ML18032A682

Environ Radioactivity Levels Annual Rept for 1984. W/

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)

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ACCESSION NBR FACIL: 50-259 50-260 50-296 AUTH. NAME HUFHAME J. W.

RECIP. NAME QRACEi J. N.

REGUL RY INFORMATION DISTRIBUTI SYSTEM (RIDS) l 8712300217 DOC. DATE: 85/04/10 NOTARIZED:

NO DOCKET Browns Ferry Nuclear Power Stationi Unit ii Tennessee 05000259 Browns Ferry Nuclear Power Station>

Unit 2i Tennessee 05000260 Browns Ferry Nuclear Power Stationi Unit 3i Tennessee 05000296 AUTHOR AFFILIATION Tennessee Valley Authority RECIPIENT AFFILIATION 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.

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ea to: Ebneteri Axelradi S. Richardson B. D. Liawi K. Barri Donohewi OI.

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Ebneter4 Axelrad4 S. Richardsoni B. D. Liawi K. Barry Donohewi OI.

05000259 05000260 05000296 REC IP IENT ID CODE/NAME JAMERSONZ C GEARSI G INTERNAL: ACRS AEOD/DSP/TPAB NRR/DEST/PSB NRR/PMAS/ILRB RGN2 F ILE 02 COPIES LTTR ENCL 0

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I I

TENNESSEE VALLEYAUTHORITY CHATTANOOGA. TENNESSEE 37401 400 Chestnut Street Tower II t.

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 RADIOACTIVITYLEVELS BROWNS PERRY NUCLEAR PLANT ANNUAL REPORT - 1984 TVA/NUC PR/RH F'DR ADQcg 0 R

PDR April 1985

CONTENTS List of Tables List of Figures.

Introduction iii 1.v Atmospheric Monitoring Terrestrial Monitoring 23 Reservoir Monitoring 43 Quality Control.

Data Analysis.

Conclusions.

55 55

LIST OF TABLES Tab l.e Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table

'fable Table Table Table Table Table Table Table Table I - Environmental Radioactivity Sampl.ing Schedule 2 - Atmospheric and Terrestrial Monitoring Station Locations - Browns Ferry Nuclear Plant 3 - Detection Capabilities for Environmental Sample Analysis 4 - Results Obtained in Interlaboratory Comparison Program 5 - Maximum Permissible Concentrations for Nonoccupational Exposure 6 - Radioactivity in Air Filter 7 - Radioactivity in Rainwater 8 - Radioactivity in Heavy Particle Fallout 9 - Radioactivity in Charcoal Filters 10 - Radioactivity in Milk ll - Radioactivity in Vegetation 12 - Radioactivity in Soil 13 - Radioactivity in Well Water 14 - Radioactivity in Public Water Supply 15 - Environmental Gamma Radiation Levels 16 Radioactivity in Cabbage 17 - Radioactivity in Corn 18 - Radioactivity in Peaches 19 - Radioactivity in Peas 20 Radioactivity in Potatoes 21 - Radioactivity in Poultry 22 - Radioactivity in Tomatoes 23 - Sampling Schedule

- Reservoir Monitoring 24 - Radioactivity in Surface Water 25 - Radioactivity in Wh'ite Crappie (Flesh) 26 - Radioactivity in Smallmouth Buffalo (Flesh) 27 - Radioactivity in Smallmouth Buffalo (Whole) 28 - Radioactivity in Sediment 29 - Radioactivity in Clam Flesh 30 - Radioactivity in Clam Shell 4

7 13 14 15 16 17 26 27 28 29 30 31 32 33

~

34 35 36 37 38

~

45 46 47 48 49 50 51

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52

LIST OF FIGURES Figure 1

- Tennessee Valley Region Figure 2

- Atmospheric and Terrestrial Monitoring Network 10 l8 Figure 3

- Local Monitoring Stations Figure 4

- TLD Locations, BFN 19 20 Figure 5

- Annual Average Gross Beta Activity in Air Filters, Browns Ferry Nuclear Plant 21 Figure Figure 6

- Annual Average Gross Beta Activity in Drinking Water, Browns Ferry Nuclear Plant 7

- Direct Radiation Levels, BFN 39 40 Figure 8

- Direct Radiation Levels, BFN (4-quarter Moving Average) 40 Figure 9

- Direct Radiation Levels, WBN Figure 10 - Direct Radiation Levels, WBN (4-(}uarter Moving Average) 41 41 Figure ll - Reservoir Monitoring Network 53 Figure 12 - Annual Average Gross Beta Activity in Surface Water

0

ENVIRONMENTAL RADIOACTIVITYLEVELS 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 Area'adiological Laboratory (WARL) located in Muscle Shoals, Alabama.

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 Station Locations Muscle Shoals Lawrenceburg Rogersville Athens Decatur Courtland Site 1 (N)

Site 2 (NNE)

Site 3 (ENE)

Site 4

(NNW)

Site 5

(WSW)

Farm B

Farm S"'arm P

Farm L Farm E Farm W

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

Various local Farms Air Filter Charcoal Filter Rain-water M

M M

M M

M M

M M

M M

Heavy Particle Fallout M

M M

M M

M M

M So'1 V~eetation M

M M

M M

M M

M M

M M

M M

M River Milk

'Water Well Water Public Aquatic Life Water and Sediment Foods W " Weekly M - Monthly (Every 4 Weeks)

"'Discontinued operation November 1984 Q - Quarterly S - Semiannually A - Annually

Table 2

ATHOSPNERIC AND TERRESTRIAL MONITORING STATION LOCATIONS BROWNS FERRY NUCLEAR PLANT Sam le Station Approximate Distance From Plant Approximate Direct,'ion From Plant LH-1 BF, LH-2 BF, LH-3 BF>

I.H-4 BF>

North North-Northeast East-Northeast North-Northwest PH-1 BF>

PH-2 BF>

PH-3 BF>

PH-4 BF>

RH-1 BF>

Rogersvillc, AL

Athens, AL Decatur (Trinity),

Courtlan<1, AL Huscle Shoals, AL (Control)

I.M-5 Bl', West-Southwest 1.0 Mile 0.9 Hile 1.0 Mile 1.7 Hiles 2.5 Hilcs 13.8 Hiles 10.9 Hiles AL 8.2 Hiles 10.5 Miles 32.0 Hiles

( 1.6 kilometers)

( 1.4 kilometers)

( 1.4 kilometers)

( 2.7 kilometers)

( 4.0 kilometers)

(22.2 kilometers)

(17.5 kilometers)

(13.2 kilometers)

(16.9 kilometers)

(51.5 kilometers)

N NNE ENE NNW WSW NW NE SSE WSW W

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

NNW g>

Farm S"'arm B

Farm 1.

I'arm P

Farm E

Farm W

Var>a N (Control)

Farm J (Control)

Farm C (Control)

Farm Ca (Control)

Farm Cb (Control Farm M (Control) 4.75 Hiles 7.0 Miles 5.0 Hiles 8.8 Miles 6.1 Miles 6.9 Miles

'7.0 Miles 40.0 Hiles

<<32.0 Miles 32.0 Hiles 22.5 Miles 22.5 Miles

( 7.6 kilometers)

(11.3 kilometers)

( 7.0 kilometers)

(14.

1 kilometers)

( 9.8 kilometers)

(11.0 kilometers)

(43.4 kilometers)

(64.4 kilometers)

(51.5 kilometers)

(51.5 kilometers)

(36.2 kilometers (36.2 kilometers)

N NW NE NE NW NNW

'N W

E ENE Discontinued operations November 1984

Table 3

DETECTION CAPABILITIES FOR ENVIRONMEhTAL SAK1PLE ANALYSIS A.

S ecific Anal ses NOMINAL LOWER LIMITOF DETECTION LLD)*

Air Particulates Charcoal Fallout Water

~CK/

~Ci/

C /K, /rri/K Vegegation and Grain IK~ci F~Dr Soil and Sediment Kerr/

DDrKD Fish Clam Flesh,

Plankton, p~Ci/ i~Dr

Foods, Meat, Clam Shells

Poultry, Milk Kerr/

DDrr r~cr/K D*r Kcr/r Gross e Gross B

3H 1311 89Sr

>>Sr 0.005 0.01 0.005.

0.001 0.02 0.05 2.0

'.3 330 10 2

0.05 0.20 0.25 0.05 0.35 0.70 1.5 0.3 0.1 0.1 0.5 0.1 0.7 0.7 5.0 1.0 25 40 8

0.05 10 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 particulates

~ct/ot NaI* ~Ge Li **

Water Vegetation Soil and and milk and grain sediment

~CL/t

~ct/

de

~ct/~dct NaI ~Ge Li NaI

~Ge Li NaI

~Ge Li Clam flesh Fish and plankton f>~Ci/,~dr

~Ci/~dry Net

~Ge Lt N t ~G* Lt Foods (tomatoes Meat and

potatoes, etc.)

poultry Ct/N e

~dt/

ee Clam shells p~Ci/

drrr NaI

~Ge Li NaI Ge(Li)

NaI

~Ge Li 38 0.35 0.56 0.07 40 90 20 60 15 40 40 26 5

90 50 15 10 10 10 10 10 10 0.15 0.07 0.07 0.08 0.17 0.08 20 15 55 15 40 15 70 20 30 15 400 50 15 10 15 10 150 15 141'144Ce 0.03 38 0.55 0.35

0. 35 0.35

>>4ce O.O2 33 0.22 0.06 0.06 0.06 Cr 0.07 0.03 60 44 1.10 0.47 0.60 0.10 0.60 0.10 0.60 0.10 131I 0.01 0.01 15 8

0.35 0.09 0.20 0.02 0.20 0.02 0.20 0.02 103 '06Ru 0.04 40 0.65 '.45 0.45 0.45 Ru 0.03 40 0.51 O.ll 0;11 0.74 0.11 134Cs 0.01 0.02 26 0.20 0.33 0'12 0.08 0.12 0.08 0.48 0.12 0.08 40 137Cs 0.01 0.01 5

0.20 0.06 0.12 0.02 0.12 0.02 0.08 0.12 0.02 40 962r-Nb

0. 01 0.20 0.12 0.12 0.12 40

>>Zr O.O1 10

0. 11 0.03, 0.03 0.03 10 0.01 5

0.05 0.01 0.01 0.01 5

58Co 0.02 0.01 5

0.23 0.05 0.20 0.01 0.20 0.01 0.20 0.01 15 5

6"Mn 0.02 0.01 0.20 0.05 0.15 0.01 0.15 0.01 0.15 0.01 10 5

662n 0.02 0.01 9

0.25 0.11 Q.23 P.02 0.23 0.02 0.23 0.02 15 9

6 Co 0.01 0.01 5

0. 17

0. 06

. 0. 11

0. 01 0.'ll

0. 01 0.11 0.01 10 5

40K 0.10

2. 50

0. 90 0.90 0.90

=

150 140Ba-La 0.02 0.68

'.15 0 )5 0.15 15

>>08 O O2 25 0.34 0.07 0.07 0.30 0.07 25 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.

