ML18025A824

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Environ Radioactivity Levels Annual Rept,1979.
ML18025A824
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 04/30/1980
From: Mills L
TENNESSEE VALLEY AUTHORITY
To:
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ML18025A823 List:
References
RH-80-3-BF2, NUDOCS 8005050275
Download: ML18025A824 (54)
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RH-80-3-BF2 ENVIRONMENTAL RADIOACTIVITY LEVELS BROWNS FERRY NUCLEAR PLANT ANNUAL REPORT 1979 KhKNMl(0Ãt(gH(( NPy April 1980

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CONTENTS Introduction ,~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~

Figure 1 Tennessee Valley Region 3 Table 1 Environmental Radioactivity Sampling Schedule 4 Table 2 Atmospheric and Terrestrial Monitoring Station Locations - Browns Ferry Nuclear Plant Table 3 Detection Capabilities for Environmental Sample Analysis Table 4 Results Obtained in Interlaboratory Comparison Program Atmospheric Monitoring .

Figure 2Atmospheric and Terrestrial Monitoring Network . 13 Figure 3Local Monitoring Stations 14 Figure 4Browns'Ferry Nuclear Plant Site Monitoring Stations 15 Table 5 Maximum Permissible Concentrations for Nonoccupational Exposure. 16 Table 6 Radioactivity in Air Filter 17 Table 7 Radioactivity in Rainwater . 19 Table 8 Radioactivity in Heavy Particle Fallout 20 Table 9 Radioactivity in Charcoal Filters 21 Terrestrial Monitoring . 23 Table 10 Radioactivity ln Milk' 25 Table Table ll Radioactivity in Vegetation 12 Radioactivity in, Soil

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26 27 Table 13 - Radioactivity in Well Water ~ ~ 29 Table 14 Radioactivity in Drinking Water ~ ~ 30 Table 15 Environmental Gamma Radiation Levels ~ ~ 31 Table 16 Radioactivity in Food Crops ~ ~ ~ ~ ~ ~ 32 Table 17 Radioactivity in Poultry 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 34 Reservoir Monitoring 35 Table 18 Sampling Schedule Reservoir Monitoring . ~ ~ 37 Figure 5 Reservoir Monitoring Network . ~ ~ 38 Table 19 Radioactivity in Surface Water . ~ ~ 39 Tabid 20 Radioactivity in Whitw Crappie . ~ ~ 40'1 Table 21 Radioactivity in Smallmouth Buffalo (Flesh) ~ ~

Table 22 Radioactivity in Smallmouth Buffalo (Whole) ~ ~ 42 Table 23 Radioactivity in Plankton ~ ~ 43 Table 24 Radioactivity in Sediment ~ ~ 44 Table 25 Radioactivity in Clam Flesh ~ ~ ~ ~ 46 Table 26 Radioactivity in Clam Shell ~ ~ 47 Quality Control ~ ~ ~ ~ ~ ~ ~ ~ 49 Data Analysis ~ ~ 49 Conclusions 49

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ENVIRONMENTAL RADIOACTIVITY LEVELS BROWNS FERRY NUCLEAR PLANT ANNUAL REPORT 1979 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 boil'ing 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 opera-tion on August 1, 1974. Unit 2 began commercial operation on March 1, 1975.

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

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

Field staffs in the Division of Occupational Health and Safety, the Division of Water Resources, and the Division of Natural Resources Services, carried out the sampling program outlined in tables 1 and 18.

Sampling locations are shown in figures 2, 3, 4, and 5, and table 2 des-cribes the locations of the atmospheric and terrestrial monitoring stations.

All the radiochemical and instrumental analyses were conducted in a central laboratory at Muscle Shoals, Alabama. Alpha and beta analyses were per-formed on Beckman Low Beta II and Beckman Wide Beta II low background pro-portional counters. Two Nuclear Data (ND) Model 100 multichannel analyzer systems employing sodium iodide, NaI(T1) detectors and one ND Model 4420 in conjunction with Germanium, Ge(Li) detection systems, wer'e used to analyze the samples for specific gamma-emitting radionuclides. Samples of water, vegetation, air particulates, food crops, and charcoal (specific analysis for 131 I) are routinely counted with NaI(T1) detection systems. If signifi-cant concentrations of radioisotopes are identified, or if there is a

reasonable expectation of increased radioactivity levels (such as during periods of increased fallout), these samples are counted on the Ge(Li) system. Identification of gamma-emitting radionuclides in all other types of samples is routinely performed by analysis on the Ge(Li) system. A TVA fabricated beta-gamma coincidence'ounting system is utilized for the determination of I<<131 concentrations in milk.

Data were entered in computer storage for processing specific to the analysis conducted. A computer, employing an ALPHA-M least squares code, was used to solve multimatrix problems associated With estimating the activities of the gamma-emitting nuclides analyzed by NaI(T1). The data obtained by Ge(Li) detectors were resolved by the ND-4420 software.

The detection capabilities for environmental sample analyses

. given as the, nominal lower limits of detection (LLD) are liste'd in ,

Table 3. Samples processed by NaI(T1) gamma for .13 specific gamma-emitting radionuclides and radionuclide combina-tions*. For these analyses, radionuclide combinations such as and Zr-Nb are analyzed as one radionuclide. All photopeaks found in

'u spectroscopy were analyzed Ge(Li) spectra were identified and quantified. Many of the isotopes identified by Ge(Li) spectral analysis are naturally occurring or naturally produced radioisotopes, such as Be, " K, Bi, "Bi, Pb, Pb y Ra -etc.

y LLD' for the analys is of the radionucl ides 1 i s ted below+ are given in Table 3B. LLD's for additional radionuclides identified by Ge(Li) analysis were calculated for each analysis and nominal values are listed in the appropriate data tables. In the instance where an LLD has not been established, an LLD value of zero was assumed. A notation in a table of " values <LLD" for an isotope with no established LLD does not imply a value less than 0; rather it indicates that the isotope was not identified in that specific group, of samples. For each sample type, only the radionuclides for which values greater than the LLD were reported are li'sted in the data tables.

TVA's Radioanalytical Laboratory participates in the Environ-mental Radioactivity Laboratory Intercomparison Studies Pro'gram conducted by EPA-Las Vegas. This program provides periodic cross-check samples of the type and radionuclide composition normally analyzed in 'an environ-mental monitoring program. Routine sample handling and analysis pro-,

cedures were employed in the evaluation of these samples. Gamma spectral analyses were performed on Nal detectors. The results received during calendar year 1979 are shown in table 4. The +3a limits are corrected for triplicate determinations.

  • The following radionuclides and radionuclide combinations are ~uantified by the ALPHA-M least-squares computer code: " '"Ce; Cr; I; lus~lo6Ru'Cs's'r-Nb'o suMn. esZn. 6oCo soK and Ba-La.

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Table 1 ENVIRORfENTAL-RADIOACTIVITYSAMPLING SCHEDULE Air Charcoal Rain- Heavy Particle River Well Public Aquatic Life station tno tron titter tilt r ter patient dail ~oe etatioa Milk Mater aeter tinter aad dedinent deeda Huscle Shoals W W M A Lawrenceburg W W M Rogersville W W M Athens W M Decatur W M Courtland W H A Site NW-l W W H A Site'N-2 W M Site NE-3 W W' Site NW-4 . W W H A Site WSW-5 W M Pam B Fam Bi Fary S Pam T

~ Farm L Control Farms Onsite Well Wheeler Daa Elk River Tennessee River Chanpion Paper Co.

Various Local Ferns W - Weekly H - Monthly 8-Saaiannually A-Annually

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

'I LM-2 BF, North 0.9 Mile NNE (1.4 kilometers)

LM-3 BF, Northeast 1.0 Mile NE (1.6 kilometers)

LM-4 BF, Trailer Park 1.7 Miles NNW (2.7 kilometers)

LM-5 BF, Davis Farm 2.5 Miles WSW (4.0 kilometers)

PM-1 BF, Rogersville, AL 13.8 Miles NW (22.2 kilometers) .

PM-2 BF, Athens, AL 10.9 Miles NE (17.5 kilometers)

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

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

RM-1 BF, Muscle Shoals, AL 32.0 Miles W (51.5 kilometers)

(Control)

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

(Control) I Farm S 4.75 Miles N (7.6 kilometers)

Farm B. 7.0 Miles NNW (11.3 kilometers)

Farm H 3.75 Miles N (6.0 kilometers)

Farm T 7.0 Miles ENE (11.3 kilometers)

Farm Bi 4.5 Miles ENE (7.2 kilometers)

Farm N (Control). 27.0 Miles NW (43.4 kilometers)

Farm J (Control) 40.0 Miles NNW (64.4 kilometers)

Farm C (Control) 32.0 Miles N (51.5 kilometers)

Farm Ca (Control) 32.0 Miles W (51.5 kilometers)

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Table 3 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS A. S eciiic Anal ses NOMINAL LOWER LIMIT OF DETECTION LLD e Fish>

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

~Ct l ~Ctl oCt/k ~Ct t >~et/ ~C ~ctl, ar I>~Ci/ ~dr I>~Ci/ ~dr gC~i/k ~gt ~il Total a 0.4 0.01 1.5 Cross o 0.005 2.0 0. 05 0.35 0.1 0.7 Cross B 0.01 --'.05 0. 20 0.70 0.1 0.7 25 330 l ill "Sr

0. 01 0.5 0.005 10 0. 25 1.5 0.5 5.0 40 10 "Sr 0.001 2 0. 05 0.3 0.1 1.0 8 2
  • All LLD values for isotopic separations are calculated by the method developed by Pasiernack and Harley as described in HASL-300.

Factors such as sample size, decay time, chemical yield, and counting efficiency may vary for a given sample; these variations may change the LLD value for. 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 ~ 3.7 x 10 Bq.

