ML18029A461
| ML18029A461 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 12/31/1980 |
| From: | TENNESSEE VALLEY AUTHORITY |
| To: | |
| References | |
| RH-81-5-BF2, NUDOCS 8504100206 | |
| Download: ML18029A461 (165) | |
Text
BETS- MASTER FILE REGUI ATOR Y INFORMATION DISTRIBUTION SYSTEM (RID L> V-80 ACCESSION NOR:8500100206, DOC.DATE: 80/12/31 NOTARIZED: NO ¹ FACIL:50-259 Browns Ferry Nuclear Power'tations Unit 1< Tennessee 05000259 50 260 Browns Ferry Nuclear Power Station~ Unit 2< Tennessee BYNAME 05000260 50 296 Browns Ferry Nuclear Power Stationi Unit 3, Tennessee 05000296 AUTH AUTHOR AfFIlIATION
SUBJECT:
"Environ Radioactivity Levels<Browns Ferry f4uclear Planti Annual Rept-1980 '
DISTRIBUTIo N CODE:. IE25L COPIES RECEIVED:LTR . FNCI ~' SIZE: 5 TITLE: Periodic Envir on Moni toring Rept (50 DKT -Annual/Semiannual/E fluent/
NOTES:NMSS/FCAF 1cy, icy Nr1SS/FCAF/PM, 05000?59 OL:06/26/73 NMSS/FCAF 1cy, 1cy NMSS/FCAF/PM'L:06/28/74
.05000260 NMSS/FCAF 1cy ~ '1cy NMSS/FCAF/PM, 05000296 OL:07/02/76 RECIPIENT COPIES RFCIP IENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR FNCL-NRR ORB2 BC OQ INTERNAL: ACRS 11= AEOD 1 IE'ILE Ol NRR/DE/EEB 08 1 N . AB 09 NRR/DS I/METH ?
N /DSI/R 10 RGN2/DRSS/EPRPB 1 RM/DDAMI/MID EXTERNAL: LPDR 03 NRC PDR 02 NOTES:
RH-81-5-BF2 TENNESSEE VALLEYAUTHORITY .
ENVIRONMENTAL RADIOACTIVITYLEVELS BROWNS FERRY NUCLEAR PLANT ANNUAL REPORT 1980 .
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'IVISIONOF OCCUPATIONALHEALTHAND SAFETY
RH-81-5-BF2 ENVIRONMENTAL RADIOACTIVITYLEVELS BROWNS FERRY NUCLEAR PLANT ANNUAL REPORT 1980 Apri1 1981
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CONTENTS List of Tables . ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ iii List of Figures. ~ ~ ~ ~ ~ ~ ~ ~ t ~ ~ ~ ~ ~ ~ ~ ~ ~ o iv Introduction 0 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 1 Atmospheric Monitoring . ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 11 Terrestrial Monitoring . ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 21 Reservoir Monitoring . ~ ~ ~ ~ ~ ~ ~ ~ ~ I ~ ~ ~ ~ ~ ~ ~ ~ 33
'uality Control. ~ ~ ~ ~ ~ ~ ~ ~ ~ 1 ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 45 Data Analysis. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 45 Conclusions. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ I ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 45
LIST OF'ABLES Table 1Environmental Radioactivity Sampling Schedule 4 Table 2Atmospheric and Terrestrial Monitoring Station Locations Browns Ferry Nuclear Plant Table 3- Detection Capabilities for Environmental Samp le Analysis ~ ~ ~ ~ ~ ~ ~ ~ 6 Table 4Results Obtained in Interlaboratory Comparison Program. 8 Table 5Maximum Permissible Concentrations for Nonoccupational Exposure 16 Table 6Radioactivity in Air Filter . 17 Table 7Radioactivity in Rainwater. 18 Table 8- Radioactivity in Heavy Particle Fallout 19 Table 9Radioactivity in Charcoal Filters 20 Table 10 Radioactivity in Milk . 23 Table llRadioactivity in Vegetation . 24 Table 12 Radioactivity in Soil 25 Table 13 Radioactivity in Well Water 26 Table 14- Radioactivity in Public Water Supply. 27 Table 15- Environmental Gamma Radiation Levels 28 Table 16 Radioactivity in Food Crops 29 Table 17 Radioactivity in Soybeans 31 Table 18- Radioactivity in Poultry 32 Table 19- Sampling Schedule Reservoir Monitoring 35 Table 20 Radioactivity in Surface Water 37 Table 21- Radioactivity in White Crappie (Flesh) . 38 Table 22- Radioactivity in Smallmouth Buffalo (Flesh) 39 Table 23 Radioactivity in Smallmouth Buffalo (Whole) 40 Table 24 Radioactivity in Sediment 41 Table 25- Radioactivity in Clam Flesh . 42 Table 26 Radioactivity in Clam Shell 43
LIST OF FIGURES Figure 1 Tennessee Valley Region . ~ ~ ~ ~ ~ 3 Figure 2 Atmospheric and Terrestrial Monitoring Network. . . . . . . . 13 Figure 3 - Local Monitoring Stations ~ ~ ~ 14 Figure 4 Browns Ferry Nuclear Plant Site Monitoring Stations . . . . . 15 Figure 5 Reservoir Monitoring Network. ~ ~ ~ ~ ~ 36
ENVIRONMENTAL RADIOACTIVITYLEVELS BROWNS FERRY NUCLEAR PLANT ANNUAL REPORT 1980 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. Ho~ever, a fire in the cable trays on March 22, 1975, forced the shutdown of both reactors. Units 1 and 2 resumed.
operation and Unit 3 began testing in August 1976. Unit 3 began commercial operation in January 1977.
The preoperational environmental monitoring program established a baseline of data on the distribution of natural and manmade radioactivity in the environment near the plant site. However, seasonal, yearly, and random variations in the data were observed. In order to determine the potential increases in environmental radioactivity levels .caused by. the plant, comparisons were made between data for indicator stations (those near the plant) and control stations (those remote from the plant) in con)unction with comparisons with preoperational data.
Staffs in the Division of Occupational Health and Safety, the
-Division of'ater Resources, and Resource Services, carried out the sampling program outlined in tables 1 and 19. Sampling locations are shown in figures 2, 3, 4, and 5, and table 2 describes the locations of the atmospheric and terrestrial monitoring stations. All the radiochemical and instrumental analyses were conducted in TVA's Western Area Radiological Laboratory (WARL) located at Muscle Shoals, Alabama and Eastern Area Radiological Laboratory (EARL) at Vonore, Tennessee. Alpha and beta analyses were performed on Beckman Low Beta II and Beckman Wide Beta II low background proportional counters. Nuclear Data (ND) Model 100 multichannel analyzer. systems employing sodium iodide NaI(T1) detectors and ND Model 4420 systems in con]unction with Germanium Ge(Li) detection systems were used to analyze'he samples for specific gamma-emitting radionuclides. Samples of water, vegetation, air particulates, food crops, and charcoal ('specific analysis for I) are routinely counted with NaI(T1) detection systems. If significant concentrations of radio-isotopes are identified, ox if the're is a reasonable expectation of
increased radioactivity levels (such as during periods of increased fallout), these samples are counted on the Ge(Li) system. Identifi-cation of gamma-emitting radionuclides in all other types of samples is routinely performed by analysis on the Ge(Li) system. A TVA fabricated beta-gamma coincidence counting system is utilized for the determination of I-131 concentrations in milk.
Data were entered in computer storage for processing specific to the analysis conducted. A computer, employing an ALPHA-M least squares code, using multimatrix techniques, was used to estimate the activities of the gamma-emitting nuclides analyzed by NaI(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 nomina1 lower limits of detection (LLD) are listed in Table 3. Samples processed by NaI(T1) gamma spectroscopy were analyzed for 1$ specific gamma-emitting radionuclides and radionuclide combina-tions ., For these analyses, radionuclide combinations such as and 95 Zr-Nb are analyzed as one radionuclide.
'u All photopeaks found in Ge(Li) spectra were identified and quantified. Many of the isotopes identified by Ge(Li) spectral analysis are naturally occurring or naturallv produced radioisotopes, such as "Be " K Bi "Bi) Pb 214 Pb<
226
~ Ra, etc. LLD's for the analysis of the radionuclides listed 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 listed in the data tables.
TVA's Radioanalytical Laboratories participate in the Environ-mental Radioactivity Laboratory Intercomparison Studies Program conducted by EPA-Las Vegas. This program provides periodic cross-check samples of the type and radionuclide composition normally analyzed in an environ-mental monitoring program. Routine sample handling and analysis pro-cedures were employed in the evaluation of these samples. Gamma spectral analyses were performed using NaI detectors. The EARL began processing samples in May 1980. The results received during calendar year 1980 are shown in table 4. The +3o limits based on one measurement were divided by the square root of 3 .to correct for triplicate determinations.
a The following radionuclides and radionuclide combinations are auantified by the ALPHA-. M least-squares computer code: 1"1'1""Ce; Cr; 3 I; 103~106Ru; 134Cs; 137Cs Zr-Nb; 58Co; "Mn'5Zn 60Co; 40K; and Ba-La.
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Table 1 ENVIRONMENTAL RADIOACTIVITY SAMPLINC SCHEDULE Air Charcoal Rain- Heavy Particle River Well Public Aquatic Life St tioo let ti e Filter tilter t r tello t Soil ~te t ti Milk W ter Steer W tr o d Sedi eet Sordo Muscle Shoals W W M Lavrenceburg W W, M H =
A RoEersville W W M M . A Athens W W M M '
Decatur W W' H A H Courtland W W H Site NW-I W W H Site N-2 Site NE-3 Site NW-4 W W M Site WSW-5 W W M M A Farm B W Farm Bi Farm H Farm T Farm L Control Farms Onsite Well Wheeler Dam Elk River Tennessee River Champion Paper Co.
Various Local Farms W - Weekly M - Monthly (every 4 Qeeks) Q-,Quarterly S-Semiannually A-Annually
Table 2 Atmospheric and Terrestrial Monitoring Station Locations Browns Ferry Nuclear Plant Approximate Distance and Sam le Station Direction irom Plant LM-1 BF, Northwest 1.0 Mile (1.6 kilometers) N LM-2 BF, North 0.9 Mile (1.4 kilometers) NNE LM-3 BP, Northeast 1.0 Mile (1.6 kilometers) NE LM-4 BF, Trailer Park 1.7 Miles (2.7 kilometers) NNW LM-5 BF, Davis Farm 2.5 Miles (4.0 kilometers) WSW PM-1 BF, Rogersville, AL 13.8 Miles (22.2 kilometers) NW PM-2 BF, Athens, AL .
10.9 Miles (17.5 kilometers) NE PM-3 BF, Decatur (Trinity), AL 8.2 Miles (13.2 kilometers) SSE PM-4 BF, Courtland, AL 10.5 Miles (16.9 kilometers) WSW RM-1 BP, Muscle Shoals, AL 32.0 Miles (51.5 kilometers) W (Control)
RM-2 BF, Lawrenceburg, TN 40.5 Miles (65.2 kilometers) NNW (Control)
Farm S 4.75 Miles (7.6 kilometers) .N Farm B 7.0 Miles (11.3 kilometers) NNW Farm H 3.75 Miles (6.0 kilometers) N Farm T ~
7.0 Miles (11.3 kilometers) ENE Farm Bi 4.5 Miles (7.2 kilometers) ENE Farm N (Control) 27.0 Miles (43.4 kilometers) NW Farm J (Control) 40.0 Miles (64.4 kilometers) NNW Farm C (Control) 32.0 Miles (51.5 kilometers) N Farm Ca (Control) 32.0 Miles (51.5 kilometers) W
Table 3 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS A. S ecific Anal ses NOMINAL LONER LIMIT OF DETECTION LLD
- Pish, Air Vegetation Soil and clam flesh, Foods, meat, plankton, shells poultry, Milk particulates
~Ci Charcoal
~C1 Fallout Ctl4P Mater
~Ct 1 and p~CI grain
~~dr Sediment
~i~Ci ~dr p~Ci/ ~dr Clam
~Ci ~~dr ~CI/k ~gt ~il Total u 0.4 0.01 1.5 Cross a 0. 005 2.0 0.05 0.35 0.1 0.7 Cross S 0. 01 0.05 2.4 0.20 0.70 0.1 0.7 25 330 I ill O. 02 5.0 0.5
~ sS 0.005 10 0.25 1.5 0.5 40 10 SOSr 0.001 2 0.05 0.3 0.1 1.0 B 2
- All LLD values for isotopic separations are calculated by the method developed by Pasternack and Harley as described in NASL-300.
Factors such as sample sire, 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 analysed within one week of the collection date. Conversion factors: 1 pCi 3.7 x 10 Bq; 1 mCi 3.7 x 10 Bq.
Table 3 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS B. Canna Anal ses NOMINAL LOWER LIMIT OF DETECTION LLD Air Water Vegetation Soil and Clam flesh Foods,(tomatoes Meat and particulates and milk and grain sediment Fish and plankton Clan shells potatoes, etc.) poultry
~Ct/o ~CL/L . NCL/LC ~dr ~CL/ dr ~ci/ ~dr ~CL/ d NCCL/ ddrr Ci/ wet k CCCL//k 'rrl:
NaI* ~Ce Li ** NaI ~Ce Li NaI ~Ce Li Nal ~Ce Li ll i ~CLL N i ~CLL NaI ~Ce Li NaI C~eLi Nal Ce(lil 1 Nr 1) 1 IIC s
1111 C
1Cr 0.03 0.07 0.02 0.03 38 60 33 44
- 0. 55 1.10 0.22 0.47 0.35 0.60 0.06 0.10
- 0. 35 0.60 0.06 0.10 0.35 0.56 0.35
- 0. 60 0.06 0.10 38 60 33'C 44 90 200 90 0.01 0.01 15 8. 0.35 0.09 0.20 0.02 0.20 0.02 0.07 0.20 0.02 15 8 50 20 101 ~ 10CR 0.65 0.45 0.45 0.45 40 0.04 40 150 106R 0.03 40 0.51 0.11 0.11 0.74. 0. 11 40 90 lSN 0.12 0.08 c 0. 01 0.02 10 26 0.20 0.33 0.12 0.08 0. 48 0.12 0.08 10 26 40 50 117C 0. 01 0.01 10 5 0.20 0.06 0.12 0.02 0.12 0.02 0.08 0.12 0.02 , 10 5 40 15 ssZr-Nb 0. 01 10 0. 20 0.12 0.12 0.12 10 40 ssz 0. 01 10 0.11 0.03 0.03 0. 15 0.03 10 20 s sNb 0. Ol 0.01 0.07 0.01
- 0. 01 5 0.05 5 15 "Co 0.02 0. 01 15 5 0.23 0.05 0.20 0. 01 0.20 0.01 0.07 0.20 0.01 15 5 55 15 0.02 0. 01 10 5 0.20 0.05 0.15 0.01 0.15 0.01 0.08 0.15 0.01 10 5 40 15 ssZn 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 coG 0.01 0.01 10 =
5 0.17 0.06 0.11 0.01 O.ll 0.01 0.08 O.ll 0.01 10 5 30 - 15
'0R 0.10 150 2.50 0.90 0.90 0.90 150 400 looBa-La 0.02 15 0. 68 0.15 0.15 0.15 15 50 1008 0.02 25 0.34 0.07 0.07 0.30 0.07 25 50 1 aoLa 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 Pasternack and Barley as described in HASL-300 and Nucl: Instr.'ethods 91 ~
533-40 (1971). These LLD values are expected to vary depending on che activities of the components in the samples. These figures do not represent the LLD values achievable on a given sample. Water is counted in a 3.5-L Marinelli beaker. Vegetation, fish, soil, and sediment are counted in a 1-pint container as dry veight. The average dry veight is 120 grams for vegetation and 400-500 grams for soi] sediment and fish. Meat and poultry are counted in a 1-pint container as dry veight, then corrected to vet veight using an average moisture content of 70X. Average dry veight is 250 grams. Air particulates are counted in a veil crystal. The counting system consists of a multichannel 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 program ALPHA-M. The assumption is made that all samples are analyzed vithin one veek of the collection, dace.
Water is counted in either a 0.5-L or 3 '-L Marinelli beaker. Solid samples such as soil, sediment, and clan shells are counced in a 0.5-I.
Marinelli beaker as dry weight. The average dry weight is 400-500 grams. Air filters and very small volume sanples are counted in pecrie dishes centered on the detector endcap. The counting syscen consists of a ND-4420 multichannel analyzer and either a 25XN 14X, 16X, or 29X Ce(Li) detector. The counting cine is normally 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. All spectral analysis is performed using the software provided with the ND-4420.
assumption is made that all samples are analyzed within one week of the collection date.
Conversion factor: ' pCi 3.7 x 10 Bq.
Table 4 Results Obtained in Interlaboratory Comparison Program A. Air Pilter (pCi/filter)
Gross Al ha Gross Beta Stontium-90 Cesium-137 EPA value TVA AVG. EPA value TVA AVG. EPA value TVA AVG. EPA value TVA AVG.
Date (+3o) WARL EARL (+3o) WARL EARL (+3o) WARL EARL (+3@) WARL EARL 12/79 10 + 9 10 29 + 9 33 9 2 2.6 , ll 10 + 9 l0 3/80 Equipment malfunction at EPA 6/80 24 + 10 26 25 28+ 9 33 36 8 2 2.6 9 8 12+9 13 12 9/80 24+ 9 24 24 10+ 9 12 16 0 0 <1 10+9 9 9 12/80 Results not received at this time B. Tritium in Urine (pCi/1)
Date EPA VALUE (+3a) TVA AVERAGE 12/79 2060 + 599 2100 3/80 2173 + 603 2300 6/80 2500 + 610 1437 2007 9/80 1700 + 589 1723 1693 12/80 3150 + 624 3287 3576
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Table 4 (Contd)
Results Obtained in Interlaboratory Comparison Pro&ram C. Radiochemical Analyses of Water (pCi/1)
Gross Al ha Gross Beta Strontium - 89 Strontium 90 Tritium Iodine - 131 EPA value TVA AVG. EPA value TVA AVG. EPA value TVA AVG. EPA value TVA AVG. EPA value TVA AVG. EPA value TVA AVG.
D te ~33a) WIIRL EARL ~435 IIARL EARL ~33a IIARL EARL ~(33a WARL EARL ~33a WARL EARL ~t3a IIARL EARL 11/79 12i9 14 2?i9 27 12/79 2040i599 2128 53i9 50 1/80 30i14 25 45i9 47 10i9 98 20i2.6 238 2/80 1?50i591 1920 3/80 13i9 12 22i9 25 4/80 3400i624 3363 44i9 41 5/80 6/80 23i9 23 20 14i9 16 1& 5i9 4 6 12i2.6 13 ll 2000i598 1947 1960 7/80 36i16 31 19 38i9 44 41
&/80 1210i570 1180 1223 36i9 9/80 32i14 34 27 21i9 26 24 24i9 27 23 15i2. 6 18 16 2J'1 10/80 3200i624 3207 3207 11/80 16i9 16 20 1349 16 24 12/80 2240i606 2270 2213 22i10 19 D. Gamma-Spectral Analysis of Water (pCi/1)
Chromium 51 Colbalt - 60 Zinc - 65 Ruthenium - 106 Cesium - 134 Cesium - 137 EPA value TVA AVG. EPA value TVA AVG. EPA value TVA AVG. EPA value TVA AVG. EPA value TVA AVG. EPA value TVA AVG.
Date ~33a WARL MIL ~(333 WARL EARL ~a3a WARL EARL ~k3a) WA)IL EARL ~a3a IIARL EARL ~a3a WARL EARL 2/80 6/80 101+9 13i9 93 0
lli9 5i9 ll 5 25i9 23i9 31 25 21 51i9 3?i9 33 40 loi9 lli9 16 15 10 30i9 17i9 31 19 18 0 7 36k 10/80 86i9 74 90 16i5 14 15 25i9 24 20 46i9 35 42 20i9 22 19 12i9 12 13
Table 4 (Contd)
Results Obtained in Interlaboratory Comparison Progrbm E. Milk (pCi/1)
Strontium - 89 Strontium 90 Iodine - 131 Cesium - 137 Barium - 140 Potassium EPA value TVA AVG. EPA value TVA AVG. EPA value TVA AVG. EPA value TVA AVG. EPA value TVA AVG. EPA value TVA AVG.
a ee ~(i3a IIARL EARL ~t3a WARL EARL ~33 IIARL EARL ~33 a MARL EARL ~33 a MARL EARL ~33 a wARL EARL 1/80 4/80 10i9 1019 ll '512.6 10 1512.6 28 18
- 0. Oii0.2 33x9 23 0 40i9 28i9 39 30 0.0110.2 0
0 0
16001139 11901103 1577 1117.
7/80 55+9 57 59 1712. 6 19 18 0 0 0 3519 34 35 0 0 0 15501135 1593 1533 10/80 23i9 25 25 : 0 1 <2 igf9 18 12 2149 22 22 0 0 <15 16201140 1447 1473 F. Foods (pCi/kg, Net Weight) 11/79 7319 71 27i2. 6 34P 127ill 127 2219 24 0.001 0 15111132 1372 3/80 Sample spoiled in transit 7/80 94t9 113P 107P 13i2.6 22P 17P 5419 47 49 2719 27 27 0 0 0 2260+225 2737 2730 11/80 819 <10 <10 0 3 3 34110 24 24 1219 ll 10 0 <15 <25 2520+208 2560 2723
- a. Western Area Radiological Laboratory, Muscle Shoals, Alabama.
- b. Eastern Area Radiological Laboratory, Vonore, Tennessee.
- c. Not reported to EPA.
- d. Low value result of deficiencies in analytical procedure.. The procedure has been revised to correct these deficiencies.
- e. I Specific analysis for 3 to test the procedures used for the analysis of ~ I in milk.
- f. Results not returned by EPA.
- g. 9Sr and Sr results reversed in report to EPA.
- h. Laboratory in start up mode: procedures being refined.
- i. Investigation of the sample and procedures produced no indication for the cause of the discrepancy. Subsequent analyses have been satisfactory.
- k. Analysis of these isotopes by NaI produce greater variation because of (1) the abundance of the main energy peaks (2) the broad shape of the peak, (3) relatively high background in the peak area, and (4) interference from radon peaks in the peak area.
- p. Discrepancies in strontium values are believed to be due to (1) inhomogeneity of the sample ash and (2) magnification of 'slight errors in weight conversions. Efforts are being made to reduce the impacts of these variables.
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 & 4). Four perimeter air mbnitors 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. Zn series 3
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 radiati'on levels at each remote and perimeter station.
Each"'of the local air monitors is fitted with a GM tube that con-tinuously scans the particulate filter. The disintegration rate of the atmospheric radioactivity is continuously recorded at each station and radio-telemetered into the plant.
Air filters are collected weekly and analyzed for gross beta activ-ity. No analyses are performed until three days after sample collection.
The samples are composited monthly for analysis of specific gamma-emitting 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.
With reference to table 5, which contains the maximum permissible concentrations (MPC) recommended by 10 CFR 20 for nonoccupationa1. exposure, it is seen that the maximum beta concentration in air is 0.12 percent MPC.
Rainwater is. collected monthly and a 3.5-liter'ample analyzed for specific gamma-emitting radioisotopes and tritium. The results are shown in table 7. During this period one sample was not obtained because of insufficient rainfall.
The gummed acetate that is used to collect heavy particle fallout is changed monthly. During this reporting period, two samples were damaged to the extent that insufficient material remained for analysis; The samples are ashed and counted for gross beta activity. The results are given in table 8.
12 Charcoal filters are collected and analyzed for radioiodine.
The filter is counted in a single channel analyzer system. The data are shown in table 9, where the highest value reported is 0.06 percent MPC in air for I.
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13 Figure 2 ATMOSPHERIC AND TERRESTRIAL MONITORING NETWORK RM.2BF LAWRENCEBURG yPULASKI FAYETTEVILLE ~
WILSON PM-IBF WHEELER ROBE SVIL FLORKNCK OAM ATHENS PM-2BF FFIEL MUSCLE SHOALS BROWNS F RRY HUNTSVILLE RM IBF NUCLEAR PL NT LEIGHTON TU SCUM BIA COURTLANO PM-4 F OECAT PM-38F0 IO MILES pRUSSELLVILLK GUN 7 SV IL HARTSKLLE OAM 4
2S HALEYVILLE
~CULLMAN 45 MILES 0- ENVIRONMENTAL MONITOIlINO STATION NOTE< THE FOLLOWING SAMPLES ARE COLLECTED FROM EACH STATION:
AIR PARTICULATES RAINWATER RADIOIODINE SOIL HEAVY PARTJCLE FALLOUT
LOCAL MONITORING STATIONS BROWNS FERRY NUCLEAR PLANT ATHENS US HWY 72 BFN ALA. HWY 20 Legend 0 Air Monitor DECATUR I Air Monitor 8 TLD Station b, . TLD Station A Automatic Well Sampler Scale Dairy Farm 0 I 2 3 0 5 H
IMiles
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.'16 Table 5 MAXIMUM PERMISSABLE CONCENTRATIONS FOR NONOCCUPATIONAL EXPOSURE In Water In Air
~C1/1* ~C1 m
- Alpha 30 Nonvolatile beta 3,000 100 TritiUIQ 3,000,000 200,000 1 37Cs 20,000 500 103>106RII 1,0,000 200 1 44Ce 10,000 200 95Zr-95Nb 60,000 1,000 140Ba-140La 20,000 1,000 131I 300 100 Zn 1000000 2,000
'4Mn 100,000 1,000 60C 30,000 300 "Sr 3,000 300 90Sr 300 30 "Cr 2,000,000 80,000 1'3 4( 9,000 400 58Co 90,000 2,000
- 1 pCi = 3.7 x 10 3 Bq.
TABLE 6 RAOIOACTIlfITY IN AIR FILTER PCI/H(3) 0 '37 BQ/H(3)
NAHE OF FACILITY hht)MBS'EBBY LOCATION OF FAC IL ITY LIMESIOUE - AL484)(4 DOCKET'NO 50m25)I*240a'K%.
REPORTING PERIOD LRBG TYPE AND LOKER LIMIT ALL CONTROL NUNBER OF TOTAL NUNBER OF INDICATOR LOCATIONS LAC4ZIO(t MIIU UIGhlESI 4(t(tllAL-HE4M - LOCATIONS NONROUTINE OF ANALYSIS DETECTION a HEAN tF) b NAHE NEAN (F)b HEAN (F)b REPOR~ED EEBEOBBEO LLLQI &ANGE b DISI4((CE 4((0 ()IEE(iIIGU R4((GE b B45GE" HEASUREHEBIS GROSS ALPHA 0 F 005 0 ~ Olt 2/ 52) 52 0 ~ 01>> 0 ~ 01 BETA 0.010 Oe03( 466/ 468) LH5 BF DAVIS F 0 F 04( 52/ 52) 0.03( 104/
'9LO4)
GROSS (NAI) 572 0 F 01 0 '2 R ~ 5 HILES MSM Oe01>> 0 '2 0 F 01>> 0 GAHNA C5 134 ill 0 ~ 010 0 'lt 1/ 90) LH2 BF NORTH 0 ~ 01( 1/ 9) Rl VALUES <LLD 0,01 ' '1 0 ~ 9 HILE NNE Oo01 0 ~ 01 I>>131 BE 7 0 ~ 010 NOT ESTAB 0 '!
Oe01(
Oo06(
10/ 90)
BR/
0 ~ OR 90)
LNZ SF NORTH 0 ~ 9 HILE NNE LH4 BF TRAILER P D'OR(
0,0'1>>
Oe08(
3/
Oo02 9/,
9) 11) 0 ~ 01(
Oe01>>
0 ~ 06(
2/
0,02, 20/ 21) 21) 0.02- 0,11 LoV HILES NNM Oe05>> Oel0 0 '2>> 0 ~ 10 GAHNA t CEL I )
32 103 0 ~ 01( 6/ RT) ATHENS'L 0 ~ Ol( 1/ 3)
RU RR 95 NOT ESTAB 0 F 010 0 ~ Ol Oo02(
0 ~ 01 3/ RT) 10e9 HILES LH5 BF DAVIS F NE 0 'l>>
Oe02(
Oe01 1/ 3) 5 VALUES <LLD 0 F 01( 1/ 5) 0 F 01 0 ~ DR 2 5 HILES MSK OeOR>> Oe02 0 F 01 Oe01 NB>>95 0 ~ 010 0 ~ 01(
OoOl 6/ RT)
Oe02 DECATUR'L 8~2 HILES SSE 0
0
'2(
'2>>
1/
Oe02
- 2) Oo01(
Oe 01>>
1/
0 ~ 01 5)
K>>40 NOT ESTAB 0 '4(
0 ~ 08-18/ 27) 0 ~ 18 LN1 BF NORTHKEST loO HILE N 0 ~ 16(
0 ~ 14 2/ 2)
Oy 18 Dell(
0 ~ OS>>
3/
0 ~ 1R 5) 81 214 0 '20 Oo04 ( Rl/ 27) LH3 BF NORTHEAST 0'o 05( 2/ 3) Oe06( 4/ 5)
PB 214 0 '20 0 '2 Oe04(
0 '7 14/ 27) 1 ~ 0 NILE NE ATHENS'L 0 F 04>>
0 '5( 0 R/
'6 3) 0 F 03>>
0 F 05]
OeOS 3/ 5) 0 F 02>> 0 ')7 10e9 HILES NE 0 '3>> Oc07 0 F 05 0 '6.
Pb 212 NOT ESTAb 0 F 02( 13/ R7) COURTLANOi AL 0 03( R/ 4) 2/ 5)
OeOg 0 '3 10 ~ 5 HlLES KSM
~
0 '3>> 0 '3 OeOR(
0 F 02>> OeOR 0.050 13/ 27) Doll( 1/ 3) 3/
'6 5)
BE-V OoOV( LH5 BF DAVIS F Oo05(
TL-208 NOT ESTAB 0 F 05-0 ~ Ol(
0 ~ 11 5/ RV) 2e5 HILES KS)t COURTLANOi AL Dell>>
O.OL(
Oo 1/
ll 0 F 05>>
5 VALUES <LLD 0
0 ~ Ol- 0 ~ Ol 10e5 HILES KSM 0 ~ Ol>> 0 F 01 AC 228 NOT ESTAB 0 '2(
0 '2 L/ RT) 0 ~ OR LNR BF NORTH 0 ~ 9 HILE NNE Oe02(
Oo02>>
1/
Oe02
- 4) 5 VALUES <LLD SR 89 0.005 )6 V4LUES <LLO 8 VALUES <LLD 44 ANALYSIS PERFORNED SR 90 0.001 16 VALUES <LLO 8 VALUES <LLO 44 ANALYSIS PERFORHED a., Nominal Lover Limit of Detection (LLD) as described in Table 3.
b, "Mean and ran8e based upon detectable measurements only. Fraction of detectable measurements of specified locations is indicated in parenthesis (P).