I

~~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 given samples.

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 in a 0.5-L Marinelli beaker as dry weight.

The average dry weight fs 400-500 grams.

Air filters and very small volume sanples are counted fn petri dfshes centered on the detector endcap.

-. The counting system consists of a ND-6620 nultichannel analyzer and gdrnaniun detector having an efffcfency of 20 percent.

The counting time is normally 4'-15 hours.

All spectral analysis fs performed using the software program HYPERMFT 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 Gross Al ha A.

Air Filter (pCi/Filter)

Gross Beta Strontium-90 Cesium-137 Date EPA value

(+3o)

TVA

~AV

~

EPA value TVA

(+3a)

~Av EPA value TVA

(+3a)

~Av.

EPA value TVA

(+3a)

~Av 11/83 3/84 8/84 19+9 15+9 17+9 a

<1 18 17 50+9 51-9 51+9 40 60 60 15+3 16 21+A 20 18+%

N/A 21+9 11+9 15+9 20 10 15 B.

Tritum in Urine (pCl/1)

Date 2/84 11/84 EPA value (+30) 2383+608 2012+598

~TVA Av 2466 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)

Date 1/84 3/84 4/84 5/84 6/84 7/84 8/84 9/84 10/84 10/84 11/84 12/84 10+9 5+9 10 6

3+9 4

6+9 ~

6 519 5

14+9 11 719 8

Gross Al ha EPA value TVA'(33a

~A Gross Beta EPA value TVA

(+3O)

~Av.

1219 15 20+9 20 6i9 6

13+9 16 1619 12 64+9 60 2019 22 25+9 32 34+9 llk9 41 12 Stroat ium-89 EPA value TVA

(+30)

~Av.

36i9 39 5+3 19+3 12+3 18

.13 Strontium-90 EPA value TVA

(+3o)

~Av 24+3 23 Tritium EPA value TVA

~3a>

~A 3508+630 3580 3081+622 2770 2817+617 2607 2810+617 2517 3182+624 3400 Iodine-131 EPA value TVA (i3a)

~Av.

6i0.8 6

34+10 36 36+10 33 D.

Gamma-Spectral Analysis of Mater (pCi/1)

Date 2/84 6/84 10/84 10/84 Chromium-51 EPA value TVA

(+3o)

~Av.

40+9

<44 66+9 72 40+9 43 Cobalt-60 EPA value TVA

(+3a)

~Av.

10i9 11 31+9 32 20+9 22 14+9 17 Zinc-65 EPA value TVA

(+3a)

~Av.

50+9 50 63i9 66 147+9 151 Ruthenium-106 EPA value

~(s3a TVA

~Av 6119 53 29+9

<40 47+9 48 Cesium-134 EPA value TVA

~(+3a 31i9 29 47+9 44 31+9 29 2i9

<5 Cesium-137 EPA value TVA

~(3a

~A 16+9 37+9 2419 26 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 Date 1/84 7/84 EPA value TVA

(+3a)

~Av.

34i9 40 25+9 N/A EPA value (f3a) 20+3 20+3 TVA

~Av.

19 N/A EPA value TVA

(+30)

~Av 20f10 20 39+10 40 EPA value TVA

(+3a)

~Av.

20+9 21 25+9 26 EPA value TVA

(+3a)

~Av.

2730+236 2670 2605+226 2624 F.

Milk (pCi/1)

Date Strontium-89 EPA value TVA

~(333

~A Strontium-90 EPA value TVA

(+3a) 'Av.

Iodine-131 EPA value TVA

~(+33

~A Cesium-137 EPA value TVA (f30)

~Av.

Potassium-40 f EPA value TVA

(+35)

~Av 3/84 6/84 10/84 25-9 22+9 24 26 17+A 16+3 18 15 6+0.9 6

43+10 39 42xlo

~

40 35i9 32+9 34 30 1496+-130 1483 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

- MAXIMUMPERMISSIBLE CONCENTRATIONS I

FOR NONOCCUPATIONAL EXPOSURE Alpha Nonvolatile beta Tritium 1 37(.

103>>106R 144(

"zr-96Nb 140Ba 140L 131I 6SZn 4Mn 60Co 89Sr "Sr

$ 1Cr 1 34(.

6 BCo In Mater

~Ci/1*

30 3, 000 3,000, 000 20,000 10,000 10,000 60,000 20,000 300 100,000 100,000 30,000 3,000 300 2,000,000 9,000 90,000 MPC 'n Air

~Ci/m

• 100 200,000 500 200 200 1,000 1,000 100 2,000 1,000

'00 300 30 80,000 400 2,000

• 1 pCi = 3.7 x 10 Bq.

. TABLE 6

NAME GF FACILITY EBQMQS EEBBX LOCATION OF~EACJLITY LIHESIQHE RACIOACTIVITY.IN AIR FILTER PCI/H(3) - 0 ~ 037 EO/V(3)

DOC<ET NO ~

SQ=2S2c2EQA22E TYPE AND TOTAL NUMBER OF ANALYSIS BEBEQBUEQ GROSS ALPHA 50 GROSS BETA 568 GAMMA (GELI) 143 LONER LIMIT CF DETECTION ILLQ2 0 ~ 005 0 ~ 010 ALL INDICATOR LOCATIONS MEAN (F)b BBHQEb CD 02( 437/ 466) c.a1-O.G4 ATHENS'L 1C ~ 9 MILES NE 0 ~ 02(

50/

52) 0C1-004 I.QChIIQb )tIIU lfIQBESI khUQhl HE'S~

NAME MEAN ())

QISI65QE SUE QIBEQIIQ5 BASTE CONTROL LOCATIONS MEAN (F)

BAtUQE 0 ~ 01 (

1/

50) 0 ~ 01-G ~ 01 0 ~ 02(

96/

1G2) 0 ~01-0%04 NUMBER OF NONROUT INE REPORTED UE8SQBELEUIS K-40 BI-214 BI-212 PB"214 PB-212 BE-1 TL-208 AC-228 PA 234M SR 89 44 SR 90 44 NGT ESTAB 0'20 NOT ESTAB 0'20 NOT ESTAB 0 ~ G50 NOT ESTAB NOT ESTAB

'NOT ESTAB 0 ~ C05 0 ~ 001 C.02(

58/ 117)

G Ga-0 C4 CD 02(

1/ 117) 0'2-0'2 0'1(

1/ 117)

C ~ 01 0 ~ 01 CD 02(

2/ 117)

G ~ 02-0 F 02 0 00(

21/ 117)

C ~ 00-0 ~ Ga CD 06(

85/ 117)

C ~05-0'1 G 00(

19/ 117) 0%00-0%00 0 00(

8/ 117) 0 F00-0 Ca CD 18(

2/'17)

CD 17-0'9 36 VALUCS <LLO ANALYSIS PERFORMED 36 VALUES <LLD ANALYSIS PERFORHEO LH2 BF NORTH 0 ~ 9 MILE NNE LM1 BF NORTHMEST 1 ~ C MILE N

RGGERSVILLEr AL 13 ~ 8 MILES NM LM1 BF NORTHMEST 1 ~ C NILE N

LM5 BF DAVIS F 2 ~ 5 MILES LSM ATHENS'L 10 ~ 9 HILES NE COURTLANOi AL 1G ~ 5 MILES MSM LV3 BF NORTHEAST 1 ~ C HILE ENE RGGERSVILLEr AL 13 8 MILES NM 0%C2(

0 ~ C1-a.c2(

0 ~ 02-0 ~ G1(

0 ~C1--

O.C2(

0 ~ C2-

- a.ca(

0 ~ Ca-0%C7(

0 ~ C5-0 CO(

~ 0 ~ Ca-0 ~ Ca(

0 ~00-0'9(

0 ~ 19-5/

13) 0.04 1/

13) 0 Q2 1/

13) 0'1 1/

13) 0 ~ 02 2/

13).

0 F 00 10/

13)

C ~ 10 1/

13) 0 F 00 1/

13) 0 F 00 1/

13)

G ~ 19 0 ~ 01(

12/

26) 0 ~ 01-C ~ 02 0 02(

1/

26) 0 ~ 02 0 ~ 02 26 VALUES <LLG 0%02(

1/

26) 0'2-G ~ 02 0 F00(

6/

25) 0 F 00-0 F 00 0'7(

18/

26) 0 F 05-0%12 0 F 00(

6/

26) 0%00-0 F 00 0'1(

2/

26) 0 00--

0 ~ 01 26 VALUES <LLD 8

VALUES <LLC 8

VALUES <LLC 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 NAHE OF FACILITY fBQBll5 EfBBI LOCATICN OF FACILITY l,jtffSIQUf RACIOACTIVITY IN RAINWATER PCI/L - 0 ~ 037 80/L DOCKET HO 5Q=252A20Qc29f REPORTIHG PERIOD 1256 TYPE ANO TOTAL NUHBcR OF ANALYSIS Pf BEQBBfQ GAMHA (GELI) 132 LONER LIMIT OF D ET ECTION LLLQl ALL INDICATOR LCCRTIONS MEAN (F)P BBUQf LQGBIIQB HJIU bZQUERI hhUQhl, BfBU NAME MEAN (FT QIDIhllQf 65Q QIBHIIQtl BESQE CONTROL LOCATIONS HEAN (F)b BBUQfb NUMBER OF NONRCUTIhc REPORTED lfhfQBfkf5IX K-4C BI-214 PB-214 PB-212 BE-1 TRITIUH 132 NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB 330 F 000 22 ~ 33(

9/ 108) 6'7-45'8 5'3(

52/ 108)

CD 13-28'8 F 08(

29/ 10S)

C 07-20 11 1 '0(

35/ 108)

C 18-4 o2 49'7(

28/ 108) 29'6-99'0 108 VALUES <LLD ANALYSIS PERFORMED LH1 BF NORTHWEST 1

0 MILE N

CCURTLAHOr AL 10 ~ 5 MILES NSX COURTLANDr AL 10 ~ 5 MILES MSil ATHENSr AL 1G ~ 9 MILES NE RCGERSVILLEr AL 13 ~ 8 MILES NX 38 ~ 51(

38 ~ 51-7 56(

0 ~ 77-6 20(

1 ~ 46-2 ~ 46(

1 ~ 20-58 F 88(

42 ~ 48-1/

12) 38'1 11/

12) 28 ~ 18 8/

12) 20 ~ 11 5/

12) 4 ~ 62 4/

12) 99 30 2'7 ~ 22 (

2/

24) 21 '5-33 F 00 6 45(

14/

24) 0'0-28 F 88 9'9(

5/

24) 3'2-24 73 F 80(

5/

24) 0 79" 3

64 45'9(

8/

24) 38'5-71 F 09 24 VALVES <LLD a.