Table 3

'.35 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS B. Canna Anal ses NOMINAL LOWER LIMIT OF DETECTION LLD Air Water Vegetation Soil and Clam flesh Foods, tomatoes Meat ac=

particulates and milk and grain sedinent Fish and plankton Clan shells potatoes, etc.) poultry

~ct/a ~CL/L ~Ct/ dr ~ct/ d ~Cjl d ~ct/ dr ~ci/ dr Ci/ vet ~ci/k e:

NaI* ~Ge Li ** Nal ~Ce Li NaI ~Ge Li Nal ~Ge Li Nai ~GLL) Nai ~GLt NaI ~Ge Li) NaI C~eLi NaI Ce(Li~

stalk ltt ttC 0.03 38 0. 55 0.35 0. 35 38 90

'"'Ce 0.02 33 0. 22 0.06 . 0.06 0.35 0.06 33 4C

  • "Cr 0. 07 0. 03 60 44 1.10 0.47 0.60 0.10 0.60 0.10 '.56 0.60 0.10 60 44 200 90 1311 0.01 0.01 15 8 0.35 ';09 0.20 0.02 0.20 0.02 0.07 0.20 0.02 15 8 50 20 103 '06Ru 0. 04 40 0.65 0.45 0.45 0.45 40 150 106Ru 0.'03 40 0.51 0.11 0.11 0.74 0.11 40 90 134C 0.01 0.02 10 26 0.20 0.33 0.12 0.08 0.12 0.08 0.48 0.12 0.08 10 26 40 50 1370 0.01 0.01 10 5 0.20 0.06 0.12 0.02 0.12 0.02 0.08 0.12 0.02 10 40 15

'0 oszr-Nb 0. 01 10 0.20 0.12 0.12 0.12 40 3Szr 0.01 10 0.11 0.03 0. 03 0.15 0.03 10 20 "Nb . 0. 01. 5 0.05 0.01 0. 01 0.07 0.01 5 15

'oco . 0.02 0.01 15 5 0.23 0.05 0.20 0.01 0.20 0.01 0.07 0.20 0.01 15 5 55 15 0.02 0.01 10 5 0.05 '.20 0.15 0.01 0.15 0.01 0.08 0.15 0.01 10 5 40 15 6SZn 0.02 0.01 15 9 0.25 0.11 0.23 0.02 0.23 0.02 0.17 0.23 0.02 15 9 70 20 ooCo 0.01 0.01 10 5 0.17 0.06 0.11 0.01 0.11 0.01 0.08 0.11 0.01 10 5 30 15 oK 0.10 150 2.50 0.90 0.90 0.90 150 400 o

Ba-La 0.02 15 0.68 0.15 0.15 0.15 15 50 1 tk 0 Ba 0.02 25 0.34 0.07 0.07 0.30 0.07 25 50 140 Le 0.01 7 0.08 0.02 0.02 0.10 0. 02 7 15

  • The NaI(T1) LLD values are calculated by the method developed by Pesternack and Harley as described in HASL-300 and Nucl. Instr. Methods 91, 533-40 (1971). These LLD values'are expected to very depending on the activities 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-L Marinelli beaker. Vegetation, fish, soil, and sediment are counted in a 1-pint container as dry weight. The average dry weight is 120 grams for vegetation end 400-500 grams for soil sediment and fish, Meat end poultry are counted in a 1-pint container as dry veight, then corrected to vet veight using an average moisture content of

,702. Average dry veight is Z50 grams. Air particulates are counted in a veil crystal. The counting system consists of a nultichannel

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analyzer and either a 4" x 4" solid or 4" x 5" well Nel(Tl) 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 veek of the collection date.

  • oThe Ge(Li) LLD values are calculated by the method developed by Pasternack and Harley as described in HASL-300. These LLD values are expected to, vary depending on the activities of the components in the samples. These figures do not represent the LLD values achievable on given samples, Water is counred in either a 0.5-L or 3.5-L Marinelli beaker. Solid samples such as soil, sediment, and clan shells are counted in a 0.5-L Marinelli beaker as dry weight. The average dry weight is 400-500 grams. Air filters and very small volume samples are counted in patrie dishes centered on the detector endcap. The counting system consists of a ND-4420 multichannel analyzer and either a 252, 142, 16X, or 292 Ce(Li) detector. The counting tine is normally 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. All spectral analysis is performed using the softvare provided with the ND-4420.

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

. Conversion factor: 1 pCi 3.7 x 10 3 Bq.

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

Gross Al ha Gross Beta Strontium-90. Cesium-137

'PA value TVA EPA value TVA EPA value TVA EPA value TVA Date (+3a) ~Av . (+3a) ~Av . (+3a) ~Av . '(+3a) . ~Av .

1/79 5 + 9 4 18 + 9 20 6 + 2.7 6 6+ 9 7 3/79 14 + 9 14 63 + 9 64 21 + 2.7 17 21+9, 18*

6/79 9 + 9 9 30 + 9 31 10 + 2.7 9 10+ 9 9 10/79 .10 + 9 10 31 + 9 33 10 + 2.7 10 12+9 -11 B. Mater (pCi/1)

Gross Al ha Gross Beta Strontium-89 Strontium-90 Tritium Iodine-131*

EPA value TVA EPA value TVA EPA value TVA EPA value TVA EPA value ,TVA EPA value TVA Date (+3a) ~Av . (+3a) ~Av . ~

(+3a) ~Av . (+3a) ~Av . (+3a) ~Av . (+30) ~Av .

11/78 11,+ 9 12 26 + 9 27 12/78 2030+400 2100 1/79 6 + 9 7 16 + 9 17 14 + 9 14 6 + 2.7 6 2/79 1280+570 1260 3/79 10 + 9 10 16 + 9 18 4/79 2270+400 2270 40 + 7 40 5/79 18 + 9 15 23+ 9 24 30 + 2.7 26 6/79 1540+580 1590 7/79 9 + 9 ll 1480+580 26 + 9 8/79 1300 26 9/79 5 + 9 8 40 +' 43 3 + 9 4 28 + 2.7 25 10/79 1560+640 1400

  • Specific analysis for I to test the procedures used for the analysis of ' in milk.

Table 4 (Contd)

Results Obtained in Interlaboratory Comparison Program C. Gamma-Emitting Radionuclides in Water (pCi/1)

"Cr 60C 6SZn 106R 13NCs 137Cs EPA value TVA EPA value TVA EPA value TVA EPA value TVA EPA value TVA EPA value TVA Date (+3') ~Av . (+3a) ~Av . (+3a) ~Av . (+30) ~Av . (+3o) ~Av . (+3a) ~Av .

10/78 117 + 10 . 150 23+9 24 82+ 9 78 46+ 9 42 25+ 9 29 125 + 10 120 2/79 0+ 9 0 9+9 9 21+9 25 0-+ 9 0 6+9 6 12+ 9 12 6/79 0+ 9 0 47+9 48 0 + 9 0 0 + 9 0 71+9 72.. 0+ 9 0 10/79 113'+ 10 108 6+9 7 0+ 9 0 0 + 9 0 7+9 '9 11' 9 ll D. Tritium in Urine (pCi/1)

Date EPA value (e3al ~1VA av 12/78 2,150 + 400 2330 3/79 3,300 + 600 2350 6/79 1,610 + 580 1590 9/79 13,200 + 710 13350

o Table 4 (Contd)

Results Obtained in .Interlaboratory Comparison Program E. Milk (pCi/1) 89sr 90sr 131T 137CS "140Ee 4 OK.

EPA value TVA EPA value TVA EPA value TVA EPA value TVA EPA value TVA EPA value -TVA Date (+36) ~Av . (+3a) ~Av . (+3a) ~Av . (+3a) ~Av . (+30) ~Av . (+3o) ~Av .

1/79 33 9 33 19 + 2.7 21 105 + 10 110 49 +- 9. 48 0-+9' 1560-135 . 1520

-9 0+9 4/79 7/79 10/79 38 5-+9 25 +-9 38 25 5

54 11 17

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5.2 2.7 3.5 61 13 22 96 + 9 17 637

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9'1 55'36 95 154 + 14 12 +- 9 49 -+- 9 150 11 45 0+-9 0+-9 0

0 0

1560"-135 1630-+3.45 1470-125 1450 1570 1490 F. Pood (pCi/kg wet weight) 3/79 48 +-

9 53 22 + 2.7 27 90 + 9 91 74 + 9 73 0+9 0 2700235 2810 7/79 8 +-

9 12  ; 3 + 1.1 7 18 + 9 16 33 + 9 35 0+-9 0 2650225 3000 11/79 Results not received at this time

ATMOSPHERIC MONITORING 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 6 4). Four perimeter air monito'rs are located at distances out to 10 miles from the plant, and two remote air monitors are located at distances out to 45 miles.

These monitoring stations are shown in figure 2. The remote monitors are used as control or baseline stations. At each monitor, air 'is continuously pulled through a Hollingsworth and Voss HV-70 particulate filter at a regu-lated flow of 3 ft /min. In series with, but downstream of, the particulate filter is a charcoal filter used to collect iodine. Each monitor has a col-lection tray and storage container to obtain rainwater on a continuous basis and a horizontal platform that is covered with gummed acetate to catch and hold heavy particle fallout. Thermoluminescent dosimeters are used to record gamma radiation levels at each remote and perimeter station.

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

Air filters are collected weekly and analyzed for gross beta activ-ity. During this reporting period, one sample was lost. because o'f equipment malfunction. No analyses are performed until three days after sample col-lection. The samples are composited monthly for analysis of specific gamma-emitting radionuclides and quarterly for Sr, Sr analysis. The results are combined for each station to obtain an annual average. These data are presented in table 6.

With reference to table 5, which contains'the maximum permissible concentrations (MPC) recommended by 10 CFR 20 for nonoccupational exposure, it is seen that the maximum beta concentration is 0.15 percent MPC.

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

in'able 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.

'harcoal filters are collected and analyzed for radioiodine.

The filter is counted in a single channel analyzer system. The data are shown in table 9, where the highest value reported is 0.04 percent MPC for ~I. In this reporting period, two samples were accidently, destroyed, and one was lost dye to equipment malfunction. t

13 Figure 2 ATMOSPHERIC 'AND TERRESTRIAL MONITORING NETWORK RM.2BF LAWRENCEBURB yPULASKI F AYETTEVILLE ~

WILSON PM-IBF WHEELER ROBE SNL FLORENCE OAM ATHENS PM-2BF FFIEL MUSCLE HUNTSVILLE SHOALS BROWNS FERRY RM-I BF NUCLEAR PL NT I.EIQHTON TUSCUMBIA COURTLANO PM-4 F OECAT R PM-3BFO IO MILES pRUSSELLVILLE UNT SV IL HARTSELLE OAM 25 HALEYVILLE CULLMAN 45 MILES Q- ENVIRONMENTAL MONITORINB STATION NOTE: THE FOLLOWING SAMPLES ARE COLLECTED FROM EACH STATION:

AIR PARTICULATES RAINWATER RADIOIODINE SOIL HEAVY PARTICLE FALLOUT

LOCAL MONITORING STATIONS BROWNS FERRY NUCLEAR PLANT ATHENS US HWY 72 BFN ALA. HWY 20 Legend Air Monitor . DECATUR Air Monitor 8 TLD Station N

TLD Station Automatic Well Sampler N

Scale Dairy Farm 0 I 2 3 IMiles

Figure 4 BROWN'S FERRY NUCLEAR PLANT SITE MONITORING STATIONS

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WHEELER LAKE

Table 5.