TABLE 7 l
RADIOACT VITY IN RAINHATKR PCl/L 0 '37 SQ/L NAME OF FACILITY BROHUS KERRY DOCKET NO ~ 5Oe25Ra200c U5 LOCATION OF FAC IL ITYLmlHKSZ09E ALABABA REPORTING PER100 1%SO TYPE AND LOHER LIMIT ALL NUHBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LQCAZIOU HIIU UIG)(ESI A((HllAL ((EAU LOCATIONS NONROUTINE OF ANALYSIS DETECT ION a MEAN (F)b NAME RA((GE'ONTROL HEAN (F)b MEAN (F)b REPORTED REREORHEO lLLDX RANDR3 DISIAHCK AND QXBECZIOH RAUGKn HKASURKHEUIS GAHMA (NAI) 134 1~131 le 000 38e70( 1/
'0ill) ATMENSJ AL 38 '0( 1/ 13) 15e40( 1/ 23)
BE 7 NOT ESTAB 38e70 4le2l(
38 71/ lll) 10 ~ 9 MILKS NE ROGERSVILLEi AL 34e70~
52 '0(
38e70 9/ ll) 15 '0.
37 51(
~
15 '0 10/ 23) 2.60- 101 40
~ 13 ~ 8 HILES NH 16e80a 101e 40 13.80- 65.90 GAMMA (GELI) 8 K%40 NOT ESTAB 7'5(
76e95
- 4) DECATUR'L 8 ~ 2 Hl( ES SSK 76 '5(
76 ~
1/
76 ~ 95
- 1) 2 VALUES <L(.0 81 214 NOT ESTAB 21 e6( 2/ 0) COURTLANDi AL 95'2e00(
1/ 15 ~ 41( 2/ L 2) 21e24 22 F 00 10 ~ 5 MILES HSH 22e00~ 22000 lle77~ 19e05-1/ 0)
'7VALUES1/<LLD PS~214 NOT ESTAB Te73( 7e'73 1/ Be67(
PB 212 NOT ESTAB 7 '3%
17e91(
7 '3 2/ 6)
COURTLANDi AL 10 ~ 5 MILKS HS'H LHl SF NORTHHEST Te73+
19e51(
(
1/
7e73 1)
- 2) 2 8 8 '7 2)
)6 ~ 30 19 ~ 51 le0 HILE N 19 ~ 51m 19e51 BE 7 NOT ESTAB 347 ~ 50( 1/ 6) ROGERSVILLEr AL 347e50j 1/ 2) 2 VALUES <LLO 330 F 000 347 '0<<
426 F 54(
347 '0 4/ 117) 13.8 MILKS NH ATHENS'L 347 '0e
'8(
347 '0 TRITIUM 142 332 ~ 12 643.26 10 ~ 9 HILES NK 550 550 '8i 5501/ '813) 25 VALUES <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 of specified locations is indicated in parenthesis (F).
TABLE B RADIOACTIVITY IN HEAVY PARTICLE FALLOU'T HCl/KH(2) 37000000 ~ 00 BQ/KHIR)
NAME OF FACILITY BRQNUS EEBLX-LOCATION OF FACILITY LIUESIOUE AL46484 DOCKET NO'Qmtj8i?AQa.296 REPORTING PERIOb IRBQ TYPE AND LOMER LIHIT ALL CONTROL NUMBER OF TOTAL NUMBER OF INDICATOR L5CATIONS LOCAZIOU WIIU UIGUESI AUUMAL UEAU NONROUT INE OF ANALYSIS DETECT ION a MBAN (F)b b ww NAHE MEAN ([) ~ LOCATIONS MEAN (~) REPORTED
-EBBEOBUEO LLLOI w w w OISIAhtCE ANO QZREGZIOU B4HGE BADGE HEASUBEHEBXS GROSS BETA 0.050 0 ARRANGE
'6(
'6- 115/ 115) LH% bF TRAILER P 0 ~ 39( 13/ 13) 0 '2( Rb/ 20) 141 0 F 07 1 ~ 7 HILES NNM 0 ~ 09~ 0 ~ 94 0 '6 Oeb5
- 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 parenthesis (F).
TABLE 9 RADIOACTIVITY IN CHARCOAL F1LTERS PCI/H(3) Oo037 80/H(3)
NAHE OF FACILITY;RRQKUS EERRX POCKET NO ~ 8Qe289a28Qa V5 LOCATION OF FAC IL ITY LIHESXOHR ALA84))4 REPORTIt G PERIOO 188O TYPE ANO LOKER L )HIT AiL CONTROL NUHBER OF TOTAL NUHBER OF INOICATOR LOCATIONS LOCAIIOU MIIU UIGUESI A((UUAL ()E48-- LOCATIONS NONROUTINE OF ANALYSIS OETBCT ION a HkAH (F)b NAHE HEAN (F)b HEAN (F)b REPORTED eEREOBUEO . ILLOl RANGE b OISIAI(CE 4((O OZRECILOU 848GE b RA((GE b BEASUREUEUIS 100INE IN AIR 572 0+020 0 '3(
Oe02-i8/ 468) 0 F 08 ROGERSVILLEi AL 13oB HlLES NM 0 '3(
0 02~
~
9/ 51)
Oo06 0.03(
Oe02~
10/ 10~)
0 '5
- 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 parenthesis (F) ~
Terrestrial Monitoxin Mi1k 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 result:s are shown in table 10.
Cow censuses were conducted in May and September 1980. 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 axe 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 (5 cm) of soil. These samples axe analyzed for gamma-emitting radionuclides and Sr and Sr. The results are given in t:able 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 composit:ed quarterly for determination of tritium. A grab sample is also taken from a control well up-gradient from the plant. The results of the analysis of well water are shown in table 13.
Drinkin Wat:er Potable water supplies taken from the Tennessee River in the vicinity of Browns Ferry Nuclear Plant are sampled and analyzed for gross
22 beta and gamma-emitting"radionuclides, and composited quarterly for tritium 89 Sr, and 90 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 sampling. Table 14 indicates the results from the analysis of drinking water samples. The maximum beta concentration is. 0.40 percent MPC.
Environmental Gamma Radiation Levels Bulb-type Victoreen Manganese-activated Calcium Floride (CaFg. Mn) 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 dosimeters, in energy compensating shields to correct energy dependence, are placed at approximately one meter above the ground, with three TLD's at each station. They are annealed and read with a Victoreen model 2810 TLD reader. The values are corrected for gamma response, self-irradiation, and fading, with individual gamma response calibrations and self-irradiation factors determined for each TLD. The TLD's are exchanged every 3 months.
The quarterly gamma radiation levels determined from these TLD's are given in table 15, which indicates that average levels at onsite stations are approximately 2 mR/quarter higher than levels at.offsite stations.
This is consistent with'evels 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. This may be attributable to natural variations in environmental radiation levels, earth moving activities onsite, the mass of concrete employed in the
.construction of the plants, or other undetermined influences.
Poult and Pood Cro s Pood crops and poultry raised in the vicinity of BPN and at control. locations axe sampled as they become available during the growing season, and analyzed for gamma-emitting radionuclides. During this sampling period samples of cabbage, corn, green beans, peaches, potatoes, tomatoes, soybeans, and poultry were collected and analyzed for specific gamma-emitting radionuclides. No sample of soybeans was taken from a control location.'he results are given in tables 16, 17, and 18.
TABLE 10 RADIOACTIVITY IN NILK PCI/l, - Oe037 BO/L NAHE.OF FACILITYBBQM((S EERILY DOCKET NO. Sa'RSBa24O.WS LOCATION Ol FAC ILITY'IHESIO)(E ALABAI(AREPORTING PERIOD 1BBO LOMER LIHIT
'EAN (P) --
TYPE AND ALL CONTROL MUNBER OP TOTAL NUHBER OF INOICATOA,LOCATIONS LQCAIIOI( )(IIU BIG'HESZ At(t(L)AL t)E48 LOCATION/ NONROUT I NE OP ANALYSIS DETECTION MEAN.,(F)b NANE b MEAN (F) REPORTED BEBEOB()EO CLLOI RANGE>>b >> >>>>>> OISIAI(CE At(O t)IBECIIOU BAI(GEb BAI(GEb BEASUBEBEHIS-GANHA (NAI) 109 i CS 137'>>40 10 ~ 000 II 10 '0
~ 38 I 4/ 59) 12 'O SNITH FAAH 4 75 NILES N lle95(
11 ~ 10>>
2/
lR ~ 80 1R) 10 '0(
10 F 60>>
1/
10eb0 50) 150 000 1241e93( 59/ 59) SHITH FARM 1302 'Tt 12/ 1R). 1229e93( 50/ 50)
IODIHE IN HILK 0 ~ 500 109Re70
'O(
1404,40 4/ 259) 4e75 HILES N 1129 e00>> 1404 0 '9t
'0 3/ 50) 1087 ~ 50 1371 ~ 00 2/ 201) 0 BROOKS . Oe54(
0 '9>>
FARN"'e0 460 Oe55 le lb MILES NN)t lelb De50>> Oe41 GANHA (GELI)
B i K<<40 NOT ESTAB 1543e00( 4/ 4) SNITH FARH 1442e00( Rl .R) 147be50( 2/ 2) l3OR.Oo- 175R.00 4e75 HILES N 1579 F 00>> 1705 F 00 1450e00<< 1503e00 BI-Rli NOT ESTAB Bb bit 5/ 4) THRASHER FARM 34.45( 1/ 20e04( 2/ 2) 24 62 34 ~ 45 Te0 NILES ENE 36.i5>> 3de45 17eb2>> 22eR5 PB 214 NOT ESTAB 24 14
'2(
'4 3/
34 '7 4) SNITH FARN 4 ~ T5 MILES N 34eiT t 36e47>>
1/
96 F 47 R) 15 ~ Bl(
15 '4>> Rl lbe57 2)
PE 212 NOT ESTAB Ib ~ 3b( 2/ 4) BITTING FARH 23e95t 1/ 2) 2 VALUES <LLD BE B) R3 ~ 95 4 ~ 5 HILES ENE 23e95 23e95 SR 69 10 F 000 $ 5 VALVES <LLO 53 VALUES CLLD 118 ANALYSIS ~ ERFORHEO SR 90 lib RE 000 4e R'e04 ll( bR/
9 'b45) BAOOKS FARN Te0 HILES NNM 5ei3(
3e34>>
12/
9 'B12) 5 2
'1(
'4>>
43/
9eb9 53)
- a. Nominal Lover Limit of Detection-(ILD) ss described in Table 3.
- b. Mean and range based upon detectable measurements only. Fraction of detectable measurements of specified locations is indicated in parenthesis (F).
TABLE ll RADIOACTIVITY IN VEGETATION PCI/G >> 0 '37 BQ/G (ORY HEIGHT)
NAME OF FACILITY BRQldUS KERRY DOCKET NO ~ SQmRSRg.26Qa 29 LOCATION OF FACILITY LIUESIOUE REPORTING PERIOD LRBQ TYPE AND LOHER L )HIT AiL CONTROL NUHBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCOIIOU MIIU>>UIGUESIOUUUOL UEOU LOCATIONS NONROUTINE OF ANALYSIS DETECTION a MEAN (F)b NAHE MEAN (F)b HEAN (F)b REPORTED BFREORUEQ CLLQI BOUGE>>b >> QISIOUCE 4UQ QIRECIIOU ROUGEb ROUGKb------
GROSS BETA 0.200 23 '6( 20/
~
- 20) THRASHER FARM 31 ~ 14( 4/ 4) 57t 16/
UEASUREUEUIS GAMMA 36 (GELI) 7e54- 50 '2 7 ~ 0 HILES ENK 16 36 40 ~ 68 18 ~
5e47>> 44 '216) 36 CE 144 0 ~ 220 Oe40( 2/ Ro) LOONEY FARM '4( 1/ 0 ~ 38'( 2/
BA 140 0 ~ 340
.Oe36 20 VALUES (LLO Oe44 5 ~ 75 HILES ENE 0
0 F 44>> 0 '4 4) Oo25, Oo59( 1/
0 ~ 50 16) 16) oe59>> Oe59 LA 140 0 F 080 Oe Oe 10(
la-1/ Ro) 0 ~ 10 THRASHER FARH 7 ' HILES ENE Oolo(
0 ~ 10>>
1/
0 ~ 10
- 4) 0 '2(
0.42.
1/
Oe42 16)
RU 103 0 '00 0,38( 5/ Ro) LOONEY FARH Oe65t 1/ 4) o.35'( 4/
13'7 0 '60 Oe21 Ool)t 0 '5 6/ 2D) 5,75 HILKS ENE 'Oe65>> oeb5 0 ~ 24. Oe50 16)
CS LOONEY FARM 0~ lb( 1/ 4) 6/ Lb)
ZR 95 0.110 0 F 07 Oe44( 5/
0 ~ 17 20) 5 '5 HILKS ENE 0,16 Oolb 0 ~ 12(
Oe08>> 0,16 LOONEY FARH Oe96( 1/ 4) 4/ 16)
Oe22<< Oe96 5 '5 HILES ENE Oo96>> 0 ~ 96 Oe48(
Oe27>> Oeb8 NB 95 0 ~ 050 0 F 54(
0 ~ 27 5/
1ooo
- 20) LOONEY FARH 5 '5 HILKS ENE l coo(
looo>>
1/
Leoo
- 4) 0 '9(
Oo31>>
4/ 16)
K>>40 NOT ESTAB 12 '4( 20/ 20) THRASHER FARH 17e77( 4/ 4) 9e29( 15/
0 ~ 84 16) 81<<214 0.100 Le37 0 ~ 28(
27ebo 17/ 20) 7 ' HILES ENE LOONEY FARH be51>>
0 ~ 34(
27ebo 4/ 4) 3,12 Oe29(
22 '9 12/ 16)
PB 214 NOT ESTAB 0 ~ 11 0 F 53 5o75 HILKS ENE Oe ll>> Oe53 Oe 10 Oo49 Oe23( LB/ 20) LOONEY FARM Oe26( 3/ 4) Oe24( 13/ lb)
PB 212 NOT ESTAB 0 F 08 Ool5t 0 ~ 41 15/ 20) 5o75 HILKS ENE LOONEY FARH Ool2>>
Oo23(
Oo34 2/ 4)
Oo12>>
oo 13(
0 '7 12/ 16)
BE 7 NOT ESTAB Ooob 7e69(
0 ~ 81 o,33 20/ 20)
R9e 11 5 ~ 75 MILES ENE BITTlNG FARH 4 ~ 5 HILES ENE 10 Oe
'lt Oe13>>
81>>-
4/
29 0 F 33
'l 4) 0 F 07>>
9e43(
2e13>>
16/
26 0 ~ R4
'7 16)
TL>>208 NOT ESTAB Oe07( 6/ 20) LOONEY FARH OeoBt 2/ Oeob( 8/ 16)
Oe03 Oe12 5.75 MILKS ENE Oe03 Oe12 Oe04>> Oolo AC-228 NOT ESTAB 0 '4( 10/ 20) LOONEY FARH Oe54( 3/ 4) 0 ~ 25( 7/ 16)
Oe 14<< 0 ~ 57 5 ~ 75 MILES ENE oe50>> Oo57 oe12>> 0 ~ 34.
- 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 parenthesis (P).
TABLE 12 RADIOACTIVITY IN SOIL PCI/G ~ 0 ~ 037 SQ/G lORY HEIGHT)
N4ME OF F4CILITY BRQL(US EERBY - DOCKET ND SOm2%Ra26Qa286 LOCATION OF FAClLITYLIBESID9E 4L4B454 REPORTING PERIOD 1RSQ TYPE AND LONER LIMIT ALL, CONTROL NUHBER 0F TOTAL NUHBER OF ANALYSIS OF DETCCT I()N a INDICATOR LOCATIONS MEAN (F)b LOCAIIO(( )t(IXU UIGL(EST 48(LUAL NAME L(EAU MEAN (F)
<- LOCATIONS HEAN (F)b NQNRQUTINE REPORTED EEREQeZEO CLLQl R4NQEP QISIAUCE AUQ OIRECZIQ(( RA((GE BA((GEb L(EASUREL(EUZS GAHMA (GEL I CS-137 ll
)
0 '20 ~
0 ~ 41( 9/ 9) ATHENSa AL Qe86( 1/ 1) 0 '0( 2/ 2) 0.18- 0.86 10 ~ 9 HILES NE 0.86- Oe86 Qo45~ De75 K~CO 0..250 5o82( 9/ 9) LH1 SF NQRTHMEST 1 ~ 0 HILE N 8 '4( 1/ 1) 4e51( 2/ 2) 3e49 8 ~ QC 8 ~ Ohe Be04 4e19 4e83 Sl 214 0 '50 le04( 9/ 9) LH2 SF NORTH 1 e39( 1/ 1) 0 ~ 91( 2/ 2)
Qe65 1 ~ 39 0 ~ 9 MILE NNE 1 ~ 39~ le39 Oe82~ le01 SI 212 0 ~ 100 ~ Qe77( 9/ 9) LHC SF TRAILER P Qe97( 1/ 1) Oe78( 2/ 2)
PB 21C 0.050 Qe50 1o10(
0 '7 9/ 9) 1 ~ 7 HILES NNM LH2 SF NORTH 0 '7~
le43( 1/
Qe97 1) 0 0
'7~
'9(
Oe78 2/ 2) 0,73 1 ~ 43 0,9 MILE NNE le43- leh3 0 F 89~ lo09 PS~212 NQT ESTAB le24( 9/ 9) PECATURi AL le56( 1/ 1) le02( 2/ 2)
Q ~ 71 le56 4 ~ 2 MILES SSE 1 ~ 56~ le%6 1 e00a le04 RA-226 0.050 1.04( 9/ LH2 BF NORTH lo39( 1/ 1) Oe91( 2/ 2)
Qo65 1 39 0 ~ 9 HILE NNE 1 ~ 39~ 1 ~ 39 Qo82 1 ~ 01 RA 213 NQT ESTAB 0 '9(
0.28-
~
6/ 9) 0,48 LH2 SF NORTH 0 ~ 9 MILE NNE 0,48(
0.48-1/
Qe48
- 1) 2 VALUES <LLD TL 208 0 '20 Oe42( 9/ . 9) PECATURe AL. Qe52( 1/ 1) Oe39( 2/ 2)
AC~228 0.060 0 '6 1.21(
0 9/
'2 () ~ 2 MILES SSE LHl SF NQRTMMEST Qe52 le51( 1/
Qy52 1) oo37>>
'loll(
Oehl 2/ 2)
Qo77. le51 1 ~ 0 HILE N 1 e 51~. le51 F 04>> lel8 Sg 89 1 o 500 9 VALuES <LLO 2 VALUES <LLD ANALY51$ PERFORMED SR 90 Oo300 .9 VALUES <LL,D 2 VALUES <LLD ANAL.YSIS PERFQRHEO
- a. Nominal Loeeer Limit of Detection LLD) as described in Table 3.
- b. Mean and range based upon detectable measurements only. Fraction of detectable measurements of specified locations is indicated in parenthesis (F).
TABLE RADIOACTIVITY IN MELL MATER PC I/L 0 ~ 037 b0/L DOCKET NO ~ 5()n25'Ra26Qa2M LOCATION OP FACILITY LIMESTONE-<< - - -4L46454 REPORTING PERIOD 1950 TYPE ANO LOMER LIMIT . ALL CONTROL NUHBER OF TOTAL ~UMBER OF INDiCATOR LOCATIONS LQCAZXOu X1ZU UZO)(ESZ 4((((uaL ((E4N LOCATloNS NONROUTINE OF ANALYSIS PEBEORMEO DETECTIONa LLLQl HEAN (F)b RAMOEP NAME OISXAHCE 4MQ QIBECZlQU MEAN R4((GE
(/) b MEAN (F)
EAHGE~ -- -
REPORTED MEASUREMEBIS-GAMMA (NAI) 22 ll VALuES <LLD ANALYSIS PERFORMED 11 VALUES <LLD GAMMA (GELI)
K~40 NOT ESTAB 67o32(
bb ~ 53 2/
68 ~ 11
- 2) BFN 0 '2 MELL'b HlLES. M 67e32(
bb ~ 53e 2/
bbsll
. 2) 69 69
'0(
'0~
1/ 2) 81 214 NOT ESTAB 13163 (
l3. 63-1/
13, 63
- 2) BFN MELL Nb 0 ~ 02 HlLES M 13,63 (
13 '3+
1/
13sb5
- 2) '4(
lb.04-b9e70'6 1/
16.04 2)
P B-214 NOT ESTAB 12.5I( 1/ 2) BFN 'MELL Nb 12g51( 1/ 2) 11 ~ 53 ( 1/ 2) 12o5i 12e51 0 ~ 02 HlLES M 12651 12e51 11.53- 11.53 PB~212 NOT ESTAB 2 VALUEs <LLD 13~35( 1/ 2) 13 '5~ 13e35 TRIT IUM 330 F 000 4 VALuES <LLD 4 VAI.UES <LLD 8 ANAiYSIS PERFQRHED
- 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 parenthesis (F).
TABLE 14 RADIOACTIVITY IN PUBLIC MATER SUPPLY PCI/L - 0.037 80/L NAHE OF FACILITY.BROWSES EEBRX FT NQ.SQ 2 LOCATION OF FAC IL ITY LIHESIO)(E 4L48454 REPORTING PERIOD 1QBQ TYPE AND LOMER LIHIT AiL CONTROL NUHBER 0F
'TOTAL NUHBER OF IND ICA'TOR LOCATIONS LQCAZIO(t MIZU UIGUESZ 4((((VAL ME48 LOCATIONS NONROUTINE DF ANALYSIS DETECTION a HEAN (F)b NAHE HEAN (F)b HEAN (F)b REPORTED EEBEOBHED CLLQI 84NGl----
b DISIAI(CE 4UD QIBECIIOU B4((GE b --84htGE b HEASUBEHEUTS--
GROSS BETA 2 F 400 3 '9( 46/ 78) MHEELER DAHi AL 5 '3( 4/ 13) 3 '5( 3/ 13) 91 Re41- llo99 TRH 274 ' Ro49>> Ill 99 Re49>> 3IBO GAHHA (NAI) 84 72 VaLuES <LLD 12 VALUES <<LLO ANALYSIS PERFORHED GAHHA (GELI) 7 K>>40 NOT ESTAB 76 ~ 44( 2/ 4) CHAHPION PAPER 78 '2( 1/ 3) 102 80( 1/ 1) j4.65- 78.22 TRH 282 F 6 78 F 22>> 78's 22 102a80>> 102e80 81-214 NOT ESTAB 19 F 88(
9 I 09 3/
26 ~ 20
- 6) MHEELER DAHi AL TRH R74 ~ 9 26 '0(
26 20 1/
26>20 9 ~ 15(
9o 15 1/
9 ~ 15 1) 2/ 6) 24I35( '3(
PB 214 NOT ESTAB 2lsb>(
lhe84 24e35 2/
CHAHPION PAPER TRH 282.6 R4 ~ 35>>
1/
24 '5 3)3) 13 13e33>>
1/
13 '3 1)
P 8-212 NOT ESTAB 15.03( 6) CHAHPION PAPER 19g43( 1/ 1 VALUES <LLD 10sbl. 19e43 TRH RBR F 6 19 ~ 43>> 19 I 43 SR $ 9 10 F 000 $ 2 VALUES <LLD 4 VALUES <LLO 16 ANALYSIS PERFORHED SR 90 2 F 000 g2 VaLuES <LLD 4 V~~UES <LLO lb ANALYSIS PERFORHED TRITIUH 330 F 000 343 ~ R9( 1/ 1R) SHEFFIELDwAL ROB 343e29( 1/ 4) 4 VALUES <<LLD lb 343eR9 343'o29 TRH 254 ' 343 '9>> 343e29
- a. Nominal Lover Limit of Detection (LLD) as described in Table 3.
- b. Hean and range based upon detectable measurements only. Fraction of detectable measurements of specified locations is indicated in parenthesis (F).
28 Table 15 ENVIRONMENTAL GAMMA RADIATION LEVELS Environmental Gamma uarter Location l ~i Radiation Levels January-April 1980 On-Site (8) b Maximum 10. 6 23.1 Minimum c
7.3 15.9 Average 9.4 + 2.3 20.7 + 5.0 Off-Site (7)
Maximum 12. 5 27.4 Minimum 6.9 15.2 Average 8.6 + 3.7 18.9 + 8.2 May-July 1980 On-Site (8)
Maximum 10.0 21. 9 Minimum 7.4 16.3 Average 9.0 + 2.0 19.8 + 4.4 Off-Site (7)
Maximum ll. 1 24.3 Minimum 6.8 14.9 Average 8.1 + 2.8 17.8 + 6.1 July-September 1980 On-Site (9)
Maximum 10.3 22.6 Minimum 7.9 17.3 Average 9.5 + 1.8 20.9 + 4.0 Off-Site (7)
Maximum 11. 0 24.2 Minimum 7.3 16.0 Average 8.5 + 2.5 18.6 + 5.5 October-December 1980 On-Site (9)
Maximum ll.5 25. 1 Minimum 7.8 17. 2 Average 10.0 i 2.3 21.9 + 5.0 Off-Site (7)
Maximum 12. 0 26.3 Minimum 7.4 16.3 Average 8.7 + 3.1 19.1 + 6.8 Data normalized to one quarter (2190 hours0.0253 days <br />0.608 hours <br />0.00362 weeks <br />8.33295e-4 months <br />)
Number of stations (normally three TLD's at each station)
All averages reported +2a (95% confidence level)
TABLE 16 RADIOACTXVXTT IH POOD CROPS PCI/KG 0 037 BO/KG (NET WEIGHT)
NAHE OF FAClLITY,BBQVUS EERIY - -- --
DOCKET NOo SOa25%8260a296 LOCATIDN OP FACILITY LlHESIOBE ALA()4))4 REPORTING PERIOD PRO()
TYPE ANO LOWER LIHIT . ALL CONTROL NUHBER OF TOTAL NUMBER OF INO1CATDR LOCATIONS LQC4ILQU XLIU UIQ))ESI 4((HL)4L ()E48 LOCATIONS NONROUT INE DF ANALYSIS OETRCTIONa HEAN (F)b NAHE HEAN (F ) ~ HEAN (Fg> REPORTED EEREOB))EQ CLLQL RA((GEE) QISI4((CE AUQ QLSECI1QU 84)IGE RA)(GE b BEASUBEBEBIS-RADIOACTIVITY IN CABBAGE GROSS BETA 2
25 '000 44i3o59(
4413.59- 4413.59 1/ 1) $ NITH FARH 4.75 HILES N 4413ef9( 1/
4413 ~ 5'9>> 4413 ~ 59
- 1) 4338 ~ 21 4338.21 t,4338.21 1/ 1)
GAHHA (GELI) 2 K>>40 NDT ESTAB 1748 ~ 00( 1/ 1) SNITH FARH 1748.00( 1/ L) 1646,00( 1/ 1) 1748,00- 1748.00 4.75 HILES N 1748 F 00>> 1748'o00 1646 F 00 1646 F 00 PB 212 NDT ESTAB 'lb ~ 52(
lbef2 L/
Lbe52
- 1) $ HITH FARN 4e75 HILE$ N 16 '2(
lbe52>>
L/
Lbe52
- 1) L VALUES <LLD RAOlOACTLVITY IN CORN GROSS BETA 25 ~ 000 3f%5 ~ 84( 1/ 1) SHITH FARN %535 e44( 1/ 1) 3247e77( 1/ 1)
GAHHA (GEL I) 2 3535ol4 3f35 ~ 84 4 '5 HILES N 3535 ~ 84>> 3535 F 84 3247 '7>> 3247e77 2
K>>40 NOT ESTAB 2440e00(
2440 F 00 1/
2440 ~ Ob
- 1) SNITH FARN 4o75 HlLES N 2440 F 00( 1/
2440 F 00>> 2440e00
- 1) 1'?58 '0t 1758e00>>
L/
1758 F 00 1)
RADIOACTIVITY Ig GREEt( BEANS GROSS BETA 25 F 000 4817e18 ( 1/ 1) SNITH FARH 4817e18( L/ 1) 4638eb3( 1/ 1) 2 4817. 18 4817 ~ LB 4o75 HILES N 4817 ~ 18>> 4817 ~ 18 4638e63>> 4638 ~ 63 GAHHA (GELI) 2 K>>40 NOT ESTAB 2916,00( 1/ 1) SHITH FARH 29lbe00( 1/ 1) 2310.00( 1/ 1) 2916.00- 2914e00 4o75 HILES 'N 2916 ~ 00>> 29lbe00 2310 ~ 00>> 2310 ~ 00 PB 212 NOT ESTAB ll e 17(
T.L ~ 17-1/
lie 17 11 SHITH FARH 4o75 HILES ~ N ll ~ 17(
llo17>>
1/
lie l7
- 1) 10 10
'8(
'8>>
1/
10 '8 1)
- a. Nominal Lower Limit of Detection (LLD) as described in Table 3.
- b. Mean and range based upon detectable measurements only. Fraction of detectable measurements of specified locations is indicated in parenthesis (F).
