 ~

NOTE: 2 ~ HEAth Ai40 RANGE BASED UPON DETECTABLE HEASUREHENTS ONl.Y ~ FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INOICATEO IN PARENTHESES (F) ~

TABLE 28 RADIOACTIVITY IN SEDIMENT PCI/G - 0 ~ 037 BQ/G (DRY biEIGHT)

NAME OF FACILITY QQQgggffBQI Doc<ET No. 19=252c259c226 LOCATION OF FACILITY LI5fgIQHfhl.55555 REPORTING PERIOD TYPE AND LONER LIHIT ALL CONTROL NUMBER OF TOTAL NUHBER OF INDICATOR LOCATIONS LQQSIIQU l!IIU UIQUEH a~~ual. Sfau LOCATIONS NONROUTINE OF ANALYSIS DETECTION HEAN (F) NAHE MEAN (F) HEAN (F) REPORTED PERFORHEO (LLD) RANGE DISTANCE ANO DIRECTION RANGE RANGE HEASUREHENTS SAHHA (GELI) ff gQIf 1 Nff HQIE 2 Xff BQIE 2----- f Ef HQIE 2 14

' 2/ '4)

- 9/

C0-60 0 ~ 01 0 ~ 15( 10) TRM 293 0 ~ 21( 3) O.OS(

0 '2 0 '3 BFN DISCHARGE 0 17 OQ 23 0.02 - 0.03 CS-134 0 F 08 0 '1(

0 F 08 "

5/ 10) 0 '8 TRH 293 '

BFN DISCHARGE 0,12(

0 F 08 3/ 3) 0 ~ 18 4 VALUES <LLD CS-137 0 '2 0 '9(

0.04 -

10/ 10)

'7 TRM 288 '8 1 ~ 08(

0 ~ 89 2/ 2) 1 ~ 27 0 F 30(

0 ~ 17 4/

0.51 4) 288 '8 1

K-40 13 F 05( 10/ 10) 1o.23( 2/ 2) 13.00( 4/ 4)

NOT ESTAB 7 '2 - 2/ 16.'72 TRM 15.73 1 6.72 11 76 13 '9 IN-65 0 ~ 02 0 04( 10) TRH 293 ' Oo07( 1/ 3) 4 VALUES <LLD 0 '2 F

07 BFN DISCHARGE 0 F 07 0. 07 8 I-21 4 0 '2 1%32( 10/ 10) 0 '6 -

D~

1.91 TRH 288 '8 1 ~

1 81(

79 2/ 2) 1.82 1 ~ 12(

0. 98 4/

1 ~

4) 22 8 I-21 2 0 10 '9( - 10/ 10) '7 TRH 288 ~ 0 1. 89(

'9 1/ 1) ~ 35( 4/ 4) 0 '8 1

1 1 1 39 1 F05 1.47 PB-214 NOT ESTAB 1 42( 10/ 10) TRM 288 78 1.o6( 2/ 2) 1 ~ 19( 4/ 4)

Oe40 - 1 99 1 93 1s99 1 ~ 01 1.40 PB-212 NOT ESTAB 1o44( 10/ 10) TRM 288.78 1.78( 2/ 2) 27( 4/ 4)

RA-226 0 '3 -

'2( 6/

1 '6

10) TRH 288 0 1 ~

1.34(

60 1/

1,96 1) 1 ~

1 ~1 1.09(

7 3/

1~36 4)

NOT ESTAB 1 0 36 - '1.34 1e34 1 ~ 34 0 '850( 1 ~ 22 RA-224 NOT ESTAB 1 ~ 20 ( 5/ 10) TRH 288 ' 1 86( 1/ 1) 1 ~ 2/ 4) 0 ~ 35 - 1 ~ 8o 1eBo 1 ~ 86 1e48 1e51 1/ 0 ~ 27( 3/ 4) 0.18(

- 2/

BE-7 NOT ESTAB 10) TRM 292.7 0 20( 1) 0 ~ 16 Oe20 0.20 0. 20 0 ~ 17 0 46 TL-208 0 02 0.50( 10/

0 '5 - 0 10)

'8 TRM 288 '8 0065(

0 63 2/ 2) 0.68 0 ~ 44(

0 '2 4/

0 '74)4)