MAXIMUM PERMISSIBLE CONCENTRATIONS FOR NONOCCUPATIONAL,EXPOSURE MPC In Water In Air

~Ci/1 ~Ci/m ~

30 Nonvolatile'beta 3,000 100 Tritium 3,000,000 ,200,000 137CS 200000 500

'i 103$ 106R 10,000 200 10,000 200 1

"Zr-"Nb 60,000 1,000 luOBa 1uOLa 20,000. ~

1,000

.1 31Z 300 100 Zn 1000000 21000

'"Mn 100$ 000 1$ 000

"-Co 308000 300 88Sr '

3,000 300 80Sr 300 30 01C 2,000,000 . 80$ 000 1 5uCs 9,000 400 5 8Co 90,000 2,000

'C TABLE 6 RADIOACTIVITY IN AIR FILTER PCI/M(3) 0.037 K/M(3) 7 NAME OF FACILITY BROWNS FERRY DOCKET NO. RH-80-3-BF-2 LOCATION OF FACILITY LIMESTONE ALABAMA REPORTING PERIOD 1979 TYPE AND LOWER LIMIT ALL 'CONTROL NUMBER OF TOTAL NUMBER LOCATION WITH HIGHEST ANNUAL MEAN

,OF INDICATOR LOCATION) NONROUTINE OP ANALYSIS LOCATIONS DETECTION MEAN ($ ) NAME MEAN (F$ MEAN (P( REPORTED PERPORMED . (LLD) RANGE DISTANCE AND DIRECTION RANGE RANGE MEASUREMENTS GROSS ALPHA 0.005 0.01( 4/ 52) 52 0.01- 0.01 GROSS BETA 0.010 0. 03 (466/467) COURTLAND,, AL 0.04( 52/ 52). 0.03(104/104) 571 0.01- 0.15 10.5 MILES WSW 0 02- 0.11 0.02- 0.09 GQDiA (NAI) 122 CE-141,144 0.030 0. 04 ( 2/101) LM-1 BFN, NORTHWEST 0.04( 1/ 13) 21 VALUES <LLD 0.03 0.04 1.0 MILES N 0.04-0.04 I-131 0.010 0.02( 10/101) COURTLAND, AL 0.03( 2/ 13) 0.02( 1/ 21) 0.01- 0.04 10.5 MILES WSW. 0.03- 0.04 0.02- 0.02 BA-140,LA-140 0.020 0.02( 4/101) IA-3 BP NORTHEAST 0.02( 1/ 13) 21 VALUES <LLD 0.02- 0.02 1.0 MILES NE 0.02- 0.02 BE-7 NOT ESTAB 0.09(100/101) 'L$4 BP TRAILER P 0.11( 12/ 12) 0.09( 21/ 21) 0.02- 0.18 1.7 MILES NNW 0.04- 0.18 0.03- 0.16 GARE (GELI) 21 KWO NOT ESTAB 0.10( 6/ 16) Ikf-..3.'BF NORTHEAST 0.12( 1/ 3) 0.08( 1/ 5) 0.8- 0.12 1.0 MILES NE 0.12- 0.12 0.08- 0.08 BIr214 0.020 0.04( 7/ 16) ROGERSVILLE, AL 0.06( 1/ 4) 0.03( 1/ 5) 0.02- 0.06 13.8 MILES NW 0.06-'. 06 0.03- 0.03 PB-212 NOT ESTAB 0.01( 4/ 16) LR-2 BF NORTH 0.02( 1/ 3) 0.01( 2/ 5) 0.01- 0.02 0.9 MILES NNE 0.02- 0.02 0.01- 0.01 "PB-214 NOT ESTAB o 02( 12/ 16) LM-3 BP NORTHEAST 0.06( 1/ 3) 0.01( 4/ 5) 0.00- 0.06 1.0 MILES NE 0.06- 0.06 0.01- 0.02 AC-228 NOT ESTAB 0.01( 1/ 16) LM-2 BF NORTH 0.01( 1/ 3) 5 VALUES <LLD 0.01- 0.01 0.9 MILES NNE 0.01- 0.01

a. Nominal Lower Limit of Detection (LLD) as described in Table 3.
b. Mean and range based upon detectable measurements only. Fraction of detectable'easurements of specified locations is indicated in parenthesis (F).

TABLE 6 (CONTD)

RADIOACTIVITY IN AIR FILTER PCI/M(3) - 0.037 BR/M(3)

NAME OF FACILITY BROWNS FERRY DOCKET NO. RH-80-3-BF-2 LOCATION OF FACILITY LIMESTONE ALABAMA REPORTING PERIOD 1979 TYPE AND LOWER LIMIT ALL CONTROL NUMBER OF LOCATION WITH HIGHEST ANNUAL MEAN TOTAL NUMBER OF INDICATOR LOCATION) NONROUTINE LOCATIONS OF ANALYSIS DETECTION MEAN (g) NAME MEAN (F) MEAN (F( REPORTED PERFORMED ~II3 RANGE DISTANCE AND DIRECTION RANGE MEASUREMENTS BE-7 NOT ESTAB 0.09( 13/ 16) DECATUR, AL 0. 11( 2/ 2) 0.07( 4/ 5) 0.03- 0.16 8.2 MILES SSE 0.06.- 0.16 0.05- 0.09 SR-89 0.005 ANALYSIS PERFORMED 8 VALUES <LLD 44 36 VALUES <LLD SR-90 0.001 ANALYSIS PERFORMED 0.00( 1/ 8) 44 36 VALUES <LLD 0.00- 0.00

a. Nominal Lower Limit of Detection (LLD) as described in Table 8.
b. Mean and range based upon detectable measurements only. Fraction of detectable measurements of specified locations is indicated in parentheses (F).

'C TABLE, 7 P

RADIOACTIVITY IN RAINWATER PCI/L - 0.037 BQ/L NAME OF FACILITY BROWNS PERRY DOCKET NO. RH-80-3-BF-2 LOCATION OF FACILITY LIMESTONE ALABAMA REPORTING PERIOD 1979 TYPE AND LOWER LIMIT ALL CONTROL NUMBER OF LOCATION WITH HIGHEST ANNUAL MEAN TOTAL NUMBER OF INDICATOR LOCATION) NONROUTINE LOCATIONS OF ANALYSIS DETECTION MEAN ($ ) NAME MEAN (F( MEAN (F( REPORTED PERFORMED (LLD) RANGE DISTANCE AND DIRECTION -

RANGE RANGE MEASUREMENTS GAMMA (NAI) 135 I-131 15.000 24.95( 6/109) ROGERSVILLE, AL 26.03 ( 3/ 12) 40.5( 1/ 26) 17.90- 32.70 13.8 MILES NW 20.50- 32.70 40.5- 40.5 BA-140, LA-140 15.00 21.10( 1/109) LM-2 BF NORTH ('1.10 1/13) 26 VALUES <LLD 21.10- 21.10 0.9 MILES NE 21.10- 21.10 BE-7 NOT ESTAB 46.55( 46/109) LM-1 BF NORTHWEST 58.45 ( 6/ 10) 35.79( 15/26) 11.60- 102.40 1.0 MILES N 12.70- 102.40 7.60- 61.20 GAMMA (GELI) 8 K-40 NOT ESTAB -93.87( 6/ 8) LM-3 BP NORTHEAST 106.60 ( 2/ 2) 58.13- 128.50 1.0 MILES NE 97.79- 115.40 BI-214 NOT ESTAB 31.44(

12.97-6/ 8) ROGERSVILLE, AL 45 '9 ( 1/ 1) 45.77 13.8 MILES NW 45.29- 45.29 PB-212 NOT ESTAB 18.81( 5/ 8) LM-1 BF NORTHWEST 23.73 ( 2/ 3) 6.74- 27.80 1.0 MILES N 19.65- 27.80 PB-214 NOT ESTAB 19.30( 6/ 8) ROGERSVILLE, AL 32.62 ( 1/ 1) 6.31- 32.62 13.8 MILES NW 32.62- 32.62 BE-7 NOT ESTAB 65.72( 1/ 8) LM-5 BF DAVIS F 65.72 ( 1/ 1) 65.72- 65.72 2.5 MILES WSW 65.72- 65.72 TRITIUM 330.00 400.50( 2/109) ROGERSVILLE, AL 422.00 ( 1/ 13) 26 VALUES <LLD 379.00- 422.00 13.8 MILES'NW 422.00- 422.00

a. Nominal Lover Limit of Detection (LLD) as described in Table 3.
b. Mean and range based upon detectable measurements only. Fraction of detectable measurements of specified locations is indicated in parentheses (F).

TABLE 8 RADIOACTIVITY IN HEAVY PARTICLE FALLOUT MCI/KM - 3,7 K 10 BQ/KM NAME OP FACILITY BROWNS PERRY DOCKET NO. RH-80-3-BF-2 LOCATION OF PACILITY LIMESTONE ALABAMA REPORTING PERIOD 1979 TYPE AND LOWER LIMIT ALL CONTROL NUMBER OP TION WITH HIGHEST NONROUTINE .

TOTAL NUMBER OF Zggl~TOR ACTIONS LOCATION) ~

REPORTED OF ANALYSIS DETECTION MEAN ([) NAME MEAN (F( MEAN (F(

PERFORMED ~LU> RANGE DISTANCE AND DIRECTION RANGE RANGB MEASUREMENTS GROSS BETA 143 0.050 0.25 (117/117$ LM-4 BP TRAILER P 0.41 ( 13/ 13) 0.24 ( 26/ 26) 0.06- 1.29 1.7 MILES NNW 0.07- 1.29 0.06- 0.67

a. Nominal Lower Limit of Detection (LLD) as described in Table 3.
b. Mean and range based upon detectable measurements only. Fraction of detectable measurements of specified locations is indicated in parentheses (F).
c. A gamma spectral analysis utilizing a GeLi detector revealed only the presence of ~Be and the naturally occurring radioisotopes of bismuth and lead. P

TABLE 9 RADIOACTIVITY IN CHARCOAL FILTERS PCI/M(3) - 0.037 BQ/M(3)

NAME OF FACILITY BROWNS FERRY DOCKET NO. RH-80-3>>BF-2 LOCATION OF FACILITY LIMESTONE ALABAMA REPORTING PERIOD 1979 TYPE AND LOWER LIMIT . ALL CONTROL NUMBER OP TOTAL- NUMBER OF INDICATOR ICATION MM HIGHEST LOCATION) NONROUTINE LOCATIONS OP ANALYSIS, DETECTION MEAN (g) NAME MEAN (F( MEAN.- (P) REPORTED PERFORMED ~I'D RANGE DISTANCE AND DIRECTION RANGE MEASUREMENTS Iodine in Air 569 0.010 0.02 ( 92/465) LM-2 BF NORTH 0.02 ( 8/ 52) 0.02 ( 21/104) 0.01- 0.04 0.9 MILES NNE 0.01- 0.03 0.01- 0.03

a. Nominal Lower Limit of Detection (LLD) as described in Table 3.
b. Mean and ranEe based upon detectable measurements only. Praction of detectable measurements of specified locations is indicated in parentheses (P).