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

b.

Mean and range based upon detectable measurements only.

Fraction of detectable measurements at specified locations is indicated in parentheses (F).

TABLE B'AME OF FACILITY QEQggg gfEEI LOCATION OF, FACILITY LIQPBIQQP RADIOACTIVITY IN HEAVY PARTICLE FALLOUT MCI/KM(2) - 570COOOG ~ 00- EQ/KF(2)

DOCKET NO 50=222c2BQA22B BLBeBuB REPORTING PERIOD JQQB TYPE ANO TOTAL NUHBER OF ANALYSIS EEEEQE5iQ GROSS BETA 142 LOMER LIMIT OF DETECTION a SLLQ?

Oo050 ALL INDICATOR LOCATIONS MEAN (F)

~

-b Bn5QR C.22( 114/

11 6) 0 06-1 25 LQKBIIQB HJIU hIQUESI BhdUBL ZEBU~

NAME MEAN ($)

QIKIBUQE BUQ QIEPQIIQU EBHQC LM4 BF TRAILER P

0 ~ 46(

12/

12) 1 ~ 7 HILES NNM 0 21-1+25 CONTROL LOCATIONS HEAN (f)P EBHQf 0 ~ 16(

25/

26) 0'6-0'6 NUMBER OF, NOhROUTINE REPORTED HFBRQEELEBI5 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 NAME OF FACILITY BBQ)tgS EEBBI LOCATION OF FACILZTY LIHESIQHE RADIOACTIVITY IN CHARCOAL FILTERS PCI/H(3) -

0 ~ 037 BQ/H(3)

DOC<ET NO ~

SQ=2S2c24QA225 hl BEh58--

RsPORTING PERIOD TYPE AND TOTAL NUHBER OF ANALYSIS BEBEQB5EQ IODINE-131 565 LOWER LIHIT OF DETECTION a SI LQ?

0 020 ALL ZNDICATOR LOCATIONS HEAN (F) b b

B689E C ~02(

27/ 463) 0 02-0'4 LQQBIIQh HIIU t)IQUESI hhU!lhL EEPH

~

NAHE MEAN (F)

QISIhUGE BN QIBEQIIQ5 BhUGE LH2 BF NORTH O.C3(

2/

52) 0 ~ 5 NILE HNE 0 ~ 02 0 ~ 03 CONTROL LOCATIONS MEAN (F)

BSHGE 0 ~ 02(

10/

1C2) 0'2-0 03 NUHBER OF NONRCUTINE REPORTED HESSQBEIEHIS 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 FAYETTEVIILE Q WILSON FLORENCE DAM PM-IBF WHEELER ROBE SVILL OAM ATHENS PM-2BF FFIEL MUSCLE SHOALS RM-IBF LEIGHTON TUSCUMBIA 44 COURTLANO PM-4 F

pRUSSELLVILLE BROWNS FERRY NUCLEAR PL NT OECAT R

PM-3BFO IO MILES HARTSELLE HUNTSVILLE GUNT SVII.

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 BROWNS FERRY NUCLEAR PLANT 19 ATHENS U.

~

Y 0

0 BFN ALA. HWY 20 Legend

~

Air Monitor DECATUR 0

AUtomatic Well Sampler Dairy Farm Other Farm" Scale 0

I 2

3 4

5 Miles

20 Figure 4

c= ~,

~

~

. i

~,,'tnt',

54 ~Q, 'g*t*

4)

/ I

~ r rrrr L,V/$~4 I

I

/

r,IC jtg...

TLD locations

, ')'tf;,i, OI n.'

Ia I

'VII L L

k. <<I.

I, I

~I II, I

t

~

~ L>>

ilj/,

I I

~ ~

l/

)/-

,'A IlI",g l 0

L

/

I/

LL ~

4 4/ ~ I

<</

i I

I I

t

~

t ~

) IL 4lp l~

') )A't

'fl

)

. !.t.,

I L fl IP ta',

(I

,~C'g, I~ ("j+,

>jf, ),

'stf

/rg(

( tq rr 4

<>1" Iv,,

Vs>>

l "t I I I

w<

r'.,4L)

I w

/

~Ll

/,/'lw I

(I a

~r IA I, ll Itl) )qtV

'I I

. 8w r(

4' I'I5a t.

(CIIt>>rIr I 'tL, I (

I rent I 7 I(

I

~I t I,,

I,) 'I<

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'i

'I g $

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="7 al

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k II

.'( tt

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~

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-. I ILL

Pigure 5

.30

.25 Preoperational Phase I

Operational Phase I

AmW AVamaE ASS Bva PCrIVm IN AIR FILTERS 1hOWS FaaV NuCLIm Purr "e

0

.20

.15

.10 o C ll 0 0 H 4J 4l co c 4J Se Ch o

cI 0 o

Sl Co m V I

Ave~ra e:

P~ro~erational Phase

.05 1

70 1971 1972 1973P 19730 1974 1975 1976 19 7

1978 1979 1980 1981 1 82 1983 1984 968 1969 19

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 one'ublic water supply upstream are sampled by taking monthly grab samples 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 activities'eported in surface water samples taken upstream-from BFN (figure 12) and in samples taken from the Tennessee River in preoperational monitoring programs conducted by TVA at other sites.

Environmental Gamma Radiation Levels Bulb-type Victoreen manganese-activated calcium fluoride (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.

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

REPORTIHG PERICO TYPE AND TOTAL NUHBER OF ANALYSIS fEBfQB5EQ IODINE-131 497 GAMMA (GELI) 124 LOWER LIHIT CF DETECTION a Ll LQX 0.500 ALL INDICATOR LOCATIONS HEAN (F) b BSUQE 195 VALUES <LLO ANALYSIS PERFORMED LQEkIIQb ltIIU UIQUEEI hhUQBL LEST~

NAPE MEAN (()

QIEIhHQE 85Q QIBEQIIQU BhHQE CONTROL LOCATIONS MEAN (f)b

.B85QE

.302 VALUES <LLG NUMBER OF NONROUTINE RcPORTEO VESEQBE"=BRIE CS-1 37 K-40 BI-214 PB-214 PB-212 TL-208 AC-228 SR 89 122 SR 90.

122 5.000 HOT ESTAB HOT ESTAB HCT ESTAB NCT ESTAB NOT ESTAB NOT ESTAB 10 F 000 2 ~ GOO 7.55(

, 7/

48) 5.15-11 01 1271 95(

48/. 48) 881 '9-17o7 ~ 99 11 '5(

27/

48) 0 47-126 67 19'5(

13/

48)

C 00'-

140 ~ 10.

2 ~ 21(

10/

48) 0 ~80-3 ~ 80 0 ~ 81(

11/

48) 0'2-3+31 21(

5/

48) 2 ~ 53 13 ~ 36 46 VALUES <LLO ANALYSIS PERFORMED 4 ~ 26(

41/

46) 2'3-7'9 PAGE FARM 8 75 HILES E

SMITH FARH 4~75 MILES N

PAGE FARM 8 75 HILES E

PAGE FARH 8 ~ 75 HILES E

PAGE FARM 8~75 HILES E

SMITH FARH 4%75 HILES N

LCCNEY FARF 5 75 HILES ENE SMITH FARM 4a75 MILES'N

- 8 ~ 20(

5 ~ 15-1337 '3(

1155 ~ 58-19 ~ 15(

1 ~ 11-39 ~ 86(

0 ~ 00-2'3(

2 ~1-1 ~ 22(

0 ~ 37-13 ~ 36(

13'6-4/

12) 11 '1 10/

10) 1787'9 10/

12) 126'7 4/

12) 140'0 2/

12) 2+74 5/

10) 3 ~ 31 1/

13) 13 36 5 ~ 10(

10/

10) 3'9-7'9 5 67(

1/

76) 5'7-5.67 1270 05(

76/

76) 789 '9-1839 06 7 43(

55/

76) 0'6 19'7 6'6(

38/

76) 0 72-25'4 1 59(

22/

76) 0 02" 4

51 1 '3(

20/

76) 0'3" 2'9 5'9(

7/

76) 0'2-25'2 76 VALUES <LLO 3 ~ 88 (

71/

76) 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 NAME GF FACILITY ggQggg gggQZ LOCATION OF FACILITY gJQg$ g{}gg RADIOACTIVITY IN VEGETATION PCI/G - 0 ~ 037 BC/G (DRY %EIGHT)

DOCKET NO ~

GQ=25$ cggQAPff ILLBOhBh REPORTING PERIOD SR 89 SR 90 52 52 TYPc AND TOTAL NUMBER OF ANALYSIS EEBEQBHPQ GROSS ALPHA 1

GROSS BETA 1

IODINE-131 220 GAHHA (GELI) 235 C0-60 CS-137 K 40 BI-214 BI-212 PB-214 PB-212 RA-223 BE-7 TL-208 AC-228 PA-234H LONER LIHIT OF DETECTION a SLLQ?