AC-228 Oe06 1 '4( 10/ 10) TRH 288 '8 1 ~ 79( 2/ 2) 1.32( 4/

Oo44 - 2.02 1eo7 91 15 41 291 '6 1 ~ 1 1 ~

PA-234M NOT ESTAB 2o54( 2/ 10) TRH 2 '1( 1/ 1) 4 '7(

~

'6 2/ 4) 2 18 - 2 '1 2 '1 2. 91 3 4 87 SR 89 1 '0 6 VALUES ANALYSIS PERFORMED

<LLO 2 VALUES <LLO SR 90 0 '5 0.35(

0.28 -

4/

0 '56) TRH 277 'b 0 41(

0 3o 2)

Oo45 Oo34(

0.34 1/

0.34 2)

NOTE: 1 NOMINAL LONER LIMIT OF, DETECTION (LLO)- AS OESCRIBEO IN TABLE 3 ~

NOTE: 2 ~ HEAN AND RANGE BASED UPON DETECTABLE MEASUREHENTS ONLY ~ FRACTION Ol= DETECTABLE HEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) ~

TABLE 29 RADIOACTIVITY IN PLANKTON (SAHPLE 1)

PCI/G - 0 ~ 03? SQ/G (ORY HEIGHT)

NAHE OF FACILITY QBQUUB EEBBI DOCKET NO ~ 19=222c2DQ/.225 LOCATION OF FACILITY LIUEGIQUE REPORTING PERIOD TYPE AND LOAER LIHIT ALL" CONTROL NUHBER OF TOTAL NUHBER OF INDICATOR LOCATIONS LQQSIIQU BIIU UIQUEAI 6UUMSL UEBU LOCATIONS NONROUTINE OF ANALYSIS OET ECTION HEAN (F) NAHE HEAN (F) HE AN (F) REPORTED PERFORHEO (LLD) RANGE DISTANCE AND DIRECTION RANGE RANGE MEASUREHENTS GEE UQIE 1 BEE UQIE 2 SEE UQIE 2 SEE UQIE 2 1/ 1)

GROSS SETA 1

NOT ESTAB SEE NOTE 3 34 '1 34 ~ ?1 (

- 54.?1 NOTE: 1 ~ NOHINAL Loi(ER LIHIT OF DETECTION (LLO) AS OESCRIBEO IN TABLE S ~

NOTE 2 ~ HEAN ANO RANGE BASED UPON DETECTABLE HEASUREMENTS ONLY ~ FRACTION OF OET CTABLE HEASUREHENTS AT SPECIFIEO LOCATIONS IS INDICATED IN PARENTHESES (F) ~

NOTE: 3. Insufficient saryle available for analysis.

TABLE 30 RADIOACTIVITY IN CLAM FLESH PCI/G - 0 ~ 037 8(4/G (ORY NEIGHT)

NAME OF FACILITY Eilgggg Efllilx DOCKET NO ~ RQ=Z22A2kgc22g LOCATION OF FACILITY l.15fggggf ilLilg5$8 REPORTING PERIOD 1gfy TYPE ANO LONER LIMIT ALL CONTROI. NU'IBER OF TOTAL NUMBER OF INDICATOR LOCATIONS l,ggilj?Q8 itIIU PIQUE KI 4lUU!liiL 5E 8U LOCATIONS NON ROUTINE OF ANALYSIS DETECTION MEAN (F) NAHE HEAN (F) MEAN (F) REPORTED PERFORHEO (LLD) RANGE DISTANCE AND DIRECTION RANGE RANGE MEASUREMENTS iAHHA (GELI)

Rf E SQIE 1 off UQIE 2 Sff Ogrf 2 off UQXE 2 12 C0-60 0.08 0 '6( 1/ 8) TRM 293 F 7 0.16( 1/ 3) 0~ 16- 0 '6 BFN DISCHARGE 0.16- 0 16 4 VALUES <LLO Z-40 NOT ESTAB 4

'900( 5/ 8) 12 '3 TRH 288a78 12 '3( 1/ 1) F 82( 4/ 4) 0 1 2~ .43 12 43 0.90 - 5.49 ZN-65 0 ~ 17 1 09( 4/ 8) TRH 293 ' 1053( 2/ 3) 4 VALUES <LLD I (Note 3) 0.64 81 BFN DISCHARGE 24- 81 BI-214 NOT cSTAB 2 40( 8/

1 ~

8) TRH 288 '8 1 ~

4 '0( 1/

-1 ~

'~45( 4/

PB-214 033-2.11 ( 8/

7 ~ 42 277 '8 4 90-

'6(

~

1/

4 '0 1 ) 1 ~

0

'0( 4 '64)4)

'68)8)