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

Cow censuses were conducted in May and September 1979. It was determined that there are no dairy farms nearer the plant than the nearest farm being sampled.

Ve etation Vegetation is sampled quarterly at the farms from which milk is collected and analyzed for gamma-emitting radionuclides. Approximately 1-2 kilograms of grass is broken or cut at ground level and returned for analysis. Efforts are made to sample vegetation that is representative of the pasturage where cattle graze. Table 11 gives the results obtained from the laboratory analyses of these samples.

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

Ground Water An automatic sequential-type sampling device has been installed on a well down-gradient from Browns Ferry Nuclear Plant. A composite sam-ple from this well is analyzed for gamma-emitting radionuclides monthly and composited quarterly for determination of tritium. A grab sample is also taken from a control well up-gradient from the plant.'he results of the analysis of well water are shown in, table 13.

Drinkin Water Potable water supplies taken from the Tennessee River in the vicinity of Browns Ferry Nuclear Plant are sampled and analyzed for gross

beta and gamma-emitting radionculides, 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 composite samples collected and analyzed weekly. Two additional supplies downstream and one public water supply upstream are collected by monthly grab'ampling. Table 14 indicates the results from the analysis of drinking water samples. The maximum beta concentration is 0.25 percent MPC.

Environmental Gamma Radiation Levels Thermoluminescent dosimeters (TLD's) are placed at nine stations around the plant near the site boundary and at the perimeter and remote air

. monitors to determine the gamma exposure rates at these locations. The TLD's are changed every 3 months. The quarterly gamma radiation levels determined from these TLD's are given in table 15.

Poultr and Food Cro s Food crops and poultry raised in the vicinity of Browns Ferry Nuclear Plant and at control locations are sampled as they become available during the growing season, and analyzed for gamma-emitting radionuclides.

During this sampling period samples of corn, green beans, potatoes, 'tomatoes, and poultry were collected and analyzed for specific gamma-emitting radio-nuclides. The results are given ig tables 16 and 17.

TABLE 10.

RADIOACTIVITY IN MILK PCI/L, 0.037 BQ/L NAME OF FACILITY 'ROWNS FERRY DOCKET NO. RH-80-3-BF-2 LOCATION OF FACILITY LIMESTONE ALABAMA REPORTING PERIOD 1979 TYPE AND LOWER LIMIT ALL CONTROL NUMBER OF TOTAL NUMBER OP INDICATOR LOCPIONS LOCATION) NONROUTINE OF ANALYSIS DETECTION MEAN ($ ) NAME MEAN (F) MEAN (F) REPORTED PERFORMED ~IID RANGE DISTANCE AND DIRECTION RANGE MEASUREMENTS GAMMA (NAI) 117 CS-137 10.000 11.01( 7/ 65) FARM T 11.40( 3/ 13) 11.90( '2/ 52) 10.20- 12.80 7.0 MILES ENE 10.30- 12.80 11.80- 12.00 K-40 150.00 1247.90( 65/ 65) FARM T 1317.20( 13/ 13) 1264'i90( 52/ 52) 1047.40- 1409.00 7.0 MILES ENE 1208.30- 1409.00 1059.62- 1446.30 IODINE IN MILK 0 500 456 ANALYSIS PERFORMED 199 <LLD 257 <LLD SR-89 117 10.000 ANALYSIS PERFORMED 52 <LLD 65 <LLD SR-90 2.000 4.76( 65/ 65) PARM B 5.77( 13/ 13) 4.89( 41/ 52) 2.24- 9.14 7.0 MILES NNW 2.78- 8.36 2.02'- 11.98

a. Nominal Lower Limit of Detection (LLD) as described in Table 3.
b. Mean and range based upon detectable measurements only. Fraction of detectable measurements of specified locations is indicated in parentheses (P).

TABLE ll RADIOACTIVITY IN VEGETATION PCI/G - 0.037 +/G (DRY WEIGHT)

NAME OF FACILITY BROWNS PERRY DOCKET NO. RH-80-3-BF-2 LOCATION OP FACILITY LIMESTONE AIJQNMA REPORTING PERIOD 1979 TYPE AND LOWER LIMIT ALL CONTROL NUMBER OP TOTAL NUMBER OP INDICATOR

~TION MM HIGHEST LOCATION) NONROUTINE ACTIONS MEAN (F( REPORTED OP ANALYSIS DETECTION MEAN ( ) NAME MEAN (P$

PERFORMED ~IUl RANGE DISTANCE AND DIRECTION RANGE MEASUREMENTS GROSS BETA 0. 200 33:13( 20/ 20) FARM T 37.37( 4/ 4) 31.13( 16/ 16) 36 10.51- 65.55 7.0 MILES ENE 16.11-'8.26 11.07- 58.96 GAMMA (GELI) 36 CE-144 0.220 0.35( 3/ 20) FARM S 0.39( 1/ 4) 0.24 ( I/ 16) 0.31- 0.39 4.75 MILES N 0.39- 0.39 0.24- 0.24 CE-137 0.060 0.10( 6/ 20) FARM S 0.14( 1/ 4) 0.08( 5/ 16) 0.07- 0.14 4.75 MILES N 0.14- 0.14 0.06- 0.12 K-40 NOT ESTAB 17.82( 20/ 20) FARM L 21;02( 4/ 4) 18.70( 16/ 16) 3.33- 40.56 5.75 MILES ENE 4.59- 40.56 3.05- 42.38 TL-208 NOT ESTAB 0.10( 4/ 20) FARM T 0.12( 1/ 4)

  • 0.06( 4/ 16) 0.09- 0.12 7.0 MILES ENE 0.12- 0.12 0.02- 0.10 BI-214 0.100 0.42( 16/ 20) FARM L 0.52( 3/ 4) 0.49( 12/ 16) 0.11- 0.82 5.75 MILES ENE 0.28- 0.66 0.16- 1.02 PB-212 NOT ESTAB 0.14( 14/ 20) FARM T 0.20( 2/ 4) 0.12( 11/ 16) 0.02- 0.33 7.0 MILES ENE 0.06- 0.33 0.03- 0.23 PB-214 NOT ESTAB 0.28( 16/ 20) FARM L 0.35( 3/ 4) 0.30( 15/ 16) 0.02- 0.68 5.75 MILES ENE 0.26- 0.41 0.06- 0.62 AC-228 NOT ESTAB 0.29( 6/ 20) FARM L 0.48( 2/ 4) 0.25( 5/ 16) 0.18- 0.57 5.75 MILES ENE 0.39- 0.57 0.17- 0.31 BE-7 NOT ESTAB 6.75( 20/ 20) FARM BI 7.46( 4/ 4) 7.96( 16/ 16) 3.92- 12.65 4.5 MILES ENE 4.00- 12.65 0.52- 19.22
a. Nominal Lover Limit of Detection (LLD) as described in Table 3.
b. Mean and range based upon detectable measurements only. Fraction of detectable measurements of specified locations is indicated in parentheses (P).

TABLE 12 RADIOACTIVITY IN SOIL PCI/G - 0.037 BQ/G (DRY WEIGHT)

NAME OF PACILITY BROWNS PERRY DOCKET NO. RH-80-3-BF-2 LOCATION OF FACILITY LIMESTONE ALABAMA REPORTING PERIOD 1979 TYPE AND LOWER LIMIT ALL CONTROL NUMBER OF TOTAL NUMBER LOCATION WITH HIGHEST ANNUAL MEAN OF INDICATOR LOC)TIONS LOCATION) NONROVTINE OP ANALYSIS DETECTION MEAN ($ ) NAME MEAN PERFORMED ~l10 RANGE DISTANCE AND DIRECTION (F$ MEAN (F$

RANGE REPORTED MEASUREMENTS GA)OQ. (GELI) 11 CS-137 0.020 0.56( 9/ 9) ATHENS, AL 1.73( 1/ 1) 1.44('/ 2)

K-40 0.250 0.07- 1.73 10.9 MILES NE l. 73- 1.73 1.20- 1.67 6.41( 9/ 9)

LM-1 BF NORTHWEST 9.19( 1/ 1) 5.86( 2/ 2) 4.18- 9.19 1.0 MILE N 9.19- 9.19 5.59- 6.14 TL-208 0.020 0.41( 9/ 9) LM-4 BF TRAILER P 0.53( 1/ 1) 0.35( 2/ 2) 0.21- 0.53 1.7 MILES NNW 0.53- 0.53 0.31- 0.38

'BI-212 0.100 0.80( 9/ 9) DECATUR, AL 1.03( 1/ 1) 0.65( 2/ 2) 0.42- 1.03 8.2 MILES SSE 1.03- 1.03 0.55- . 0.76

, BI-214 0.050 1 15'( 9/ 9) LM-4 BP TRAILER P 1.50(

~

1/ 1) 1.05( 2/ 2) 0.75- 1.50 1.7 MILES NNW 1.50-. 1.50 ~ 0.96- .1.15 PB-212 NOT ESTAB 1.00( 9/ 9) DECATUR, AL 1.34( 1/ 1) 0.88( 2/ 2) 0.52-' 1.34 8.2 MILES SSE 1.34 1.34 0.82- 0.94 PB-214 0.050 1. 17(

  • 9/ 9) IMA BF TRAILER P 1.51( 1/ 1) 1.07( 2/ 2) 0.75- 1.51 1.7 MILES NNW 1.51- 1.51 0.94- 1.20 RA-226 0.050 1.15( 0/ 9) LM-4 BF TRAILER P 1.50( 1/ 1) 1.05( 2/ 2) 0.75- 1;50 1.7 MILES NNW 1.50- 1.50 a,96- 1.15 AC-228 0.060 1.24( 9/ 9) DECATUR, AL 1.65( 1/ 1) 1.09( 2/ 2) 0.67- 1.65 8.2 MILES SSE, 1.65 1.65 0.99- 1.20
a. Nominal Lower Limit of Detection (LLD) as described in Table 3.
b. Mean and range based upon detectable measurements only. Fraction of detectable measurements of specified locations is indicated in parentlieses (F).