0'50 0'00 NOT FSTAB 0'60 0'60 NOT ESTAB 0'00 NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB 0'50 0'50 0 ~ 14(

0 ~ 14-0 ~08(

0 ~ G6-10 ~75(

0%46-0 ~17(

0 ~10" 0 27(

0 ~ 06-G ~08(

0 ~00-0'4(

0 F 00 0'2(

0 12-5 F 88(

0 ~ 21-0'2(

0 ~ GO-0 ~ 11(

C 00-3'4(

2 ~78-CD 48(

0'9" 0'6(

0 ~05-1/ 193) 0 ~ 14 11/ 193) 0 ~ 15 193/ 193) 40 10 57/ 193) 0%43 10/ 193) 0 ~ 38 167/ 193) 0 40 136/

193) 0 ~ 27 1/ 193) 0 ~ 12 192/ 193) 25%72 114/ 193) 0 ~ 10 111/ 193) 1 ~ 15 4/ 193) 4 ~ 96 5/

46) 0 ~ 80 45/

46)

F 05 ALL INDICATOR LOCATIONS McAN (F)

BBUQE 0%05(

1/

1)

C ~ 05-0 05 7'4(

1/

1) 7'4-7 94 0 00( 161/ 194) 0 00-0%01 LH1 BF NORTHMEST 1 '

MILE N

SMITH FARH 4 ~ 75 HILES N

LH2 BF NORTH 0 ~ 9 HILE NNE ATHENSr AL 10 ~ 9 HILES NE MISER FARM 6%9 HZLES NE EVANS FARM 6%1 MILES NE LH4 BF TRAILER. P 1 ~ 7 MILES NNX LH5 BF DAVIS F 2'

MILES bSll ROGERSVILLEr AL 13 ~ 8 MILES NN LH3 BF NORTHEAST 1%G HILE ENE ATHENSr AL 10 ~ 9 HILES NE LH1 BF NORTHNEST 1

C MILE N

LP4 BF TRAILER P 1 ~ 7 HILES NNM ROGERSVZLLEr AL 13 8 MILES NW 0 ~ 14(

0 ~ 14-0 ~ 15(

0 ~ 15-14 ~ 35(

1 ~ 25-0 25(

0 ~ 25-0'%37(

0 ~ 37-0 ~ 11(

0 ~ G1-0%C(

0 ~ 02-0 ~ 12(

0 ~ 12 9 ~ 71(

1 ~ 23-0'4(

0 CO" 0%31(

0 ~ CO-4 ~ 96(

4 ~ 96-0 ~ EO(

0 EO-0 ~ 75(

0 ~ 63-1/

13) 0 ~ 14 1/

13) 0 ~ 15 13/

13) 34 ~ 03 1/

13) 0'5 1/

13) 0 37 13/

13) 0'0 12/

13) 0 ~ 16 1/

13) 0'2 12/

12) 25 ~ 72 6/

13) 0 10 4/

13) 1 ~ 15 1/

13) 4 96 1/

3) 0 80 3/

3) 0 ~ 86 LQCIIIQh HJIU UlQUESI hhBQhL HEST 8

NAME MEAN (F)

QIBIBHQE 85Q QIBEQIKQU HBUQC b SHITH FARM 0 ~ C5(

1/

1) 4 ~ 75 HILES N

0'5 0 F 05 SMITH FARH 7 ~ 94(

1/

1) 4 75 MILES N

7 ~ 94-

'7 ~ 94 LH1 BF NORTHWEST 0 ~ CO(

13/

13) 1%0 MILE N

0 ~ CO-0'1 CONTROL LOCATIONS MEAN (F)b 888QE 0 F 00(

19/

26) 0 F 00-0'1 42 VALUES <LLO 0'2(

5/

42) 0 07-0 F 25 13'2(

42/

42) 0'2-39'4 0%19(

14/

42) 0 11-0'8 0'7(

3/

42) 0'5-0'8 0 10(

35/

42) 0 F 00-0'2 0'6(

25/

42) 0 F 00-0 27 42 VALUES <LLD 6 53(

42/

42) 0 88-17'3 0 02(

21/

42) 0 00-0 ~ 1G 0%11 (

18/

42) 0%00-0 ~ 33 2 ~ 03(

1/

42) 2 03-2 ~ 03 6 VALUES <LLC 0 46(

6/

6) 0 26-CD 91 NUMBER OF NCNROUT INE REPORTcD 5E85QEEEf BIK 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 NAME CF FACILITY ggQii55 EEBBI LOCATION OF FACILITY I,?5ESIQBE PCI/G - C.037 BC/G (CRY I EIGHT)

DOCKET NO. gg-252c25Qc225 REPORTING PERIOD 1255 TYPE AND TOTAL NUMBER OF ANALYSIS RRBEQ85EQ GAHHA (GELI) 11 LONER LIMIT ALL CF, INDICATOR LOCATIONS DETECTION MEAN (F)

LLLQ?

8889K I.QQEIIQh'LIU UKQUfhI hhBQBL t)ach8 ~

NAME MEAN (F)

QISI68QE hHQ QIEEQIIQ5 88UQE CONTROL LOCATION(

MEAN (F) 885QE NUMBER OF NCNROUTINE REPORTED lEBKQBEEEUI5 CS-134 CS-137 K 40 BI-214 BI-212 PB-214 PB-212 RA-226 RA-223 RA-224 BE-?.

TL-208 AC-228 PA-234H SR 89 SR 90 NOT 0%160 0'20 0'60 ESTAB 1 '00 0 300 0 080 O.C20 0.250 0 050 0 100 0'50 NOT ESTAB 0 050 NOT ESTAB NOT ESTAB CD 16(

C ~ 16-CD 39(

C 06-5.28(

3 32-1 00(

G ~ 61-1 24(

C%75 4.

1 ~ 10(

G ~ 68-F 08(

G 57-F 00(

0 ~ 61-0 ~35(

0 ~ 28-1 09(

0 ~ 67-9 VALUE 1/

9) 0'6 9/

9) 1 '3 9/

9) 7 29 9/

9) 1 30 9/

9) 1 '9 9/

9) 1 '7 9/

9) 1 60 9/

9) 1 ~ 30 4/

9) 0 ~ 43 6/

9)

F 47 S

<LLO 0'8(

9/

9) 0 20-0 53 1 13(

9/

9)

G ~ 60-1 '8 2 34(

5/

9) 1 '0-3 64 9

VALUES <LLO ANALYSIS "PERFORMED 9

VALUFS <LLO LH1 SF NORTHMEST 1 ~ C MILE N LM5 SF DAVIS F 2 ~ 5 MILES

'IISM LH4 BF TRAILER P

1 ~ 7 HILES NNM LM1 SF NORTHMEST 1 ~ C HILE N

LM1 BF NORTHMEST 1 ~ C HILE N

LH1 BF NORTHMEST 1

0 HILE N

LM1 BF NORTHMEST 1 ~ 0 MILE N

LH1 SF NORTHMEST 1%C HILE N

ATHENSr AL 10 9 HILES NE OECATURr AL 8 ~ 2 HILES SSE LH1 BF NORTHMEST 1%C MILE N

LH1 BF NORTHMEST 1%C MILE N

LH1 BF NORTH'MEST 1 ~ C HILE N

0%16(

0 ~ 16-1 ~ C3(

1 C3-7.29(

7 29-1 ~ 30(

1 30-1 89(

1 ~ 89-1 ~ 47(

1 ~ 47-1%60(

1 ~ 60-1 ~ 30(

1 ~ 30-0 ~ 43(

0%43-1 ~ 47(

1 ~ 47 0'3(

0 53-1.68(

1 ~ 68-3 ~ 64(

3 64-1/

1) 0 16 1/

1) 1 ~ 03 1/

1) 7 29 1/

1) 1 $ 0 1/

1) 1 ~ 89 1/

1) 1 ~ 47 1/

1) 1 60 1/

1) 1%30 1/

1) 0%43 1/

1) 1%4?

1/

1) 0 53 1/

1) 1%68 1/

1) 3%64 2

VALUES <LLC 0 34(

0%34-1/

2) 0'4 0 51(

2/

2) 0%26-0 '76 4 63(

2/

2) 4 ~ 15" 5 ~ 11 1 06(

2/

2) 0 90-1 ~ 21 1 30(

2/

2) 1 ~ 25-1 35 1%13 (

2/

2) 0 98-1 ~ 28 1 ~ 16(

2/

2) 1 ~ 15 1 ~ 17 1 06(

2/

2) 0 90-1 '1 0'9(

1/

2) 0'9" 0

29 2

VALUES <LLD 0 19(

1/

2) 0%19-0 ~ 19 0 F 42(

2/

2) 0'2-0'2 1%18(

2/

2) 1 ~ 15-1 ~ 22 2 ~ 19(

1/

2) 2 ~ 19-2 ~ 19 2 VALUES <LI.D 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 NAME CF FACILITY EBQB5B EfBBZ LOCATION OF FACILITY LI5EJIQ5E RACIOACTIVZTY IX MELL MATER PCI/L - 0 ~ 037 BC/L DOCKET NO ~ EQ=222c25Qc226 8L8E858 REPORTING PERICD gBB8 TYPE AND TOTAL NUHBER OF ANALYSIS BEBEQB5EQ GAHHA (GELI) 26 LO'NE R LIMIT CF DETECTION a SL.LQ2 ALL INDICATOR LOCATIONS MEAN (F) n B85QE

! QQ8IIQ5 )lII5 5IQUEBI 855!l8L 5E85

~

NAYE MEAN (F)

QLBI85QE 85K QIBEQIIQ5 B85Q CONTROL LOCATION[

MEAN (F)

B85QE NUMBER OF NGNROUTINE RcPORTED 5E8EQBE 5f5IB K-40 SI-214 PB-214 PB-212 TL-208 AC-228 NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAS NOT ESTAB NOT ESTAS TRITIUM 330 F 000 8

21 ~78(

1/

13) 21 ~78-21 78 7 ~ 23(

11/

13)

C 12-14'0 7%50(

7/

13)

'4-13'6 1 '7(

3/

13)

C ~ 07-2 ~ 32 1'3(

2/

13) 0'9-1 '8 13 VALUES <LLD 4

VALUES <LLD ANALYSIS PERFORMED BFN MELL 06 0 ~ C2 MILES SFN MELL A6 0 ~ 02 HILES M

BFN MELL A6 0

C2 HILES M

BFN MELL P6 0

C2 HILES SFN

'MELL N6 0 ~ C2 MILES M

21 ~ 78(

21%i 8-7 ~ 23(

0 ~ 12 7'0(

2 ~74-1 C7(

0 ~ C 7-1 ~03(

0 ~ 39-1/

13) 21 78 11/

13) 14 ~ 30 7/

13) 13 26 3/

13) 2%32 2/

13) 1%68 15'8(

2/

13) 12 F 05-19'1 187'4(

13/

13) 14% 57

" 344 ~ 52 186 72(

13/

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

3/

13) 3'0-5'1 0%64(

3/

13) 0'1-0'6 4'9(

2/

13) 2 47-6'0 4

VALUES <LLC 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).