NOT ESTAB TRM 2 1) 4/

P8-212 NOT ESTAB 0~ 30-0.10( 5/

6 TRH 277 '8 0 296-21( 1/

2 '6 1) 1 0 12 0 '0( 3/

4 '84)

Oi 04 0 21 0 21 0. 21 0.11 0 25 Tl.-208 NOT ESTAB 0 03( 3/ 8) TRH 291 76 0 F 05( 1/ 1) 0.02(- 1/ 4)

AC-228 0 '2 0 16( 2/

0 F 05

8) '

0.05 0 F 05 0+02 0,02 NOT ESTAB TRH 293 Oo16( 2/ 3) Oe14( 1/ 4) 0 15 0 ~ 17 BFN DISCHARGE 0 ~ 15 0 ~ 17 0 ~ 14 0.14 NOTE 1 ~ NO'IINAL LONER LIHIT OF DETECTION (LLD) AS DcSCRIBED IN TABLE 3 ~

NOTE: 2 ~ MEAN ANO RANGE BASED UPON DETECTABLE MEASUREMENTS ONLY ~ FRACTION OF DETECTABLE HEASUREH NTS AT SPECIFIEO LOCATIONS IS INOICATEO IN PARENTHESES (F) ~

NOTE: 3. Zinc-65 in clam flesh reported to the Nuclear Regulatory Conmission on. June 25, 1985. Samples collected in November contained no evidence of fission or activation products.

TABLE 3l RADIOACTIVITY IN CLAM SHELL PCI/G - 0 ~ 037 SQ/G (DRY FREIGHT)

NAHE OF FACILITY EBQH55 EEBBZ DOC<ET NO ~ 29=222c25Qc225 LOCATION OF FACILITY ggQESIQUE SL85888 REPORTIVG PERIOD /PER TYPE ANO LONER LIMIT ALL CONTROL NUMBER OF TOTAL NUHSER OF INDICATOR LOCATIONS LQQBIIQU eIXU tfZGuEDI 835Qhl. HEST . LOC~TI~NS NONROUTINE OF ANALYSIS DETECTION MEAN (F) NANE MEAN (F) MEAN (F) REPORTED PERFORMED (LLD) RANGE OIS T ANCE AND GIREC T ION RANGE RANGE MEASUREMENTS XEE UQXE 1 SEE UQIE 2 SEE HQIE 2 E E UQIE 2 GAMMA (GELI) 12 CO-60 0 ~ 01 0 01( 1/ 8) TRM 293 F 7 0 01( 1/ 3) 4 VALUES <LLD 0 01 - 0.01 BFN DISCHARGE Oe01 - 0.01 K-40 NOT ESTAB 0 ~ 13(

0.01 - 6/

0 29

3) TRM 277 '8 "

0.22(

0 '2 -

1/

0 1)

'2 0 '4(

0.09 2/

0.20 4)

BI-214 Oe05 Oe16( 6/ 3) TRH 288.78 0 ~ 25( 1/ 1) 0 ~ 19( 3/ 4)-

0 '9 - Oe28 0 '5 " 0.25 0 '9 0.35 BI-212 OrlO 0 12( 1/ 8) TRH 292.7 0 12( 1/ 1) 4 VALUES <LLD Oe12 -

~

0 ~ 12 0~ 12- 0 ~ 12 PB-214 0.05 0 0 '717(

- 7/

0 54

3) TRH 288 '8 0 27(

~

0.27 -

1/

0 1)

'7 0 ~ 17(

0.09 3/

'24)4) 288 '8 0

PS-212 0 '6( 8/ 0.16( 1/ 0 F 02( 3/

Ra-226 NOT ESTAB 0 F 05 0

0

'1 -

'1( 2/

0 '6S)8) TRM TRH 293 '7 0.16 -

0 12(

~ 1/

1) 0 ~ 16 3) 0,01 4 VALUES <LLO Oe04 0 ~ 10 - 0 ~ 12 BFN DISCHARGE 0 12-

~

~ 12 TL-208 0. 02 0 F 05( 3/ 3) TRN 288o78 0.08( 1/ 1) VALUES <LLD 0.02 - 0 F 08 O.OS - 0.08 AC-228 0 '6 0 '0( -

0 F 07 7/

0 '08) TRN 288 '8 0~40(

0 '0 - 1/

0 1)

'0 0 0 '113(

- 3/ Or14 4)