TABLE 12 (CONTD)

RADIOACTIVITY IN SOIL PCI/G 0.037 BQ/G (DRY WEIGHT)

NAME OF FACILITY BROWNS PERRY DOCKET NO i RH-80-3-BP-2 IAKATION OF PACILITY LIMESTONE ALABAMA REPORTING PERIOD 1979 TYPE AND LOWER LIMIT ALL CONTROL NUMBER OF TOTAL NUMBER OF INDICATOR IggPZONS

~TION MM HI~ST LOCATION) NONROUTINE OP ANALYSIS DETECTION MEAN ($ ) NAME MEAN (F) MEAN (F( REPORTED PERFORMED ~IID RANGE DISTANCE AND DIRECTION MEASUREMENTS SR-89 11 1.500 ANALYSIS PERFORMED 9 VALUES LLD 2 VALUES <LID SR-90 11 0.300 0.43( 1/ 9) LM-1 BF NORTHWEST 0.43( 1/ 1) 2 VALUES <LLD 0.43- 0.43 1.0 MILE N 0.43- 0.43

a. Nominal Lower Limit of Detection (LLD) as described in Table 3.
b. Mean and range based upon detectable measurements only. Fraction of detectable measurements of specified locations is indicated in parentheses (F).

TABLE 13 RADIOACTIVITY IN WELL WATER PCI/L 0.037 BQ/L NAME OP FACILITY BROWNS FERRY DOCKET NO. RH-80-3-BF-2 LOCATION OP FACILITY LIMESTONE ALABAMA REPORTING PERIOD 1979 TYPE AND LOWER LIMIT ALL CONTROL NUMBER OF LOCATION ITH HIGHEST TOTAL NUMBER OF INDICATOR ~TIONS LOCATION) NONROUTINE OF ANALYSIS DETECTION MEAN (g) ~ NAME MEAN (P) MEAN (F) REPORTED PERFORMED ~I1D RANGE DISTANCE AND DIRECTION RANGE RANGE MEASUREMENTS GAMMA (NAI) 24 ANALYSIS PERFORMED 13 VALUES <LLD 11 VALUES <LLD GAMMA (GELI) 2 K-40 NOT ESTAB 70.90( 1/ 2) BROWNS FERRY 70.90( 1/ 2) 70.90- 70.90 WELL 86 70.90- 70.90 BI-214 NOT ESTAB 13.80( 1/ 2) BROWNS PERRY 13.80( 1/ 2) 13.80- 13.80 WELL F6 13.80- 13/80 PB-214 NOT ESTAB 11.26( 1/ 2) BROWNS FERRY 11.26( 1/ 2) 11.26- 11.26 WELL t6 11.26- 11.26 TRITIUM 8 330.00 537. 00 ( 1/ 4) BROWNS PERRY 537.00( 1/ 4) 361.00( 1/ 4) 537.00- 537.00 WELL 86 537.00- 537.00 361.00- 361.00

a. Hominal Lover Limit of Detection (LLD) as described in Table 3.
b. Mean and range based upon detectable measurements only. Praction of detectable measurements of specified locations is indicated in parentheses (F).

TABLE 14 RADIOACTIVITY IN DRINKING WATER PCI/L 0.037 BQ/L NAME OF FACILITY BROWNS PERRY DOCKET NO. RH-80-3-BF-2 LOCATION OP FACILITY LIMESTONE ALABAMA REPORTING PERIOD 1979 TYPE AND LOWER LIMIT CONTROL NUMBER OF TOTAL NUMBER OF ~IVOR ~PZONS LOCATION) NONROU TINE OF ANALYSIS DETECTION MEAN (g) NAME MEAN (F) MEAN (F$ REPORTED PERFORMED ~LID RANGE DISTANCE AND DIRECTION RANGE MEASUREHENTS GROSS BETA 2.400 3.71( 48/ 78) CHAMPION PAPER 3.92( 38/ 52) 3.11( 4/ 13) 91 2.40- 7.42 TRM 282.6 2.40- 7.42 2.47- 3.62 GAMMA (NAI) ANALYSIS PERFORMED 86 75 VALUES <LLD 11 VALUES WLD GAMMA (GELI) 5 K-40 NOT ESTAB 153.70( 3/ 3) CHAMPION PAPER 153.70( 3/ 3) 96.07( 1/ 2) 89.19- 281.60 TRM 282.6 89.19- 281.60 96.07- 96.07 BI-214 NOT ESTAB 15.73( 1/ 13) CHAMPION PAPER 15.73( 1/ 3) 44.48( 1/

15.73- 15.73 TRM 282.6 15.73- 15.73 44.48- 2)'4.48 PB-212 NOT ESTAB 4.46( 1/ CHAMPION PAPER 4.46( 1/ 3) 24.72( 1/ 2) 4.463)'.46-TRM 282.6 4.46 4.46 24.72- 24.72 PB-214 NOT ESTAB ANALYSIS PERFORMED 19.04( 1/ 2) 3 VALUES CLLD 19.04- 19.04 SR-89 16 10.000 ANALYSIS PERFORMED 12 VALUES <LLD 4 VALUES <~LD SR-90 16 2.000 ANALYSIS PERFORMED "12 VALUES <LLD 4 VALUES <LLD TRITIUM 16 330.000 403.67( 3/ 12) SHEFFIELD, AL 453.00( 1/ 4) 400.50( 2/ 4) 377.00- 453.00 TRM 254.3 453.00- '453.00 330.00- 471.00

a. Nominal Lover Limit of Detection (LLD) as described in Table 3.
b. Mean and ranEe based upon detectable measurements only. Fraction of detectable measurements of specified locations is indicated in parentheses (P).

31 Table 15 ENVIRONMENTAL GAMMA RADIATION LEVELS Environmental Gamma uarter Location ~/ ~/

Radiation Levels February-March 1979 On-Site (9)*

Maximum 9~4 20. 5 Minimum 6.4 14.1 Average** 7.9 + 2.4 17.4 + 5.2 Off-Site (6)

Maximum 9.4 20. 6 Minimum 5.9 13.0 Average 7.9 + 2.6 17.2 + 5.6 April-June 1979 On-Site (9)

Maximum 9.6 21.0 Minimum 6.7 14.7 Average 8.4 + 2.0 18.4 + '4.4 Off-Site (7)

Maximum 10.6 23.2 Minimum 6.2 13.5

'0.3 Average 7.6 + 3.0 16.6 + 6.5 July-September 1979 On-Site (9)

Maximum 22.5 Minimum 6.8 14.9 Average 9.1 + 2.6 20.0 + 5.8 Off-Site (7)

Maximum 11.6 25". 3 Minimum 6.8 15;0 Average 9.1 + 2.9 20.0 + 6.4 October-December 1979 On-Site (9)

Maximum 10. 0 21.9 Minimum 7.8 17.0 Average 9.0 + 1.8 19.8 + 3.9 Off-Site (7)

Maximum Minimum Average 8.0 11.5 6.0

+ 3.5

'3.1 25.2 17.6 + 7.7

  • Number of stations (normally three TLD's at each station)
  • +All averages reported +2a

TABLE 16 RADIOACTIVITY IN FOOD CROPS PCI/KG 0.037 BQ/KG (WET WEIGHT)

NAME OF FACILITY BROWNS FERRY DOCKET NO. RH-80-3-BF-2 LOCATION OF FACILITY LIMESTONE ALABAMA REPORTING PERIOD 1979 TYPE AND LOWER LIMIT CONTROL NUMBER OF LOCATION WITH HIGHEST ANNUAL MEAN TOTAL NUMBER OF INDICATOR LOC)TIONS LOCATION) NONROUTINE OF ANALYSIS DETECTION MEAN (g) NAME MEAN (P) MEAN (P) REPORTED PERFORMED ~IUI RANGE "

DISTANCE AND DIRECTION RANGE RANGE MEASUREMENTS RADIOACTIVITY IN CORN GROSS BETh 2 25.000 4868.'83( 1/ 1) FARM BI 4868.83( 1/ 1) 5228.90( 1/ 1) 4868.83- 4868.83 4.5 MILES ENE 4868.83- 4868.83 5228.90- 5228.90 GAMMA (GELI) 2 K-40 NOT ESTAB 1963.00( 1/ 1) PARM BI 1963.00( 1/ 1) 2349.00( 1/ 1) 1963.00- 1963.00 4.5 MILES ENE 1963.00- 1963.00 2349.00- 2349.00 RADIOACTIVITY IN GREEN BEAHS GROSS BETA 2 25.000 3669. 31(

3669.31-1/ 1) 3669.31 PARM BI 4.5 MILES ENE 3669.31(

3669.31-1/ 1), 4157.19(

3669,31 4157.19-1/ 1) 4157.19 GAD(A (GELI) 2 K-40 NOT ESTAB 1711.00( 1/ 1) FARM BI 1711.00( 1/ 1) 1782.00( 1/ 1) 1711.00- 1711.00 4.5 MILES ENE 1711.00- 1711.00 1782.00- 1782.00 PB-212 NOT ESTAB 11.73( -1/ 1) FARM BI 11.73( 1/ 1) 11.73- 11.73 4.5 MILES EHE 11.73- 11.73 1 VALUE <LLD

a. Nominal Lour Limit of Detection (LLD) as described in Table 3.
b. Mean and range based upon detectable'measurements only. Praction of detectable measurements of specified locations is indicated in parentheses (P).

TABLE 15 '(CONTD)

RADIOACTIVITY IN FOOD CROPS PCI/KG - 0.037 BQ/KG (WET WEIGHT)

NAME OF PACILITY BROWNS FERRY DOCKET NO. RH-80-3-BF-2 LOCATION OF PACILITY LIMESTONE ALABAMA REPORTING PERIOD 1979 LOWER LIMIT TYPE AND ALL CONTROL NUMBER. OF LOCATION WITH HIGHEST ANNUAL MEAN TOTAL NUMBER OP INDICATOR LOC)TIONS LOCATION) NONROUTINE OF ANALYSIS DETECTION 'EAN (g) NAME MEAN (F) MEAN (F( REPORTED PEBFORMID ~LUl RANGE DISTANCE AND DIRECTION RANGE RANGE MEASUREMENTS RADIOACTIVITY IN POTATOES GROSS BETA 2 25.00 3449.46( 1/ 1) PARM BI 3449.46( 1/ 1) 7579.60( 1/ 1) 3449.46- 3449.46 4.5 MILES ENE 3449.46- 3449.46 7579.60- 7579.60 .