NAME OF FACZLITY j}BQQ{ig EEBBI LOCATZON OF FACILITY LI((EEIQBE TABLE 14 RADIOACTIVITY ZN PUBLIC WATER SUPPLY PCI/L -

0 037 BO/L DOCKET NO ~

KQ=222c2{lQA225 8L8E858 REPORTING PERIOD TYPE ANO TOTAL NUMBER OF ANALYSIS BEBEQBBEQ GROSS BETA 90 GAHHA (GELI) 91 K-40 BI-214 PB-214 PB-212 TL-208 AC-228 SR 89 16 SR 90 LOWER LIMIT OF DETECTION a SLLQK 2'00 NOT ESTAB NOT ESTAB NOT ESTAB NOT cSTAB NOT ESTAB NOT ESTAB 10 F 000 F 000 16 TRITIUM 330 F 000 16 ALL INDICATOR LOCATIONS MEAN (F) b B85{ij b 3 00(

46/

77) 2'1-5'0 17 ~88(

6/

?8) 9 70-33'6 5 64(

46/

78)

Ce14" 24 79 4 28(

26/

78)

Ce35-19+47 1 '9(

23/

78)

-0'5-4'0

~

1 ~ 18(

11/

78)

Oa28-3'8 19(

7/

78) 1+08-17'9 12 VALUES <LLO ANALYSZS PERFORHEO 12 VALUES <LLO ANALYSIS PERFORMED 12 VALUES <LLO ANALYSIS PERFORMED CHAHPION PAPER TRH 282 6

WHEELER OAHr AL TRH 274 '

CHAMPION PAPER TRH 282 '

SHEFFIELDiAL ROB TRV 254 '

WHEELER DAHr AL TRH 274 ~ 9 CHAHPION PAPER TRH 282 '

18 ~ 62(

9 ~ 70 6+86(

2 85-5 17(

0 ~ 41 2 ~ 38(

0 ~ 58-1 37(

1 ~ 22-

?e?3(

1 ~08-5/

52) 33 96 9/

13) 12'8 14/

52) 19 ~ 47 4/

13) 4'0 2/

13) 1 '2 4/

52) 17 ~ 19 LQQ8IIQh HLIU l{IQUEEI 8ht{U8L 5E88 8

NAME HEAN (F)

QISI8BQE 85Q QIBEQIIQB B8U{ijb CHAHPICN PAPER 3'2(

40/

52)

TRH 282 '

2'6-5'0 CONTROL LOCATIONS HEAN (F)b B8UQE b 3 ~06(

5/

13) 2 55" 3 ~ 51 28~73(

1/

13) 28'3-28'3 6'3(

9/

13) 3'9" 8'?

5 50(

6/

13) 1 84-11 '6 1 95(

6/

13) 0'7-4'4 1 65(

5/

13) 0'3-2'2 0'6(

1/

13) 0'6-0'6 4 VALUES <LLO

.4 VALUES <LLD 4

VALUES <LLC NUHBER OF NONROUT INE REPORTED BE8lMBElEBIE 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 Miles Avera e External Gamma Radiation Levels-b 2nd uarter 3rd uarter 1st uarter 4th uarter 0-1 1-2 2-4 4-6

>6 19.4+1.7 18.5+2.0 17.5+1.5 16.9+1.3 16.7+1.3 19.9+1.4 17.5+1.7 17.8+1.9 17.5+1.7 16.4+1.1 21.9+3.0 19.2+3.7 17.7+3.5 17.2+2.7 15.9+2.6 20.5+1.5 19.4+2.2 17.8+2.1 17.9+1.4 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 aDate" normalized to one quarter (2190 hours0.0253 days <br />0.608 hours <br />0.00362 weeks <br />8.33295e-4 months <br />) bAll averages reported +lo (68~/ confidence level)

NAME OF FACILITT BB{}HHS fEEBI q LOCATION OF FACILITT LIBESIQhE TABLE 16 RAOIOACTIVITT IN CABBAGE PCI/KG 0 ~ 037 BQ/KG (IIET liEIGI'.T)

DOCKET NO ~ >Q=2S2c24Qc228 TTPE ANO TOTAL NUHBER OF ANALTSIS BEBEQEBEQ GROSS BETA 2

GAMMA (GELI) 2 K-40 BI-214 PB-21.4 PB-212 LONER LIHIT OF DETECTION a SLLQ}

25 F 000 NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB ALL INDICATOR LOCATIONS MEAN (F) b E8uar.

b 3903 25(

1/

1) 3903 '5 3903 '5 1557 05(

1/

1) 1557 05-155? ~ 05 1

VALUES <LLO 1

VALUES <LLO 2 24(

1/

1) 2 ~ 24-i2 24 7 PILES NNIi 1557 '5(

1/

1) 155?~05-1557 F 05 7 FILES NNIi 2 ~24('/

1) 2'4-2a24 LQC8IIQb 'HJIU LZQUESI 8htlll8L UE88 >

NAME MEAN (F)

QISI8tllf, 8tlQ QIBfQIIQH B88QE 7 RILES NNli 3903 25(

1/

1) 3903 ~ 25-3903'5 2257~49(

225? ~ 49-4'6(

4 96-5'3(

5 13-0'1(

0 91-1/

1) 2257 '9 1/

1) 4'6 1/

1) 5 ~ 13 1/

1) 0'1 CONTROL LOCATIONS MEAN (F) b E859f 3687'8(

1/

1) 3687 18-3687 18 NUMBER OF NCNROUTINE REPORTED 5C8SUBfBCUIS 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).

NAHE CF FACILITY EBQBBQ EEBBI LOCATION OF FACILITY LIBEgIQBE TABLE 17 RADIOACTIVITY IN CORN PCI/KG - 0 ~ 037 BC/KG (NET 'NEIGHT)

DOCKET NO ~ 2Q=222c28Qc228 8L8E8$ 8 REPORTING PERICD TYPE AND TOTAL NUHBER OF ANALYSIS EEBEQBHEQ GROSS BETA 2

GAHHA (GELI) 2 LONER LIHIT OF DETECTION SLLQ?

25.000 ALL INDICATOR LOCATIONS HEAN ([)

B8hQE 3551 07(

1/

1) 3551 '7-3551 F 07 LQQ8IIQh HJIll llIQUESI 8hUll8L UE88 NAHE HEAN (F%

QIBI8UQE 85'IBEQIIQ5 B85QE 7 HILES NNN 3551 ~ 07(

1/

1) 3551 '7-3551 07 CONTROL LOCATIONS HEAN (FP B8KiP 2172+74(

1/

1) 2172 74-2172 ~ 74 NUHBER OF NONROUTZNE REPORTED BE85MBELEUIG K-40 BZ-214 PB-214 PB-212 NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB 2254 ~ 39(

1/

1) 7 HILES NNN 2254 '9-2254 39 1

VALUES <LLO 1

VALUES <LLO 1 '4(

1/

1)-

7 PILES NMN-1 ~44-1'4 2254 ~ 39(

1/

1) 2254 39-2254 '9 1 ~ 44(

1/

1) 1 ~ 44-1 ~ 44 2094%54(

1/

1) 2094 '4-2094 '4 3'6(

~ 1/

1) 3'6-3'6 0048(.

1/

1) 0'8-0 F 48 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).

NAHE OF FACILITY EBQ555 EEBBI LOCATION OF.FACILITY LI5EBIQ5E TABLE lg RADIOACTIVITY IN PEACHES PCI/KG -

0 ~ 037 BQ/KG (WET WEIGHT) hl.hea5h DOCKET NO ~ XQ=212c20Qc225 REPORTING PERIOD TYPE AND TOTAL NUHBER OF ANAL'ISI 5 BEBEQB5EQ GROSS BETA 2

GAHHA (GELI) 2 K-40 BI-214 PB-214 PB-212 LOWER LIHIT OF DETECTION a SLLQl 25 F 000 NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB 1955 '0(

1955

~ 30-Co?9(

0 79-9'7(

9e47-0.98(

0 ~ 98-1/

1) 1955 '0 1/

1)

Oe?9 1/

1) 9 47 1/

1) 0 ~ 98 ALL INDICATOR LOCATIONS PEAN (F) b Bh5QE b 2273 65(

1/

1) 2273 '5-2273 '5 4 FILES N

4 HILES N

4'ILES N

4 HILES N

1955 30(

1955 ~ 30-0'9(

0 ~ 79-9'7(

9 ~ 47-0'8(

0'8 1/

1) 1955 '0 1/

1)

Oe?9 1/

1) 9'7 1/

1) 0'8 l QChISQh HIIU UI{iUEEI h555hl 5Eh5 8

NAME MEAN (F)

QIEIh5CE h5Q QIBEQIIQ5 Bh5QE 4 PILES N

2273 ~ 65(

1/

1) 2273 65-2273'5 1595 08(

1595 ~08-5 79(

5 ~ 79-2 46(

2 46-1 ~ 68(

1 ~ 68-1/

1) 1595 F 08 1/

1) 5'9

- 1/

1)

F 46 1/

1) 1'8 CONTROL LOCATIONS MEAN (F)

Bh5QE 2772 95(

1/

1) 2772 '5 2?72 '5 NUFBER OF NONROVTINE REPORTED 5EhEQBEBE5I5--

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 NAME OF FACILITY BBQljUE EEBBI LOCATION OF FACILITY LJUE5IQUg

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

DOCKET NO ~ 5Q=222c25Qc226 6L8BBU8"----

REPORTING PERICD TYPE AND TOTAL NUHBER OF ANALYSIS PEBEQBUEQ GROSS BETA 2

GAMMA (GELI) 2 LONER LIHIT OF DETECTION SLLQ?