TABLE l6 (Cqntd)
RADIOACTIVITY IN FOOD CROPS PCI/KG - O.037 Sa/KG (MET HEIGHT)
NAHE OF FACILITY BBP)(BS LOCATION OP FAC IL ITY LIHESIOHE EEBBY
- -ALAaA(IA .------ DOCKET NO ~ Spm25o)a250a296 REPORTING PERIOD 12()O TYPE ANO LONER LIMIT ALL CONTROL NUMBER OF TOTAL NUHSER OF INDICATOR LOCATIONS LOCAIIOU )(II)j UIGQESI 4((UL)AL ()EAU ~- LOCATIONS NONROUT INE OF ANALYSIS DETECTION MEAN (F)b NAME HEAN tF) MEAN tF)b REPORTED EEBEOBIIEO LLLQL RANGES-- OISIAUCE AUD OIBECIIOh BA((GE BAI(GEb LEASUBEIIEUIS RADIOACTIVITY IN PEACHES GROSS SRTA 25 ~ 000 5690 ~ 34( 1/ 1) SMITH FARH 5490 ~ 34( 1/ 1) 4935 ~ 15( 1/ 1) 2 5490 ~ 34 5490 ~ 34 4 ~ 75 MILES N 5490 ~ 34'490e34 6935oL5~ 6935 ~ 15 .
GAMMA (GELI) 2 K~40 NOT ESTAB 2183 e00( 1/
2183 ~ Oo 2183 ~ 00
- 1) SHITH FARH 4 ~ 75 MILES N 2183 ~ 00( ll 2183 ~ 00+ 2143 ~ 00
- 1) '1SBS ~ 00( 1/
1888 ~ 00~ 1888 ~ 00 1)
GROSS GAHHA BETA (GELI) 2' 25 F 000 7789 '5(
7789e95 1/
7749 F 95 1)
RA010ACTIVITY IN POTATOES HARGROVE FARH 3 ~ 75 HILES N 7789 7789
'5(
'5~
1/
7749o95
- 1) 8228 ~ 30( '/
~ 30~ 822bo30 1)'228 K 40 NOT ESTAB 4121 o 00 1/ 1) HARGROVE FARM 4121e00(
( L/ 1) 34S3 F 00( 1/ 1) 4121 ~ 00 4121 ~ 00 3 ~ 75 HILES N 412Lo00~ 412le00 3483o00~ 3443 F 00 RAOIOACTlVITY IN TOHATOES GROSS SETA 2
25 F 000 4876o55(
4876 '5~ 487bo55 1/ 1) SHITH FARH 4 '5 HILES N 4874 ~ 55(
4S74 ~
ll 55r 4876o55
- 1) 4844 ~ 24(
4844 '4+ 4844 1/
'4 1)
GAHHA (GELI) 2 K 40 NOT EST~8 2485.0Ot 2485,00- 2445.00 ll 1) SMITH FARM 4 ~ 75 MILES N 2485 ~ 00( ll 1) 2456e00( I/ 1) 2485e00~ 244% ~ 00 2456 ~ 00~ 2456 ~ 00
- a. Nominal Lower Limit of Detection (LLD) as described in Table 3.
- b. Hean and range based upon detectable measurements only. Fraction of detectable measurements of specified locations is indicated in parenthesis (F).
TABLE RAOlOACTIVITY IN SOYBEANS PCI/G - 0.037 80/G (ORY MElGHT)
NAHK OF FACILITY'BQQUS KELLY - - - QOCKET NO SQa2%Ra264a LOCATION OF FACILITY LmIUESIOUE ALAS4U4 REPORTING PER100 1914 TYPC AND LOMER LIHIT AiL CONTROL NUHBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOC4IIOU llIIUUIGUESZ 4UULl4L NONROUTINE DETECT ION a HEAN (F)b U84U->--'AME LOCATION)
OF ANALYSIS HEAN ($ ) HEAN ([) REPORTEQ eEBEOBUEQ CLLQl BANGS b QISIAUCE 4UQ-QIBECIIQU-----EAUGE RAUGE UEASUBEUEUZS-GROSS BETA 0 '00 40.89( 1/ 1) HARGROVE FARH %O S &9( 1/ 1) l 40 '9- 60 ~ 89 3.75 MILES N 60.89- 40.89 GAHMA (GELI) 1 NOT ESTAB 17e07( 1/ 1) HARGROVE FARH 17e07( 1/ 1)
Kecj,O I7 ~ 07 17' 07 3 '5 HILES N 17e07~
'6( 17o07 8 I-2]b NOT ESTAB 0 'b(
'b 1/
0 '6 1) HARGROVE FARH 3o75 HILES N 0
0 '6~
1/
0 F 06 1) 0 PB-214 NOT ESTAB 0 '6( 1/
0 '6
- 1) HARGROVE FARH 0 '6( 1/ 1) 0 '6 3 ~ 75 HlLES N 0 '6~ 0,06
- 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 parenthesis (P).
TABLE 18 RADlOACTIVITY IN POULTRY PCI/KG - 0 ~ 057 BQ/KG Ii)ET itEIGHT) tkAME OF FACILITY SROMUS EERRY DOCKET NO ~ SOmZSQcZlhOa&5 REPORTING PERIOD IRSO TYPE AND LOMER LIHIT'F ALL CONTROL NUMBER OF TOTAL tJUMBER INDICATOR LOCA/IONS LOCAZIOV )IIZU UIGVESZ aNUUAL.I)EAII~ LOCAT ION) NONROUTINE OF ANALYSIS DETECTION a HEAN IF) NAHE HEAN IF) HEAN ([) REPORTED REREORI)ED ILLO> BAUGEJ----- OISZAUCE ANO OIRECZIOU B4IIGEb RANGE I) EASUREHEHIS GROSS BETA 25e000 45i4.98( 1/
4514.98- 4514.98
- 1) SHITH FARM 4 ~ 75 MILES N 4514e98( 1/
4514 ~ 98>> 45'14 ~ 98
- 1) 2496 2496
'9( 1/
'9>>. 2496 '9 1) 2 GAHMA (GELI) 2 CS 157 15 ~ 000 iBe96( 1/ 1) SMITH FARH 18e96( 1/ 1) 1 VAI.UES <LLD i8.96- 18.96 4 ~ 75 HILES N 1$ e'94>> 18 ~ '96 K>>40 NOT ESTAB 1950e00( 1/ 1) SHITH FARH 1950e00( 1/ 1) 2152 ~ 00 I 1/ 1) 1980 F 00 1950e00 4 ~ 75 MILES N 1950 F 00>> 1950 F 00 2152 F 00>> 2152e00 Bl 214 NOT ESTAB 1 VALUES <LLD 19 '6(
19e76>>
1/
19e76 1)
PS-214 NOT ESTAB VALUES <LLD 11.81( 1/ 1) lle81>> lle81 TL-208 NOT ESTAB 20eDII 1/ 1) SHITH FARH 20 F 01( 1/ 1) 1 VALUES <LLD 20.01- 20.01 4.75 MILES N 20 F 01>> 20e01
- a. Nominal Lover Limit of Detection (LLD) as described in Table 3.
- b. Hean and range based upon detectable measurements only. Praction of detectable measurements of specified locations is indicated in parenthesis (P).
33 R'eservoir Monitorin Samples are collected from the Tennessee River as detailed in table 19. Samples collected for radiological analysis include plankton from three of these cross sections and bottom fauna and sediment from four cross sections. 'The locations of these cross sections are shown on the accompanying map (figure 5) and conform to sediment ranges established and surveyed by the Data Services Branch, TVA.
Parer Water samples are collected automatically by sequential type sampling devices at three cross sections and composite samples analyzed monthly for gamma-emItting radionuclides. Further composites are made quarterly for strontium and tritium analyses. In addition to these required samples, grab samples were also collected monthly from the vicinity of the plant discharge to the Tennessee River, and at a point on the Elk River, and analyzed for gross beta, gamma-emitting radionuclides, and strontium. Results are displayed in table 20.
Fish Radiological monitoring for fish is accomplished by analysis of composite samples of adult fish taken from each of three contiguous reser-voirs Wilson, Wheeler, and Guntersville. No permanent sampling stations have been established within each reservoir; this reflects the movement of fish species within reservoirs as determined by TVA data from the 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 21, 22, and 23.
Plankton As indicated in table 19, 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 accuracy. Samples are collected semiannually and submitted for gross beta analysis, and when quantities are sufficient, for gamma activity and Sr
nd eo Sr content. During this reporting period, all samples contained in-sufficient volume of material for gross beta, strontium, or gamma analyses.
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 19. Results are shown in table 24.
Bottom Fauna The flesh and shells of Asiatic clams collected semiannually from the cross sections at four stations (table 19) are analyzed for gamma-emitting radionuclides. Levels of Sr and Sr are determined on the shells, and on the flesh when sufficient amounts were available. A 50-gram (wet weight) sample provides sufficient activity for counting. During this reporting period, one sample of clam flesh contained insufficient volume for analysis. Results are given in tables 25 anl 26.
Table 19 SAMPLING SCHEDULE RESERVOIR MONITORING Biolo ical sam les collected semiannuall Zooplankton, chlorophyll, Benthic Water samples River/river mile h to lankton fauna Sediment Fish collected monthl Tennessee 277.9 X Tennessee 285.2 Tennessee 288.7 Tennessee 291.7 X Tennessee 293.5 Tennessee 293.7 (discharge area)
Tennessee 305.0 Tennessee 307.5 X 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.
36 Figure 5
-R ESERVOI R MONITORING NETWORK Elk River WHEELER DAM mile 274.90 mi)e 277.98 Rogersville 0
mile 29l.76 Athens mile 282.6
~mile 285.2 B.F. NUCLEAR PLANT S
Champion Paper Co.
le 288.78 mile 293.50 mite 305.0 Courtland mile 295.70 0
Decatur mile 307.52 Scale of Miles
~ - Automatic Sam ter
TABLE 20.
RADlOACTIVITY IN SURFACE MATER TOTAL PC1/L 0 '37 80/L NAHE OF FAC IL 1TY BRO)t(IS EERRY DOCKET NO ~ SQm2%%a26Qa~
LOCATION OP FAC IL I TYLIIIESIOIIE 4L4B4II4 REPORTING PER100 19BQ TYPE AND LONER LIHIT ALL CONTROI. NUHBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCAIIOu MIIU )IIGIIESX NIIUAL.))%48 LOCAT10NS NONROUTINE OF ANALYSIS DETECTlON a HEAN IF) b NAME HEAN (F)b HEAN (F)b REPORTED EEREORIIEQ ILLQI w w BANGEw b QISIAI{CE AUQ QIREGIIOII -- RAIIGE RA(IGE b IIEASUREIIEIIIS GROSS BETA F 400 3e48( 6/ 13) TRH R93 ~ 7 3 88( 6/ 13) 4e2R( 10/ 13)
GAHHA (DELI26 (NAI)
Re47- 6 '3 BFN 01SCHARGE 2 '7>> ee63 2 '4>> 12 '5
( 50 26 VALUES <LLD 24 VALUES <LLD ANALYSlS PERFORHED GAHHA )
15 K 40 NOT ESTAB 92 '0(
156eRD
- 13) TRH 293 '
8FN 01SCHARGE 106e54{
64 '4>>
4/ 4) R VALUES <LLD 156 F 20 Bl 214 NOT ESTAB 23.3o(
Te75 -
9/
39 ~ ll13) TRH 293 '
BFN 01SCHARGE 24e50{
12e74>>
3/
30 '3 6) 13 13
'9{
'9 1/ 2) 13 '9 PB>>214 NOT ESTAB I8.04( TRH R93 ~ 7 19e91( 1/ 6) 2 VALUES <LI.D
~
11.96- 24.02 BFN 01SCHARG'E 19e91>> 19e91 PB 212 NOT ESTAB 16e5o( 5/ 13) TRH 285 ' 18 62( 4/ 5) 2 VALUES <LLD 8.04- 24,93 12e09>> R4e93 SR 89 10 ~ 000 21 VALUES <LLD 17 VALUES <LLD 38 ANALYS1$ PERFORHED SR 90 RE 000 $ 1 V4LUES <LLD 17 VALUES <LLD 38 ANALYS1S PERFORHED TRlT IUH 330e000 460e44( 2/ 1R) TRH 285 ' 489elR{ 1/ 4) 599.3R{ 1/ 8) 20 431 ~ 76 489e12 489 ~ 12>> 489 ~ 12 599 '2 599e32.
- 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 parenthesis P .
TABLE 21 RAO(OACTlVlTY lN XH(TE CRAPPlE (FLESH)
PCl/G 0 ~ 037 SQ/G lORY XElGHT)
NAHE OF FAClL1TY ()ROWUS EERRY REPORTINGOOCKET NO ~ 5Om259626Oa29~
LOCAT(ON OF FAC 1LlTY LIUESIOUE- - ALA()AUA PER100 l((nQ TYPE ANO LOWER L1HIT ALL CONTROL NUHSER OF TOTAL NUMBER OF 1NDICATOR LOCAT10NS LQCAIIOU MIIU UIQUESI AUUU4L UEAU LOCAT)ONS NONROUTlNE OF ANALYS1S OETECT lONa HEAN (F)b NAHE HEAN (F)b MEAN (F) REPORTED REREORUEQ CLLQI aANQEb QISIAUCE-AUQ QIRECIIQU RAUGEb ILAUGE b UEASUREUEUZS GROSS BETA 0 ~ 100 33 F 49( 4/ 4) WHEELER RES 35I32( 2/ 2) 4be19( 2/ 2) 6 28o97 3be75 TRH 275"349 .33 F 89>> 3be75 43e78 48obl (GELl)
'/
GAHHA 6
CS 137 0 020 0 ~ 10( 4/ 4) )(lLSON RESERVO(R 0 ~ 10( 2/ 2) 0 ~ Oi ( 2) 0 F 08 0 ~ 11 TRH 259"275 oa09>> Oell 0 ~ 08>>- 0 ~ 10 K>>40 NOT ESTAB . 15 ll( 4/ 4) XHECLER RES 15 '2( 2/ 2) 17 '5(
lbebo 2/ 2) 13 ~ 40 16,84 TRH 275"349 13 F 40>> 1beb4 18 ~ 10 81 214 0 ~ 020 0 ~ 05( 2/ 4) WHEE(.ER RES o.'ob( 1/ 2) oeob( 1/ 2) 0 F 05 0 '6 3/ 4)
TRH 275"349 0 F 06>> ooob o,ob- o.oe 1/
PS 214 NOT ESTAB 0 ~ OS( X1LSON RESERV01R 0 F 08( 2/ 2) 0 F 05( 2) o, ll
=
ooob TRH 259-275 0(06>> OIll Oe05 oo05 PS 212 NOT ESTAB Oo03( 1/ 4) XlLSON RESERVOlR oe03( 1/ 2) 2 VALUES CLL0 0)03 og03 TRH 259 275 O.O3- Oe 03
- a. Nominal Lower Limit of Detection (LLD) as described in Table 3.
- b. Mean and range based upon detectable measurements only. Fraction of detectable measurements of specified locations is indicated in parenthesis (F).
TABLE 22 RADlOACTlVITY lN SMALLHOUTH BUFFALO (FLlSH)
PCl/G ~ 0 ~ 037 8()/G tORY ME'(GHT)
NAHE OF FACILITY BRONZES EERRY DOCKET NO', 5Qm25Ra2bQ<395 LOCATION OF FACILITYLSHESZOBE- ALABAMA REPORTING PERIOD lRBO TYPE AND LONER LIMIT ALL CONTROL NUMBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCATION )tuM UZGUESZ ANNUAL IRAN LOCATIONS NONROUTINE OF ANALYSIS DETECTION a HEAN (F)b NAHE MEAN (F) > MEAN (F)b ,
REPORTED REREOBBED iLLQ1 BABQE b OISIAMCE AHQ QlREQILOU RAtlGSb -RAUGEb MEASUREHENS gb.30( 4/ 4) 30 ~ 91( 2/ 2) 2/
GROSS GAMMA BETA (GELI) b 0 ~ 100 20 ~ 4B 31 ~ 03 MHEELER RES TRH 275-349 30 ~ 78~ 31 ~ 03 31 ~ 17 (
29e93~ 32 '2 2) b CS 137 0 ~ 020 0 ~ 04( 3/ 4) MHEELER RES 0 ~ 05( 1/ 2) 0 ~ 05( 2/ 2) 0 F 03 0 ~ 05 TRH 275 349 0 ~ 05r OI 05 0 F 04~ oo05 K%40 NOT ESTAB 11.7o( 4/ 4) MHEELER RES 12e82( 2/ 2) 15 ~ 39( 2/ 2) gobb 13'3 TRH 275 349 12 ~ 41~ 13e23 15IOB~ 15eb9 8 l-214 0 ~ 020 0 '7(
Oo04-3/ 4) 0 ~ 09 MILSON RESERVOIR TRH 259-275 0 ~ 08(
0 ~ 07~
2/
0 ~ 09
- 2) 0 ~ 14(
0,14 1/
0 ~ 14 28 PB 214 NOT ESTAB 0 ~ 07( 2/ 4) MILSON RESERVOIR 0 F 08( 1/ 2) oslo( 1/ 2) 0 F 06 0 F 08 TRH 259-275 0 F 08~ 0 F 08 0 ~ 10 0010 PB 212 NOT ESTAB 0 ~ 01( 1/ 4) MILSON RESERVOIR 0 ~ 01( 1/ 2) 0 F 07( 2/ 2) 0 ~ Oi- o,ol TRM 259-275 os Ole 0 ~ 01 0 '4m oo09
- 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 parenthesis (P).
TAB).E 23 RADIOACTIVITY IN SHALLHOUTH BUFFALO (WHOLE)
PCI/O>> 0 ~ 037 BQ/G (ORY WEIGHT)
NAHE OF FACILITY,BRgeuS EERRY DOCKET NO ~ 5Om259a26OaMS-------
LOCATION OP FACILITY LLHKSIOUE ALABAIIA REPORTING DECONTROL PERIOD lQR()
TYPE AND LOWER LIHIT ALL NUHBER OF TOTAL NUHBER . OF INDICATOR LOCATIONS LOCAILOu ){CIU UIGHEKI N({UAL (IEO(( LOCATIONS NONROUT INE OF ANALYSIS OETljCTION a HEAN {F) NAHE MEAN (F)~ MEAN {F) REPORTED REREORUEO CLLD1 ROUGE - DISIauCE A({D DCBEGXlOU BAUGE b B48(lE b BEASURE)IENIS GROSS BETA 0 ~ 100 15 ~ 81( )/ h) WHEELER RES 19o ll( 2/ 2) 13 '5{ 2/ 2)
GAMMA {GELI) 6 lQ 86- 20 '2 TRH 275-3h9 17 '0>> 20 '2 11 ~ 1lr 15 ~ 99 6
CS 137 0 '20 Qe{}3( 3/ h) WILSON RESERVOIR TRH 259"275 0.03( 1/ 2) 0 '3( 1/
'3 2) 0 02 Qe03 Q ~ Q3>> Qeoa ., 0 F 03>> 0 K>>40 NOT ESTAB 7 '3( h/ h) WHEELER RES Bo81( 2/ 2) Bo38{ 2/ 2) be2i" Pe67 TAH 275-3h9 7e95>> Pe67 7e95>> 8 F 81 BI 21h 0 ~ 020 0 ~ 11{ 3/ h) WHEELER RES 0 ~ 16( 1/ 2) 0 F 07{ 1/ 2) 0 ~ 08 0 ~ 16 TRH 275-3h9 Qolb>> Qe lb 0 ~ 07, 0 ~ 07 PB 21h NDT ESTAB Dell( 3/ h) WHEELER RES Oo21( 1/ 2) 0 '3{ 1/ 2)
Qe05-. 0 '1 TRH 275-3h9 Qe21>> 0 ~ 21 Oe03 0 '3(
Oo03 1/
PB SR 212 89 NOT ESTAB 0.500 h VALUES <LI.O 2 VALUES <LLD Oo03>>
0 VALUES <LLD 0 '3 2) 2 ANALYSIS PEAFORHED SR 90 2
0 '00 0 '2(
0 ~ 11-2/
0 ~ 13
- 2) 'WHECLER RES TRH 275-3h9 0 '2(
0, 1 lr 2/
Oe 13 2)
- a. Nominal Lower Limit of Detection (LLD) as described in Table 3.
- b. Mean and range based upon detectable measurements only. Praction of detectable measurements of specified locations is indicated in parenthesis (P).
TABLE 24 RAOIOACTIVITY IN SEDIMENT PCI/G 0 ~ Q37 80/G (DRY WEIGHT)
NAHE OF FACILITY RRQWUS KERRY DOCKET 50s25Ra20Oa~
OCATIDN OF FACILITY Ltt(ES10UE ALARAU4 REPORTING NO ~
PERIOD LRRO TYPE AND LOWER LIHIT ALL CONTRDL NUHBER Of TOTAL NUHBER OF INDICATOR LOCATIONS LOC4ZIOU )ttIU UIGUESX 4UUUAL UE4U. LOCATIONS NDNROUTINE QF ANALYSIS DETECTION a HEAN (F) b NAHE MEAN tg)b MEAN t i')b REPORTED REREOBUEO XLL'OX RANG@. OISIAUCE AUO t)LRECZIOUROAN R4UGE RAUGEb UEASUREUEUIS-GAHHA (GELI) 8 C0-60 0 '10 Q.LQ t 5/ 4) TRM 293 ' 10( 2/ R) Qe07( 1/ 2)
Oo00>> 0 ~ 14 BFN DISCHARGE Q~
0 F 00>> 0 ~ 14 0' 07>> 0 '7 CS-137 0 '20 1 0 '4
~ 32( 6/
2 '0 6) TRM 277 ~ 98 2 2
'&t
'0>>
2/
2 '0 2) 0 '5(
Doll>>
2/ 2)
Qe99 X>>40 NDT ESTAB 15 79
~ ( 0/ 0) TRH 2&&~ 78 09( 2/ R) la 67t 2/ 2)
SobQ R5e71 Lhehb>> R5e71 10.03>> Lbe71 Bl 214 0 ~ 020 1.33(
Do23" 0/
'7 0) TRM 277 '8 Leb3(
le45>>
2/ 2) Le25t lelQ 2/ 2) 2 1 ~ &5 1ehl Bl 212 0 100 Lo05( 6/ 0) TRM 28'& lo24( 2/ 2) Qe97t 2/ 2)
~ Oe51 1 ~ 60 Oe87>> le00 0 F 84>> lel0 PB 2L4 NDT KSTAB 1.58( 0/ 6) TRM RBB ~ 78 le9lt 2I 2) le32( 2/ 2)
PS 212 NOT ESTAB 0
1
'982t
~
2 '3 0/ 0) TRH 2SB ~ 78 le28>>
2o24(
2 '3 2/ 2) leL&>>
lohb(
lo47 2/ 2) 0 ~ 79- R,e&9 Le89>> 2o59 le leb3 RA 226 NOT ESTAB 1.50t Oobb 4/
2 '7 0) TRH 288 '8 le&0(
23>>
2/
2 ~ 3'7
- 2) 1 ~
29 25t lel0>>
2/
le41 2) 1
'5(
~
RA 223 NDT ESTAB Oebbt 3/ 0) TRH 284 78 0 2/ 2) 0.56( 1/ 2)
BK 7 NOT ESTAb 0 '0 l/De&0 0)
Qe22( TRH R93o7 0 '0>>
Oe2R(
0 AD &0 1/ 2) 0 '0 2 VAI.UE <L(,D Oe5b 0 '2 S
OeR2 SFN DISCHARGE Oe22>> Qe 22 TL 208 0 '20 0.5&t 6/ 0) 0 '0 TRH RBSo78 Oo71( 2/ 2) 0 '0( 2/ 2)
AC 228 0.060 0 27 1
F
~ 77( 6/ 6) TRH 288 F 78 0 'R>>
2 ~ 21(
Qe90 2/ 2) 0 '4>>
1.56(
0 '0 2/ 2) 0 AD &2 2 ~ 78 1 ~ 64>> 2e7& 1 ~ 28 1 ~ S4 SR &9 LE 500 6 VAI.UES <LLO 2 VALUES <LLD ANALYSIS P ERFORHED SR 90 0 '00 0 0
'2(
'2 2/ 6)
Qe32 TRH 293 SFN DISCHARGE 0 Oe32t
'R>>
1/
Qe3R
- 2) 2 VALUES <LLD
- a. Nominal Lower Limit of Detection (LLD) as described in Table 3.
- b. Mean and range based upon detectable measurements onl n y.. Frraction of detectable measurements of specified locations is indicated in parenthesis (F).
TABLE RADIOACTIVITY IN CLAH FLESH PCI/G - 0 ~ 037 BQ/G (DRY HEIGHT)
NAME OF FACILITY.BRObtNS EERRY DOCKET NO 50s25Ba260 395 LOCATI OF A ILITY LIHESXOUE 'LABAMA REPORTING PERIOD 1RBO TYPE AND LOMER LIHIT ALL CONTROL NUHSER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCAXION BXZU OXGVESZ N((()AL BEAN - LOCATIONS NONROUTINE OF ANALYSIS DET(FACT ION a HSAN (F)b NAHE HEAN (F)+ HEAN (s) b REPORTED REREORBEO CLLOl---- -- --- RANGE----- OISIAUCE-ANO OlBECI1ON RANGE -BAI(GE BEASUBEHENIS-GAHHA (GELI)
K~40 7
NOT ESTAB 1'$
10 03
( 3/
32 '6 5) TRH 288,78 32 '6(
32>>36>>
1/
32 '6 2) 21>>40(
21 '0.
1/
21 F 40
')
BI 214 NOT ESTAB 2 '6( 4/ 5)
~
TRH 293 ' 2>>39t 2/ 2) 2 '1t 2/ 2) 8-214 'OT 1>>24 3 '4 3/ 5)
BFN 01SCHARGE
'8 1 '4m 4 '3(
3 '4 1>>34~ 3>>67 2/ 2)
P ESTAB 3 41(
~ TRH 288 1/ 2) 2>>33(
1>>54- 4>>93 h>>93~ 4>>93 1>>30>> 3 ~ %7 PB 212 NOT ESTAB 1>>52( 5/ 5) TRH 277 '8 1>>75( 1/ 1) 2 '4( 2/ 2) 0>>47 F 78 F 75~ 1>>75 1>>07 4 ~ 22 TL 208 NOT ESTAB 0 '8( 1/
'8 5) TRH 293>>7 0>>58( 1/ 2) 16( 1/ 2) 0 '8 0 SFN'1SCHARGE 0 '8~ 0>>58
$ ~
1,16- 1>>16 I
- a. Hominal Lover Limit of Detection (LLD) as described in Table 3.
Mean and range based upon detectable measurements only. Fraction of detectable measurements of specified locations is indicated in parenthesis (F).
TABLE 26 RA010ACTIVITY IN CLAN SHELL PCI/G - 0.037 80/G (ORY MElGHT)
NAHE OF FAC1LITY SRQ)(NS EERRY DOCKET HDe 5Qs>>25Ra2lhQcÃk-LOCAT1DN DF FACILIT'Y Lit)ESIO){E - -- -'-At.45454 REPORTIHG PERIOD IMQ TYPE AND LOMER LIHIT . ALL CONTROL NUHSER OF TOTAL NUH8ER OF INDICATOR LOCATIONS LOCAXIOB MIIII BIG){ESI Attt(t)AL gl48 LOCAT1DNS HONROUT INE OF ANALYSIS OETfCTIONa HEAN (F)b NAHE MEAN (F )b HEAN (F,) b REPORTED (IEREORt{EO GAHHA (GELI)
ILLQ) RANGE b OISZA({CE ANQ QIRECZlat{ R4(IGEh RAI{GE == .I(EASUREIIEBZS .
8 CS 137 0 '20 Oo04(
Oo02 2/
0 '5 6) TRH SFN 293 '
DISCHARGE 0
0
'5{
'5>> 0905 ll 2) Oe03(
0 F 03>>
1/
0 '3 2}
K>>40 NOT ESTAS le78(
0 F 43>>,
6/
4 ~ 96
- 4) TRH 277 '8 3 '9(
0 '3>>
2/ 2) 4e96 1 ~ Ob(
le05>>
2/ 2) 1 12 277 '8
~
81 214 0+050 0.39( 6/ 4) TRH Oe48( 2/ 2) Oe44( 2/ 2)
Oe lb Oe79 0,18>> Oo79 0 ~ 3'7>> Oo51 81>>212 0 F 100 Oe28( 2/ IS) TRH 293 ' 0 ~ 31( 1/ 2) 0 ~ 45( 1/ 2) 0 ~ 25 0 ~ 31 SFN 01SCHARGE Oe31>> Oe31 0 '5>> 0 F 45 PS 214 0 '50 0 '9{
0,14 6/ 4) 0 '8 TRH 277o98 Oebl(
0 ~ 14>>
2/ ?)
Oebb 0
Oe
'3{
36.
2/
0 '9 2)2)
PS 212 NDT ESTAS Oe29{ 4/ 4) TRH 293 ' 0 '4( 2/ 2) 0 '4( 2/
0, ll- 0.47 8FN DISCHARGE 0'e 40>> Oe47 0 16>> 0 '5 RA>>224 0 F 050 Oe39{
Oe 18 6/ 4)
Oe79 TRH 277 '8 Oe48{
Oelb>>
2/
0 2)
'9 2)
~
Oe44{
Oe37 2/ 2) 0 '1 TL 208 0 '20 Oe lo{ 4/ 6) TRH 293 ' 0 ~ 14( 2I 0 '2( 2/ 2) 0 ~ 05 0 ~ 15 SFN DISCHARGE Oe13>> Oe 15 0 07>>
F Oel7 AC-228 0,060 0 ~ $ 6{ 3/ 6) TRH 293o7 Oe53{ 2/ 2) Oe39{ 2)
Oe32 . 0 F 58 SFN 01SCHARGE 0 '8>> Oe58 Oo28>> Oe50 SR 89 F 000 6 VALUES <LLO 2 VALUES <LLO ANALYS1S PFRFORHEO 000 4/ 6) 288e78 '0( 2l 2) 4.35( 2/
90 3
'5 2)
SR 1 3~11( TRH 1 ~ 97- F 08 3 ll>> 4e08 3 '4>> 4
- a. Nominal Lover Limit of Detection (LLD) aa described in Table 3.
- b. Mean and ranbe based upon detectable measurements only. Praction of detectable measurements of ecified s pec e loocat ions is in d icated in arenthe i (Pj
W j.
45 ualit Control A qu'ality 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 Perry Nuclear Plant are forwarded to these laboratories for analysis, and results are exchanged for comparison.
Data Anal sis Data measured at the control stations for each medium were aver-aged for each sampling period. In order to describe the distribution 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 Ximits, we will perfoxm further analyses to determine if the difference is attributable to the nuclear pl'ant.