GAMMA (GELI) 2 K<<40 NOT ESTAB 3808.00( 1/ 1) FARM BI 3808.00( 1/ 1) 3704.00( 1/ 1) 3808.00- 3808.00 4.5 MILES ENE 3808.00- 3808.00 3704.00- 3704.00 BI-214 NOT ESTAB ANALYSIS PERPORMED 8.83( 1/ 1) 1 VALUE <LLD 8.83- 8.83 RADIOACTIVITY IN TOMATOES GROSS BETA 2 25.00 2993.59( 1/ 1) FARM BI 2993.59( 1/ 1) 5057.58( . 1/ 1) 2993.59- 2993.59 ~ 4.5 MILES ENE 2993.59- 2993.59 5057.58- 5057.58 GAMMA.GELI K-40 2

NOT ESTAB 2154.00(

2154.00; 1/ 1) 2154.00 PARM 4.5 BI MILES ENE 2154.00(

2154.00-

'/ 1) 2154.00 2557.00(

2557.00-1/ 1) 2557.00 PB-214 NOT ESTAB 6.45( 1/ 1) FARM BI 6,45(. 1/ I}

6.45 '.45-4.5 MILES ENE 6.45- 6.45 1 VALUE <LID

a. Nominal Lover Limit of Detection (LLD) as described in Table 3.
b. Mean and range based upon detectable measurements only. Fraction of detectable measurements of specified locations is indicated

. in parentheses (P).

TABLE 17 RADIOACTIVITY IN POULTRY PCI/KG - 0.037 BQ/KG (WET WEIGHT)

NAME OP FACILITY BROWNS. PERRY DOCKET NON RH-80-3-BF-2 LOCATION OF PACILITY LIMESTONE 'LABAMA REPORTING PERIOD 1979 TYPE AND LOWER LIMIT ALL CONTROL NUMBER OF LOCATION WITH HIGHEST NONROVTINE TOTAL NUMBER OP INDICATOR LOCATION)

ACTIONS MEAN (P$ MEAN REPORTED OF ANALYSIS DETECTION MEAN (g) NAME (F$

PERFORMED ~UD = RANCE DIETANCE AND DIRECTION RANGE MEASUREMENTS GROSS BETA 2 25.00 4171.80( 1/ 1) PARM D 4171.80( 1/ 1) 4430:82( 1/ 1) 4171.80- 4171.80 2.5 MILES WSW 4171.80- 4171.80 4430.82- 4330.82 GlQSA (GELI) 2 K-40 NOT ESTAB 1750.00( 1/ 1) FARM D 1750.00( 1/ 1) 1440.00( 1/ 1) 1750.00- 1750.00 2.5 MILES WSW 1750.00- 1750.00 1440.00- 1440.00 BI-214 NOT ESTAB 11.22( 1/ 1) FARM D 11.22( 1/ 1) 17.88( 1/ 1) 11.22- 11.22 2.5 MILES WSW 11.22- 11.22 17.88- 17.88 PB-212 NOT ESTAB 4.78( 1/ 1) PARM D 4.78( 1/ 1) 6.06( 1/ 1) 4.78- 4.78 2.5 MILES WSW 4.78- 4.78 6.06- 6.06 PB-214 NOT ESTAB 10.25( 1/ 1) PARM D 10.25( 1/ 1) 14.60( 1/ 1) 10.25- 10.25 2 ~ 5 MILES WSW 10.25- 10.25 14.60- 14.'60

a. Nominal Lover Limit of Detection (LLD) as described in Table 3.
b. Mean and range based upon detectable measurements only. Fraction of detectable measurements of specified locations is indicated in parentheses (P).

35 Reser'voir Monitorin Samples are collected from the Tennessee River as detailed in table 18. Samples collected for radiological analysis include plankton from three of these cross sections and bottom fauna and sediment from four cross sections. The locations of these cross sections are shown on the accompanying map (figure 5) and conform to sediment ranges established and surveyed by the Data Services Branch, TVA.

Water ~

Water samples are collected automatically by sequential type sampling devices at thr'ee cross sections and composite samples analyzed monthly for gamma-emitting radionuclides. Further composites are made quarterly for strontium and tritium analyses. Sampling locations are shown in table 18. 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. During this reporting period, gross beta analyses were not performed on three of these grab samples and strontium analyses were not performed on five of

, them. Results are displayed in table 19.

Fish Radiological monitoring for fish is accomplished by analysis of composite samples of adult fish taken from each of three contiguous reser-voirs Wilson, Wheeler, and Guntersville. No permanent sampling stations have been established within'ach reservoir; this reflects the movement of fish species within reservoirs as determined by TVA data from the Browns Ferry Nuclear Plant preoperational monitoring program. Two species, white crappie and smallmouth buffalo, are collected representing both commercial and game species. Sufficient fish are collected in each reservoir to yield 250 to 300 grams oven-dry weight for analytical purposes. All samples are collected semiannually and analyzed for gamma-emitting radionuclides. The composite samples contain approximately the same quantity of flesh from each fish. For each composite a subsample of material is drawn for counting.

Results are given in tables 20, 21, and 22.

Plankton As indicated 'in table 18, net plankton (all phytoplankton and zooplankton caught with a 100 p mesh net) is collected for radiological analyses at each of three stations by vertical tows with a 1/2-meter net.

At least 50 grams (wet weight) of material is necessary for analytical

36 t

accuracy. Samples are collected semiannually and analyzed for gross beta activity, and when .quantities are sufficient, for gamma activity and Sr and Sr content. During this reporting period, two samples did not con-tain sufficient material .for gross beta analysis and none contained suffi-cient material for strontium or gamma analysis. Results are shown in table 23.

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

-semiannually in composite samples collected from each of four stations.

Locations of. these stations are shown in table 18. Results are shown in table 24.

Bottom Fauna The flesh,and shells of Asiatic clams collected semiannually from the cross emitting radionuclides. Levels of Sr and 'r sections at four. stations (table 18) are analyzed for gamma-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 25 and 26.

Table 18 SAMPLING SCHEDULE RESERVOIR MONITORING Biolo ical sam les collected semiannuall Zooplankton, chlorophyll, Benthic a Water samples River/river mile h to lankton fauna Sediment Fish

. (collected monthl Tennessee 277.98 X Tennessee 285.2 Tennessee 288.78 X Tennessee 291.76 Tennessee 293.5 Tennessee 293.70 (discharge area)

Tennessee 305.0 b-Tennessee 307. 52 Elk 20.5

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.

38 Figure 5 R ESERVOIR MONITORING NETWORK N

Elk River WHEELER DAIVI mile 274.90 mile 277.98 Rogersville 0

mile 29l.76 Athens mile 282.6 0

~mite 285.2 B.F. NUCLEAR PLANT Champion Paper Co, le 28878 mite 293.50 mile 305.0 Cour tland mile 295.70 0

Decatur rnite 307.52 Scale of Miles

~ - Automatic Sam ler

'6 TABLE 19 RADIOACTIVITY IN SURPACE WATER PCI/L 0.037 BQ/L NAME.OP FACILITY BROWNS PERRY DOCKET NO. RH-80-3-BF-2 LOCATION OF FACILITY LIMESTONE ALABAMA REPORTING PERIOD 1979 TYPE AND LOWER LIMIT ALL CONTROL NUMBER OF LOCATION WITH HIGHEST TOTAL NUMBER OP INDICATOR LOCATION) NONROUTINE OF ANALYSIS, DETECTION ACTIONS MEAN (g) NAME MEAN (F) MEAN (F$ REPORTED PERFORMED ~IID) RANGE DISTANCE AND DIRECTION RANGE MEASUREMENTS GROSS BETA 23 2.400 3,05( 10/ 12) TRM 293.7 2.97( 10/ 12) 4.56( 9/ 11) 2.41- 3.77 2.41- 3.77 2.41- 9. 11 GA%fA (NAI) 57 BA-140,LA-140 15.000 ANALYSIS PERFORMED 15.00( 1/ 23) 34 VALUES <LLD 15.00- 15.00 GAMMA (GELI)

K-40 NOT ESTAB 86.51( 3/ 5) TRM 293.7 97.89(, 1/ 1) 169.65( 2/ 3) 78.67- 97.89 97.89- 97.89 116.60- 222.70 BI-214 NOT ESTAB ~

20.52( 3/ 5) TRM 285.2 20.52( 3/ 4) 26:14( 2/ 3) 9.78- 36.74 9.78- 36.74 18.77- 33.50 PB-212 NOT ESTAB 6.82( 1/ 5) TRM 285.2 6.82( 1/ 4) 18.94( 1/ 3) 6.82- 6.82 6.82- ,6.82 18.94 18.94 PB-214 NOT ESTAB 17.54( 2/ 5) TRM 285.2 17.54( 2/ 4) 18.29( 2/ 3) 13.79- 21.29 13.79- 21.29 15.85- 20.73 SR-89 10.000 ANALYSIS PERFORMED 14 VALUES <LLD 33 19 VALUES <LLD SR-90 2.000 ANALYSIS PERFORMED 14 VALUES <LLD 33 19 VALUES <LLD TRITIUM 20 330.000 ANALYSIS PERFORMED 8 VALUES <LLD 12 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 of specified locations is indicated in parentheses (F).