25 000 ALL INDICATOR LOCATIONS HEAN (F)

-b BGUQs 6965 '6(

1/

1) 6965 '6-6965 66 LQQhIIQb UJIU UIQUEEI 8UUllhL UfhU~

NAVE HEAN ($ )

QZKISUQa EUQ QIEHIZQU EaUQE 4 PILES N

6965 ~ 66(

1/

1) 6965 '6 6965 '6 CONTROL LOCATIONS HE AN (g)

BEUQE 5614 ~ 87(

1/

1) 561 4 ~ 87 561 4 ~ 87 NUHBER OF NONRCUTINE REPORTED UBSEQEf PBUIK K-40 BI-214 PB-214 NOT ESTAB NOT ESTAB NOT ESTAB 3461

~ 39(

3461 ~ 39-6'3(

6 ~ 03-5'3(

5 ~ 03-5 ~ 03-1/

1) 3461

~ 39 1/

1) 6 03 1/

1) 5+03 5'3 4 VILES N

4 PILES N

4 FILES N

3461

~ 39.(

3461 ~ 39-6'3(

6'3 5'3(

5'3" 5 ~ C3-1/

1) 3461~39 1/

1) 6~03 1/

1) 5 03 5'3 3651 ~ 65 (

1/

1) 3651 ~ 65-3651 ~ 65 1

VALUES <LLO 1

VALUES <LLO 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).

NAME OF FACILITY EPQg~t.g fEEP LOCATION.OF. FACILITY LILVE)IQJE TABLE 20 RADIOACTIVITY IN POTATOES PCI/KG - 0 ~ 037 BC/KG (MET MEIGHT)

BLBEB5B OOCKFT NO. SQ-222c25QA225 REPORTING PcRIOD TYPE AND TOTAL NUHBER OF ANALYSIS PEEPQEUEQ GROSS BETA 2

GAHHA (GELI) 2 LONER LIMIT OF 0 E T 5 C TI0 lP S'IL QI 25 ~ COO ALL INDICATOR LOCATIONS MEAN (~)b RBZQE 7312+07(

1/

1) 731 2 ~ 07 731 2 ~ 07 LQC>IIQh HIIU VIQUEEI BDHQBL 5EB5~

NAME MEAN ($ )

QIEIBHCE MQ QIEEGIIM BB5QE 7 PILES NNM 7312.07(

1/

1) 7312 ~ 07-7312 ~ 07 CONTROL LOCATIONS HEAN (g)

EBBQE 6571 '0(

1/

1) 6571+60-6571 '0 NUHBcR OF NON ROUTINE REPORTED UEBEllEEKEUIE K-40 BI-214 PB-214 PB-212 NOT ESTAB NOT ESTAB NOT ESTAB NGT ESTAB 3287 97(

3287.97" 2o73(

2.73-C.78(

0.78-CD 83(

0 ~ 83-1/

1) 3287 '7 1/

1) 2 73 1/

1)

Oo78 1/

1) 0 83 7 PILES NNM.

H ILES NNM 7 PILbS NNM 7 PILES NNM 3287.97(

3287 ~ 97-2'3(

2 73-0 78(

0'8" 0'3(

0 ~ 83-1/

1) 5287 97 1/

1) 2 F 73 1/

1) 0'8 1/

1) 0.83 3924 ~ 85(

1/

1) 3924 85-3924 F 85 3'9(

1/

1) 3'9" 3

29 12 F 44('/

1) 12'4-12 44 1

VALUES <LLD 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).

NAHE OF FACILITY fgQQgl ffggg LOCATION OF FACILITY gjgfgfQgf TABLE 21, RADIOACTIVITY IN POULTRY PCI/KG - 0 037 BQ/KG (NET 'HEIGl T)

OOCKcT NO.

NQ=212A25QA225 TYPE ANO TOTAL NUMBER OF ANALYSIS EfBEQBHfQ GROSS BETA 2

GAMMA (GELI) 2 LONER LIMIT OF DETECTION Su.QZ 25 F 000 ALL INDICATOR LOCATIONS MEAN ($ )

B85Qf 5016 '7(

1/

1) 5016 '7-5016 '7 LQt'BIZQh HJIU VIQUfXI hhUQhl lfhH NAHE HEAN (F7'ISI65QE 650 QIBrQIIQH 868QE PAGE FARM 5016 ~ 47(

1/

1) 8 ~ 75 HILES E

5016 ~ 47-5016 ~ 47 CONTROL LOCATIONS MEAN gF j'hhQ 4902 '4(

1/

1) 4902 '4-4902 '4 NUMBER OF NONROUTINE REPORTED 5f85UEfLfHIS K-40 BI-214 PB-214 NOT ESTAB NOT ESTAB NOT ESTAB 2511 67(

2511 ~ 67-12.62(

12 ~ 62-8 61(

8 ~ 61-1/

1) 2511 '7 1/

1) 12'2 1/

1) 8 ~ 61 PAGE FARH 8 ~ 75 MILES E

PAGE 'FARH 8 ~ 75 HILES E

PAGE FARH 8 ~ 75 HILES E

2511 67(

1/

1) 2511 '7-2511 '7 12 ~ 62(

1/

1) 12'2-12'2 8'1(

1/

1)

Saki-8'1 2317 '0(

2317 20-8 41(

8. 41-8 ~ 90(

8>> 90-1/

1) 2317 20 1/

1) 8 41 1/

1) 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).

NAME OF FACILITY BQ'gB$ EEBBI LOCATION OF. FACILITY LItlfgIQBE TASL E 22 RACIOACTIVITY IN TOHATCES PCI/KG - 0 ~ 03?

SQ/KG (NET NEIGVT)

.. DOCKET NO ~ 59222c2kQs22fi BLllEBllB R

PORTING PERIOD 1255 TYPE ANO TOTAL NVHSER OF ANALYSIS BEBEQB5EQ GROSS SETA 2

GAHHA (GELI) 2 K-40 LONER LIHIT CF DETECTION fLLQ?

25 F 000 NOT ESTAS ALL INCICATOR LCCATIONS HEAN (F)

BaBQE'617 91(

1/

1) 1617 ~91-1617 ~ 91 LQLEIIQh HIIll UIQUESI BhUQBL BEBOP~

HAVE MEAN (F)

QIEIBBQE SBQ QIBEGIIQB BOUSE 7 VILES NNX 1617 ~ 91(

1/

1) 161? ~ 91-1617 91 CONTROL LOCATIONS HEAN (F) b BOUGE 3007 '6(

1/

1) 3007'6-3007~66 2161 ~ 25(

1/

1) 7 VILES NNN 2161 ~ 25-2161+25 2161+25(

1/

1) 2552 92(

1/

1) 21 61 ~ 25 2161 ~ 25 2552 ~ 92 2652 ~ 92 NUVSER OF NONROUTINE REPORTED UfhfQBEEEUIE 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 JJa~

Q

'o JJ Q

C JJ C0 'o CJ JJ JJ C

CQ SJ Co NCo C

JJ JJ cJJ rJ JJ Sl Vl o

JJ C

O V

JJ C

C OQ Preoperational Phase Operational Phase ANNIALAVERAGE 6ROSS HEfA kTIVITY I N HRI tKI% HATER SUPPLIES Prem FERRY ihCLEAR l&NT Averao,e:

Preooerational Phase 4

Iri r"+

~ I-'

'I G

. J

,I

'J~Irl i~(.

'hl.

19 8

a

!X I

!1-.,

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

(I0

~f, W

PIguru 7

4 Olrecl Rod(orion Levels 6rowns Ferry Nucleor Plonl 22 00 0 18 0

C I

/

I 1

I I

I;Orrslie 28 O((s I (e

\\

I I

I I

I'1 i I,h,.~i i l I'1 /

I P.

I' 1

b 1

0 I

~

l',

(xg

~ + 0-g I (t I

b

\\

I I

'1 I

'll It 12 1976 1977 1978 1979 1988 1981 1982 1983 1981 2N FIPure 8

Oirecl Rodioilon Levels groans Ferry Nucleor Plonl H-guorier, Moving Averoge

(.0

(.

18 0

16 O((s((e 0'0.

(('A

~

s Pw~

(//

/

0

'0'"'~

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

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

22 4

e 0 18 0

e 16 Ons>>e Ol Is>>eo o-e

(

I

~

(

0

(

'I(

'e

(

'o w ll(I l

I

(

e I

i!

I

(

'd

\\ ('

e, i

'0~

('~

(

I

~

'l2 1976 1977

978

1979, 1988 1981 1982 1983 I984 2l I'Igurv 10 0 (reel Rod 1 ol I on Levels Valls 8or Nuclear Plonl 1-Ouorler Hov!ng Average 22 28 0

s 18 0

e 16 One( le

/

~

0.$

/e-on

'e. ~

,O-.o 7(

e-~g'e

~

i elis>>e o-e~

e d

(

0 12 1976 1977 1978 Ig7g 1988 Iggl 1982 Ig83 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.

44

~

rt a

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, River/river mile phytoplankton Benthic fauna Sediment Fish Water Samples (collected monthly' Tennessee 277.9 X

Tennessee 285.2 Tennessee 288.7 Tennessee 291.7 Tennessee 293.5 X

Tennessee 293.7 (discharge area)

Tennessee 305.0

.(Control) b Tennessee 307.5 (Control)

Elk 20.5 (Control) a.

Gill net and/or electroshocker will be used for collection.

from Guntersville,

Wheeler, and Wilson Reservoirs.

b.

Automatic sampler.

c.

Grab sample.