Conclusions A vast ma)ority of the indicator station data was found to be within the distribution defined by the control station data. The ALPHA-M least squares computer program identified concentrations slightly excee exceedinng 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.
Increased levels of radioactivity were observed in milk, rain-water,'air particulates, heavy particle fallout, vegetation, and in atmos-pheric radioiodine in October, November, and December following the atmo-spheric nuclear weapons testing conducted by the Republic of China in mid-October. This increase was seen in control stations as wall as indicator stations, and was widely reported in the eastern portion of the United State@.
Levels: of I in milk as high as 1.2 pCi/1 were observed. The primary radioisotopes identified in the atmospheric media were SZr, Nb, 214Bi,'nd 103Ru
46 Dose estimates were made from concentrations of radioactivity found in samples of environmental media. Media sampled include, but are not limited to, air, milk, meat, vegetation, drinking water, and fish.
Doses estimated for persons at the indicator locations were essentially identical to those determined for persons at control locations. Greater than 99 percent of those doses were contributed by the naturally 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 significant increases in environmental radioactivity attributable to the operation of Browns Ferry Nuclear Plant.
ENVIRONMENTAL RADIOACTIVITY LEVELS BROWNS FERRY NUCLEAR PLANT ANNUAL REPORT - 1981 TVA/OMS/OHS-82 7 April 1982
CONTENTS I,ist of Tables 1.21 List of Figures. ~ ~ ~ ~ 1V Introduction .
Atmospheric Monitoring 11 Terrestrial Monitoring 23 Reservoir Monitoring 41 Quality Control. 53 Data Analysis. ~ ~ 53 Conclusions'. ~ ~ ~ ~ 53
P l
1 a~
LIST OF TABLES Table 1- Environmental Radioactivity Sampling Schedule 4 Table .
2'- Atmospheric and Terrestrial Monitoring Station Locations - Browns Ferry Nuclear Plant 5 Table 3- Detection Capabilities for Environmental Sample
~ ~
Analysis 6 Table 4- Results Obtained in Interlaboratory Comparison Program. 8 Table 5" Maximum Permissible Concentrations for Nonoccupational Exposure 13 Table 6- Radioactivity in Air Filter . ~ ~ 14 Table 7 Radioactivity in Rainwater. 15 Table 8- Radioactivity in Heavy Particle Fallout .
~ ~
16 Table 9 ~
Radioactivity in Charcoal Filters 17 10- Radioactivity in Milk Table Table Table ll- Radioactivitj'n 12 '-
Vegetation Radioactivity in Soil 26 27 28 Table 13- Radioactivity in Well Water 29 Table 14- Radioactivity in Public Water Supply. 30 Table 15- Environmental Gamma Radiation Levels ~ ~ 31 Table 16- Radioactivity in Food Crops ~ ~ 32 Table 17- Radioactivity in Soybeans ~ ~ 35 Table 18- Radioactivity in Poultry 36 Table 19 " Sampling Schedule - Reservoir Monitoring 43 Table 20- Radioactivity in Surface Water 44 Table 21- Radioactivity in White Crappie (Flesh . 45 Table 22 " Radioactivity in Smallmouth Buffalo (Flesh) 46 Table 23 " Radioactivity in Smallmouth Buffalo (Whole) 47 Table 24- Radioactivity in Sediment ~ ~ 48 Table 25 " Radioactivity in Clam Flesh . 49 Table 26- Radioactivity in Clam Shell 50
\
LIST OP FIGURES Figure l - Tennessee Valley Region . 3 Figure 2 - Atmospheric and Terrestrial Monitoring Network. l8 Figure 3 - Local Monitoring Stations 19 Figure 4 TLD Locations, BFN 20 Figure 5 Annual Average Gross Beta Activity in Air Filters, Browns Ferry Nuclear Fiant 21 Figure, 6- Annual Average Gross Beta Activity in Drinking Water, Browns Perry Nuclear Plant Figure 7- Direct Radiation Levels, BFN 38 Figure 8 - Direct Radiation Levels, BFN (4-Quarter Moving Average) 38 Figure 9- Direct Radiation Levels, WBN 39 Figure 10 - Direct Radiation Ievels, WBN (4-Quarter Moving Average)
Figure 11 - Reservoir Monitoring Network 51 Figure 12 - Annual Average Gross Beta Activity in Surface Water 52
1r
~ I ttq
ENVIRONMENTAL RADIOACTIVITY LEVELS BROWNS FERRY NUCLEAR PLANT ANNUAL REPORT 1981 Introduction The Browns Ferry Nuclear Plant (BFN), operated by the Tennessee Valley Authority, is located on a site owned by TVA containing 840 acres of land in Limestone County, Alabama, bounded on the west and south by Wheeler Reservoir (see figure 1). The site is 10 miles southwest of Athens, Alabama, and 10 miles northwest of Decatur, Alabama. The plant consists of three boiling water reactors; each unit is rated at 3,293 MWt and 1,098 MWe. Unit 1 achieved criticality on August 17, 1973, and began commercial operation on August 1, 1974. Unit 2 began commercial operation on March 1, 1975. However, a fire in the cable'rays on March 22, 1975, for'ced the shutdown of both reactors. Units 1 and 2 resumed operation and Unit 3 began testing in August 1976. Unit 3 began commercial operation in January 1977.
The preoperational environmental monitoring program established a baseline of data on the distribution of natural and manmade radioactivity in the environment near the plant site. However, seasonal, yearly, and random variations in the data were observed. In order to detexmine the potential increases in environmental radioactivity levels caused by the plant, com-parisons were made between data for indicator stations (those near the plant) and control stations (those remote from the plant) in conjunction with com-parisons with preoperational data.
Staffs in the Division of Occupational Health and Safety and the Office of Natural Resources carried out the sampling program outlined in tables 1 and 19. Sampling locations are shown in figures 2, 3, 4, a'nd 11, and table 2 describes the locations of the atmospheric and terrestrial'onitor-ing stations. All the radiochemical and instrumental analyses were conducted in TVA's Western Area Radiological Laboratory (WARL) located at Muscle Shoals, Alabama, and Eastern Area Radiological Laboratory (EARL) at Vonore, Tennessee.
Alpha and beta analyses were performed on Beckman Low Beta II and Beckman Wide Beta II low background proportional counters. Nuclear Data (ND) Model 100 multichannel analyzer systems employing sodium iodide NaI(Tl) detectors and ND Model 4420 systems in conjunction with Germanium Ge(Li) detection systems were used to analyze the samples for specific gamma-emitting radionuclides. Samples of water, vegetation, air particulates, food crops, and charcoal (specific analysis for I-131) are routinely counted with NaI(Tl) detection systems. If significant concentrations of radioisotopes are identified, or, if there is a reasonable expectation of increased radioactivity levels (such as during periods of increased fallout), these samples are counted on the Ge(Li) system.
Identification of gamma-emitting radionuclides in all other types of samples
is routinely performed by analysis on the Ge(Ii) system. A TVA fabricated beta-gamma coincidence counting system is utilized for the determination of I-131 concentrations in milk.
Data were entered in computer storage for processing specific to the analysis conducted. A computer, employing an ALPHA-M least squares code, using multimatrix techniques, was used to estimate the activities of the gamma-emitting nuclides analyzed by NaI(T1). The data obtained by Ge(Li) detectors were resolved by the ND4420 software.
The detection capabilities for environmental sample analyses given as the nominal lower limits of detection (LLD) are listed in table 3. Samples radionuclide combinations such as 'u processed by NaI(T1) gamma spectroscopy were analyzed for 13 specific gamma-emitting radionuclides and radionuclide combinations a . For these analyses, and Zr-Nb are analyzed as one radionuclide. All photopeaks found in Ge(Li) spectra were identified and
'i, quantified. Many of the isotopes identified by Ge(Li) spectral analysis are naturally occurring or naturally produced radioisotopes, such as 7Be, 4oK, Bi . Pb, Pb, Ra, etc. LLDs for the analysis of the radio-nuclides listed below are given in table 3B. LLDs for additional radio-nuclides identified by Ge(Li) analysis were calculated for each analysis and nominal values are listed in the appropriate data tables. In the instance where an LLD has not been established, an LLD value of zero was assumed. A notation in a table of " values <LLD" for an isotope with no established LLD does not imply a value less than 0; rather it indicates that the isotope was not identified in that specific group of samples. For each sample type, only the radionuclides for which values greater than the LLD were reported are listed-in the data tables.
TVA's Radioanalytical Laboratories partioipate in the Environmental Radioactivity Laboratory Intercomparison Studies Program conducted by EPA-Las Vegas. This program provides periodic cross-check samples of th'e type and radionuclide composition normally analyzed in an environmental monitoring program. Routine sample handling and analysis procedures were employed in the evaluation of these samples. The EARL began processing samples in May 1980.
The results received during calendar year 1981 are shown in table 4. The
+36 limits based on one measurement were divided by the square root of 3 to correct for triplicate determinations.
'u; a
The following radionuclides and radionuclide combinations are quantified by the ALPHA"M least-squares computer code: 141'l44Ce; Cr; I;
~Cs'Cs, .Zr-Nb'o; + Mn; Zn; oCo; OK; and OBa-La.
LOOISVILLE I N D.
.t- TENNESSEE VALLEY REGION 4 (TVA NUCLEAR PLANT SITES) 4,'
W V A 1
) (" K E -N T U C K Y r ~
r l.
OAOVCAH
/ BOWLING CREEN I'
\
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+N~ N~-
NASHVILL N E S S E~
OAK RIOGE+
" "' -N g rc A R.
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JACKSON+ /
// r (xr
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7
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MEMPHIS SON J jl I J I
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+HUNTSVILLE 1 lg / ~
1 J
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LEGEND
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-HARTSVILLE NUCLEAR PLANT t ~ / /gal -PHIPPS BEND NUCLEAR PLANT M S S. / 78%V- CLINCH
~-
I RIVER BREEDER I
A L A rB A M A G EORG I A REACTOR
-WATTS BAR NUCLEAR PLANT XE -SEQUOYAH NUCLEAR PLANT' BELLEFONTE NUCLEAR PLANT
~ --
9E5[ BROWNS FERRY NUCLEAR PLANT YELLOW CREEK NUCLEAR PLANT
Table 1 ENVIRONMENTAL RADIOACTIVITY SAMPLING SCHEDULE
'ir station rotation Filter Charcoal kilter Rain- Heavy Particle ater tello t soil ~lla River Mell aration Milk water Mater Public Aquatic Life rater 'nd dedi ent Foods Muscle Shoals W M M Lawrenceburg W Rogersville M Athens Decatur M M Courtland W Site NM-l W M M Site N-2 M M Site NE-3 M M Site NM-4 Site WSW-5 W Farm B Farm Bi/Farm P Farm H Parm T Farm L Control Farms Onsite Well Wheeler Dam Elk River Tennessee River Champion Paper Co.
Various Local Farms M Weekly M Monthly (every 4'eeks) Q-Quarterly S-Semiannually A-Annually
Table 2 Atmospheric and Terrestrial Monitoring Station Locations Browns Ferry Nuclear Plant Sam le'Station Approximate Distance and Direction from Plant LM-1 BF, Northwest 1.0 Mile (1.6 kilometers) .'
IM-2 BF, North 0.9 Mile (1.4 kilometers) NNE LM-3 BF, Northeast 1.0 Mile (1.4 kilometers) . ENE LM-4 BF, Trailer Park 1.7 Miles (2.7 kilometers) NNW LM-5 BF, Davis Farm 2.5 Miles (4.0 kilometers) WSW PM-j. BF, Rogersville, AL 13.8 Miles (22.2 kilometers) NW PM-2 BF, Athens, AL 10.9 Miles (17.5 kilometers) NE PM-3 BF, Decatur (Trinity), AL 8.2 Miles (13.2 kilometers) SSE PM-4 BF, Courtland, AL 10.5 Miles (16.9 kilometers) WSW RM-1 BF, Muscle Shoals, AL 32.0 Miles (51.5 kilometers) W (Control)
RM-2 BF, Lawrenceburg, TN 40.5 Miles (65.2 kilometers) NNW (Control)
I Farm S 4.75 Miles (7.6 kilometers) N Farm B 7.0 Miles (11.3 kilometers) NNW Farm H 3.75 Miles (6.0 kilometers) N Farm T 7.0 Miles (11.3 kilometers) ENE Farm Bi (Out of business 4.5 Miles (7.2 kilometers) ENE 7/20/82)
Farm P (Sampling, begun 8.8 Miles (14.1 kilometers) E 8/3/82)
Farm N (Control) 27.0 Miles (43.4 kilometers) NW Farm J (Control) 40.0 Miles (64.4 kilometers) NNW Farm C (Control) 32.0 Miles (51.5 kilometers) N Farm Ca (Control) 32.0 Miles. (51.5 kilometers) W
Table 3 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS A. S ecific Anal ses HOMINAL LOWER LIMIT OF DETECTION LLD
- Fish, Air Vegetation Soil and clam flesh, Foods, meat, Particulates Charcoal Fallout Water and grain Sediment plankton, Clam shells poultry, Milk
~cr ~cr / mCi/km p Ci/1 ~CE/ ~d ~C// ~ dr ~C1/ dr ~cr/ d dc//k~dc dcr/1 Total a 0.4 0.01 1.5 Cross c3 0. 005 2.0 0.05 0.35 0.1 0.7 Gross B 0. 01 0.05 2.4 0.20 0.70 0.1 0.7 25 330 3331 0.02 0.5 SSS 0.005 10 0. 25 1.5 0.5 5.0 40 10 44sr 0.001 2 0.05 0.3 0.1 1.0 8 2
- All LLD values for isotopic separat.ions are calculated by the method developed by Pasternack n k and a Harle y 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 Mithin one s/eek of the collection date. Conversion factors: 1 pCi ~ 3.7 x 10 Bq; 1 mCi ~ 3.7 x 10 Bq.
Table 3 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS B. Canna Anal ses NOMINAL LOWER LIMIT OF DETECTION LLD Air Water Vegetation Soil and Clan flesh Foods,(tomatoes Meat and parciculates and milk and grain sedinenc Fish and plankton Clan shells potatoes, etc.) poultry
~c/Io ~ci/I Li ** Nal
~Ci/ dr Li
~cz/ dr ~
deci/
it I
dd Li
~ci/
I ~ce
'd Cccal/ a acr Li Ci/ vet NaI* ~Ce ~Ce Li Nal ~Ge NaI ~Ce Li) ~ce M La NaI ~Ge NaI C~eLi Naf Ge(Li>
l 1 /d ~ 1 0.03 0.55 0.35 0.35
'3 dr dr Ce 0. 35 38 90 C 0.02 33 0.22 0. 06 0.06 0. 35 0.06 4C
$ 0.47 0.10 0.60 1Cr 0.07 0.03 60 44 1.10 0.60 0.10 0.60 0. 56 0.10 60 44 200 90 1111 0.01 0.01 15 8 0.35 0.09 0.20 0.02 0.20 0.02 0.07 0.20 0.02 15 8 50 20 141d 146R 0.04 40 0.65 0.45 0.45 0.45 40 150 1 46Ru 0.03 40 0.51 0.11 0.11 0.74 0.11 40 90 1 ldrC 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 13$ 0.01 0.01 10 0.20 0.12 0.02 0.12 0.02 0.08 0.12 0.02 10 5 40 C 5 0.06'.20 15 Zl-Nb 0.01 10 0.12 0.12 0.12 10 40
$ 0.03 0.03 0. 15 529 0. 01 10 0.11 0. 03 10 20 "Nb 0. 01 5 0.05 0.01 0.01 0.07 0.01 5 15
'4Co 0.02 0.01 15 5 0.23 0.05 0.20 0.01 0.20 0.01 0.07 0.20 0.01 15 5 55 15 Mn 0.02 0.01 10 5 0.20 0.05 0.15 0.01 0.15 0.01 0.08 0.15 0.01 10 5 40 15 6$
Zn 0.02 0.01 15 9 0.25 O.ll 0.23 0.02 0.23 0.02 0.17 0.23 0.02 15 9 70 20 Co 0.01 0.01 10 5 0.17 0.06 O.ll 0.01 0.11 0.01 0.08 0.11 0.01 10 5 30 ~ 15
'4K 0.10 150 2.50 0.90 0.90 0.90 150 400 Ba-La 0.02 15 0.68 0.15 0.15 0.15 15 50 164Ba 0.02 25 0.34 0.07 0.07 0.30 0.07 25 50 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 Pasternack 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 activities of the conponents in the samples. These figures do not represent the LLD values achievable on a given sample. Water is counted in a 3.5-L Marfnelli beaker. Vegetation, fish, soil, and sedfment are counted in a 1-pint container as dry veight. The average dry veight is 120 grans for. vegetation "and 400-500 grams for soil sedfnent and f fsh. Meac and poultry are counted in a 1-pint container as dry vefght, then corrected to vet veight using an average moisture content of 70X. Average dly weight is 250 grams. Air particulates are counted in a veil crystal. The counting system consists of a multichannel analyzer and either a 4" x 4" solid ol 4" x 5" veil NaI(T1) crystal. The counting time fs 4000 seconds. All calculations are performed by the least-squares conputer progran ALPHA-M. The assumption is made that all samples are analyzed vithin one week of the collect fon date.
<<The Ge(Lf) LLD values are calculated by the method developed by Pasternack and Hal'ley as described in HASL-300. These LLD values are expected co vary depending on che activities of the components in the samples. These figures do not represent the LLD values achievable on given samples.
Water. is counced in either a 0.5-L or 3.5-L Marinelli beaker. Solid sanples such as soil, sediment, and clan shells are counted in a 0.5-L Marfnelli beaker as dry weight. The average dry weight is 400-500 grams. Afr filters and very small volume sanples are counted fn pectic dishes centered on the detector endcap. The counting system consists of a ND-4420 multichannel analyzer and either a 25X, 14X, 16X, or 29X Ge(f,f) 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 software provided with the ND-4420.
assumption is made that all samples are analyzed within one week of the collection date.
Conversion factor( 1 pCi ~ 3.7 x 10 Bq.
Table 4 Results Obtained in Interlaboratory Comparison Program A. Air Filter (pCi/filter)
Gross Al ha Gross Beta Strontium-90 Cesium-137 EPA value . TVA AVG. EPA value TVA AVG. EPA value TVA AVG. EPA value TVA AVG.
Date (+3a) WARL EARL (+3a) WARL EARL (+3a) MARL'EARL (+3a) WARL EARL 12/80 21+9 22 23 19+9 24 26 2 <2 19+9 20 22 3/81 30+13 31 31 50+9 55 49 18+2.6 18 15 14+9 15 14 6/81 28+12 29 32 54+9 62 59 19+2.6 19 23 16+9 17 18 9/81 25+ 11 26 25 51+9 61 54 16+2.6 16 19 19+9 21 20 B. Tritium in Urine (pCi/L)
Date EPA Value (+3a) TVA AVERAGE WARL EARL 3/81 .810+549 713 390 6/81 1600+585 1637 1830 9/81 2050+599 2103 11/81 2700+615 2573 2623
- a. Western Area Radiological Laboratory, Muscle Shoals, Alabama
- b. Eastern Area Radiological Laboratory, Vonore, Tennessee
- c. Efficiency curves were checked and known spikes were run. Everything found was within acceptable limits.
We are awaiting the next cross-check for further investigation.
- d. Results were mailed to EPA but not reported by them.
to obtain another sample, from EPA and reanalyze
Table 4 (Contd)
Results Obtained in Interlaboratory Conparison Progran ED Nilk (pCi/L)
Strontiu3a - 89 Strontiun - 90 Iodine - 131 Cesiun - 137 Bariun - 140 Potassiun .Cobalt - 60 value TYA AVG. EPA value TVA AVG. EPA value TVA AVG. EPA value TVA AVG. EPA value TVA AVG. EPA value TVA AVG. EPA value TVA AVG.
IM EPA
~(.33 I:AEL EAIIL (a3a) WARL EARL 'MARL EARL 'MARL EARL (a3o) WARL EARL WARL EARL ~3a) MARL EARL 1/81 0 <10 <10 20s5.2 21 20 26a17 24 21 43t16 40 41 <25 <15 1550 232 1490 1453 4/81 25 9 28 11a2.6 13 26t10 21 29 22 9 21 24 <15 <15 1559 135 1513 1674 7/81 ,25t9 23 30 17s2.6 14 16 ,01+ <15 <15 31t9 32 32 <15 <15 1600t139 1623 1620 10/81 23t9 25 28 18a2.6 17 16 52s10 49 47 25'9 27 27 1530 133 1620 1500 0
F. Foods (pCi/kg, Wet Weight) 3/81 47+9 42 44 29a2.8 38P ZI P 119t21 126 121 53t9 56 55 0 <15 <15 2640t229 2857 2917 7/81 44a9 53 51 31a2.8 31 32 82i14 80 106 45~9 43 54 0 <25 <25 2640t229 2870 3437 q 11/81 38t9 49 54 23 2.6 25 22 None 33i9 29 35 0 <15 <25 2730t237 0 9 25
- k. Values for potassiun are reported, as ng/liter of sanple.
- n. Results were narginally out of linits. Efficiency curves were checked with no conclusive findings. Subsequent results have been satisfactory.
- n. Only two results were sent. to EP*. Results were not included in their analysis.
- o. Values for potassiun are reported as ng/kg sa~le.
- p. Investigation of this problen was initiated bur. no satisfactory conclusions have been reached. We suspect difficulties arising (ron sanple inhos3ogeniety.
An incorrect weight was obtained in the gama analvsis of this sanple. Further analysis destroyed the sanple so that the correct weight could not be deternined.
Invesrigarion was conducted. No satisfactory explanation was found. Other cross-checks on this isotope in different nedia are satisfactory.
Table 4 (Contd)
Results Obtained in Interlaboratory Comparison Program C. Radiochemical Analyses of Water (pCi/L) f Gross Alpha Gross Beta Strontium - 89 Strontium - 90 Tritium Iodine 131 EPA value TVA AVG. EPA value TVA AVG. EPA value TVA AVG. EPA value TVA AVG. EPA value TVA AVG. EPA value TVA AVG.
Date (+3u) WARL EARL ~
(+3a) WARL EARL (+3o) WARL EARL (f3o) WARL EARL (f3a) WARL EARL ~(-3o WARL EARL 1/81 9+9 10 9 44r9 49 49 16+9 11 14 34%3. 1 388 28 2/81 1760L591 1917 1753 3/81 25+ 10 23 15i 25f9 26 29 4/81 27104615 2467 2723 30+10 32 28 5/81 2L+9 21 14 14+9 14 16 36+9 40 33 22f2.6 21 22 6/81 1950f 596 1990 1947 7/81 22t 10 20 22 15i9 15 18 8/81 9/81 33+ 14 29 18 i 28t9 29 26 23+9 26 23 lla2.6 11 10 26303613 2623 2713 73a13 79 73 10/81 2210+603 2263 2197 11/81 2li9 21 13 23+9 18 24 12/81 27003615 2717 2807 76+13 65 56~
D. Gamma-Spectral Analysis of Water (pCi/L)
Chromium - 51 Cobalt - 60 Zinc 65 Ruthenium - 106 Cesium - 134 Cesium - 137 EPA value TVA AVG. EPA value TVA AVG. EPA value TVA AVG. EPA value TVA AVG. EPA value TVA AVG. EPA value TVA 'AVG.
Eal ~RI) WARL EARL ~3I) WARL EARL ~33 IIARL EARL ~EW WARL EARL ~(-+3l WAIIL EARL ~RW WARL EARL 2/81 0 <60 <60 25i9 25 25 85f9 84 83 0 <40 <40 36+9 39 35 . 4i9 6 10 6/81 0 <60 <60 17+9 18 17 0 <15 <15 15+9 <40 <40 21+9 23 21 31+9 27 30 10/81 34+9 <60 <60 22i9 25 22 24a9 26 21 0 <40 <40 21+9 21 24 32+9 35 32
- f. Specific analysis for '
to test the procedures used for the analysis of milk.
- g. Investigations cLf the analytical procedure were conducted and new efficiency curves were determined. Results have been satisfactory since that time.
- h. New efficiency curves were determined subsequent to this analysis. Subsequent results were satisfactory.
- i. Excess humidity in counting room and a change in the amount of solid introduced into the sample by EPA are suspected in the difficulty with this sample type. Steps have been taken to correct or compensate for these items.
Results are possibly due to an incorrect chemical form of the precipitate counted in this procedure. Investigations continue.
Atmos heric Monitorin
~ The atmospheric monitoring network is divided into three groups.
Four, local -air monitors are located on or adjacent to the plant site in the general areas of greatest wind frequency. One additional station is located at the point of maximum predicted offsite concentration of radionuclides based on preoperational meteorological data (see figures 3 and 4). Four per'imeter air monitors are located at distances out to lO miles from the plant, and two
,remote air monitors are located at distances out to 45 miles. These monitoring stations are shown in figure 2. The remote monitors are used as control or baseline stations. At each monitor, air is continuously pulled through a Hollingsworth and Voss LB5211 glass fiber filter at a regulated flow of 3 fts/min. In series with, but downstream of, the particulate filter is a charcoal filter used to collect iodine. Each monitor has a collection tray and storage .container to obtain rainwater on a continuous basis and a hori-zontal platform that is covered with gummed acetate to catch and hold heavy particle fallout. Thermoluminescent dosimeters are used to record gamma radiation levels at each remote and perimeter station.
Each of the local air monitors is fitted with a GM tube that con-tinuously scans the particulate filter. The disintegration rate of the atmospheric radioactivity is continuously recorded at each station and radio-telemetered into the plant.
Air filters are collected weekly and analyzed for gross beta activ-ity. No analyses are performed until three days after sample collection. The samples are composited monthly for analysis of specific gamma-emitting radio-nuclides and quarterly for Sr and oSr analysis. The results are combined for each station to obtain an annual average. During this reporting period, three samples were not obtained because of equipment malfunction. These data are presented in table 6.
The'nnual averages of the gross beta activity in the air particulate filters at the indicator stations (local and perimeter monitors) and at the control stations (remote monitors) for the years 1968-1981 are presented in figure 5. Increased levels due to fallout from atmospheric nuclear weapons testing are evident, especially in 1969, 1970, 1971, 1977, 1978, and 1981.
These patterns are consistent with data from monitoring programs conducted by TVA at nonoperating nuclear power plant construction sites. Table 5 presents the maximum permissible concentrations (MPC) recommended by 10 CFR 20 for nonoccupational exposure.
Rainwater is collected monthly and a 3.5-liter sample analyzed for specific gamma-emitting radioisotopes and tritium. The results are shown in table 7.
The gummed acetate that is used to collect heavy particle fallout is changed monthly. The samples are ashed and counted for gross beta activity.
The results are given in table 8.
12 Charcoal filters are collected and analyzed for radioiodine.
The filter is counted in a single channel analyzer system. The results are shown in table 9. During this reporting period, two samples were not taken because of equipment malfunction.
13 Table 5 HAXIHUN PERNISS IBLE CONCENTRATIONS FOR NONOCCUPATIONAL EXPOSURE MPC In Water In Air
~Ci/1* ~C1/m +
Alpha 30 Nonvolatile beta 3,000 .
100 Tritium 3,000,000 200,000 1 37CS 20,000 500 103~106Ru 10,000 200 144( e 10;000 200 9szr-"Nb 60,000 1,000
'40Ba-140La 20,000 1,000, 131Z 300 100 6SZn . 100,000 2,000 54Nn 100,000 1,000 60Co 30,000 300 89Si 3,000 300 "Sr 300 30 51Cr 2,000,000 80,000 1 34CS 9,000 400 58Co 90,000 2;000
- 1 pCi ~ 3.7 x 10 Bq.