TABLE 20 RADIOACTIVITY IN WHITE CRAPPIE PCI/G - 0.037 BQ/G (DRY WEIGHT)

-NAME OF FACILITY BROWNS PERRY DOCKET NO RH-80-3-BF-2 LOCATION OP PACILITY LIMESTONE ALABAMA REPORTING PERIOD 1979 TYPE AND LOWER LIMIT ALL CONTROL NUMBER OP TOTAL NUMBER OF INDICATOR LOCATION) NONROUTINE OF ANALYSIS DETECTIONa ACTIONS MEAN (g) NAME MEAN (F( MEAN (F( REPORTED PERFORMED LUl RANGE DISTANCE AND DIRECTION RANGE RANGE MEASUREKBiTS GROSS BETA

6. 0. 100 38.52( 4/ 4) WHEELER RESERVOIR 39.21( 2/ 2) 34.11( 2/ 2) 36.00- 42.42 TRM 275-349 36.00- 42.42 30.38- 37.83 GAMMA (GELI) 6 CS-137 0.020 0.12( 4/ 4) WHEELER RESERVOIR 0.13( 2/ 2) 0.20( 2/ 2) 0.07- 0. 18 TRM 275-349 0.07- 0.18 0.13- 0.28 K-40 NOT ESTAB 17.63( 4/ 4) WHEELER RESERVOIR 19.96( 2/ 2) 17.72( 2/ 2) 12.04- 20.82 TRM 275-349 19. 10~ 20.82 17 42-

~ 18.03 BI-214 0.020 0.15( 4/ 4) WHEELER RESERVOIR 0.16( 2/ 2) 0.23( 2/ 2) 0.05- 0.24 TRM 275-349 0. 10- 0.22 0.19- 0.28 PB-212 NOT ESTAB 0.03( 1/ 4) WHEELER RESERVOIR 0.03( 1/ 2) 0.11( 1/ 2) 0.03- 0.03 TRM 275-349 0.03- 0.03 0.11- 0.11 PB-214 NOT ESTAB 0.10( 4/ 4) WHEELER RESERVOIR 0.11( 2/ 2) 0.11( =2/ 2) 0.04- 0.16 TRM 275-349 0.06- 0.16 0.10- 0.11

a. Nominal Lover Limit of Detection (LLD) as described in Table 3.
b. Mean and range based upon detect'able measurements only. Fraction of detectable measurements of specified locations is indicated in parentheses (F).

TABLE 21 RADIOACTIVITY IN, SMALLMOUTH BUFFALO (FLESH)

PCI/G --0.037 BQ/G (DRY WEIGHT)

NAME OF PACILITY BROWNS FERRY DOCKET NO. RH-80-3-BP-2 LOCATION OF FACILITY LIMESTONE ALABAMA REPORTING PERIOD 1979 TYPE AND LOWER LIMIT ALL CONTROL . NUMBER OF LOCATION WITH HIGHEST ANNUAL MEAN TOTAL NUMBER'P OF INDICATOR LOC)TIONS LOCATION) NON ROUTINE ANALYSIS DETECTION MEAN (g) NAME MEAN (F$ MEAN (P( REPORTED PERFORMED ~IZJl DISTANCE AND DIRECTION MEASUREMENTS GROSS BETA 0. 100 35.00( 4/ 4) WHEELER RESERVOIR 36.52( 2/ 2) 61. 39 ( 2/ 2)

GA101A (GELI) 6 25.39- 41.56 TRM 275-349 33.92- 39.11 26.79- 96 '2 TL-208 6

NOT ESTAB ANALYSIS PERFORMED 4 VALUES <LLD 0.04(

0.03-2/ ')

0.05 CS-137 0.020 0.05( 4/ 4) WHEELER RESERVOIR 0.05( 2/ 2) O.DQ( 2/ 2) 0.04- 0.06 TRM 259-275 0.05- 0.06 0.09. 0.10 K-40 NOT ESTAB 13.20( 4/ 4) WHEELER RESERVOIR 16.51( 2/ 2) 11.84( 2/ 2) 9.28- 19.36 TRM 275-349 13.65- 19.36 11.22- 12.47 BI-214 0.020 3/ 4) '.23(

WHEELER RESERVOIR 0.23( 2/ 2) 0.20( 2/ 2) 0.14- 0.32 TRM 275-349 0.14- 0.32 0.22- 0.23 PB-212 NOT ESTAB 0.08( 2/ 4) WHFELER RESERVOIR 0.08( 2/ 2) 0.12( 1/ 2) 0.07- 0.08 TRM 275-349 0.07- 0.08 0.12- 0,12 PB-214 NOT ESTAB 0.11( 4/ 4) WHEELER RESERVOIR 0.14( 2/ 2) ,0.20( 2/ 2) 0.05- 0.16 TRM 275-349 0. 12- 0.16 0.15- 0.25

a. Nominal Lover Limit of Detection (LLD) as described in Table 3.-
b. Mean and range based upon detectable measurements only. Praction of detectable measurements of specified locations is indicated in parentheses (F).

TABLE 22 RADIOACTIVITY IN SMALLMDUTH BUFFALO (WHOLE)

PCI/G - 0.037 BO/G (DRY WEIGHT)

NAME OF FACILITY BROWNS FERRY DOCKET NO. RH-80-3-BF-2 LOCATION OF FACILITY LIMESTONE ALABAMA= REPORTING PERIOD 1979 TYPE AND LOWER LIMIT ALL CONTROL NUMBER OF LOCATION WITH HIGHEST ANNUAL MEAN TOTAL NUMBER . OF INDICATOR LOCATION) NONROUTINE OF ANALYSIS ACTIONS DETECTION MEAN ($ ) NAME MEAN MEAN (F) REPORTED

~llD (F$

~

PERFORHED RANGE DISTANCE AND DIRECTION MEASUREMENTS GROSS BETA 6 0..100 38,19( 4/ 14) WHEELER RESERVOIR 18.80( 2/ 2) 16.93( 2/ 2) 3.89- 30.23 TRM 275-349 7.36- 30.23 13.02- 20.84 GA101A(GELI) 6 CS-137 0.020 0.05( 1/ 4) WHEELER RESERVOIR 0.06( 1/ 2) 0.04( 2/ 2)

K-40 0.06- 0.06 TRM 275-349 0.06- 0.06 0 '4- 0.05 NOT ESTAB 8.96( 4/ 4) WHEELER RESERVOIR 10.85( 2/ 2) 8.37( 2/ 2) 6 13.86 TRM 275-349 7.84- 13.96 8.13- 8.61 BI-212 NOT ESTAB 0.25( 1/ 4) WILSON RESERVOIR 0.25( 1/ 2) 2 VALUES< LLD 0.25- 0.25 TRM 259-275 0.25- 0.25 BI-214 0.020 0.17( 4/ 4) WHEELER RESERVOIR 0.22( 2/ 2) 0. 16( 2/ 2) 0.06- 0.36 TRM 275-349 0.08- 0.36 0.10- 0.21 PB-212 NOT ESTAB 0.12( 4/ 4) WHEELER RESERVOIR 0.16( 2/ 2) 0.04( 2/ 2) 0.07- 0.24 TRM 275-349 0.08- 0.24 0.04- 0.04 PB-214 NOT ESTAB 0.12( 4/ 4) WHEELER, RESERVOIR 0.13( 2/ 2) 0.09( 2/ 2) 0.06- 0.21 TRM 275-349 0.06- 0.21 0.07- 0.11 AC-228 NOT ESTAB 0.08( 2/ 4) WHEELER RESERVOIR 0.10( 1/ 2) 2 VhLUES<LLD 0.07- 0. 10 TRM 275-349 0.10- . 0.10

a. Nominal Lower Limit of Detection (LLD) as described in Table 3.
b. Mean and range based upon detectable measurements only. Fraction of detectable measurements of specified locations is indicated in parentheses (F).

TABLE 23 RADIOACTIVITY IN PLANKTON PCI/G - 0.037 BQ/G (DRY WEIGHT)

NAME OF FACILITY BROWNS, FERRY DOCKET NO RH-80-3-BF>>2 LOCATION OF FACILITY LIMESTONE ALABAMA REPORTING PERIOD 1979 TYPE AND LOWER LIMIT ALL CONTROL NUMBER OF LOCATION WITH HIGHEST ANNUAL MEAN TOTAL NUMBER OF INDICATOR LOCATION) NONROUTINE LOCATIONS OF ANALYSIS DETECTION MEAN ($ ) NAME MEAN (F( MEAN (F) REPORTED PERFORMED ~IID RANGE DISTANCE AND DIRECTION RANGE MEASUREMENTS GROSS BETA 0. 100 28.39( 2/ 2) TRM 291.7 41.69( 1/ .1) 44.05 ( 2/ 2) 15.08- 41.69 41. 69- 41. 69 34.83- 53.77

a. Nominal Lover Limit of Detection (LLD) as described in Table 3.
b. Mean and range based upon detectable measurements only. Fraction of detectable measurements of specified locations is indicated in parentheses (F).

I

TABLE 24 RADIOACTIVITY IN SEDIMENT PCI/G 0.037 BQ/G (DRY WEIGHT)

NAME OP FACILITY BROWNS FERRY DOCKET NO. RH-80-3-BF-2 LOCATION OF PACILITY LIMESTONE ALABAMA REPORTING PERIOD 1979 TYPE AND LOWER LIMIT ALL CONTROL NUMBER OF IOCATION ITH H CHEST LOCATION) NONROU TINE TOTAL NUMBER OF OF ANALYSIS DETECTION MEAN (g) NAME MEAN (F$ MEAN (F( REPORTED PERFORMED ~IXB RANGE DISTANCE AND DIRECTION MEASUREMENTS GAMMA (GELI)

CO-60 0.010 O.ll( 4/ 6) TRM 288.78 0.12( 1/ 2) 2 VALUES <LLD 0.08- 0.12 0.12- 0.12 CS-137 0.020 1;87( 6/ 6) TRM 277.98 2.30( 2/ 2) 0.21( 2/ 2) 1.42- 2.40'/

2.20- 2.40 0.12- 0.29 K-40 0.250 15. 86( 6) TRM 288.78 16. 14( 2/ 2) 15.38( 2/ 2) 14.51- 17.10 15.18- 17.10 14 ~ 93- 15.83 TL-208 0.020 0.61( 6/ 6) TRM 277.98 0.65( 2/ 2) 0.53( 2/ 2) 0.56- 0.66 0.65- 0.66 0.47- 0.59 BI-212 0. 100 1.14( 6/ 6) TRM 293.70 1. 16( 2/ 2) 0.95( 2/ 2) 1.04- l. 24 l. 16- 1.17 0.89- 1.00 BI-214 0.020 1.58( 6/6) TRM 277.98 1.60( 2/ 2) 1.32( 2/ 2) 1.40- l. 72 1.50- 1.69 1.15- 1.48 PB-212 NOT ESTAB 1.90( 6/ 6) TRM 277.98 1.94( 2/ 2) 1.70( 2/ 2) 1 ~ 63- 2. 14 1.92- 1.96 1.44- l. 97 PB-214 0.050 1.64( 6/ 6) TRM 277.98 1.66( 2/ 2) 1.40( 2/ 2) 1.49- 1.83 1.49- 1.82 1.29- 1.51

a. Nominal Lower Limit of Detection (LLD) as described in Table 3.
b. Mean and range based upon detectable measurements only. Fraction of detectable measurements of specified locations is indicated in parentheses.(F).
c. The distribution of ~s Cs between indicator and control locations reported herein is comparable to the distribution reported in the preoperational monitoring program from 1968 to mid-1973.