Samples of fish are collected

T ABt. c.24 hAPl=

CF FACILITY zoBtttth~z LOCATICN OF FACILITY t,jHggI('thy RACiOACTiVITY IN SURFACE hATER TOTAL ssCI/L -

0 ~ 037 BO/L DOCKET NO ~ 's"=c22ciPstcZ R

kcPORTzHu P>>RICO TYPE AHO TOTAL HUHBcR OF AHALYSIS 2RBr()BE =9 GROSS ALPHA 1

GROSS BETA 65 GAHHA (GELI) 6c LOwcR LIHIT CF OETECTIOh a 2.COO 2 '00 ALL IHCICATOR LCC 'ICtiS EAM (F) b ycpsnc b 4

IJ4$

C VALUCS <LLC ANALYSIS P RFORY.ED 3'2(

27/

39) 2 '4-5.18 TRY 293 '

3.31(

8/

13>

2.54-4.25 l QtiAIIOh ALIT LIt'ttt'0I AhltlAI FAYE YEAh (F)S 2ISIntttif, >ht'IB=CII9h BA5<ta COHTRCL.

LOCATIONS Yc AN

<~>b

~ HG

~~hG hGj 1

VALLES <LLC 3.62(

20/

25) 2 43-12.06 HUYB R

CF tiChROUT INE REPORTEO

"=82QBEYghIK K

4C BI-214 PB-214 PB-212 SR d9 SR 9C TRITIUH 2C Zu 2C hCT ESTAB

'<CT cSTA3 HCT cSTA3 HCT cSTAB 10 COO 2 'Gv 330.COO 21.09(

5/

39)

C ~ 59-,

38 69 5.56(

14/

39)

C.61-18 71 3.06<

7/

39)

C.01.-..

7 14>>.

1'1(

20/

39) 0'0-4'2 12 VALUES <LLO ANALYSIS PERFORYEO 12 VALUES <LLC ANALYSIS PERFORNEO 387 92(

2/

12) 359 53-416 '

TRY 285 '

TRY 293 '

BFh OIS CHARGE TRY 293 '

oFh-OISCI:ARGE TRY 285 '

TRY 29z ~ 5 23 C5(

23'5" 8.39(

2 ~ 18 3 ~ 95(

0 ~ 72-2'4(

0 99-1/

13) 23 F 05 5/

13) 18 ~ 71 4/

13) 7 ~ 14 5/

13).

4. 52 416>>31(

1/

4) 416 ~ 31-416 ~ 31 23 43(

2/

25) 19 74-27 ~ 12 8 ~ 57(

15/

26) 0.72-25 ~ 47 6.71(

14/

25>

0 F 59-18 'C 2 64(

7/

26).

0'd-5'5 8

VALUES <LLG 8

VALUES <LLC 8

VALUES <LLO 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).

hAME CF FACILITY g(Q)lhA" fjggg LOCATICt'F FACILITY Lig~gJQgf TABLE 25 RADIOACTIVITY IN MHITE CRAPFI= (FLESM)

PCI/O - C.C37 BC/6 (CRY ~EIGl T) h! ARnYik 0GCl(ET NG.

'Q=i~2ciRQc2ZO REPORTING F E RICO ()~<4 TYPE ANO TOTAL NbMBER OF ANALYSIS PE!!EQR" EQ GROSS BETA GAMMA (GELI)

CS-137 l(-4C BI-214 PB-214 PB-212 SR 89.

SR 9C LONER LIMIT CF DETECTION a KLI Q?

0. 100 0 ~ 020 NCT ESTAB OsC20 NCT ESTAB NCT STAB 0'00 0 ~ 100 ALL IllCICATOR LCCATIONS N (F)b nANnc b Sl 2E e19(

4/

4) 21 ~ 10 3 ~ 50 C C9(

/

4)

C CE-0 ~ 11 15 'C(

4/

4) 12 'C-17.51 C ~ C4(

1/

4)

CD 04-O.C4 CD 17(

2/

4)

C 05-O.ZB C 01(

1/

4)

C ~01-0 ~ 61 2

VALUES <LLD ANALYSIS P ERFORMCO 2

VALUES <LLD ANALYSIS PERFORMED WILSON RESERVCIR TRP Z55-275 NMEELER RES TRP 275-349 ill.EELER RcS TRP 275-349 wILSON REScMVCIR TRl'59-275 Ql'EELER RES TRP 275-349 0 ~ 11(

C ~ 11 16 ~ 14(

14 ~ 77-C.e4(

C.C4-C.ZB(

'.2-0 ~ C1(

0 ~ C1-1/

2)

C ~ 11 2/

2) 17 ~ 51 1/

2)

".. 04 1/

2)

C ~ 28 1/

2) 0'1

! QQiKEQl'iIL tIQL!ca'I Ahl s!A!. LcA4 NAPE PEAN (F)

Q+5IBBQi She QIRLScQIIQ5 P.ABQcb hHE LcR R

S 29'(

2/

2) 275-349 25'9-32.93 CONTROL LOCATIONS MEAN (F)

-b EBhQc Zc ~ B9(

2/

2) 20.46-37.33 0.09(

Z/

2) 0 07-C ~ 11 14'9(

2/

2) 11 72-1E.85 0 02(

1/

2)

C.02-C ~ 02

. 0.03(

1/

2) 0.03-0.03 O.OC(

1/

2) 0.00-0 OC 1

VALLES <LLC 1

VALl:ES <LLC NLvBER GF NC'iROUTILE REPCRTE" 5a cSQB~t'ghT 5 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 CF FACILI Y gBgBb5 Es33I-LOCATICN OF FACILITY gip2$Ili ag fc2c45QL42a REFORTING PcRIOG TYP=

ANO TOTAL NUNBER OF ANALYSIS EfBFQBCRQ GROSS SETA GAHHA (GELI)

LQ~ER LI."IT CF CETCCT Ch a ELLE 0.100 ALL INCICATCR LCCATICNS r EAU

(

)

8659=

2' 56(

4/

<<)

1 2'2-39'8 LGHIiQh yiIU hi9gtSI Ahullkl vEE NAr 5

~

REAh'F) hi5IhbQ=.hbC OiB=GIIQh RAbkE htEELER RES 32 'c(

2/

2)

TRr 275-345 25.'9-39 1d CONTROL LCCATIONS an Bsa 20 ~ 42(

2/

19'6-20'o NLrBER DF NChRCUT ihc RcPCRTcD l.h94L/Ks ABi5 CS-137 j<-40 BI-214 PB 214 PB-212 SR 89 SR 9C Goi23 NCT ESTAB 0 '20 NCT ESTAB NCT ESTAB 0.5GG 4

0.100 C ~ 05(

3/

4)

CeG4-G.C7 12 '6(

4/

4) 2 '6" 15.33 C ~ C4(

2/

4)

CeG4.-

G.GS C.G4(

3/

4)

~ "C ~ 02 0 ~ Go e'o01(

1/

4)

C.C1" G ~ 01 3.VALUES <LLC

'LYSIS PcRFORNEO VALUES <LLC ANALYSIS PERFORNEO Hgc L

R REc TRr 275-349

'Al EELER RES TRr 275-349 hILSON RESERVCIR TRR 259-275 WILSON RES RVCIR

~TRR'59-275 MHEELER RES TRr 275-349 C.C6(

C C4-15 ~ 44(

12.55-G.C5(

Ge(5" Coi6(

C ~ C6-G C1(

2/

2) 0.07 2/

2) 15'3 1/

2) 0 F 05 1/

2)

G ~ 06 1/

2) 0 01 0.06<

1/

2) 0'6-C.06 12.11(

2/

2) 9'4-14 F 58 2

VALUES <LLC 0.02(

2/

2) 0'1-GAG 0 01(

2/

2),

0 ~ 00" C ~ 01 1

VALLcS <LLC 1

VALUES <LLC a.

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

ed locar.ions.is indicated in arentheses (F).

b.

Nean and

".ange based 'upon detectable

=easurenents only.

Fraction of 'detectable neasu'renents at specified locar.ions.is indicated in parentheses F

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

PC

/C -

C ~ 0 7

3

/G

("RY FE Gl T)

NAME cF FAcILITY ! orb~'5 f!Eric CATION OF FACILITY LgH!$ggQ!

NO ~ 2Q:222c262c22~

TYPc Att5 TOTAL hGM3 OF ANALYSI o! ItfQR."!2 GROSS SETA ER SR 89 SR 9C 6

GAtlNA (G=LI) 6 CS-1 37 I(-4 C bi-214 PB Z14 PS-212 RA-223 AC-228 LDa R

a. PIT CF 0

T CTICh SL,hu?

0 ~ 10C 0.020 NCT ESTA3 0'20 NCT ESTA3 NGT ESTA3 NCT cSTA8 0 ~ 500 0 ~ 100 C 04(

C ~ C3-E.56(

7 ~ 27-C.03(

C ~ G2-C.04(

C.G3-Co01(

C.C1-C ~ 26(

C ~ 26-CD Od(

C.CE-2 VAL ANALYSIS 2-VAL 2/

4)

O.C4 /)

10.79 2/

4) 0'4 2/

4)

Oo05 1/

4) 0.01 1/

4) 0 ~ co 1/

4) 0.08 UES

<LLD PERFD>BED VES

<LLD ALL ItiCIC>>TCR LCC>> TICitS

ÃE/N (F) aiNn b

>>N % 4 2'2(

4/

4) 13o60-33.71 NILSON REScRVCIR TRt'59-2?5

)IILSDtt RESERVCIR TRI'59-275 NILSON RESERVCIR TRt 259-275 IttIEELER RES TRP 275-349 Itt'EELER RcS TRY 275-349 NILSON RESERVOIR TRF 259-275 leILSON P.ESERVCIR TRP 259-275 0 ~ C4(

O.C3-9.65(

8 c1 0 ~ C4(

O.C4" OeC5(

0 ~ CS-G.C1 (

0 ~ C1-0 ~ 26(

0'0 0 Co(

Go(3-2/

2)

G.G4 2/

2) 10m?9 1/

2) 0'4 1/

2)

G.05 1/

2) 0.01 1/

2)

G ~ 2o 1/

2)

O.OS LQCBI:91 dII(I Like!;I c'huuAl..".!AS hAYE BEAN (F)

QL~<IBDC! Eh'IB!GIiIt5 868k!