TABLE 6 RADIOACTIVITY IN AIR FILTER PCI/N(3) " 00637 BG/N (3)
NANE OF FACILITY Qf~ot~4~ERRY DOCKET NO ~ 50 25~9 LOCATION OF FAC'ILITY LIHESTO~N ALA AHA PERIGG~I9 'EPORTING TYPE A ND LOYER L IHIT ALL CONTROI. NUHBER OF TOTAL NU HBEP. OF, ItJLI GATOR LOCATIONS i GER~IN lfIIH ~HHEEE RMHiiRj NEIN LGCATIGINS NONRDUT INE
,OF ANALYSIS DETECTION a HEAN qF)b HEAN (F)b REPORTED Pf Rf QR~N ~Lt Q) R ANt(L R ANGf b ~NIRUII II Nil GROSS ALPHA 00005 0001( 3/ 52) 52 0 F 01- Oeol GROSS BETA 0~ 010 Ge 08( 456/ 465) LN4 BF TRAILER P 0 F 09( 50/ 52) 0 '8( 103/ 104) 569 0 ~ 01 6038 I e 7 HI LES NNV 0001 DN36 0001- CD 39 GAHNA (NAI) 49 CE 141s144 0003D 0
0~
~
05(
03 8/
0 F 06
- 39) LN3 BF NORTHEAST 1 ~0 HILE ENE 0 F 06(
0006 ll0006 4) 0 04(
0003-4/
0 ~ 07 10)
RU 1'03s 106 00C40 0005( 5/ 39) Lt(3 BF NORTHEAST 0F 06( 1/ 4) 6005( "
2/ 10) 0 ~ 05- 0 ~ 06 1 ~ 0 NILE ENE 0 ~ 06- 0 ~ 06 0 ~ 05- 0 '5 ZR-95st(B-95 O.O10 0~ C6( 20/ 39) ATHENS'L 0.13( 1/ 3) 0 ~ 06( 5/ 10) 0~ 01- 0013 16 9 NILES NE 0 ~ 13- 0~ 13 0002- CD 13 1-131 F 010 0 ~ 02( 6/ 39) DECATURs AL 0 F 02( 1/ 5) 10 VALUES (LLD 0~ Ol 0 ~ 62 8 2 HILES SSE 0 ~ 62- 0 F 02 BE-7 35/ 3/ 3) 10( 10/
D9( 39) 12(
'316)
NDT E'STAB 6~ ATHENSs AL 0~ 0 ~
0~ 01- 0 ~ 21 1009 NILES NE 0F 67 0 021 0 F 05- 0 GANNA (GELI) 94 CE-141 0 ~ 016 0~
0~
01(
01-8/ 78) 0 ~ 62 ATHENSs AL 1009 H.ILES NE D~
6 ~
02(
62-ll 0210)
D~
'16 VALUES R.'LLD CE-144 0 C2C 0~ C4( 16/ 78) ROGERSVILLEs 'AL - *0 ~ 05( 2/ 16) 0012 ( 3/ '16) 0002- 0 ~ 67 13 ~ 8 t'.ILES NV 0 ~ 04- 0 ~ 07 0002- 0 ~ 30 RU 103 NOT ESTAB 6061( 38/ 78) LNl BF NORTHVEST O. 02( 4/ 8) 0 F 01( 7/ 16) 00 03 1 ~ 0 NIILE N 0 ~ 01- '3 0 F 01- 02
')
0 F 0 0 0 F
- ZR 95 0 ~ 016 D~ 03( 34/ 78) RDGERSVILLEs AL 0 ~ 04( 5/ 16) 0 ~ 02( 8/ 16)
Dool- , 0 ~ 06 13 ~ 8 HILES tJV 0 ~ 02- 0 ~ 66 , 0001 0 ~ C3 NB-95 Deolo 0~ 05( 40'/ 78) DECATURs AL 0 07( 4/ DRAGS(" 8/ 16)
K-40 0061-58/
~
0 ~ 03- D012 3/
0002 0 '9 NOT, ESTAB 0012(
6006 0 ~
78) 30 LH2 BF NORTH 0 ~ 9 H I LE tJNE 0~ 16(
0 ~ 12 0 ~ 18
- 6) C013(
0~ ll- 13/ '616) 0
'9
.BI-214 De 020 04( 44/ 78) DECATURs AL 0 ~ D5( 6/ 8) 0 04( 7/ 16)
BI"212 NOT ESTAB D~
0 0
~ 02-
~ 04(
0 '9 1/ 78) 8 2 HILES SSE DECATURs AL=
0~
0 '4(
02- 0 1/
'9 8) 0
~
03-
.16 VALUES '(LLD 0 ~ 08 PB-214 0 '2D 0 ~ 04-G ~ 04(
0 02-28I 0
0 F 04 78) 08 8 ~ Z HILES SSE DECATURs AL 8 ~ 2 NI LES SSE 0 0~
~
04-
. 6 ~ 05(
03-3/')
0 F 04 De D7 0
0
~ 03(
02-6/ 16) 6 07 PB 212 NOT ESTAB
~
01( 35/
F
- 78) LN3 BF NORTHEAST 0 '2( 1/ 9)
~
0 F 01( 7/
~
16)
BE-7 0 ~
0F 0~
0068(
60-41/
0 ~ 03 78) 1 ~ 0 HILE ENE DECATURs AL 0 ~ 02-0 ~ 16(
0 '2 5/ 8) 0' Do 0 ~ 07( 9/ 16) 0 ~ 02 OS('OT 0 ~ 05- 0 ~ 47 8 Z HILES SSE 0 ~ 05- 6 ~ 47 ~ 0 DS- 0 ~ 10 TL 208 ESTAB 0 F 01( 14/ 78) LH4 BF TRAILER P 0 F 01( 2/ 7) 6 ~ 01( 3/ 16) 0 F 00 0 F 01 le7 HILES NNQ 0 ~ 01- 0 F 01 0001- 0 F 01 SR 89 0 ~ DOS 0 ~ Gl( 18/ 36) LH5 BF DAVIS F 0 F 01( 2/ 4) 0 F 01( 4/ 8) 0 ~ 01- 2 ~ 5 H ILES VSV '- 0 ~ Dl- D 0'01 SR 90 00001 O.OD( 7/
0 ~ 01
- 36) ROGERSVJLILE's AL 0 ~ 0$
0 ~ DD(
0,0 1I 01 4') 0 "e'00( 3'/ '8)
EE PNILES NV 0 ~ 00- 0 F 00 0 ~ 00 C 00
RADIOACTIVITY Itl RAIN!JATER PCI/L - 0 '37 BO/L NAt,E OF FACILITY RROV~NFERRY LOCATIOtl OF FAC)LITY L IH~STO~tl ALABAMA REPORTI toG PERIOD 9 TYPE AND LO4ER LIMIT ALL CONTROL NUMBER OF TOTAL NUMBER OF I JJOICATOP LOCATIOtJS LOCATIONS NONROUTINE OF ANALYSIS DETECT ION a MEAN (F) MEAN (F) b REPGR TED P~FRFOR'!EO (LLD) RANGr h RANG b GAMMA (NAI) 97 CC-141 144 38 ~ OGO 77 VALUES <LLO 43 '0(
'0- I/ '0 20) 43 43 RU-103 '06 40 ~ ODO 48 '0( I/ 77) DCCATUR ~ AL 48 ~ 20( 1/
'0 8) 20 VAl.UES <LLD 48 ~ 20- 48 'O 8 2 MILES SSC 48 ~ 20- 48 ZR-95 ~ 'JB-95 10 DOG 15 F 02( 19/ 77) LH4 BF TRAILER P 20 '0( 3/ 8) 19e63(
'0- 3/ 20) 10e10- 25 ~ 10 lo7 MILES Nt(M 15 60-
~ 25 10 F 10 35 F 10 I-131 15 000 22 ~ 10( 1/ 77) LHS BF DAVIS F 22 F 10( 1/ 6) 2C VALUES <LLD 22 ~ 10- 22 ~ 1D 2 ' MILES JJSM 22 ~ 10- 22 10 4/
BE-7 ,'JOT ESTAB 51 F 80(
7 ~ 30-49/
133 '0 77) LHS BF DAVIS F 2e5 MILES )JSM 67 F 88(
39 ~ 70- 115 '0 6) 56 ~ 86(
14 F 00-14/
108 '020)
GAMMA (GCL I) 46 ZR-95 40 VALUES <LLD 10 '2( 1/ 6) 10 ~ ODO
'2( 7) 1De12- 10 '2 I/ 6)
JJ8-95 So000 9e63( 2/ 40) LH5 BF DAVIS F 10 1/ 13e82(
93- 10 '2 2 ~ 5 MILES )JSll 10 32- ).0 ~ 32 13o82- 13 '2 58 '9(
8 ~
81 '7(
~
K-40 21/ 40) LH3 OF tJORTMEAST 125 F 00( I"/ 6) 2/ 6) 54 '9- 61 '8 NOT CSTAB 32 71- 125 00 1 ~ 0 HILE Ct'E 125o00- .
12S ~ 00 22 '9( 25/ 40)
F F BI-214 LM3 BF NORTHEAST 29 ~ 43( 4/ 6) 40 21( 3/ 6)
'8 23 '9-NOT ESTAB 11 '2- 48 '8 1 ~0 MILE ENE 16 ~ 24- 48 70 '1 Pi)-214 17o15( 12/ 40) LH3 BF NORTHEAST 28 '8( 1/ 6) 11 '6( 2/ 6) 28 '8 8 '5- 14 '6 NOT ESTAB F 41- 29 '7 1 D MILE ENE 28 38-
~
PB-212 14 '2( 8/ 40) COURTLAtJDt AL 18.09( 1/ 3) 6 VALUES <LLD 8 '9-NOT ESTAB 18 09 10 ~ 5 MILES MSM 18 ~ 09- 18 ~ 09 NOT ESTAB 49 '5(
F 3/ 40) LH5 BF DAVIS F 49 '5( 3/ 7) 105 F 00( 1/ 6) 43 '8- 54 '6 Oc 7 2o 5 HILES MS M 43 ~ 28- .54 ~ 06 .105 F 00- 105 00 TRITIUM 330 F 000 117 VALUES <LLO 26 VALUES <LLD 143 ANALYSIS P ERFORHED
- a. )toninal Lower Linit of Detection (LLD) as described in Table 3.
- b. Mean and ran8e based upon detectable neasureaents only. Fraction of detectable aeasurements of specified locations is indicated in parentheses (F).
- c. Identified as fallout.
TABLE B RADIOACTIVITY IN HEAVY PARTICLE FALLODT HCI/KH(2) - 37GCOOCO ~ GO BG/KH(2)
NAHE, GF FACILITY SRO'MNS FLURRY
/LABAH/
DOCKET h0 ~~~~0296 LOCATION OF FACILITY LIHESTONE REPORTING PER IOD~981 TY~E ANO LOMER L I HIT ALL CONTROL NUHBER OF TCTAL )JUHBER OF IhOICATOR LOCATiORS LGCATIONS NONROUTINE OF 1',JALYS IS OETECTIONa HEAN Ig)b NAHE HEAN (F) b HEAN IF)b REPORTED
~(L Q) RANG/ ~RAN b
'50 09< 117/ 117) I ~ 354 13/ 1+04 I 26/
GROSS BETA 143 0 1~
0~ 08- 3 ~ 73 LH4 BF TRAILER P 1 ~7 HILES )JNM 0 '6- 3 '313) 0+12- 2 '926)
- a. IIominal Lover Limit of Detection (LLD) as described in Table 3.
- b. Hean and range based upon detectable measurements only. Fraction of detectable measurements of specified locations is indicated in parentheses (F).
TABLE 9 RADIOACTIVITY IN CHARCOAL FILTERS FLURRY PCI/Y (3) - 0 ~ 037 BQ/H(3)
NAHE OF FAC ILITY ~Fi Vt-'Q DOCKET NO ~ 50-259 '~60 296 LOCATION OF FACILITY LIH~STONQ ALABAMA REPORTING FERIOD 198/
CONTROL NUHBER OF TYPE AND LOi(ER L IHIT ALL TOTAL WUHBER OF INDICATOR LOCATIONS ~OCC T~IGtl M TH ~Hg~HJ ilhN~~AH LOCATIONS NONROUT INE BETE CT IONa MEAN ([)b NAME HEAN (g)b REPORTrD OF ANALYSIS RANG~ ((I ST~ANC ~AN" A I P~rCT I ON RANGE ~H~ASUR HEN T S (QQ )
PQRF~ORH 0 IODINE IN AIR '20 03( 62/ 466) COURTLANDt AL 0 '6( 2/ 50) 0 ~ 02( 13/ 104) 570 0 0 0 '2- 0 '9 I 0 ~ 5 > ILES 'a S) 0.02- 0.09 0+02- 0 '%
- 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).
18 Figure 2
. ATMOSPHERIC AND TERRESTRIAL MONITORING NETWORK RM.2BF LAWRENCEBURO yPULASKI FAYETTEVILLE gy PM-IBF WILSON WHEELER ROBE SVIL OAM OAM ATHENS FLORENCE PM-2BF FFIEL MUSCLE HUNTSVILLE SHOALS BROWNS FERRY NUCLEAR PL NT RM-IBF LEIGHTON TUSCUMBIA COURTLANO PM-4 F OECAT PM-3BFO IO MILES pRUSSELLVILLE UNT SV IL HARTSELLE OAM 25 HALEYVILLE CULLMAN 45 MILES Q- ENVIRONMENTAL MONITORING STATION NOTE: THE FOLLOWING SAMPLES ARE COLLECTED FROM EACH STATION:
AIR PARTICULATES RAINWATER RADIOIODINE SOIL HEAVY PARTjCLE FALLOUT
Figure 3 LOCAL MONITORING STATIONS',
BROWNS FERRY NUCLEAR PLANT ATHENS US HWY 72 BFN ALA. HWY 20 Legend Air Monitor DECATUR Automatic Well Sampler H Dairy Farm Scale 0 I 2 8 0 5 Miles
20 Figure 4 j'(
I) )I h,' <<<<<<$
'1 'r
.ht,',
t'(ht("
TLD Locations t h)1 l.,r) l I 'v ,'tlt1 t rt
('~
~
Ir I)
) ~
)l;
",j'ij(',
I>>
JJ t
~J I. n r
") .$ .
I 1,
'l
' ' )I
., Igp
,'>> tl 1, )
)$ (j 4,th I
<< t)t>> O'I xt
+I) I r'I a( J I w<
n al Er tI';
trl >> I <<I t)
~ t,(j I
)
/ <<I IW
,'l!', n t'I ~
n,, 7
'O
.I!Ihg I)$.
al <<I I w r ~ IA I 1<>
f l>>~
~
,roh(t I '
)
I I I ~
I
~A I <<
't I s, I I
al W".'jt
>>'I
'<< S 4
I, I ) I <<
, I
~,~t . a r t
r I2
,()
W
)
gsk ' I I )
I, 1 )I
) I J" '1'pi '
.)(.Y5~:
'KR<< ( I/)
""O))I I I ~<<~I I <<Tl r <<
<< I I PI ~ 0
\
ISI<<SE <<$
~$ 0 V I
Figure 5 AWUAL AVERAGE .
.30 6ROSS 8ETA ACTIVITY IN AIR FILTERS HROWS FERRY NUCLEAR PLANT Preoperational Phase Operational Phase
.25 0'
o co 4J 0
.20 ~v IJ 4J N +v 4J CC 0
0 4J wc O 0
.15 Average: Preonerational Phase
.10
.05 I
19 68 ?969 1970 ,1971 1972 1973 19730 1971 1975 1976 1977 1978 1979 1980 1981
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 results are shown in table 10.
Cow censuses were conducted in May and September 1981. It was determined that there are no dairy farms nearer the plant than the nearest farm being sampled. During this period however, one of the dairy farms being sampled (farm B, table 2) went out of business and all .cows were sold. Another dairy farm (farm P) was added to the monitoring program on August 3, 1981.
V~e etation Vegetation is sampled quarterly at the farms from which milk is-collected 'and analyzed for gamma-emitting radionuclides. Approximately 1-2 kilograms of grass is broken or cut at ground level and returned for analysis.
Efforts are made to sample vegetation that is representative of the pasturage where cattle graze. Table ll gives the results obtained from the laboratory analyses of these samples.
Soil Soil samples are collected annually near each monitoring station to provide an indication of a long-term buildup of radioactivity in the environ-ment. An auger or "cookie cutter" type sampler is used to obtain samples of the top two inches (5 cm) of soil. These samples are analyzed for gamma-
. emitting radionuclides, Sr, and oSr. The results are given in table 12.
Ground Water An automatic sequential-type sampling device has been installed on a well downgradient from BFN. A composite sample from this well is analyzed for gamma-emitting radionuclides monthly and composited quarterly for determination of tritium. A grab sample is also taken from a control well upgradient from the plant. The results of the analysis of well water are shown in table 13.
Drinkin Water Potable water supplies taken from the Tennessee River in the vicinity of BFN are sampled and analyzed for gross beta and gamma-emitting radionuclides, and composited quarterly for tritium, Sr, and oSr analyses. The first potable water supply downstream from the plant is equipped with an automatic sampler with samples collected and analyzed weekly. The sampler is located on the water intake structure and takes the sample from the river as the raw water is drawn into the water treatment facility. Two additional supplies
24 downstream and one public water supply upstream are sampled by taking monthly grab samples of treated water at user points. Table 14 indicates the results from the analysis of drinking water samples. During this reporting period, six of the weekly samples were not taken because of the malfunction of automatic sampling equipment.
Figure 6 shows the trends in gross beta activity in drinking water from 1968 through 1981. The annual average level from the raw water samples tends to run slightly hi'gher than the average for treated water samples; however, the levels are consistent with the activities reported in surface water samples taken upstream from BFN (figure 12) and in samples taken from the Tennessee River in preoperational monitoring programs conducted by TVA at other sites.
Environmental Gamma Radiation Levels Bulb-type Victoreen manganese-activated calcium fluoride (Ca~F: Mn) thermoluminescent dosimeters (TLDs) are placed at sixteen stations around the plant near the site boundary, at the perimeter and remote air monitors, and at nineteen additional stations out of approximately five miles from the site to determine the gamma exposure rates at these locations. The dosimeters, in energy compensating shields to correct energy dependence, are placed at approxi-mately one meter above the ground, with three TLDs at, each station. They are annealed and read with a Victoreen model 2810 TLD reader. The values are corrected for gamma response, self-irradiation, and fading, with individual gamma response calibrations and self-irradiation factors determined for each TLD. The TLDs are exchanged every three months. The quarterly gamma radiation levels determined from these TLDs are given in table 15, which indicates that average levels at onsite stations are approximately 2-4 mR/quarter higher than levels at offsite stations. This is consistent with levels reported at TVA's nonoperating nuclear power plant construction sites where the average radiation levels onsite are generally 2-6 mR/quarter higher than levels offsite. The causes of these differences have not been completely isolated; however, it is postulated that the differences are probably attributable to combinations of influences, such as natural variations in environmental radiation levels, earth moving activities onsite, the mass of concrete employed in the con-struction of the plant, and other undetermined influences.
Figure 7 compares plots of the data from the onsite or site boundary stations with those from the offsite stations over the period from 1976 through 1981. To reduce the variations present in the data sets, a four-quarter moving average was constructed for each set. Figure 8 presents a trend'lot of the direct radiation levels as defined by the moving averages. The data follow the same general trend as the raw data, but the curves are smoothed considerably.
Prior to 1976 measurements were made with less sensitive dosimeters, and consequently the levels reported in the preoperational phase of the moni-toring program are 1-2 times the levels reported herein. Those data are not included in this report. Therefore, for comparison purposes, figures 9 and 10 depict the environmental gamma radiation levels measured during the construction of TVA's Watts Bar Nuclear Plant to the present. Note that the data follow a similar pattern to the BFN data and that, as discussed above, the levels reported at onsite stations are similarly higher than the levels'at offsite stations.
25 Poultr and Pood Cro s Pood crops and poultry raised in the vicinity of BFN and at control locations are sampled as they become available during the growing season, and analyzed 'for gamma-emitting radionuclides. During this sampling period, samples of cabbage, corn, green beans, peaches, potatoes, turnip greens, tomatoes, soybeans, and poultry were collected and analyzed for specific gamma-emitting radionuclides. No sample of soybeans or cabbage'as taken from-a control location. The results are given in tables 16, 17, and 18.
RADIOACTIVITY Ik HILK PCI/L - DH037 BG/L NAHE OF FACILITY DHARMA(S FLURRY DOCKET t(O ~ 50-25~92~60 ~96 LOCATION OF FAC ILITY~LillATONE ALABAHA RCPORTIttG PERIOD 19&1 TYPE AND LO'MER LIH IT ALL CONTROL NU)E DER OF-TOTAL NUHBER OF INDICATOR LOCATIONS LOCATIQN IIITH HIO~HT ANNUAL EHAN LOCATION/
toONROUTINE OF ANALYSIS P~RF g R H~O GAHHA (NAI)
~II OETECTIO HEAIN AWOr'3 (F)b NAHE HEAN ( ) HCAN (IF)
RAN ~V.
REPORTED A yRQ~HNTS 107 CS-137 10 F 000 63( 3/ 55) PAGE FARH 13 '3( 3/ 4) 10 '0(
'0- 1/ 52)
Ill 70- 16 F 00 8 ~ 75 t'.ILES E 11H70- 16 F 00 10 10 'G 15D ~ ODD 1246 '1(
'0- 55/ 55)
'0 THRASHER FARY 1308 '1( 12/ 12) 1232 '5( 52/
'052) 1049 1569 7 ~ 0 HILES ENE 1127 20- 1569 20 ,
1037H20 1391 IODIN'E IN HILK DH500 253 VALUES <LLD 201 VALUES <LLC 454 ANALYSIS PER FORHCO GAHHA (GELI) 6 CS-137 5 ~ 000 8 '0( 3/ 6) SHITH FARH 10 '6( 1/ 1)
K-40 'tOT ESTAB 7~ 54-15DD F 50(
15 16 6/ 6) 4 ~ 75 HILES THRASHER FARH N ID+16-1845 'D(
10 1/
'6 1) 1287 F 00- 1845HDD 7 0 HILES ENE 1845 ~ 00 1845 F 00 81-214 RIOT ESTAB 20 63( 5/ 6) SHITH FARH 30 F 43( 1/ 1) 7 39- 30 43 4 ~ 75 HILES N 30H43 30 F 43 PB-214 NOT ESTAB 18 14
'5(
'9- 3/
2D ~ 63
- 6) BROOKS FARM 7~0 HILES NNM 20 '3(
20 1/
2D ~ 63 1)
PB-212 NOT ESTAB 14H88( 3/ 6) SHITH FARH 20~96( 1/ 1)
TL-258 '
9HS3-
'3( 2/ 6) 20 '6 4~75 HIl CS N 2D ~ 96-6H48(
2DH96 1/
'8 1)
NOT ESTAB 89 2 '8- F 48 PAGE FARH 8 ~ 75 HILES E 6H48- 6 SR 10 F 000 61 VALUES <LLD 52 VALUES <LLO 113 ANA(.YSIS PERFORHED
'5( 61/ 4 ~ 74( 13/ '3( 40/
SR 90 113 2 000 3 F 01- F 19
- 61) SHITH FAR)t 4 75 HILES N 3H12- 8 19
- 13) 4 2 '6- 7 '652)
- a. Nominal Lover Limit of Detection (LLD) as described in Table 3.
- b. Hean and range based upon detectable measurements only. Fraction of detectable measurements of specified locations is indicated fn parentheses (F).
TABLE ll RADIOACTIVITY IN VEGETATION PCI/G 00037 BO/G (DRY VEIGKT)
NAME OF FACILITY SROVNS FERRY DOCKCT NO ~ 50-259 260 LOCA'TION QF FAC ILITY~IMESTOtlE ALABAMA REPORTING PERIOD~~98 TYPE ANO LO'VCR LI HIT ALL CONTROL NUNSER OF TOTAL NUNBCR OF INDICATOR LOCATIONS LO ATIOII VT TK KIGKEST ANtiUA MEAN LOCATIONS NONROUT INE OF ANALYSIS DETECT IONa HEAN (F)b NAME HCAN (F)b HEAN CF) b REPORTED
~FR F 0 R R - 0 CLLO) R~NI+b GROSS BETA 0 ~ 200 26 '3(
7070-20/. 20) 48082 SITTING FARM 35 ~ 32(
88-2/ 2) 26 '2(
10007-16/
'416) 36 4~5 MILES ENE 31 38 75 45 GAMNA (GCL I) 38 CE-141 00200 1 ~ 93( 5/ 21) THRASHER FARM 2 '2( 1/ 4) 93( 4/ 17)
CE-144 00270 1021-1.56( 1?
2e92 I 21 )
700 IIILES ENE LOONEY FARM 2 ~ 92-2060C 2/
2 '2 4) 1 1016-
'9C 13/ 17) 2 '6 op.-144 NOT ESTAB 0023-3 '0( 5 ~ 49 3/ 21) 5075 MILES LOONEY FARM CNE 0 ~ 41-4061 ( 1/
4 '0 4) 1 0
2 '1(
~ 30- 5 '5 1/ 17)
RU-103 5 200 1~
F 43-25(
4e61 6/ 21) 5 75 MILES EtlE LOONEY FARM 4061-1053( 1/
4 '1 4) 2 '1- 2 '1 1 ~ 39( 4/ 17) 0 22- 2014= 5 ~ 75 HILCS ENE 1 53- 1053 1010- 1 ~ 65 RU-106 0 510 1 ~ 28(
1001-2/ 21) THRASHER FARM
-7 ~ 0 MILES. CNE 1 ~ 54(
1054-1/ 4) 1
'9-
~ ll( 2/ 17) 1 05.4 1054 0 1034 CS-137 00060 0016( 14/
'2 21) BITTIilG FARM 0032( 1/ 2) '1( 7/ 17) 2R-95 0 110 0007
'6( 0 10/ 21) 4 ~5 MILES ENE SITTING FAR)I 0032 3e95( 1/
0032 2) 0 0
1
'690( 8/
0 ~ 40 17) 0 1
~ 17- 4 ~ 46 4 ~ 5 MILES ENE 3 ~ 95- 3095 0 '0-
~
4 '1 NB-95 0005G 2 '4( 18/ 21 ) BITTING FARM 4038( 2/ 2) 2065( 13/ 17) 0006- 10 ~ 28 4~5 HILES ENC 0 ~ 39- 8036- 0 F 06- 9 '6 K-40 'COT'ESTAB 10 ~ 40( 21/ 21) BROOKS FARM 17086( 4/ 4) 11 'TC 17/ 17) 2000- 25098 700 HILES tRICV 2 ~ 88- 22 F 06 2 '3- 28 '5
'lN-54 0 050 0 F 08( 21) THRASHER FARH 0 ~ 10( 1/ 4) 0 10( 4/ 17)
NOT ESTAB F 1818(
0 ~ 06-02(
0 ~ 10 1/ 71) 7 ~ 0 HILES Ct(E SITTING FARM 0 ~ 10-0 ~ 02( 1/
0 '0 2) 0
~
F 08-17 VALUES <LLO 0 '2 0 ~ 02- 0.02 4 ~5 MILES ENE 0 ~ 02- 0 02 II I-214 0 '00 0035( 9/
'2 21) SITTING FARI' 0 ~ 49( 1/ 2) '0( 10/0'0641?)
BI-212 NOT ESTAB 0~
0 14-
'3( 0 1/ 21)
~5 H ILES ENE LH1 BF tlORTHVEST 0 ~ 49-0 ~ 33( 1/
0 '9 I) 0 0011-17 VALUES <LLD, PB-214 NOT ESTAB 0033-0020( 19/ 21) 0 '3 le0 NILE SITTING N
FARH 0 ~ 33-0 27(
~
2/
0033
- 2) 0 '1( 12/ 17) 0~ Sl- 0041 4eS MILES ENE 0016- 0038 0010- 0~ 50 oS 212 NOT STAB y 20/ 21) LH1 SF NORTHVEST 0 '2( 1/ 1) 0017( 14/ 17)
RA-226 NOT CSTAB 0 03-
'9(
~ 0 3/
~ 72 21) 1 ~ 0 NILE BROOKS FARM N 0 ~
0014(
72-1/
0072 4) 0 ~ '04-0 F 07(
0 '3 2/ 17)
BE-7 NOT E'STAB 0
0 5 '5(
~ 06-21/
0 ~ 14 21) 700 MILES NNV LOONEY FARM 0 ~
7017(
14- 0 '4 4/ ,4) 0 ~ 03-5 96( 17/
F 11 17)
TL-208 NOT ESTAB 1012-0 08(
15063 16/ 21) 5075 MILES ENE LHI SF NORTHVEST 1 ~ 12-0029(
13061 1/ 1) 2 ~ 29-0 ~ 05(
14 '0 9/ 17)
AC-228 NOT ESTA B 0
F
~
0023(
00-18/
0 ~ 29 21) 1 ~ 0 NILE LN1 BF NORTHVEST 0 ~ 29-0 '6( 1/
0 '9 1) 0 ~ 01-F 17(
0 '6 14 I 17) 0007- 0 ~ 48 1 ~ 0 HILE N 0 ~ 36- 0 36 0 ~ 02- 0 ~ 52
- a. Nominal Lover Limit of De t ection (LU)) as d escribed in Table 3.
- b. Mean and range ba sed upon detectable measurements only.. Fraction of detectable measurements of specified locations is indicated in paientlieses (p).
TABLE 12 RADIOACTIVITY IN SOIL PCI/G - 0 '37 BD/G (DRY INEIGHT)
NAHE OF FACILITY QRGV)JS FERRY DOCKET tJO ~ 50 259 ~ 26~0296 LOC A TI ON OF F AC (L I T Y L I YES TONr ALAnAYA REPORTING PERIOD~19IGNIS I TYPE AtJD LOVER LIMIT ALL CotJTROL NUMBER OF TOTAL NUl'BE4 OF I'NDICATDR LOCA TI OIJS LOCAT NONROUTINE OF ANALYSIS DETECT ION YEAN (() NAYs HEAN ([) MEAN (f) REPORTED PERFORMED GAYHA (GELI)
(L D) RANGE C~ISTRMC ~RMII CIR I:TICII ~RRNR RANGE ~RISC~RIMMTS 11 CE-141 0 '30 0006( 1/ o) LH2 BF NOPT4 o. oe( I/ 1) 2 VALUCS <LLD 0 '6- 0 ~ 06 C 9 MILE NNC 0 ~ Ce- 0 ~ 36 CC-144 0 '60 0013( 4/ 9) ROGERS VILLC~ AL 0 ~ 24( I/ I) 0 ~ 10( 2/ 2) 0 F 08- 0 ~ 24 13 ~ 8 MILES NV 0~ 24- 0 ~ 24 0008- 0 ~ 12 RU-1D3 NOT ESTAB 0002( 4/ 9) LH1 BF NORTHVEST 03( 1/ 1> 0 '3( 2/ 2)
CS-137 0 '20 0032-De55(
3 9/
'3 9) 100 MILE ROGERSVII.LCC tJ 0~
0 ~ 63-1~ 82(
0003 1/ 1) 0~
0 '6(
02- 0 2/
'3 2) 0~ 10- F 82 13 ~ 8 MILES tJV 1082- I ~ 82 0 ~ 64- 1028 Zo-95 0 ~ 030 0-06( 8/ POGERSVILLEt AL 0 ~ 11( 1/ 1) 0 'B( 2/ 2) 0 F 04 Dell 13 8 MILES WV 0 ~ 11- F 11 G ~ 04- 0 12 ti'8-95 0 010 0014( 9/ 9) VILLE'L 0 ~ 35( 1/ I) 0 'R( 2/ 2)
K-40 0
~
'50 0006-5042(
0 9/
'5 ROGERS 1308 MILES NV LHR BF TRAILER P 0 035-R 7 13(
-:0 35 1/ I )
0 4
09-
'7(
~ 0019 2/ 2)
BI-214 0 ~ 050 1 01(
F 13 9/
9)'090-9) 107 KILCS tJNV LH2 BF NORTH 7 ~ 13-F 40(
7 1/
'3 1) 4097-D090(
4098 2/ 2)
C ~ 51- 1 ~ 40 009 HI LE NtJE 1 ~ 40- F 40 0 ~ 78- F 02 BI-212 00100 0 66(
0029-9/
0086
- 9) DECATUR'L O086(
86-1/
86
- 1) 0 '6(
0034-2/ 2) 8 ~ 2 MILES SSC 0 ~ 0 F 0 ~ 58 Pf'.-214 0 '50 1 08( 9/ 9) LH2 BF NOPTH 1 ~ 46( 1/ 1) 0092( 2/ 2)
PB-212 NOT ESTAP 0 F 58-1 ~ 08(
0059-F 46 9/
1 ~ 43 9) 0 9 MILE NtJE DECATUR'L 8 ' t(ILES SSE 1046-F 43(
1 ~ 43-I 1/
~
1043 46 I) 0081-0 0 '4(
'6-1 ~
2/
1 ~
')
04 03 RA-226 0 '50 1 ~ 16( 9/ 9) ATHCNSc AL F 43( 1/ I) 0 '0( 2/ 2)
RA-223 NOT ESTAB De51-36(
2 '3 4/ 9>
10 ' YIILCS NE LKc BF TRAILEP P 2 ~ 43-0 F 46(
2 1/
I>
0~ 78-2 VALUES <LLD F 02 I) E-7 160 0 '9
'4( 0 2/
~ 46 9) 1 ~ 7 MILE;S JJNV LHz BF NORTHEAST 0046-0 ~ 26(
0 1/
~ 46
- 1) '5( 2/ 2) 0 F 0
'1- '6 0 0 0 26 1 ~ 0 HILC FNE 0 ~ 26- 0 0019- 0 30 TL-208 DE 020 0 '8( 9/
~
- 9) LH1 BF NORTHVEST 0 F 48( 1/ I) 0 '3( 2/
~
2) 0~ 18- 0 F 48 1 ~ 0 t( I LE ti 0 ~ 48- o.48 0031- 0 ~ 36 AC-228 0 060 12( 9/ 9) DECATUR'I. I ~ 46( 1/ 1) 97( 2/ 2)
~ 1 0 '2- 1 ~ 46 8 ~ 2 HILES SSE 1 ~ 46- 46 DE 0 '0 - 1 ~ 05 PA-234M NOT ESTAB 3 '50( 1/ '9) LK2 BF NORTH F 50(
1 ~
I/ 1> '9(
'9- '9 2) I/
SR 89 I ~ 500 3050-9 VALUES <LLD 3050 0 ~ 9 HI LF Nt(E 3 ~ 50- 3 '0 4 4
2 VALUES <LLD 4
11 AYAI.YSIS PERFORMED SR 90 De300 9 VALUES <LLD 2 VALUFS <I.LD 11 ANALYSIS PERFORHED
- a. Itominal Lower Limit of Detection (LLD) as described in Table 3.