TABLE 24 (CONTD)

RADIOACTIVITY IN SEDIMENT PCI/G - 0.037 BO/G (DRY WEIGHT)

NAME OF FACILITY BROWS FERRY DOCKET -NO. RH-80-3-BF-2 LOCATION OF PACILITY LIMESTONE ALABAMA REPORTING PERIOD 1979 TYPE AND LOWER LIMIT ALL CONTROL NUMBER OF TOTAL NUMBER LOCATION WITH HIGHEST ANNUAL MEAN OP INDICATOR LOC)TIONS LOCATION) NONROUTINE OF ANALYSIS DETECTION MEAN ($ ) NAME MEAN (F) MEAN (F( REPORTED PERFORMED (LLD) DISTANCE AND DIRECTION RANGE MEASUREMENTS RA-223 NOT ESTAB 0.60( 1/ 6) TRM 277.98 0.60( 1/ 2) 2 VALUES <LLD 0.60- 0.60 0.60- 0.60 RA-226 0.050 1.58( 6/ 6) . TRM 277.98 1.60( 2/ 2) 1.32( 2/ 2) 1.40- 1.72 1.50- 1.69 1.15- 1.48 AC-228 0.060 1 75( 6/ 6) TRM 277.98 1.83( 2/ 2) 1.56( 2/ 2) 1.60- 1.89 1.77- 1.89 1.40- 1.73 PA-228 NOT ESTAB 0.07( 1/ 6) TRM 288.78 0.07( 1/ 2) 2 VALUES< LLD 0.07- 0.07 0.07- 0.07 SR-89 1.500 ANALYSIS PERFORMED 6 VALUES <LLD 2 VALUES <LLD SR-90 0.300 0.37( 2/ .6) TRM 293.70 0.42( 1/ 2)- 2 VALUES <LLD 0.32- 0.42 0.42- 0. 42

a. Nominal Lower Limit of Detection (LLD) as described in Table 3.
b. Mean and range based upon detectable measurements only. Fraction of detectable measurements of specified locations is indicated in parentheses (P).

TABLE 25 RADIOACTIVITY IN CLAM FLESH PCI/G 0.037 Bg/G (DRY WEIGHT)

NAME OF FACILITY BROGANS FERRY DOCKET NO. RH-80-3-BF-2 LOCATION OF FACILITY LIMESTONE ALABAMA REPORTING PERIOD 1979 TYPE AND LONER LIMIT CONTROL NUMBER OF TOTAL NUMBER INDICATOR -ACTIONS MOTION MM HIGHEST NONROUTINE OF LOCATION)

OF ANALYSIS DETECTION MEAN ($ ) NAME MEAN (F) MEAN (F( REPORTED PERFORMED ~IID RANGE DISTANCE AND DIRECTION MEASUREMENTS GAMMA (GELI)

CS-137 0.080 0.33( 4/ 6) TRM 288.9 0.43( 2/ 2) 2 VALUES <LLD 0.11- 0.74 0.11- 0;74 K-40 NOT ESTAB 7.09( 6/ 6) TRM 277.9 8 '3( 2/ 2) 9 ~ 47( 2/ 2) 5.35- 8.07 7,.98- 8.07 8.75- 10. 19 BI-214 NOT ESTAB 1.24( 6/ 6) TRM 277 ~ 9 1.29( 2/ 2) 2.06( 2/ 2)

'0.77- 1.80 0.78- 1.80 0.88- 3.24 PB-212 NOT ESTAB 0.68( 6/ 6) TRM 288.9 0.70( 2/ 2) 0.58( 2/ 2) 0.54- 0.86 0.54- 0.86 0.57- 0.59 PB>>214 NOT ESTAB 1.19( 6/ 6) TRM 277.9 1.34( 2/ 2) 2.01( 2/ 2) 0.66- 1.90 0.79- 1.90 1.02- 3.00 AC-228 NOT =ESTAB 0.85( 4/ 6) TRM 293.7 1.06( 2/ 2) 1.09( 2/ 2) 0;40- 1. 38 0.74- 1. 38 0.97- 1.21 TL-208 NOT ESTAB 0.20( 3/ 6) TRM 293.7 0.22( 1/ 2) 0.30( 2/ 2) 0.16- 0.22 0.22- 0.=22 0.14= 0.46 I

a. Nominal Lover Limit of Detection (LUO as described in Table 3.
b. Mean and ranEe based upon detectable measurements only. Fraction of det'ectable. measurements of specified locations is indicated in parentheses (F).

"K-

TABLE 26 RADIOACTIVITY IN CLAM SHELL PCI/G 0.037 BQ/G (DRY WEIGHT)

NAME OF FACILITY BROWNS FERRY DOCKET NO. RH-80-3-BF-2 LOCATION OF FACILITY LIMESTONE ALABAMA REPORTING PERIOD 1979 TYPE AND LOWER LIMIT ALL CONTROL LOCATION WITH HIGHEST ANNUAL MEAN NUMBER OF TOTAL NUMBER OF INDICATOR LOCPIONS LOCATION) NONROUTINE OF ANALYSIS DETECTION MEAN ($ ) NAME MEAN (F)

PERFORMED ~LUl RANGE DISTANCE AND DIRECTION MEAN (F( REPORTED MEASUREMENTS GA10fA (GELI)

CO-60 0.010 0.03( 1/ 293.7 0.03(

TRM 1/ 6) 2 VALUES <LLD 0.03- 6)'.03 0.03- 0.03 CS-137 0.020 0.04( 6/ 6) 293.7 0.05( 2/ 2)

TRM 0.03( 1/ 2) 0.03- 0.05 0.04- 0.05 0.03- 0.03 K-40 0.250 0.59( 6/ 277.9 0.73( 2/ 2) 6)'.

TRM 0.75( 2/ 2) 0.47- 90 0.56- 0.90 0.66- 0.84 BI-212 0.100 0.32( 4/ 6) TRM 293.7 0.46( 2/ 2) 0.24( 1/ 2) 0.11- 0.47 0.45- 0.47 0.24- 0.24 BI-214 0.020 0.33( 6/ 6) 293.7 0.58( 2/ 2)

TRM 0.40( 2/ 2) 0.17- 0.66 0.51- 0.66 0 ~ 39- 0.41 PB-212 NOT ESTAB 0.37( 6/ 6) 293.7 0.64(

TRM 2/ 2) 0.36( 2/ 2) 0.16- 0.69 0.60- 0.69 0.31- 0.42 PB-214 0.050 0.34( 6/ 6) 293.7 0.59( 2/ 2)

TRM 0.41( 2/ 2) 0.18- 0.65 0.53- 0.65 .0.38- 0.'43 RA-226 NOT ESTAB 0.33( 6/ 6) 293.7 0.58(

TRM 2/ 2) 0.41( 1/ 2)

0. 17- 0.66 0.51- 0.66 0.41- 0.41 AC-228 0.060 0.43( 6/ 6) TRM 293.7 0.77 ( 2/ 2) 0.44 ( 2/ 2) 0.21- 0.78 0.77- 0.78 0.44- 0.45
a. Nominal Lover Limit of Detection (LLD) as described in Table 3.
b. Mean and range based upon detectable measurements only. Fraction of detectable measurements of specified locations is indicated in parentheses (F).

TABLE 26 (CONTD)

RADIOACTIVITY IN CLAM SHELL

. PCI/G - 0.037 BQ/G (DRY WEIGHT)

NAME OF FACILITY BROWNS PERRY DOCKET NO. RH-80-3-BF-2 LOCATION OF FACILITY LIMESTONE ALABAMA REPORTING PERIOD 1979 TYPE AND LOWER LIMIT CONTROL NUMBER OP LOCATION WITH HIGHEST ANNUAL MEAN TOTAL NUMBER OF INDICATOR LOCPIONS LOCATION) NONROUTINE OF ANALYSIS DETECTION MEAN (F( MEAN REPORTED PERFORMED ~llJl NAME DISTANCE AND DIRECTION RANGE (F$

MEASUREMENTS TL-208 0.020 0.12( 6/ 6) TRM 293.7 0.20( 2/ 2) 0. 13( 2/ 2) 0.06- . 0.21 0.20- 0.21 =-

0.12- 0.14 SR-89 5.000 ANALYSIS PERFORMED 8 6 VALUES ~LLD 2 VALUES <LLD SR-90 8 1.000 3. 91( 6/ 6) TRM 277.9 4.49 ( 2/ 2) 3.29( 2/ 2) 3.40- 4.52 4 '5- 4.52 2.52- 4.06

a. Nominal Lover Limit of Detection (LLD) as described in Table 3.
b. Mean and range based upon detectable measurements only. Fraction of detectable measurements of specified locations is indicated in parentheses (F).

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 the Browns Ferry Nuclear Plant are forwarded to these laboratories for analysis, and results are exchanged for comparison.

Data measured at the control stations for each medium were aver-aged for each sampling period. In order to describe the di.stribution of control station data, a mean, standard deviation, and 3-sigma value were calculated. We can expect, with 99 percent confidence, that background concentrations would be distributed within these limits. This provides us the basis for comparing control and indicator data. If the indicator data fall within the limits defined for control data, we can say, with 99 per-cent confidence, that the indicator data were not significantly affected by the nuclear plant. If the data do not fall within the 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 were found to be within the distribution defined by the control station data. The ALPHA-M least squares computer program identified concentrations slightly exceeding the limits of the control station data for a small number of radionuclides in samples from indicator stations. Many of these values may be discounted because the error reported by the ALPHA-M program was greater than the cal-culated concentration. The remaining isolated elevated concentrations may be the result of fallout, fluctuations in the existing environment, com-puter program artifacts, or analytical errors. The same type of isolated high values occurred in the control station data and may be attributed to the same sources.

Dose estimates were made from concentrations of radioactivity found in samples of environmental media. Media sampled include, but are not limited to, air, milk, meat, vegetation, drinking water, and fish.

Doses estimated for persons at the ind'icator locations were essentially identical to those determined for persons at control locations. Greater than 99 percent of those doses were contributed by the naturally occur-ring radionuclide potassium-40, and by strontium-90 and cesium-137 which are long-lived radioisotopes found in fallout from nuclear weapon testing.

It is concluded from the above analysis of the data that there were no signif1cant increases in environmental radioactivity attributable to the. operation of Browns Ferry Nuclear Plant.

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