WILSON RESERVCIR 23ito(

2/

2)

TRt'59-2?5 13.cO-33 '1 CONTRCL LCCATIOi'IS MEAN (F) b L'9 E 15'0(

2/

2) 15.55-16.25

.0.02(

" 1/

2) 0 02-G ~ 02 7'1(

2/

2) 7.61-

? ~ 62 0'5(

1/

2) 0 05-C ~ 05 0,04(

=1/

2) 0 04-0 04 0 ~ 01(

1/

2) 0 ~ 01-C.51 2 VAlUES <LlC 2 VALUcS <LLC 1

VALlES <LLC 0'3(

1/

1) 0'3-Co23 Nb"" -R Oc h'CNR CL 1 I NE RFPC=TEG W!SKMoc"chloe 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 NE CF FACILITY ~~gg)lb) jn3$ $

LOCATICN OF FACILITY.I4E<<e5jgha RADIOACTIVITY Ih'EC IFchT PCI/O - 0'37 BQ/G (ORY )/EIGHT)

O<<KET NO.

RC=KZoc249422O REPORTING PERIOD TYPE ANO TOTAl. NURSE R OF ANALYSIS 22EE9Rh=2 GANJA (GELI)

LQ~ER LIMIT CF "ETECTIOh SI.L0}

I!s 0IC ALL ATOR LOCA(IONS PEAN (F) 8459E

..EAN (F)

(ii'IA56i 65K 'dIBRCiTQB RANGE CONTRCl.

LCCATIONS r

At( (F)b b

8

!luC NL'NSER CF NGNRCL'TINE REPORTED 5EAkl!R=rCNKS CO"60 CS 134c CS-137 K-4C BI-214 BI-212

'B 214 PB-212 RA 225 RA-224 TL-203 AC-228 PA-2348 SR 89 SR 9C c

0. C10 0.060 O.C20 lCT ESTAB OoCZO 0+ 100 NCT CSTAB VCT ESTAB NCT ESTAB NCT ESTAB G.C20 0 C50 NCT ESTAB 1 '00 0.3GO C ~ 31(

C.27-C.14(

C.1C-C.90(

C 7o-14 ~ G2(

11.?B-1.37(

0.94; 2'01 (

1 86-1 55(

1 ~ 21" 1<<49(

1 ~ 33-.

1 ~ 52(

1 ~ 51-1 '9(

1.69-C.53(

C ~ 33-1+50(

1.17-3eCC(

40" VALUES ANALYSIS PER 6

VALUES ANALYSIS PER

<</

5) 0'36 2/

o) 0 17

/

6) 1 ~ 12 6/

o) 1o EZ 6/

o) 1'2 4/

6) 2 05 6/

5)

F 68 5/

5).

1 '1 2/

o) 1 '4 1/

o) 1 69 6/

o) 0 "1 6/

5) 1.94 1/

o) 3.40

<LLO FORHEO

<LLC FQRrgo Tgl'77.98 TRY 293 '

SFh OISChARGE TRr 277 '8 Tpr 277 ~ 98 Trr 277.98 TRr'77 98-TRr 288 ~ 78 TRP 277.98 TR<<

277 '8 TRP BFh

- DISCHARGE TRr 277 '8 TRr 2?7.98 TRY 277 98 C'32(

0 ~Z-G.1.7(

0 ~ 17-0 ~ 95(

GI?d-15i54(

14 ~ Zo-1 49(

1 ~ 44-2 ~ C6(

2 Co-1 ~ 64(

1 ~ c1 1 ~ 60(

1 ~ ~8 1.54(

1 <4-

,1 e 69(

G ~ 56(

0 '2-1 ~ 73(

1 ~ 52 3 ~ 40(

3 ~ CO-1/

2) 0.32 1/

2) 0 ~ 17 2/

2) 1 ~ 1 2 2/

2) 16 BZ 2/

2) 1 '4 2/

2) 2.05 2/

2) 1.68 2/

2) 1 ~ 81 1/

2) 1 ~ 54 1/

2) 1 '9 2/

2) 0'1 2/

2) 1 94 1/

2) 3'0 Go48(

0.30-10 F 54(

7 91-1 ~ 11(

1.01-1 ~ 45(.

1

~d 1 25(

1 ~ 16-1 21(

1 ~ 1d-1 11(

1 01-1.28(

1. 28-0.41 (

0.3"-

1 ~ 22(

1 ~ 15-Z VALL 2/

'2)

C ~ 65 2/

2) 13 ~ 38 2/

2) 1 '1 2/

2) 1 ~ 53 2/

2) 1 '4 2/

2) 1 '4 2/

2) 1 ~ 21 1/

2) 1 ~ ZB 2/

2)

CD 44 2/

2) 1 28 ES

<LLC 2 VALLcS <LLC 2

VALLES <LLC 0 02(

1/

2)

OIGZ-C.02 2

VALUES <LLC 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 conparable 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 13<

reported in sanples from the Tennessee River in preoperational monitoring prograns conducted, by TVA at other sites.

TABLF 29 RACIOACTIVITY It CLAII FLESI.

hAIIE CF FACILITY vc~ogbbg tc3ttg LOCATION OF FACILITY

{,AMggjggf, PCI/C C ~ 0 7

BC/0 (CRY W=IGI T) cAH'ike QCi(CT NO cr os,p

~ cs CRXLCswcZ g

RcFORTING P=Rs"0 T'YPE ANO TOTAL NUBBER OF A IALYSIS PCRF935=2 0AIIN'GEI.I) 5 LOWE R LivIT c

0"TECTION ELLil AI.L Iii'CICATCR LCCAbTICNS HE'N (F)

~is 59 ~

LGSAIIQh III'IMIICSI~hbQhl 52c5 <

NAPE vcAN (()

Q 528hCS 65K BLED:GIi9d 6~99r.

CO LCC 2A NTROL AT IBNS N ([)

iinr Hs c Nl.i""

R NQh R O'. 1 Itl =

REFCRTc K-40 BI"214 PB-214 PB 212

'TL-205 AC-228 NOT ESTAB NCT EST'6 NOT ESTAB NGT cSTAB NCT

=STAB flOT EST'B VAI UcS

<I I 2.47(

3/

3) 1 '6-3<<60 2 33(

3/

3) 1 58-2.75 C.26(

1/

3) 0'6-0'o 3

VALUES <LLQ 3

VALUES <LLG TRv 2?7 ~ 9r TRY 277 ~ 9E TRP 2c= ~ 7E 3'0(

3ocG-2.75(

2 75-0 26(

0 ~ 25-1/

1) 3'0 1/

1) 2 75 1/

1)

0. 26.

2.06(

1og5-1 ~ 32(

OoE5(

0 6~-

G.15(

Go15-0.07(

0 ~ 03-1 ~ 39(

1 ~ 39-2/

2) 2'7 2/

2) 2 ~

2 2/

2) 1 '7 1/

2)

C ~ 15 2/

2)

C ~ 1G 1/

2) 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 hAWE CF FACILITY 2pg'ctbg calif LOC'TICh OF FACILITY LJLtc~IIQJt AO 0 CTIVITY I" LAP eHcLL oCI/O - 0 ~ 0'7 8>>/G (ORY HEI

~ hT)

ALAcP~A No. RE=2)2r2RCc2o" REPORTING PERICC TYP:'ND TOTAL NU4BER OF AtiALYSIS PRAEQBL'2 GAUM'GELI) 7

'C>>ER LIM T CF ETcCTION It!.RI ALL INQIC>>TOR LCCATICNS t',EAti (F)

Pl Qka LQCEII9h aIId CItt"~cSI Ehdhl L>>chal NAPE tcEAh (FT JIHAD(I2 455 9IB=tcTIQlt EAbi'ONTRCL LCCATIOIJS HEcAN (F BLANC+

8

~

NQPBCR vc NChRCLT INE RcPCRTt>>

Mgk~cliELZc "LclhTS K-4C BI-214 PB" 214 PB-212 RA-226 AC-228-SR 89 SR 9C

"<CT 8 ST AB 0+C50 0 ~ C50 ttCT ESTAB Co050 Q.CoQ 5 ~ COC 1

COO C.OG(

CoCO-C ~ 22(

G.C7-C ~ 28(

G.08-C.06(

C.C4-C.C7(

C C7-C.G7(

C.C7-6.24(

6.24-1 ~ 14(

1.01-1/

5) v ~ ~V 3/

5) 0 ~ 42 5/

5)

C.SC 3/

5) 0 ~i7 1/

5) 1/

5)

O.C7 1/

5) 6 F 24 4/

5)

F 24 TRP

c.78 TRt'93.7 BFh CISCMARGE TRF 277 ~ 98 TRP 288.78 TRP 288.78 TRP 288 F 78 TRP 293 F 7 bFh 0 I SCHA RG 8 TRP 288 7c C ~ CO(

C. CO-C.30(

0.17-0 F 50(

C c0-C.C6(

G.C4-0 ~ C7(

C C7-

0. 7(

0. C7-6.24(

o ~ c4.

1+23(

1 ~ 21-1/

2) 0.00 2/

2) 3'2 1/

1)

G ~ 50 2/

2) 0 F 07 1/

2) 0 07 1/

2) 07 1/

2) 6'4 2/

2) 1 '4 CD 13(

0.13-C.15(

0.06-0.18(

0'?(

Qe02-Go06(

C ~ Oo-C 07(

C.07-2 VALL 1/

2)

C 13 2/

2)

CD 23 2/

2)

CD 29 1/

2)

C.02 1/

2) 0.06 1/

2)

C.07 cS

<LLC'

'6(

1/

?)

1 ~ 16" 1>>16 a.

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

b.

Mean and

=ange based upon detectable tceasurercents only.

Fraction of detectable tceasurenents at specified locations is indicated in parentheses (F).

Figure ll R ESERVOI R MONITORING NETV/ORK 53 Elk River N

WHEELER DAlVI mile 274.99 mile 277.98 Rogersville 0

mile 282.6

~mile 285.2 mile 29I.76 Athens

,0 B.F. NUCLEAR PLANT

( II Champion Paper Co.

,,0 Cour tland ile 288.78 mite 293.50 rnite 295.TO 0

Decatur mile 305.0 mile 307.52

~ - Automatic Sam ler Scale of Miles 0

Pigure 12 eno wn 4J o W

4l 4J cc e Lr M o

o V

'o n n 0 Preoperational Phase

't V

T Operational Phase Areeu AVERAGE 6ROSS HETA ACTIVITY IN SURFACE HATER HNMS FERRY NUCLEAR PLANT Average:

Preoperational Phase 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.

0 0 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.