- b. Mea n and ranoe based upon detectable measurements only Fraction of detectabl e measurements of specified locations is indicated in parentheses (p).
TABLE 13 RADIOACTIVITY IN QELL )I'ATER PCI/L - ON037 BQ/L NAME. OF F "CILITY BROl'NS FERRY DOCKET NON~l~~oa26~0 LOCATION OF FACILITY I lr~STOgr AL/BAHA REPORTING PERIOD~>~
I YPE ANO LOVER LIMIT ALL CON TROI NUNBER OF TOTAL NUMBER OF INDICATOR LOCATIONS ~LO IITION HITH HIOH'SI LLI'U'L MCRII LOCATIONS NONROUT INE OF ANALYSIS OETECTIONa XE/N (F)b R(A ROE MEAN (F)b MEAN ( )b REPORTED RANGE b ~ISTANC II; I OIRgCTIOR ~R4N R R ~IN ASUR~~HTS GAMMA (NAI )
I CS 12 VALUES <LLO 7 VALUES <LLD ANALYSIS PERFORMED GAMMA (GEL I) 7 K-40 NOT ESTAB 1 VALUES <LLD 99 F 84( 3/ 6)
BI-214 NOT ESTAB VALUES <LLD 86 ~ 85-28 F 00(
115 1/
'0 6) 28 F 00- 28 'G PB-214 NOT ESTAB 1 VALUES <LLD 12 '9(
7~42-2/
17 '6 6)
PB-212, NOT ESTAB 1 VALUES <LLD 6 6
48(
'8VALUES F 1/
6N48 6)
TRITIUM 330LN 00 0 4 VALUES <LLD 4 <LLO 8 ANALYSIS PERFORNED
- a. Nominal Lover Limit of Detection (Lu)) as described in Table 3.
- b. Mean and range based upon detectable measurements only. Praction of detectable measurements of specified locations is indicated in parentheses (p).
TABLE, I4 RAO IOACTIV IT Y I ti PUBL IC )JAT ER SUPPLY PCI/L 0 ~ C37 BQ/L NAHE OF FACILITY PROM)JS F/RRY DOCKET NO ~ -2<9 60 296 LOCATION OF FACILITY QIH~SYON~r ALABAMA REPORTING PERIOD~~8 TYPE. AND LO)RER L IH IT ALL CONTROL NUMBER OF TOTAL NUMBER OF INDICATOR LOCATIOtJS QQQATIOh NITH HIGHEST At(NUAL MEAN LOCAT I OQS NONROUTI WE OF ANALYSIS DETECT I 0'J a IJEAN (F)b tJAHE HEAN (F) b HEAN (F) REPORTED P f R~FR~MF (Q~L ) P,AN~Gb O~ISTANC ANO STRICTION RIINOEO ~R4 EO ~HAS~R~EN TS GROSS BETA 2 '00 3%96( 61/ 72) CHAMPION PAPER 4 ~ 11C 44/ 46) 3%20( 11/ 13) 85 2%46- 14 F 70 TRJ'82 ' 2 46>> 14 ~ 70 2 50- 4 08 GAHHA (tJAI )
70 61 VALUES <LLO 9 VALUES <LLO llew ANALYSIS PERFORMED GAHHA CGBLI) 15 40 ESTAB 74 F 11( 2/ 11) CHAMP IOtJ PAPER 74 11( 2/ 8) 101%00( I/ 4)
'9-K JJOT F 72 75 F 73 TRH 282 ' 72 ~ 49- 7S ~ 73 101 F 00 101 F 00 I-214 24%80( 8/ 11) SHEFF I E LD ~ AL ROB 28%91( I/ 1) '17%78( 2/ 4)
B NOT ESTAB 12 F 00- 43 F 03 TRH 254 3 28%91-
'3( 3/
28 '1 8) 13 60-
'2( 21%95 2/
4/ 16 15 PB-214 NOT ESTAB 15%03(
lb 23 '3 11) CHAHPIOtJ PAPER TRH 282 ' 12 52- 23 '3 lS%68- 15 '5 4) 1/ 11) SHEFF IELDi AL 11 '0( 1/ ..1) 16 18( 21 19 '2 PB-212 NOT ESTAB 11%90( ROB 11%90- 11%90 TRJ'. 254%3 11%90- 11%90 13%13-I/ 4)
~
-5 F 84(
TL-208 NOT ESTAB 11 VALUES <LLD 5%84-4 5
VALUES <LLO
'4 SR 89 10%000 12 VALUES <LLO 16 ANALYSIS PFRFORHEO 2 F 000 3 '5( 1/ 12) SHEFFIELO+AL ROB 3 '5(
'5- '/-- 1/ . 4) 4 VALUES <LLD SR 90 16 3%25- 3 '5 TRH 254%3 3 3%25 1/
TRIT IUH 16 330 000 369%21(
369 '1- 1/ 12) 369 '1 CHAHPION PAPER TRK 282 6 369 21(
369 21- 369 '1
~ 4) 376 F 59(
376 F 59- 376 '9 4)
- a. Nominal Lower Limit of Detection (LLD) as described in Table 3.
Mean and range based upon detectable measurements only. Fraction of detectable measurements of specified locations is indicated in parentheses (F).
b.
31 Table 15 ENVIRONMENTAL GAMMA RADIATION LEVELS Average External Gamma Radiation Levels at Various Distances from Browns Ferry Nuclear Plant for Each Quarter - 1981 mR/Quarter Distance Avera e External Gamma Radiation Levels b miles 3rd uarter 4th uarter 0-1 18.8 + 1.2 21.7 + 2.0 21.0 + 1.6 20.0 + 1.5 1"2 17.1 + 1.2 17.3 + 2.2 16.7 + 3.2 20.0 + 5.0 2-4 16 5 + 1.",2
~ 15.6 + 1.8 16.2 + 3.3 16.5 + 1.7 4-6 16.6 + 1.1 17.0 + 1.6 17.1 + 2.2 16.6 + 1 ~ 3
>6 16.5 + 2.2 16.8 + 2.7 15.9 + 3.5 16.6 + 2.3
- Average, 0-2 miles (Onsite) 18.4 + 1 ' 20.6 + 2.8 19.9 + 2.7 20.1 + 2.1
- Average,
>2 miles (Offsite) 16.5+ 1.5 16.7 + 2.0 16.6 + 2.8 16.6 + 1.7
- a. Data normalized to one quarter (2190 hours0.0253 days <br />0.608 hours <br />0.00362 weeks <br />8.33295e-4 months <br />).
- b. All. averages reported +la (68 percent confidence level).
.TAPLE 16 RADIOACTIVITY IN FOOD. CROPS PCI/KG 0~ 037 BQ/KG (MET I(EIGHT)
NAHE OF F/CILITY /Roar>S FLURRY SOCKET NO ~3~5. I"A'-TOG LOCATION OF FACELESS~IN STONE AI ABAHA REPOPTIIRG PER IOD~PQ TYPE A)ID LOVER LIHIT ALL CONTROL NUMBER OF TCTAL NUMBER OF INDICATOR LOCATTOII I'ITN NIGIIEST ANNIIIL MEAN LOCATIONbs NONROUTINE LOCATIONS WEAN (F) 'I A I!E OF AN ALYS trRFORV IS DETECT IONa (LLO) RANGE V E AN (F~) HEAN RAN E (P REPORTED
~NEAR ~AGENTS GROSS (OETA GAHwA (GELI )
1 25 F 000 4286 86(
4286 '6- 1/
4286 '6 1)
RADIOACTIVITY IN CABBAGE,
)IILES N 4286 '6(
')286N86- 4286
'/ '6 1) 1 K 40 NOT ESTAB 1873 F 00( 1/ 1) MILES N 1873M OC( 1/ 1) 1873 ~ 00- 1873 F 00 1873M 00- 1873 F 00 o I-'R14 'iOT EST AB 13 F 40( 1/ 1) HILLS N 13 ~ 40( 1/ I) 13 ~ 40- 13 40 13 ~ 40- 13N40 PB-212 '5( 1/ 1) '5( 1/
NOT ESTAB 15 15 ~ 75- 15 F 75 4 H ILES tA 15 15N75- 15 '5 1)
RADIOACTIVITY IN CORN 25 F 000 4163 '2( 1/ 1) 4163~82( 1/ 399S ~ 66( 1/
'2 1) '6 1)
GROSS BETA LH2 BF NORTH GAHVA (GELI) 2 4163 '2- 4163 F 82 0~9 NILE t(tiE 4163 '2- 4163 3995 '6- 3995 2
K 40 NOT ESTAB 1964 F 00( 1/ 1) LH2 BF 'NORTH 1964 F 00( I/ 1) 1932 F 00( 1/ 1) 1964 F 00- 1964 F 00 "
0 ' '9ILE tiNE 1964 F 00- 1964N00 1932 F 00- 1932 F 00 RADIOACTIVITY Iti GREEN BEANS 4874 '3( 1/
'3 1) 4874 '3( 1/ '4( 1/
GROSS GAHHA BETA (GELI) 2 25 F 000 4874 '3- 4874 2 H ILES NNM 4874 F 83- 4874 '3 1) 3251
-3251 '4- 3251 '4 1)
N K-40 NOT FSTAB ~ 2132 F 00( 1/ 1) 2 I' L E S NNii 2132 F 00( 1/ 1) 1682 F 00( 1/ 1) 2132 'C- 2132 F 00 2132 'C- 2132 F 00 1682 ~ 00- 1682 F 00 BI-214 NOT ESTAB 1 VALUES (LLD 20.50( 1/ 1) 20 ~ SG- 20 F 50 PB-212 NOT ESTAB 6 ~ 89( 1/ 1) 2 HILES NN)i 6 ~ 89( 1/ )) 29 58( 1/ 1) 6 ~ 89- 6 ~ 89 5 ~ 89- 6.89 29 ~ 58- 29 F 58
- a. Nominal Lower Limit of Detection (LLD) as described in Table 3.
- b. Mean and range based'pon detectable measurements only. Fraction of detectable measurements of specified locations is indicated in parentheses (F).
TABLE 16 (Contd)
RADIOACTIVITY 1'OOD CROPS PCI/KG - 0~ 037 EO/KG (NET VEIGHT)
NAH'F FACILITY BROVNS FERRY LOCATION OF FAC ILITY~H~Tg1ti(, ALAQAHA REPORTI)MG PERIOD )o81 TYPE AND LONER LIHIT ALL CONTROL NUHBER OF TOTAL NUHBER OF INDICATOR LOCATIONS LOCAT TOM MATH HIGH~S~TA 'UUAQ M~AM LOCATION) NONROUT INE OF ANIALYSIS DETECTION <<EAN (F)b NAKE 'EAN ($ ) HEAN (f) REPORTED ISTANCE AND OIR CTI ON PANGE RANGE HEASUREPENTS RADIOACTIVITY IN PEACHES GROSS BETA 25 F 000 3127 '3(
'3- 1/ SHITH FARH 3127 13( 1/ 2970~49( 1/
GAHHA (GELI )
2 3127 3127 '3 4 ~ 75 )'.ILES K 3127 '3- 31?7 '3 1) 2970 '9- 2970 '9 1) 2 K-4 0 NOT ESTAB 1697M 00 t 1/ 1) SHITH FARH 1697 F 00( 1/ 1) 1252 F 00( 1/ 1) 1697 ~ 00- 1697 'O 4 ~ 75 HILLIS 1697 ~ 00- 1597MOG 125? F 00- 125? ~ OG BI-214 NOT ESTAB 22 '3( 1/ 1) SKITM FARM 22 '3( I/ 1) VALUES <LLD PB-212 22 ~ 43-19 '3(
22 ~ 43 1/
4 ~ 75 MILES 22 ~ 43-19 '3(
22 '3 I)
'3 1) 1/
NOT ESTAB SMITH FAR>> VALUES <LLD 19 '3 1
19 53-
~ 19 4 ~ 75 H ILES 19 ~ 53-RADIOACTIVITY IN POTATOES GROSS BETA 25 F 000 7112 ~ 16( I/ I) 2 MILES NNN 7112 ~ 16( I/ 1) 7721H34( 1/ 1)-
2 7112+16- 7112 F 16 7112 ~ 16- 7112HI6 7721 ~ 34- 7721M34 GAHHA (GEL I )
2 K-40 NOT ESTAB 3201 'O( 1/ 1) H ILES NNL' 3201 F 00( 1/ 1) 3473 F 00( 1/ 1) 3?01MO"- 3201 F 00 3?01 00- 3201 F 00 3473 F 00- 3473 F 00 BI-214 NOT ESTAB 15 ~ 62( 1/ 1) H ILES NN I 15 '2( 1/ 1) VALUES <LLD
'2( 1/ '2 I) '2 1 15 ~ 62- 15 15 ~ 62- 15 PB-212 NOT ESTAB 13 13 '2 2 HILES NNM 13 '2( 1/ 1) VALUES <LLD 13 ~ 62- 13 62- 13 '2 1
- a. Nominal Lower Limit of Detection (LLD) as described in Table 3.
- b. Mean and range based upon detectable measurements only. Praction of detectable measurements of specified locations is indicated in parentheses (P).
TABLE 16 (Contd)
RPDIOACTIVITY IM POOD CROPS PCI/KG - 0 037 80/KG (MET MCIGIIT)
NANC GF FACILITY BRO'wtJS FERRY DOCKET toO ~ 50-259 ~ 260 '96 LOCATIOH OF FACILITY~~I~OOL A 6A ABACA REPORTING PERIOD 19RI TYPE AND LOQER LIHIT ALL CONTROL NUHBER OF TOTAL NUNBER OF IHOICATOR LOCATTOHS LOCATIOH IIITH HIGH ST REROLL~HAH LOCATIONS NONROUT INE OF ANALYSIS DETECTION a NEAN (F)b .I;AIIS IICAO IRIS HEAN RANGE
([) H REPORTED SUR H TS RADIOACTIVITY IN TOHATOES llew GROSS BETA 25 000 5130 21( I/ 1) BROOKS FARM 5130 '1( 1/
5130 ~ 21- 5130 ~ 21
- 1) 5669 17( 1/
5669 ~ 17- 5669 ~ 17 1) 2 5130 ~ 21- 5130.21 - 7 ~ 0 MILES NN)t GANNA (GCLI )
2 K 4G NOT ESTAB 2513 '0( 1/
2513 F 00- 2513 F 00
- 1) BROOKS FAFI.
7 ~ 0 NILES NNI 2513 F 00( 1/
2513oQO- 2513 F 00
- 1) 2381 F 00( 1/
2381 F 00- 2381 F 00 1)
PB-212 NOT ESTAB 11 '5( llH15 ii+15- ,
I/ I) BROOKS FARtl 7a0 NILES NNls 11 F15(
15
- 1) 1 VALUES CLLO RADIOACTIVITY IN TURNIP GREENS llew GROSS BETA 2
25a000 5500 16( 1/
5500 F 16- 5500 ~ 16
- 1) 4 MILES N 5500 5500
'6(
'6- 1/
5500 '6 1) 5969e01( I/
5969~01- 5969H01 1)
GAHHA (GELI) 2 K-40 NOT ESTAB 2262 F 00( 1/ 1) 4 N ILES N 2?62 00( 1/ ll 2980HGG( 1/ 1) 2262 ~ 00- 2262 F 00 2262 00 2262 F 00 2980 00- 2980 00 BI-214 NOT ESTAB 22 '3( 1/
'3 1)I) NILES tt 22 '3(
'3- 1/ 37 '4(
'4- 1/ I)
PD-214 NOT ESTAB 22 ~ 93-13 '3( ?2 1/ 4 NILCS N 13 '3(
22 1/
'3 1) 1)'2 37 37 '4 VALUES o:LLO 13 '3- 13 '3 1
13 53- 13H53 11 '2(
~
PB-212 NOT ESTAB 1/ 1) ANILCS N 11 '2( 1/ I) 26H21( I/ I) 11 42-194 '0(
~ 11 ~ 42 lle42- 42 26 '1- 26+21
'0 I)
BE-7 1/ 1/
NOT ESTAB 194 ~ 40- 194 '0 1) HILES N 194H40(
194 F 40- 194 1 VALUES <LLO
- a. )Ioafnal Lower LfrTft of Detectfon (LLD) as described in Table 3.
- b. Mean and range based upon detectable sTeasurenents only. Fraction of detectable neasurements of specified locations is indicated in parentheses (p) , ~
TABLE 17 RADIOACTIVITY IN SOYBE ANS PCI/G - 6 ~ 037 80/G (CRY VEIGHT)
NAME OF FACILITY BROVNS FERRY DOCKET NO ~ 50-259 260 296 LOCATION OF FlCILI'IY ~III STONE ~AARA)(A R POllT INC PERIOD~IS TYPE ANO LOVER LIMIT ALL COt(TROL NUMBER OF TOTAL NUt(BER OF It)DICATOR LOCATIONS ~LO IITIDH NITH H1DHfST AIMDAL MEAN LOCAT I.ONS NONROUTINE OF ANALYSIS DETECTION a NAIIE IIEIIN IF ID MEAN (F)b REPORTED ILLOI ISTA.MC ARD R TION ~RA RA G b ~MASU~RM~N TS PER~FRM D 200 LM2 BF NORTH 29 '3( 2/ 2)
GROSS BETA 2
0 ~
=29 '0- 29 '5 0 ' MilLE NNE 29040- 2o065 GAMMA CGELI) 2 K-40 15 '4( 2/ 2) LM2 BF hORTH 15074( 2/ 2)
NOT ESTAB 14070- 16077 009 MILE NNE 14070- 16 '7 BI-214 hOT ESTAB 0 '3(
0003-1/
0 '3 2) Lt(2 BF hORTH 009 MILE NNE 0403(
0 ~ 03-1/
0 ~ 03 2)
PB-214 '5( 2/ 2) LiM2 BF NORTH 0 '5( 2/ ?)
NOT ESTAB 0 0 '4 0020(
0 1/
'6 2) 009 MILE NNE 0 ~ 04-
'0(
0 1/
F 06 2)
BE-7 NOT ESTAB
~ 0. 20- 0 '0 LM2 BF NORTH 0 9 MILE NNE 0
'0 20-
~ 0 '0 AC-228 NOT ESTAB 0011 ( I/ 2) LM2 BF NORTH F 11( 1/ 2) 0 ~ 11 0 '1 009 MILE iNNE 0011 0411
- a. Nominal Lower Limit of Detection (LLD) as described in Table 3.
- b. )(can and range based upon detectable measurements only. Fraction of detectable measurements of specified locations is indicated in parentheses (F).
~
P
TALLE 18 RADIOACTIVITY It> POULTRY PCI/t(G - OH037 BO/KG (t'ET MEIGMT)
Nht(E OF FACILITY BROMNS FERRY LOCATION OF FACILITY LINESTOtlE ~ALII 'AHA REPORT ING PER IOD~98 TYPE AtoO LOMER LIMIT ALL CONTROL NUNBER OF TOTAL t;Uo(BER OF INDICATOR LOCATIONS ~ICATION IIITH HIGH RT ANHUA~LII AR LOCATIONS NONROUTINE OF ANALYSIS OETEC T ION a YEAN (F)b NAME t(EAtt (F )b ttEAN (F )b, REPORTED
~PR P 0 R I'. I (LLO) RAN~ A b TS GROSS BETA 2
25 000 4972 ~ 66( I/ I) 49T2 ~ 66- 4972 ~ 66 .
LNS BF DAVIS F 2H5 MILES )tS)R 4972~66(
4972~66- 4972 I/
'6 I)- 6458 6458
'6(
'6- 1/
6458 '6 I)
GA)(t(A (GELI )
2 K 40 NOT ESTAB 2412H 00 ( 1/ 1) Lt(5 BF DAVIS F 2412 ~ 00( 1/ Il 2137 F 00( 1/ 1) 2412H00- 2412 F 05 2 o5 MILES MS)t 2412 F 00- 2412 F 00 2137 F 00 2137 F 00 8 I-214 NOT. ESTAB I VALUES <LLD 19 ~ 56( I/ I) 19 ~ 56- 19 ~ 56 o8-214 NOT ESTAB 1 VALUES <LLD 18 38( 1/ I)
PB-212 NOT ESTAB I VALUES <LLD 18 ~ 38-10 '6( 1/ 1)18 '8 10 86- 10 86
- a. Nominal Lmrer Limit of Detection (LLD) as. described in Table 3. TA
- b. Mean end range based upon detectable measurements only. Fraction of detectable measurements of specified locations is indicated in parentheses'(F). =.
Figure 6 ANNIAL AVERAGE Preoperational Operational 6ROSS BETA kl'IVITY Phase Phase I N ERI%1% MATER SUPPLIES tO 0 HROW% FERRY itLLEAR RAhT 0 v<<
0 4J Ql C LI 5e Ch 0
4J 0
jj0 0 0 Q
Average:
Preoperational
<<5 ,?L Phase
<<L
<<k-IL LL II jL I-I
,j j
'I I<<
t.
4'.
19 8 19 9 19 0 1 1 19 2 19 3P 19 30 1 4 1 5 19 6 1 7 -19 8 1 9 19 0 1 1
38 Figure 7 0 tr ec 1 Rod I at Ion Levels Browns ferry Nuclear Plant 22 Onsi te 9 il 1 I t I t O i '1 p r",
C. t g 18 1 C7 I
I 6 I 't i '~O o
I 'l/
o' I
~Of fsi te 12 1976 1977 1978 1979 1988 1 981 Figure 8 Otrect Rodiation Levels Browns ferry Nuclear Plant I-Quarter Hovtng Average 22 8
Q C.
o 18 l7 6
16 Onsite 0
/P Offstte
.A
' r'o p"
1976 1977 1978 1979 , 1988 1981
Figure 9 39 Otr ect Radtot ion Levels Mat ts Bar Nucleor Plant I'Fi h
C.
Onstte t
C. I 0 18 Ct p..
I
/
Ct:
C Offsi tee 9"w I l I I
/
(/
I 12 1978 1977 1978 1979 1988 1981 Figure 10 2% Oirect Radiation Levels Motts Bor Nucleor Plant
'I-Quarter Moving Average 22 Onstte 0
t.
0 18 a /
b.m.~
e / ~
~.W Offstte 12
) 978 1977 1978 '979 1988 1981
41 Reservoir Monitorin Samples are collected from the Tennessee River as detailed in table 19. Samples collected for radiological analysis include plankton from three of these cross sections and bottom fauna and sediment from four cross sections. The locations of these cross sections are shown on the accompanying map (figure ll) and conform to sediment ranges established and surveyed by TVA.
Water Water samples'are collected automatically by sequential type sampling devices at three cross sections and composite samples analyzed monthly for gamma-emitting radionuclides. Further composites are made quarterly for strontium and tritium analyses. Xn addition to these required samples, grab samples were also collected monthly from the vicinity of the plant discharge to the Tennessee River, and at a point on the Elk River, and analyzed for gross beta, gamma-emitting radionuclides, and strontium. Results are displayed in table 20. Figure 12 presents a plot of the gross beta activity in surface water from 1968 through 1981. No gross beta measurements were made in surface water samples in 1978. The levels reported are consistent with gross beta levels measured in surEace water samples taken from the Tennessee River in preoperational monitoring programs conducted by TVA at other sites.
Fish Radiological monitoring for fish is accomplished by analysis of composite samples of adult fish taken from each of three contiguous 'reser-voirs--Wilson, Wheeler, and Guntersville. No permanent, sampling stations have been established within each reservoir; this reElects the movement of fish species within reservoirs as determined by TVA data from the BFN preoperational monitoring program. Two species, white crappie and smallmouth buffalo, are collected representing both commercial and game species. Sufficient fish are collected in each reservoir to yield 250 to 300 grams oven-dry weight for analytical purposes. All samples are collected semiannually and analyzed for gamma-emitting radionuclides. The composite samples contain approximately the same quantity of flesh from each fish. For each composite a subsample of material is drawn for counting.. Results are given in tables 21,, 22, and 23.
Plankton As indicated in table 19, net plankton (all phytoplankton and zoo-plankton caught with a 100 p mesh net) is collected for radiological analyses at each of three stations by vertical tows with a 1/2-metei 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, all samples containe'd insufficient volume of material for gross beta, strontium, or gamma analyses.
42 Sediment Sediment samples are collected from Ponar dredge hauls made for bottom fauna. Gamma radioactivity and Sr and Sr content are determined semiannually in composite samples collected from each of four stations.
Locations of these stations are shown in table 19. Results are shown in table 24.
Bottom Fauna The flesh and shells of Asiatic clams collected semiannually from the cross sections at four stations (table 19) are analyzed for gamma-emitting radionuclides. Levels of Sr and Sr are determined on the shells, and on the flesh when sufficient amounts were available. A 50-gram (wet weight) sample provides sufficient activity for counting. During this reporting period, one sample of clam flesh contained insufficient volume for analysis.
Results are given in tables 25 and 26.
Table 19 SAMPLING SCHEDULE - RESERUOIR MONITORING Biolo ical sam les (collected semiannuall )
Zooplankton, chlorophyll, Benthic River/river mile phytoplankton fauna Sediment Pish (co8ecfe8 mlnNly)
Tennessee 277.9 X Tennessee 285 '
Tennessee 288.7 X Tennessee 291.7 Tennessee 293.5 Tennessee 293.7 K (discharge area)
Tennessee 305.0 (Control)
Tennessee 307.5 X X (Control)
Elk 20.5 (Control)
- a. Gill net and/or electroshocker will be used for collection. Samples of fish are collected from Guntersville, Wheeler, and Wilson-Reservoirs.
- b. Automatic sampler.
- c. Grab sample.
TABt.E 20 RA310ACTIVITY It,'URFACE "ATER TOTAL PCI/L - 0 '37 BQ/L NAHE OF FACILITY BR))ONS FERRY DOCKET KO ~55-259 2~65 296 LOCATION OF FACILITY ~~HQ~Ottg REoORT It(G PERIOD~1 T YPE A'iD LOMER LIHIT ALL CONTROL NUHBER OF TOTAL t(UHBER OF INDICATOR LOCATIONS LOCATIOt'ITH HIGHEST ANNUAL HQAN LOCATIONS NONROUTINE OF ANALYSIS DCTCCTIONa HEAR (F )b NAHL HEAN 4[)b HEAN (F) REPORTED 0 (LLD) R ANGE b 0 IS I A NCE At'P QI RECT I Oti RANGE RANGEb RSOR IIERT.
'7(
PER ~ll GROSS F~OE(H BETA 2 '00 3 '3( 14/ 17) TRH 293 ' 3 '6( 2/
'2 2) 5
'9- 12/ 15) 32 2 '3- F 16 3 '0- 4 2 9 '8 GAHHA (NAI) 45 27 VALVES (LLD 18 VALUES (LLD ANALYSIS PERFORHE.D GAHHA (GELI )
20 K-4 0 NOT ESTAB 105 '0( 5/ 12) TRH 293 ' 139 45 ( 2/ 3) 96 '3( 2/ 8)
BI-214 NOT ESTAB 51 F 52-15 '9( 159 '0 5/ 12)
BFN DISCHARGE 285 '
119 10-
'0(
159 F 80 2/ 3) 74 31 '4(
F 85- 118 6/
'0 8)
TRH 18 PB-214 4 '6- 23 '7 1/ 12) '
18 ~ 14- 19 F 06 1/ 3) 5500-27 '4(
83 ~ 65-4/ 8)
NOT ESTAB 26 F 00( TRH 293 26 F 00(
26 F 00- 26 F 00 BFti DISCHARGE 26500- 26 00 10 '4- 55 '9 3/
PB-212 NOT ESTAB 12 '3- 3/17 '212) 15525( TRu 285~2 17 F 62(
17 ~ 62-1/
17 '2 3) . 13 F 83(
8 '2- 22 '1 8)
SR 89 10 F 000 20 VALVES (LLD 16 VALUES (LLD ANAL IS YS P ERFO RHEO SR 90 2 000 2 '1( 1/ 20) TRH 293 ' 2 F 81( 1/ 12) F 07( 1/ 16) 2 '1" '1 '7 F
F 81 BFIN D I SCHARGC 2 81- 2 2507- 2 IT IUH 330 F 000 372511( 2/ 12) TRH 293 ' 379535( 1/ 4) 8 VALUES (LLD 379 '5 TR 364 86 F 379 '5 379 ~ 35-I
- a. Hominal Lower Limit of Detection (LLD) as described in Table 3.