SR 89 5 F 00 4 VALUES <LLD 2 VALUES <LLD ANALYSIS PERFORNEO SR 90 1 ~ 00 1 ~ 09(

- 1/ 4) TRH 293 ' 1 ~ 09(

" 1/ 2) 1 02( 1/ 2) 1 ~ 09 1 ~ 09 BFN DISCHARGE 1 ~ 09 1 ~ 09 1 02 1.02 r

NOTE: 1 ~ NOMINAL LOWER LIMIT OF DETECTION (LLD) AS OESCRISEO IN TABLE 3 ~

NOTE: 2 MEAN A'VO RANGE BASED UPON DETECTABLE HEASUREHENTS ONLY ~ FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATEO IN PARENTHESES (F) ~

Figure 11 i54 N

R ESERVOIR MONITORING NETWORK N

Elk River WHEELER DAM mile 270.90 mile 277.98 Rogersville 0

mile 282.6 mile 29l.76 Athens

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

ite 28878 mite 293.50 0

Courtland mile 305.0 mile 293.70 Decatur rnIle 307.52 Scale of Mile8 e- Automatic Sam ler 0

Figure 12 AHNNL AVERAGE 6ROSS SETA ACTIVITY CC Preoperational Operational 0 CC Phase Phase IN SURFACE HATER C

CJ CC ~0 Cj Jk BOWS FERRY i@CLEAR PLANT Cll Jl A CC 0

Cj CC 0 CJ C

wV 0 Average:

Preoperational Phase t

1968 1969 1970 1971 1972 1 973P 19730 1974 1975 197 6 1 9 77 1 78 1979 1980 1 hl 19 2 19 19 4 I9 5

a. No gross beta measurements made in 1978.

0 57 ualit Control A quality control program has been established with the Alabama Department of Public Health Environmental Health Administration . ~

Laboratory and the Eastern Environmental Radiation Facility, Environmental Protection Agency, Montgomery, Alabama. Samples of air, water, milk, and'vegetation collected around BFN are forwarded to these laboratories for analysis, and results are exchanged for comparison.

Data Anal sis i

The results from each sample are compared with the concentra-tions from the corresponding control stations and appropriate preopera-tional and background data to determine influences from the plant.

During this report period, concentrations in two samples were found to exceed the reporting levels as outlined in the plant Environmental Technical Specifications.

Cobalt-60 was identified in one vegetation sample collected near the site boundary in April. No indication of the presence of .,

cobalt-60 was observed either at the control stations or at any of the other stations around the plants. Subsequent samples showed no indication of the presence of cobalt-60. This single, isolated occurrence, the absence of other fission and activation products in

'the sample, and the lack of an increase in cobalt-60 releases from the plant prevented an identification of the causes for the presence of the isotope in the sample.

In May 1985, zinc-65 was identified in one sample of clam flesh taken from the Tennessee River approximately one-half 'mile downstream from the plant discharge. No fission or activation products had been identified in this medium during the previous report period.

Followup samples collected in June revealed zinc-65 at these downstream stations, with highest value being about two-thirds and the other values about one-third of the concentration reported in May. No fission or activation products were found in clam flesh samples collected in the November sample period. The exposure to an individual consuming clam with the highest activity was calculated to be less than 0.01 mRem/year, or 0.03 percent of the annual exposure limit. *.

However, to the best of our knowledge clams from the Tennessee River are not harvested for human consumption, therefore, even this small exposure is unlikely to take place.

Dose estimates were made from concentrations of radioactivity found in samples of environmental media. Media sampled include, but are not limited to, air, milk, food products, drinking water, and fish. Inhalation and ingestion doses estimated for persons at the indicator locations were essentially identical to those determined for persons at control locations. Greater than 95 percent of those doses were contributed by the naturally occurring radionuclide potassium-40, and by strontium-90 and cesium-137 which are long-lived radioisotopes found in fallout from nuclear weapons testing.

58 Conclusions It is concluded from the above analysis of the data and from the trend plots presented 'earlier that there were no measurable increases in the exposure to members of the general public attributable to the operation of BFN. Indications of the presence of small quantities of fission and activation, products have been seen, especially in aquatic media. Although the levels reported sometimes exceed the values reported at the corresponding control stations, they are similar to levels reported in samples co).lected in conjunction with preoperational monitoring programs being conducted by TVA at nuclear plant construction sites upstream from Browns Perry. The radioactivity reported herein may be 'the result of fallout, fluctuations in the existing environment, or computer program artifacts, and may include small contributions from plant operations. Any activity resulting from plant operations which may be present is generally difficult to distinguish from background.

~ ~