- b. Yuan and range based upon detectable measurements only. Fraction of detectable ueasureuents of specified locations is indicated in parentheses (F).
T>BLE 21 RADIOACTIVITY I)G'HITE CRAPPIE (FLESH)
PCI/G 0 ~ 037 BO/G ('DRY MEIGHT)
NAME OF F AC ILITY QRRM~NjERRY DOCKET NO~ 50-25%~0 LOCATION OF FACILITY LIYESTONE R PORTING PERIOD 19IRI TYPE AND LOMER L I HIT ALL CONTROL NUHBER OF TOTAL NUMBER OF INDICATOR LOCATIONS DOCRTIGP~III IN N NEST~N~iNU D ~NRN NONROUTINE LOCATIONS (F)
OF ANALYSIS DETECT ION a PEAN (F)b NAPE HEAN CF)b HEAN REPORTED CLLD) RANGE b R~N~b ~SIDDUR ~NUTS GROSS BETA Oo1 00 35N 18( 4/ 4) MILSON RESERVOIR 35 '6(
'8- 2/ 2) 34 F 87(
33~03-2/ 2)
ES 33 ~ 04- 37 ~ 16 TRY 259-275 34 35a54 36 72 GAHHA (GEL I )
6 CS-137 '20 ON12( 4/ 4) MILSON RESERVOIR 0~ 13( 2/
'3 2) F 14(
'9- 2/ 2) 0 0 '9 14 '5(
0 ~ 14 TRH 259-27c 0~ 13- 0 2/
0 F 18 2/ 2)
K-40 NOT ESTAB 12 ~ 72-4/
-15 ~ 63
- 4) MILSON RESERVOIR TRH 259-275 15 20(
1,4 ~ 77-
'9(
15 '3
- 2) 17 15 '950(
F 19 '1 BI-214 '20 0~07( 2/ 4) MHEELER RES 0 1/ 2) 0 06(
'6- 1/ 2)
'9 0 F 0005- 0 TRH 275-349 0 ~ 09- 0~09 0 ON06 PB-214 NOT ESTAB Oo0?(- 2/ 4) MILSON RESERVOIR 0 F 07( 1/ 2) 2 VALUES (LLD 0 ~ 06- 0 07 TRH 259-275 0 ~ 07- 0 +0-7 PB-212 NOT ESTAB 0 '2(
0~02-1/
0 F
'2 4) MHEELER RES TRH 275'-349 0
0
'2C 02-1/
Oo02
- 2) 0 ~ 02(
0 ~ 02-1/
0 ~ 02 2)
- a. Nominal Lover Limit of Detection (LLD) as described in Table 3.
- b. Ncaa and range based upon detectable measureaeats only. Fraction of detectable neasureaeats of specified locations is indicated in parentheses (F).
TA) LE 22 RADIO~C~IVITY IN SHALLHOUTH BUFFALO (FLESH)
PCI/G - 0 ~ 037 BO/G (IORY 'dC IGHT)
NAKE OF FiECILITY BPOMNS FLURRY LOCATION OF FACILITY LIHESTONC ALABAHA REPORT 1RG PERTOO~OGI TYPE ANO LOMER LI HI T ALL CONTROL NUHBER OF T OT Ai. NUK DER OF I'GDI CATOR LOCATIONS LOCATIONS NOiVROUTINE OF ANALYSIS DETECTION HiEAN (F ) b HEAR (F)b REPORTED
~PFORII 0 (LLO) R AN GCb DISTANCE ANO DIR CTION RANGLb llew ~RAGG ~HASQ~RH NTS GROSS aCta 0 ~ 100 23>> 07(
19>> 04-4/ 4) QHECLEF RES 275-34o 25 '7( 2/
'0 2) 22 40( 2/
'8 2) 6 27>>20 TRil 24>>74- 27 20 12- 24 GA~H4 (GELI )
6 CS-137 0>>920 0 '5(
0.04-4/ 4) VHCELEP RES 0 F 05(
04-2/ 2) 0 08(
'7-F 2/ 2) 0.06 TRH 275-349 0 0 06 0 0 F 08 8 '2(
F K-40 NOT ESTAB 9 ~ 64( 4/ 4) MHCELER RES 11 ~ 03( 2/ 2) 2/ 2) 7 '6- 11 '6 TRH 275-349 10>>49- 56 F 00- 10 '4 8 I-214 0 '20 0 '6(
'5- 3/ 4) LfILSON EEESERVOIR 0>>08( 1/
'8 2) F 14(
14-1/
'4 2) 0 0 08 TRH 259-2?5 0. ~ 08- 0 0~ 0 PB-214 NOT ESTAB 0.06( 2/
F 0 ~ 07( 1/ 2) '9( 1/ 2)
PB-212 NOT ESTAB 0 '5-
'4( 1/
0 '7 4) @HEELER RES TRH 275-349 MHEELER RES 0 ~ 07-0 '4( 1/
0 '7 2) 0 0
'9-2 VALUES <LLD 0 '9 0
0 '4- 0 04 TRH 275-349 0~ 04- 0 04 TL-2Iii8 0 '20 0 0
'2(
~ 02-1/
0 F
'2 4) iGHEELCR RCS TRK 275 349 0>>02(
0>>02-I/
F 0 F 02
- 2) 2 VALUES <LLD SP 89 0 '00 1 VALVES <LLD 0 VALUES <LLD ANALYSIS PERFORHED SR 90 0 F 100 1 VALUES <LLD '0 VALUES,<LLD ANALYSIS PERFORHED
- a. Honinal Lower LimEit of Detection (LLD) as described in Table 3.
- b. Mean and range based upon detectable aeasurecEents only. Fraction of detectable rEeasurements of specified locations is indicated in parentheses (F).
TABLE RADIOACTIVITY IN SHALLVOUTH BUFFALO (MHOLE)
PCI/G GD 037 BC/G (DRY ME IGHT)
NAME OF FACILITY BROMt)S FLURRY DOCKET KD 5~5-259 "55 E9ET LOCATION OF FACILITY L~HESTOt(E ALA~AHA REPORTING PER I OD~aal LIHIT ALL CONTROL NUMBER OF TYPE AND LOMER OF INDICATOR LOCATIONS LOCATIONS NONROL'TINE TOTAL tJUHBER OF ANALYSIS DETECT IONa HEAN (F)b NAME MEAN (F)o HEAN (g) REPORTED
~PIIF R~ RANGEb
'2( 4/ 4) '6( 2/ 2) 20 RANGE
'4( 2/ 2)
QQAQ~R~M)(TS GROSS BETA 6
0 ~ 100 19 18 F 57- 19 '5 MHEELER RES TRH 275-349 19 18957- 19 '5 14 97- 26 91 GAHHA (GELT)
CS-137 6
020- 03C 2/ 4) MHEELER RES 0%03( 1/ 2) 0 '4( 1/
'4 2) 0 ~ 0~
Oa03-8008( 4/
0 '3 4)
TRH 275-349 0~ 03-
'0( 2/
0003 2) 0 7
F 04-
'8C 0
2/ 2)
K-40 NOT ESTAB
~ 6 '3- 9 '1 4) MKEELER RES TRH 275-349 8
7 ~ 50- 8 '9 5910-0 '6C 9 67 BI-214 0 '20 0~ 06C
'4- 4/ MILSOt9 RESERVOIR TRH 259-275 0.06(
04-2/
0 08 2) 0 '3- 2/
0 08 2) 0+08 0 PB-214 NOT ESTAB 0
0 '7( 3/ 4) MILSON RESERVOIR 0 '2(
12-1/
F
- 2) 0 '8(
08-1/
0~08 2) 0504- 0 ~ 12 TRH 259-275 0~ 0512 0 F I/ 0 '3( 2/ 2)
PB-212 NOT ESTAB 0~03(
0 03-2/ 4) 0 F 03 MHEELER RES TRH 275-349 0
0+03 03(
0 '3 2) 0 F 03 0 VALUES <LLD
'4 SR 89 '0 ~ 500 1 VALUES <L'LD G ANALYSIS PERFORMED SR 90 0~ 100 1 VALUES <LLO 0 VALUES <LLD ANALYSIS PERFORHED
- a. )tominal 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 RADIOACTIVITY IN SEOIHENT PCI/G 0 '37 BO/G (DRY )(EIGHT)
NAHE OF FACILITY BRO)tNS FERRY DOCKET t'0>> 50-25~9 260+9$
LOCATION OF FACILITY LIHfSTO~N ALABAHA REPORT IttG PE'RIOO 1981 TYPE At(0 LOVER LIHIT ALL CONTROL NUHBER OF TOTAL NUHBER OF It(0 I GATOR LOCATIONS OCATION MITH HIGHEST ANhUAL HEAN NONROUTINE ANALYSIS OETECTIONa MEAN (F)b (j)b LOCATION) REPORTED OF PQ~FgH jQ ~() ) ~RR' IIRRRRR~C NAHE RR PIRQC7704 HEAR
~RRRR ~ASgf+~HN T S GAHHA (GEL I )
8 CO-60c 010 5/ 6) 2/ 2)
CS-134 0~
0F 080 0>>14 (
0 '7-0>>13(
0 ~ 21 1/ 6)
TRH 293 F 7 BFN DISCHARGE 293 '
0 0
0
'920(
~
13( 1/
0 ~ 21 2) 2 VALUES <LLO 2 VALUES <LLD CS-137c '20 0 ~ 13- 0 6/
'3 6)
TRHR BFN DISCHARGE
'8 F 13 2>>24( 2/
0>>13
'7( 2/ 2)
ZR-95 0
0~ 030 1 ~ 70(
0 6
83- 2 '5 VALUES <LLD TRH 277 2 '3 2 '5 2) 0 0 ~ 23-0>>07(
O>>31 1/ 2) 0>>07 0>>07 NB-95 010 6 VALUES <LLD F 12( 1/ 2)
K>>40 0 ~
NOT ESTAB 14 '0( 6/ 6) TRH 288 '8 15 '5( 2/ 2) -
0>>12 14 '5(
0 '2 2/ 2) 11 ~ 42- 16 ~ 42 ".15 ~ 07- 16>>42 13>>64- 15 86 II HN-54 0 '10 0 '5(
'4- 2/ 6) TRH 293 7 0F
'606( 1/ 2) 0 03( 1/ 2)
'3 81-214 0>>020 0
1 '5( 0 6/
'6 61 BFN TRH DISCHARGE 277 '8 0 1 '4( 2/
0 '6 2) 0
~
~ 03-1>>79(
0 2/ 2) 1 11- 1>>53 35- 1 ~ 53 le61 96 288 '8
~ 1~ 1 ~
BI-212 0 100 1 06( 5/ 6) TRH l>>33( 1/ 2) 1>>15( 2/ 2) 0>>68- 1 ~ 33 33- 1 ~ 33 0 ~ 93- 1 ~ 36 277 '8 1~
P B-214 NOT ESTAB '0( 6/ 6) TRH '8( 2/ 2) 1 ~ 86( 2/ 2)
PB-212 NOT ESTAB 1
1~
1~
18-86(
1 ~
6/
71
- 6) TRH 288 '8 1
1 ~ 66 F 01( 2/
1 ~ 71 2) l>>64-2F 00( 2/
2 '9 2) 57- F 05 98- 2 F 05 1>>82 F 18 277 '8 1 ~ 1 ~
RA-226 NOT ESTAB 35( 6/ 6) TRH 1 ~ 44( 2/ 2) 1 ~ 79( 2/ 2)
RA-223 1
1~ ll-49(
1 ~ 53 2/ '
1 ~ 35 1/
1 '3 2) 1>>61 0>>75(
le96 2/ 2)
NOT ESTAB 0 6) TRH 293 0 ~ 50(
TL-208 '20 0>>47-
) ~ 57(
0 6/
'0 6) BFN TRH DISCHARGE 277 98 0 F 50
'5( 2/
0 F 50 2) 0>>62
'3( 2/
0 '7 21 AC-228 0
0 '60 0 ~ 44-1.72(
0 6/
'7 6) TRH 277.98 0
0 62-
~
1 ~ 89( 2/
0067 2) 0 0>>68-2 '2( 2/
0 ~ 78 2) le35- 1>>94 1 ~ 83- 1 ~ 94 1>>95- 2>>68 SR P9 1 ~ 533 6 VALVES <LLO 2 VALVES <LLD 8 ANALYSIS PERFORt".EO SR -90 0 ~ 300 6 VALUES <LLD 0 0
'2(
52-1/
0 52 2)
- a. Nominal Lowek 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).
nd 3 Cs'etween indicator'and control locations'reported herein is comparable to the distribution reported << the
TABLE 25 RADIOACTIVITY IN CLAN FLESH PCI/G - 0 '37 BC/G 'tORY VEIGHT)
NAME OF FACILITY FROWNS FERRY OGCKET NO ~5 +~59 gggx?Si LOCATION OF FACILITY L~IM STOL( ALABAMA REPORT ING PERIOD )981 TYPE AND LOVER LIHIT ALL CONTROL t UHBER OF TOTAL hUHBER OF INDICATOR LOCATIOt)S LOCATION VI TM HIGHEST AtthUAL HEAN LOCATI Ot(S tiONROUTINE OF ANALYSIS DETECT IOti~ ME N (F) b NAME MEAN (F) o HEAN (F)b REPORTED (Q,Q) RANGFb RAt'Gfb YQ~AS ~RH N S GAMMA (GELI)
K-40 7
NOT ESTAB 8 ~ 97(
6 ~ 49-4/
12 '5 5) TRH 288 '8 9 6 4o 32( 2/
12 '5 2) 17 'l
'1 2/171/ 2)2) 17 F 11(
277 '8 BI-214 NOT ESTAB 4 ~ 2.7 ( 5/ 5) TRH F 40( 1/ 1) 2 72(
lo70- 7 ~ 05 6 ~ 40- 6 '0 2 '2- 3 '2
~8-214 NOT ESTAB 4s59( 5/ 5) TRH 277 '8 9e 05( 1/ 1) 4 71( 2/ 2)
I ~ 10- 9 ~ 05 9 ~ 05- F 05 l. 80- 7 '3 PB-212 NOT ESTAB 12( 3/ 5) TRP 288~78 1 '7( I/ 2) 0 '0(
F
'0- I/ 2)
TL-208 NOT ESTAB I ~ 02-0.40(
1 ~
1/
17
- 5) TRM 288 '8 1 0
17-
'0( i+17 1/ 2) 0 2 VALUES <LLD 0 '0 Oo40- Os40 0~ 40- 0 ~ 40
- a. Noninal Lower Linit of Detection (LLD) as described in Table 3.
- b. Mean and range based upon detectable neasurenents only. Fraction of detectable neasurenents of specified locations is indicated in parentheses (F).
TABLE 26 RADIOACTIVITY IN CLAM SHELL PCI/G 0 ~ 037 Bf /G (DRY ):EI G)IT)
NAHE. OF F AC ILII Y PROVNS FURR~ DOCKET NO ~ ~P$ ~9~0t7~
LOCATION OF FACILITY LIMESTONE ALABAHA RrPORTING PERIOD 1981 CONTROL NUHBER OF TYPE ANO LOI'ER LIMIT ALL OF INDICATOR LOCATIONS LOCATION MITH HIGHEST ANNUA~ LOCATIONS NONROUTINE TOTAL NUHBER OF ANALYS IS DETECTION MEAN (F)b HEAr'AME HE,AN (F)b MEAN CF) REPORTED (LLD) RANGL DISTANCE AN~DIRECTION RANGP RANGEb GA""A (GELI)
K-4 0 8
NOT ESTAB 1~ 15(
19-6/
3 '2 6) TRH 277 '8 2 0
'6(
~ 99-2/
92
- 2) 1 ~ 13(
0%86-2/
1 ~ 41 2)81-214 0 '50 0~
0 F 48( 6/ 6) TRH 2T7 ~ 98 0 '2(
0%27-2/ 2)
'0- 2/ 52 2) 0%46(
0 ~ 11- 1%57 1 57 0 0 91-212 0F 100 0 '0( 1/ 6) TRH 293 ' 0 '0(
0%20-1/
'0 2)2) 2 VALVES <LLD 0%20- 20 DISCHARGE 0 PB-214 0 '50 0 '6( 0 6/
~
6)
BFN TRH
=
277 '8 0 ~ 63( 2/ 0 '6(
'2- 2/2/0%50 2)2) 09- 0%21 05 0 0 ~
'9( 1 ~ 05 5/ 6) 49( 2/
1
- 2) '5(
PB-212 NOT ESTAB 0 09- 0%90 TRH 2T7 ~ 98 0 ~
0%09- -0.90 0
0 '7
'6(
0 '4 RA-226 0 '50 0
0 '8(
~
I?-
6/ 6) TRH 277 '8 0 92(
0 ~ 27-.
2/
57
- 2) 0 0 40-2/ 2) 0 '2 0 1 ~ 57 s 1 ~ F TL-208 0 '20 0 ~ 08( 4/ 6) TRH 293 ' 0 ~ 10(
0%09-2/ 2) 0%13(
F 11-2/
14*
2) 0 ~ 05- F 11 BFN DISCHARGE 0 ~ 11 0 ~ o AC-228 0 '60 0 '1(
0.28-3/
'3 6) TRH 288 '8 0 0.32(
~ 32-1/
0 '2 2) 0%53(
0 '3- 1/
0%53 2) 0 SR 89 5 F 000 6 VALUES <LLD 2 VALUES <LLD ANALYSIS P ERFORHED
' 2/ 2 '2( 2/
SR 90 1F 000 I ~ 99(
1~ 28-6/
2 ~ 70
- 6) TRH BFN 293 DISCHARGE 2%49(
2 '7- 2 F 70 2) 2 '1 2 '3 2)
- a. Nominal Lower Limit of Detection (LLD) as described in Table 3.
- b. Mean and range based upon detectable measurements only. Fraction of detectable measurements of specified locations is indicated in parentheses (F).
Figure 11 51 R ESERVOI R MONITORING NETWORK N
Etk River WHEELER DAIVl mile 274.90 rnite 277.98 Rogersville 0
mile 29l.76 Athens rnite 282.6 I-mi(e 285.2 B.F. NUCLEAR PLANT II Champion Paper Co.
ite28878 mite 293.50 0
Cour tland mile 305.0 mile 293.70 0
Decatur mile 307.52 Scale of Miles e- Automatic Sam ter
Figure l2 Oem AVERAGE 6ROSS IIETA ACTIVlTY C Preoperaclonal Operational o cl Phase C Phase 1N SURFACE HATER kJ o 4J th ll IRONS FERRY NUCLEAR PLANT 4 tf, o
o 0l Q
'o Il 0 Average:
Q Preoperational Phase 1
1968 1969 1970 1971 1972 1973P 19730 1974 1975 1976 1977 1 78 1979 1980 1 81
53 ualit Control A quality control program has been established with the Alabama Department of Public Health Environmental Health Administration Laboratory and the Eastern Environmental Radiation Facility, Environmental Protection Agency, Montgomery, Alabama. Samples of air, water, milk, and vegetation collected around BFN are forwarded to these laboratories for analysis, and results are exchanged for comparison.
Data Anal sis Data 'measured at the control stations for each medium were averaged for each sampling period. In order to describe the distribution of control station data, a mean, standard deviation, and 3-sigma limits were calculated.
We can expect that background concentrations would be distributed within these limits. This 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 f'all within the limits, we will perform further analyses to determine if the difference is attributable to the nuclear plant.
Conclusions A vast majority of the indicator station data was found to be within the distribution. defined by the control station data. The data analysis software identified concentrations slightly exceeding the limits of the control station data for a small number of radionuclides in samples from indicator stations. Many of these values may be discounted because the error reported by the analysis program was greater than the calculated concentration. The remaining isolated elevated concentrations may be the. result of fallout, fluctuations in the existing environment, computer program artifacts, or analytical errors. The same type of isolated high values occurred in the control station data and may be attributed to the same sources.
Increased levels of radioactivity were observed in rainwater, air particulates, heavy particle fallout, and in vegetation in the winter and spring following the atmospheric nuclear weapons testing conducted by the Republic of China in mid-October 1980. This increase was seen in control stations as well as indicator stations. The primary radioisotopes identified in the atmospheric media were, Zr, ~.Nb, I, Bi, and Ru.
Dose estimates were made from concentrations of radioactivity found in samples of environmental media. Media sampled include, but are not limited to, air, milk, meat, vegetation, drinking water, and fish. Doses estimated for persons at the indicator locations were essentially identical to those determined for persons at control locations. Greater than 99 percent of those doses were contributed by the naturally occurring radionuclide potassium-40,
54 and by strontium-90 and cesium-137 which are long-lived radioisotopes found in fallout from nuclear weapon testing.
't is concluded from the above analysis of the data and from the trend plots presented earlier that there were no measurable increases in environmental radioactivity attributable to the operation of BFN.
TENNESSEE VALLEY AUTHORITY MUSCLE SHOALS. ALABAMA35660 River Oaks Building .
i'~S May 5, 1982
~ ~r
~A.
C)
U.S. Nuclear Regulatory Commission (3 C>
c/o Regional Administrator 9 Region II /~$
Attention: A. L. Cunningham ~
C Suite 3100, 101 Marietta Street Atlanta, GA 30303 The enclosed report No. TVA/OMS/OHS-82/7 "Environmental Radioactivity Levels Browns Ferry Nuclear Plant Annual Report 1981," is furnished for your information and use.
Very truly yours, R, B. Maxw ll, Chief Radiological Hygiene Branch Enclosure An Equal Opportunity Employer
P l
TENNESSEE VALLEY AUTHORITY CHATTANOOGA. TENNESSEE 37401 400 Chestnut Street Tower II April 30, 1982 U.S. Nuclear Regulatory Commission Region II ATTN: James P. O'Reilly, Regional Administrator 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303
Dear Mr. O'Reilly:
Enclosed is a copy of the following report prepared by the Tennessee Valley Authority pertaining to environmental monitoring at the Browns Ferry Nuclear Plant:
Environmental Radioactivity Levels, Browns Fet ry Nuclear Plant, Annual Report 1981 This monitoring program is specifically responsive to the recommendations and requests of the United States Fish and Wildlife Service. We understand that the Office of Nuclear Reactor Regulation will transmit five copies of the report to the Secretary of the Interior.
Very truly yours, TENNESSEE VALLEY AUTHORITY L. M. Mi ls, Manager Nuclear Licensing Enclosure cc: Director of Nuclear Reactor Regulation (
Enclosure:
20)
Attention: Mr. Darrell G. Eisenhut, Director Division of Licensing U.S. Nuolear Regulatory'ommission Washington, DC 20555 Go>+~
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RH-81-5-BF2 ENVIRONMENTAL RADIOACTIVITY LEVELS BROWNS FERRY NUCLEAR PLANT ANNUAL REPORT 1980 April 1981 SO>aalu OPr1CV~ COrV 850O100voe PDR ADOCK 05000259 El-F93 R PDR
CONTENTS List of Tables . ~ ~ ~ ~ 0 ili List of Figures. ~ ~ ~ ~ ~ o iv Introduction ~ ~ ~ 1 Atmospheric Monitoring . ~ ~ ~ 11 Terrestrial Monitoring . 21 Reservoir Monitoring ~ ~ ~ ~ ~ ~ 33 Quality Control. 45 Data Analysis. ~ ~ ~ ~ ~ ~ ~ ~ 45 Conclusions. ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ ~ 45
LIST OF TABLES Table Environmental Radioactivity Sampling Schedu le ~ 4 Table Atmospheric and Terrestrial Monitoring Stat ion Locations Browns Ferry Nuclear Plant 5 Table 3Detection Capabilities for Environmental Sam pie Analysis 6 Table 4Results Obtained in Interlaboratory Compari so Program. 8 Table 5Maximum Permissible Concentrations for Nonoccupational Exposure 16 Table 6Radioactivity in Air Filter . 17 Table 7Radioactivity in Rainwater. 18 Table 8Radioactivity in Heavy Particle Fallout 19 Table 9Radioactivity in Charcoal Filters ~ ~ ~ ~ 20 Table 10 Radioactivity in Milk . 23 Table 11 Radioactivity in Vegetation . 24 Table 12 Radioactivity in Soil . 25 Table 13 Radioactivity in Well Water . 26 Table 14 -. Radioactivity in Public Water Supply. 27 Table 15 Environmental Gamma Radiation Levels 28 Table 16 Radioactivity in Food Crops 29 Table 17- Radioactivity in Soybeans 31 Table 18 Radioactivity in Poultry 32 Table 19 Sampling Schedule - Reservoir Monitoring 35 Table 20 Radioactivity in Surface Water 37 Table 21 in White Crappie (Flesh).
'adioactivity 38 Table 22- Radioactivity in Smallmouth Buffalo (Flesh) 39 Table 23 Radioactivity in Smallmouth Buffalo (Whole) 40 Table 24 Radioactivity in Sediment 41 Table 25 Radioactivity in Clam Flesh 42 Table 26 Radioactivity in Clam Shell'. 43
LIST OF FIGURES Figure 1 - Tennessee Valley Region . ~ ~ 3 Figure 2 Atmospheric and Terrestrial Monitoring Network. 13 Figure 3 Local Monitoring Stations ~ ~ ~ ~ 14 Figure 4 Browns Ferry Nuclear Plant Site Monitoring Stations . . . . . 15 Figure 5 Reservoir Monitoring Network. 36
ENVIRONMENTAL RADIOACTIVITYLEVELS BROWNS FERRY NUCLEAR PLANT ANNUAL REPORT 1980 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 Decatux, Alabama. The plant consists of three boiling water reactors; each unit is rated at 3,293 MWt and 1,098 MWe. Unit 1 achieved criticality on August 17, 1973, and began commercial operation on August 1, 1974. Unit 2 began commercial operation on March 1, 1975. However, a fire in the cable trays on March 22, 1975, forced the shutdown of both reactors. Units 1 and 2 resumed operation and Unit 3 began testing in August 1976. Unit 3 began commercial operation in January 1977.
The preoperational environmental monitoring program established a baseline of data on the distribution of natural and manmade radioactivity in the environment near the plant site. However, seasonal, yearly, and random variations in the data were observed. In order to determine the potential increases in environmental radioactivity levels caused by the plant, comparisons were made between data for indicator stations (those near the plant) and control stations (those remote from the plant) in con)unction with comparisons with preoperational data.
Staffs in the Division of Occupational Health and Safety, the .
- =--Division of'Water Resources, and Resource Services, carried out the sampling program outlined in tables 1 and 19. Sampling locations are shown in figures 2, 3, 4, and 5, and table 2 describes the locations of the atmospheric and,terrestrial monitoring stations. All the radiochemical and instrumental analyses were conducted in TVA's Western Area Radiological Laboratory (WARL) located at Muscle Shoals, Alabama and Eastern Area
'adiological Laboratory (EARL) at Vonore, Tennessee. Alpha and beta analyses were performed on Beckman Low Beta II and Beckman Wide Beta II low background proportional counters. Nuclear Data (ND) Model 100 multichannel analyzer systems employing sodium iodide NaI(Tl) detectors and ND Model 4420 systems in con)unction with Germanium Ge(Li) detection systems were used to analyze'he samples for- specific gamma-emitting radionuclides. Samples of water, vegetation, air particulates, food crops, and charcoal ('specific analysis for I) are routinely counted with NaI(Tl)'detection systems. If significant concentrations of radio-isotopes are identified, or if the're is a reasonable expectation of
increased radioactivity levels (such as during periods of increased" fallout), these samples are counted on the Ge(Li) system". Identifi-cation of gamma-emitting radionuclides in all other types of samples is routinely performed by analysis on the Ge(Li) system. A TVA fabricated beta-gamma coincidence counting system is utilized for the determination of I-131 concentrations in milk.
Data were entered in computer storage for processing specific to the analysis conducted. A computer, employing an ALPHA-M least squares code, using multimatrix techniques, was used to estimate the activities of the gamma-emitting nuclides analyzed by NaI(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 listed in Table 3. Samples processed by NaX(T1) "gamma spectroscopy were analyzed for 13 specific gamma-emitting radionuclides and radionuclide combina-tions a . For these analyses, radionuclide combinations such as and Zr-Nb are analyzed as one radionuclide. All photopeaks found in
'u Ge(Li) spectra were identified and quantified. Many of the isotopes identified by Ge(Li) spectral analysis are naturally occurring or naturallv produced radioisotopes, such as Be " K t ' Bi 4Bi t Pb t 214 Pb<
226 Ra, etc. LLD's for the analysis of the radionuclides listed 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 listed in the data tables.
TVA's Radioanalytical Laboratories participate in the Environ-mental Radioactivity Laboratory Intercomparison Studies Program conducted by EPA-Las Vegas. This program provides periodic cross-check samples of the type and radionuclide composition normally analyzed in an environ-mental monitoring program. Routine sample handling and analysis pro-cedures were employed in the evaluation of these samples. Gamma spectral analyses were performed using NaI detectors. The EARL began processing samples in May 1980. The results received during calendar year 1980 are-shown in table 4. The +3@ limits based on one measurement were divided by the square root of 3 to correct for triplicate determinations.
a The following radionuclides and radionuclide combinations are quantified by the ALPHA-M least-squares computer code: " '4Ce; Cr; I; 103 106Ru; 134Cs; "Cs; Zr-Nb; 58Co; "Mn. 65Zn..60Co; " K; and 140Ba-La.
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~ Table 1 ENVIRONMENTAL RADIOACTIVITY SAMPLING SCHEDULE Air Charcoal Rain- Heavy Particle River Well Public Aquatic Life dtatioa ioaaei ritter ritter ater Parle t soil ~vetatf o Milk w ter rater rater aad aedia ot Foods Muscle Shoals W M M A Lawrenceburg W M M, A Roger sville W M M A Athens M M A Decatur M M A Courtland W Site NW-1 Site N-2 M A Site NE-3 M A Site NW-4 W M .
A Site WSW-5 W M M A Perm B Perm Bi Farm H Farm T Farm L Control Farms Onsite Well Wheeler Dam Elk River River S Tennessee Champion Paper Co.
Various Local Farms A W - Weekly M - Monthly (every 4'eeks) ~rterlya ..-' S-Semiannually A-Annually e
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 (1.6 kilometers) N LM-2 BF, North 0.9 Mile (1.4 kilometers) NNE LM-3 BF, Northeast .1.0 Mile (1.6 kilometers) NE LM-4 BF, Trailer Park 1.7 Miles (2. 7 kilometers) NNW LM-5 BF, Davis Farm 2.5 Miles (4.0 kilometers) WSW PM-1 BF, Rogersville, AL 13.8 Miles (22.2 kilometers) NW PM-2 BF, Athens, AL 10.9 Miles (17.5 kilometers) NE PM-3 BF, Decatur (Trinity), AL 8.2 Miles (13.2 kilometers) SSE PM-4 BF, Courtland, AL 10.5 Miles (16.9 kilometers) WSW BF, Muscle Shoals, AL 32.0 Miles (51.5 kilometers) W (Control)
RM-2 BF, Lawrenceburg, TN 40.5 Miles (65.2 kilometers) NNW (Control)
Farm S 4.75 Miles (7.6 kilometers) N Farm B 7.0 Miles (11.3 kilometers) NNW Farm H 3.75 Miles (6.0 kilometers) N Farm T 7.0 Miles (11.3 kilometers) ENE Farm Bi 4.5 Miles (7.2 kilometers) ENE Farm N (Control) 27.0 Miles -, (43.4 kilometers) NW Farm J (Control) 40.0 Miles (64.4 kilometers) NNW Farm C (Control) 32.0 Miles, (51.5 kilometers) N Farm Ca (Control) 32. 0'iles (51. 5 kilometers) W
Table 3 DETECTIOH CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS A. S ecific Anal ses NOMINAL LOWER LIMIT OF DETECTION LLD
- Pish, Air Vegetation Soil and clam flesh, Foods, neat, Particulates Charcoal Fallout Water and grain Sediment plankton, Clan shells poultry, Milk
~C/ ~C// 0//k ~ci I: ~C// d ~c// . ar ~Ci/ ~dr ~Ci/ <<~dr pC1/k~gg ~il Total a 0.4 0.01 1.5 Gross o 0. 005 2.0 0.05 0.35 0.1 0.7 Cross 8 0. 01 0.05 2.4 0.20 0.70 0.1 0.7 25 4H 330 444I 0.02 0.5 "Sr 0.005 10 0.25 1.5 0.5 5.0 40 10 44S 0.001 2 0.05 0.3 0.1 1.0 8 2
- All LLD values for isotopic separations are calculated by the method developed by Pasternack and Harley as described in HASL-300.
Factors such as sample site, decay time, chemical yield, and counting efficiency nay vary for a given sample; these variations may change the LLD value for che given sample. The assunption is nade that all samples are analysed within one veek of che collection date. Conversion factors: 1 pCi ~ 3.7 x 10 Bq; 1 nCi ~ 3.7 x 10 Bq.
Table 3 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS B. Canna Anal ses NOMINAL LOWER LIMIT OF DETECTION LLD Air Water Vegetation Soil and Clam flesh Foodsk(tomatoes Meat and particulates and milk and grain sediment Fish and plankton Clan shells potatoes, etc.) poultry CL/o -~Ct/1 . r~Ctl d NCCL// de re N~CL/ ~ar ~CL/ dr ~CLI dr Ci/ vet ~Ct/k NaI* ~Ce Li ** NaI ~Ge Li local ~Ge Li NaI ~Ge Li Far ~Ge LL Nar ~Ge Lr NaI ~Ce Li Nal C~eLi Nal Ge(Li>
1 6 1 N 1 Na s Ce 0.03 38 0. 55 0.35 0. 35 0.35 38 90 166C G. 02 33 0.22 0.06 0.06 0.35 0.06 33'4 4C 3 1Cr 0.07 0.03 60 44 l. 10 0.47 0.60 0.10 0.60 0.10 0.56 0.60 0.10 0.02 60 200 90 1311 0.01 0.01 15 8 0.35 0.09 0.20 0.02 0.20 0.02 0.07 0.20 15 8 50 20 103 ~ 106R 0.04 40 0.65 0.45 0.45 0.45 40 150 106R 0.03 40 0.51 O.ll O.ll 0.74 0. 11 40 90 136Cs 0.01 0.02 10 26 0. 20 0.33 0.12 0.08 0.12 0.08 0. 48 0.12 0.08 10 26 40 NO 1 33C 0.01 0.01 10 5 0.20 0.06 0.12 0.02 0.12 0.02 0.08 0.12 0.02 10 5 40 15 "Zr-hq 0.01 10 0.20 0.12 0.12 0.12 10 40 "Zr 0.01 10 0.03 0.03 0. 15 0. 03 '10 20 "Nb 0.01, 5 0.01 0.01 0.07 0. Ol 5 15 "Co 0. 02 0. 01 15 5 0.23 0.20 0.01 0.20 0.01 0.07 0.20 0.01 15 5 55 15 0.02 0.01 10 5 0.20 0.15 0.01 0.15 0.01 0.08 0.15 0.01 10 5 40 15 63zn 0.02 0.01 15 9 0.25 0.23 0.02 0.23 0.02 0. 17 0.23 0.02 15 9 70 20 60C 0.01 0.01 10 . 5 0.17 0. 11 0.01 O.ll 0.01 0.08 0.11 0.01 10 5 30 15 K 0.10 150 2.50 0.90 0.90 0.90 150 400 Ba-La 0.02 15 0. 68 0.15 0.15 0.15 15 50 .
1008 0.02 25 0. 34 0. 07 0.07 0.30 0.07 25 50 160La 0.01 7 0.08 0. 02 0.02 0.10 0.02 7 15
- The Nal(Tl) LLD values are calculated by the method developed by Pasternack and-Harley as described in HASL-300 and Nucl. Instr, Methods 91, 533-40 (1971) ~ These LLD values ate expected to vary depending on the activities of the components in the samples. These figures do not represent the LLD values achievable on a given'sample. Water is counted in a 3.5-L Marinelli beaker. Vegetation, fish, soil, and sediment are counted in a 1-pint container as dty weight. The average dry veight is 120 grams for vegetation and 400-500 grams fot soil sediment and fish. Meat and poultry are counted in a 1-pint container as dry weight, then corrected to vet weight using an average moisture content of 70'. Average dry weight is 250 grams. Air particulates are counted in a veil crystal. The counting systen consists of a multichannel analyzer and either a 4" x 4" solid ot 4" x 5" well NaI(T1) crystal. The counting time is 4000 seconds. All calculations are petforned by the least-squares computer program ALPHA-M. The assumption is made that all samples are analyzed within one week of the collection. date.
+*The Ge(t,i) LLD values are calculated by the method developed by Pasternack and Harley as described in HASL-300. These LLD values ate expected to vary depending on the activities of the components in the samples. These figures do not represent the LLD values achievable on given samples.
water is counted in either a 0.5-L or 3.5-L Matinelli beaker. Solid samples such as soil, sediment, and clam shells are counted in a 0,5-L Marinelli beaker as dry weight. The average dry weight is 400-500 grams. Air filters and very small volume samples are counted in pattie dishes centered on the detector cndcap. The counting system consists of a hq3-4420 nultichannel analyzer and either a 25ZN 14Z, 16K, ot 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 software Provided with the ND-4420. The assumption is made that all samples ate analyzed vithin one veek-of the collection date.
Conversion factor: 1 pCi 3.7 x 10 Bq.
Table 4 Results Obtained in Interlaboratory Comparison Program A. Air Fil.ter (pCi/filter)
Gross Al ha Gross Beta Stontium-90 Cesium-137 EPA value TVA AVG. EPA value TVA AVG. EPA value TVA AVG. EPA value TVA AVG.
Date (+3o) WARL EARL (+3o) WARL EARL (+3a) WARL EARL (+3o) WARL EARL 12/79 10 + 9 10 29 + 9 33 9 + 2.6 ll 10 + 9 10 3/80 Equipment malfunction at EPA 6/80 24 + 10 26 25 28+ 9 33 36 8'+26 9 8 12+9 13 12 9/80 24+ 9 24 24 10+ 9 12 16 0 0 (1 -10 + 9 9 9 12/80 Results not received at this time B. Tritium. in Urine (pCi/1)
Date EPA VALUE (+3a) TVA AVERAGE WARL EARL 12/79 2060 + 599 2100 3/80 2173 + 603 2300 6/80 2500 + 610 1437 2007 9/80 1700 + 589 1723 1693 12/80 3150 + 624 3287 3576
Table 4 (Contd}
Results Obtained in Interlaboratory Comparison Program C. Radiochemical Analyses of Water (pCi/1}
Gross Al ha Gross Beta Strontium 89 Strontium - 90 Tritium Todine - 131 EPA value TVA AVG. EPA value TVA AVG. EPA value TVA AVG. EPA value TVA AVG. EPA value TVA AVG. value Date (a3a) WARL EARL (i3a) WARL EARL ~3a wARL EARL (33a) wARL EARL ~(e3a wARL EARL EPA
~33a TVA AVG.
wARL EARL 11/79 12+9 14 27i9 27 12/79 2040+599 2128 53x9 50 1/80 3M14 25 45+9 47 10+9 98 20+2.6 238 2/80 1750f591 1920 3/80 13i9 12 22i9 25 4/80 3400j624 3363 44i9 41 5/80 23t9 23 20 14+9 16 18 5+9 4 6 12i2.6 13 11 6/80 2000i598 1947 1960 7/80 36il6 31 19 38i9 44 41 8/80 1210+570 1180 1223 36R9 33 26" 9/80 32+14 34 27 2&9 26 24 24j9 27 23 1542.6 18 16 10/80 3200+624 3207 3207 11/80 1619 16 20 13f9 16 24 12/80 2240+606 2270 2213 22+10 21 19 D. Gamma-Spectral Analysis of Water (pCi/1)
Chromium - 51 Colbalt - 60 Zinc - 65 Ruthenium 106 Cesium - 134 Cesium - 137 EPA value TVA AVG. EPA value TVA AVG. EPA value TVA AVG. EPA value TVA AVG. EPA value TVA AVG. EPA value TVA AVG.
Date ~(A3a wARL EARL (+3o) WARL EARL ~3a IIARL EARL ~(A3a WARL EARL ~e3a WARL EARL ~3a WARL EARL 2/80 6/80 10li9 13i9 93 0
11+9 ll 25+9 23+9 31 51+9 37+9 33 1019 11+9 16 30+9 31 18 Op 519 7 5>> 25 21 36k 40 15 10 1719 19 10/80 86i9 74 90 16f5 14 15 25+9 24 20 46i9 35 42 20+9 22 19 1219 12 13
Table 4 (Contd)
Results Obtained in Interlaboratory Comparison Program E. Milk (pCi/1)
Strontium 89 Strontium 90 Iodine 131 Cesium - 137 Barium - 140 Potassium EPA value TVA AVG. EPA value TVA AVG. EPA value TVA AVG. EPA value TVA AVG. EPA value TVA AVG. EPA value TVA AVG.
Deca ~33a WARL EARL ~3tf WARL EARL ~33a WARL EARL ~33a WARL EARL ~3a llARL EARL ~3a llARL EARL 1/80 4/80 1019 10i9 ll 10 25+2.6 15f2.6 28 18 0.0140.2 33+9 0
23i 40+9 2819 39 0.01%0.2 0 16001139 1577 30 0 0 11901103 1117 7/80 55i9 57 59 17+2.6 19 18 0 0 0 35t9 34 35 0 0 0 1550j135 1593 1533 10/80 23i9 25 25 0 1 <2 lgf9 18 12 21+9 22 22 0 0 <15 1620+140 1447 1473 F. Foods (pCi/kg, Wet Weight) 11/79 3/80 73+9 71 2712.6 34 Sample 127i ll 127 spoiled in transit 22i9 24 0.001 0 1511+132 1372 7/80 94i9 113P 107P 13+2.6 22 17P 54+9 47 49 2719 27 27 0 0 0 2260+225 2737 2730 11/80 gi9 <10 <10 0 3 3 34ilo 24 24 12+9 11 10 0 <15 <25 '5204208 2560 2723
- a. Western Area Radiological Laboratory, Muscle Shoals, Alabama.
- b. Eastern Area Radiological Laboratory, Vonore, Tennessee.
- c. Not reported to EPA.
- d. Low value result of deficiencies in analytical procedure.. The procedure has been revised to correct these deficiencies.
- e. Specific analysis for I to test the procedures used for the analysis of I in milk.
- f. Results not returned by EPA.
- g. Sr and Sr results reversed in report to EPA.
- h. Laboratory in start up mode: procedures being refined.
- i. Investigation of the sample and procedures produced no indication for the cause of the discrepancy. Subsequent analyses have been satisfactory.
- k. Analysis of these isotopes by NaI produce greater variation because of (1) the abundance of the main energy peaks (2) the broad shape of the peak, (3) relatively high background in the peak area, and (4) interference from radon peaks in the peak area.
m.
n.
Values for potassium reported as mg 6X'otassium per t of sample.
Values for potassium reported as mg of potassium per kg of sample.
p isc pane s in atro t um ~~l~~s are believed to be due to (I) inhomogeneity n we g t conversions. of. the ~ample ash and (2) magnificatio~ of 'sli8 h Efforts are being made to reduce the impacts of these variables.
Atmos heric Monitorin The atmospheric monitoring network is divided into three groups.
Pour local air monitors are located on or ad)acent 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 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 HV-70 particulate filter at a regu-lated flow of 3 ft3 /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-telemetere'd into the plant.
Air filters are collected weekly and analyzed for gross beta activ-ity. No analyses are performed until three days after sample collection.
The samples are composited monthl~ 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.
With reference to table 5, which contains the maximum permissible concentrations (MPC) recommended by 10 CPR 20 for nonoccupational exposure, it is seen that the maximum beta concentration in air is 0.12 percent MPC.
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 period one sample was not obtained because of, insufficient rainfall, The gummed acetate that is used to collect heavy particle fallout is 'changed monthly. During this reporting period, two samples were damaged to the extent that insufficient material remained for analysis.
The samples are ashed and counted for gross beta activity. The results are given in table 8.
12 Charcoal filters are collected and analyzed for radioiodine.
The filter is counted in a single channel analyzer system. The data are shown in table 9, where the highest value reported is 0.06 percent MPC in air for 131I.
13 Figure 2 ATMOSPHERIC AND TERRESTRIAL h(lONITORING NETWORK RM.28F LAWRENCEBURG yPULASKI FAYETTEVILLE ~
WILSON PM-IBF WHEELER ROGE SVIL FLORENCE OAM ATHENS PM-28F FFIEL MUSCLE BROWNS FERRY HUNTSVILLE SHOALS RM-I BF NUCLEAR PL NT LEIGHTON TUSCUMSIA It COURTLANO PM-4 F OECAT PM-38FD IO MILES pRUSSELLVILLE GUN T SV IL HARTSELLE OAM 2S HALEYVILLE CULLMAN r
45 MILES O- ENVIRONMENTAL MONITORING 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 Qa US HWY 72 BFN ALA. HWY 20 Legend 0 Air Monitor DECATUR O Air Monitor 8 TLD Station N b,:TLD Station h Automatic Well Sampler Scale H Dairy Farm 0 I 2 3 4 5 Miles
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.'16 Table 5 MAXIMUM PERMISSABLE CONCENTRATIONS FOR NONOCCUPATIONAL EXPOSURE MPC In Water In Air
~Ci./1* ~Ci/m'*
Alpha 30 Nonvolatile beta 3,000 100 e
Tritium 3,000,000 . 200,000 137CS 20,000 500 10 3 106RU s
10,000 200 144Ce 100000 200 95zr-95Nb 60,000 1,000 140Ba 140L 20,000 1,000 131I 300 100 65Z 100,000 2,000 s4Mn 100,000 1,000 Co 30,000 300 89Sr 3,000 300 "Sr 300 30 51C 2,000,000 80,000 134CS 9,000 400 s0G 90,000 2,000
- 1 pCi = 3.7 z 10 3 Bq.
TABI.E 6 RADIOACTIVITY IN AIR FILTER PC I/H(3) Os037 BQ/H(3)
NAHE OF F AC IL I TY~RRDM(IS E ERR Y DOCKET NDo 5DeeRBR*26Dc2%.
LOCATION OF FACILITY LIHESlOHE - - ALAB4))4 REPORTING PERIOD 198D TYPE ANO LOWER LIHIT ALL CONTROL NUHBER OF TOTAL NUHBER OF INDICATOR LOCATIONS LDCAIID(I-KIIUUIGUESI NhlQAL IIE48 LOC AT IONS NONROUT INE OF ANALYSIS DETECTION a HEAN (F) b NAHE HEAN (F)b HEAN (F)b REPORTED EEREORBED ILLDI 84NGE b DISZAIICE 4ND DIREDIIDII R4uGE b R4t(GE b BEASUREHEBZS GROSS ALPHA 0+005 0 ~ 01( 2/ 52) 52 Os01>> 0 ~ 01 GROSS BETA 0 ~ 010 0 F 03( 466/ 468) LH5 BF DAVIS F 0 '4( 52/ 52) 0 F 03( 104/ 104)
GAHHA (NAI) 572 0 F 01>> 0 ~ 1R 2 ~ 5 HILES WSK Oe01 Oe12 0 F 01>> 0 '9 1ll CS>>134 0 ~ 010 0~0I( ' 1/ 90) LH2 BF NORTH Oo01( 1/ 9) Rl VALUES <LLO 0 F 01 ~ 01 0 ~ 9 HILE NNE 0 ~ Ol>> 0 ~ 01 I>>131 0 010 0 ~ 01( 10/ 90) LH2 BF NORTH 0 ~ OR( Sl 9) 0 ~ 01( 2/ 21) 7 0 F 01
'6(
0 ~ OR 0 ~ 9 HILE NNE 0,01>> 0
'9/
'2 0 ~ Ol>> 0 ~ 02 BE GAHHA (GEL I)
NOT ESTAB 0 Os 02 BR/
0~ ll90) LH4 BF TRAILER le7 HILES NNK P 0 F 08(
0 F 05>> Oe 1
10
- 1) 0 ~ 06(
0 '2>>
20/
0 '021) 32 RU>>103 NOT ESTAB 0 ~ 01( 6/ ATHENS'L 0 ~ 01(
LR 95 0 ~ 010 0 F 01-0 F 02(
0 3/
'1RT) 10e9 HILES NE Oo01>>
1/
0 F 01
- 3) 5 VAI.UES <LLO RT) LH5 BF DAVIS F OeOR( 1/ 3) 0.01( 1/ 5) 0 ~ OI- 0 ~ OR 2,5 HILES WS'K 0 ~ OR>> Oe02 0 ~ 01 0 ~ 01 NB>>95 0 '10 0 F 01( 6/ RT)-
DECATUR'L Oe02( 1/ 2) 0 ~ Ol( 1/ 5)
Os01 O,OR 8~2 HILES SSE O,OR>> Oe02 Oo 01>> 0 ~ Ol X 40 NOT ESTAB 0 ~ 14(
0 F 08 18/
0 '8 27) LH1 BF NDRTHKEST loO HILE N Oe Oo 16(
14>>
2/ 2)
Oe18 0~
0e08 ll ( 3/
0 ~ 12 5) 8 l>>214 0 '20 Os04( 21/ RT) LH3 BF NORTHEAST Oe05( 2/ 3) 0 F 06( 4/ 5) 0 F 02" 0 ~ OT 1 ~ 0 NILE NE Oo04>> Oe06 Os03>> 0 F 08 PB 214 -Os020 Oo04( 14/ 27) ATHENS'L 0 F 05( 2/ 3) 0 F 05( 3/ 5)
OoOZ>> Oo07 10 ' HILES NE 0 ~ OS>> Oe07 0 F 05. Oe06.
PB 212 NOT ESTAB 0 F 02(
0 F 00 13/
0 '3 27) COURTLANOi AI.
10 ~ 5 HILES MSM.
0 ~ OS(
OeOS>>
Rl OeOS
- 4) 0 '2(
OoOR>>
2/ 5) 0 '2 BE<<T Os050 -0 '7( 13/ RT) LH5 BF DAVIS F ll( 1/ 3) 3/ 5)
TL>>208 NOT ESTAB 0 05 F
(
0~ ll 5/ 27) 2 ~ 5 HILES MS'K COURTLANDi AL 0~
Oe ll>>
0 ~ Ol( 1/
Oe ll4) Oo05(
0 '5 0 F 06 OsOI 5 VALUES <LLO 0 F 01 0 ~ Ol 10 ' HILES WSM 0 ~ Ol>> 'e01 AC 228 NOT ESTAB 0 F 02(
0 F 02 1/
0 '2 27) LH2 BF NORTH 0 ' NILE NNE 0
0
'2(
'2>> llOs02 4) 5 VALVES <LLD SR'9 0.005 q6 ViLVES <I.LD 8 VALVES <LLD 44 'ANALYSiS PERFORHEO SR 90 0 ~ 001 36 VALUES <LLO 8 VALUES <LLO 44 ANACYSIS PERFORHEO 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 parenthesis (P).
TABLE 7 RADIOACTIVITY IN RAINWATER PCI/L - 0e037 8()/L NAHE OF FACiLITY BBOWUS EEBLY- DOCKET NO ~ NaZSRa26Qa Q9 LOCATION OF FAC IL ITY il)(ESIO9E -- - 4L484((4 REPORT ING PERIOD 198O TYPE AND LOWER LIHIT AiL CONTROL NUHBER OF TOTA( NUHBER OF INDICATOR LOCATIONS LOCAZIOI( WIZEN UIGIIESZ 4((MAL.IIE4N LOCATIONS NONROU TINE OF ANALYSIS DETECT ION a HEAN (F)b NAHE HEAN (f)b SEAN (F) REPORTED REBEOBHEQ ILLQJ. B4NGRJ---- QISX4(1CE 4((Q QIBECZIOU 84((GEo- - 845GEo " 8EASUBEHEBIS GAHHA (NAI) 134 1~131 15 ~ 000 38.70(
3S ~ 70 1/ ill) 38 ~ 70 ATHENS'L 10 ~ 9 HILES NE 38s70(
38e70~
1/
38e70
- 13) 15e40(
15e40~
1/
15s40 23)
BE 7 NOT ESTAB 41e21(
2 ~ 60 71/ 111) 101 e 40 ROGERSVILLEi AL 13 ~ 8 HI LES NK 52.50(
16 F 80~
9/
-101 '0ll) 37 e51(
13.80-10/ 23) 65.90 GAHHA (GELI) 8 K~40 NOT ESTAB 76 76
'5(
'5 1/
76e95
76s95~
1/
T6e95
- 1) 2 VALUES <LLD 81 214 NOT ESTAB 21e62( 2/ 6) COURTLANOs AL 22 F 00( 1/ 1) 15e41( 2/ 2) 21 ~ 24 R2 F 00 10 5 HILES WSW 22 '0m 22e00 1 l,e 77~- 19 ~
7eTa( 1/ 6) COVRTLANQs AL 7s73( 1/ 1) 1/ 05'e67(
2)
PS~2%4 NOT ESTAB 7 '3%
17.9i(
7 ~ 73 2/ 6) 10e5 HILES WSW 7e73>'9e51(
7e73 I,/ 2) 8 2
'7~ 8 '7 VALVES <LLD PB 212 NOT ESTAB
)6e30 347 ~ 50(
19 ~ 51 1/ 6)
LH1 BF NORTHWEST 1 ~ 0 HILE N ROGERSVILLEi AL 19 'la 347s50(
19 ~ 51 1/ 2) 2 VALUES <LLD 7 NOT ESTAB BE 347 '0"
'4( 643 347 '0 6/ 117) 13 ~ 8 HILES NK 347e50e 550e98(
347e50 1/ 13) 25 VALUES <LLD TRIT IUH 142 330 F 000 426 3$ 2e 12 '6 ATHENS@ AL 10 ~ 9 HI LES NE 550 '8i 550e'98
- 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 parenthesis (P).
TABLE 8 RADIOACTIVITY IN HEAVY PARTICLE FALLOUT HCI/KH(2) 37000000i00 BQ/KH(2)
NAME OF FACILITY BBQNUS EEBBY - - - - '
DOCKET ND Ns2$ %a25Qa296 LOCATION OF FAC I L ITY LuIHESZOHE ALABAIIA REPORTING PERIOO IQBQ TYPE AND LONER LIHIT ALL CONTROL NUHBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCAIIOU MIZU UIOHESX AUhlUAL 5EAhl-~-- LOCAT logS NONROUTINE OF ANALYSIS DETECT ION a MEAN (F) NAME MEAN ([) MEAN (f) REPORTED EEBEOBHEO CLLQl RANQE-b QISZAHCE ANQ QIBE(:rIObl BA((QE BAHGE BEASUBEHEBXS-GROSS BETA 0.050 Oo26( 115/ 11$ ) LH4 BF TRAILER P 0 ~ 39( 13/ 13) 0 ~ 22( 26/ 26) 141 0 '6
- F 07 1 ~ 7 MILES NNN 0 ~ 09~ Oe94 0 F 06 0 '5
- a. Nominal Lower Liuit of Detection (LLD) as described in Table 3.
- b. Mean and range based upon detectable neasureuents only. Fraction of detectable neasurenents of specified locations is indicated in parenthesis (P).
OF TYPE AND TOTAL NUHBER ANALYSIS EEREORHED IODINE IN AIR NAME OF LOWER OF DETECTION a CLLD}
0.020 FACILITY'ROW((S LOCATiON OF FAC ILiTV iIHESZOhla LIHIT ALL EERRY INDICATOR LOCATIONS HEAN (F) b RANGE b Oe03(
'2- 48/ 468)
PCI/H(3)
LOCAZIOI(
NAHE TABLE 9 RADIOACTIVITY IN CHARCOAL FILTERS Oe037 ALAB454 80/H(3)
REPORTIt MllU UIGUESI N(IU4L DISIAIICE 48D DIRECIIOU ROGERSVILLEi AL 0 ~ 03(
UE48 HEAN (F)b R4((GE b 9/
POCKET NO 51)
G SDn25Ra24Da PERi00 19RD CONTROL LOCATIONS HEAN BABGEb Oo03(
(F)
V5" 10/ 104)
NUHBER OF NONROUTINE REPORTED BEASUREHEBIS 572 0 0 F 08 13 ~ 8 HILES NM 0 ~ 02 Oe06 0 ~ OR>> 0 '5
- 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 parenthesis (P).
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 results are shown in table 10.
Cow censuses were conducted in May and September 1980. Xt 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'ong-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'and Sr and Sr. The results are given in table 12.'round 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. 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 Browns Ferry Nuclear Plant are sampled and analyzed for gross 4
- 22 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'ith an automatic sampler with composite samples collected and analyzed'eekly. Two additional supplies downstream and one public ~ater supply upstream are collected'y monthly grab sampling. Table 14 indicates the results from the analysis of drinking water samples. The maximum beta concentration is 0.40 percent MPC.
'S Environmental Gamma Radiation'Levels Bulb'-type Victoreen Manganese-activated Calcium Floride (CaFg. Mn) thermoluminescent dosimeters (TLD's) are placed at nine stations around the plant near the'ite boundary and at the perimeter and remote air monitors to determine the gamma exposure rates at these locations. The dosimeters, in energy compensating shields to correct energy dependence, are placed at approximately one meter above the ground, with three TLD's at each station. They are annealed and read with a Victoreen model 2810 TLD reader. The values are corrected for gamma response, self-irradiation, and fading, with individualgamma response calibrations and self-irradiation factors determined for each TLD. The'LD's are exchanged every 3 months.
=
The quarterly gamma radiation'levels determined from"these TLD's are given in table 15, which indicates that average levels at.onsite stations are approximately 2 mR/quarter'igher 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. This may be attributable to natural variations in environmental radiation, levels, earth moving activities onsite, the mass of concrete employed in the
.construction'of the plants, or'other undetermined influences.
Poultr and Food Cro s Food crops and poultry raised in the vicinity of BFN and at control. locations are sampled as they become available during the growing season, and analyze'd for gamma-emitting radionuclides. - During this sampling period samples'f cabbage, corn, green beans, peaches, potatoes, tomatoes', -so'ybeans, and'poultry were collected and analyzed for specific gamma-emitting radionuclides.- No sample of soybeans was taken from a control location. 'The results are given'n tables 16, 17, and 18.
TABL'E lo RADIOACTIVITY IN XILK PCI/L Oe037 84/L f
NAME.OF AC ILITYBRQbt(IS EERRY LOCATION Of FAC IL ITY LIIIESIQI(E 4L464II4 - --
DOCKET NOD SQsRHa26Oa29$
REPORTING PERIOD 1984
'f 137'ONER LIMIT ALL NUHBER OF TYPE AND CONTROL TOTAL NUHBER OF INDICATOR LOCATIONS LQCAIIQH MIIU UIGI(ESI NBLIAL 5E48 I.QCAT ION/, NQNROUT INE ANAI.YSIS DETECTION a MEAN. (F)b - NAHE HEAN (P) b MEAN (F) REPORTED I,LLQl 84NGE b QISIAI(CE AUQ ()1RECIIQM 'a((GER REBEQ85EQ 84hlGEb IIEASUREIIEBIS GANHA (NAI)
- 109
'CS 10 000 -le 38( 4/) 59) SHITH FARM llo95( 2/ 1R) 10.60( 1/ 50) x0.5o- 12.80 4o75 HILES N 11 ~ 10>> 12 F 80 -10.60- 10.60 K>>40 .
150 F 000 .1261 109'0<<,
'3( 59/ 59) 1406e40.
SNITH FARH-
'4e75'ILES N 1302 F 87( 12/ 1R).
1129 ~ 00>> 140be40 1229.93( 50/ 50) 1087 ~ SO 1371 ~ 00 IODINE IN NII.K 'Oo500 0 F 80( 6/ 259) BROOKS FARH'e0 Oe89( 3/ 50) . Oe56( 2/ 201) 460 Oe55 le 18 MILES NN)( Oeb9>> le 18 Oo50>> Oebl GAHHA (GEL I) 8 K>>40 NOT ESTAB 15<3 F 00( . 6/ 6) SNITH FARM 1642e00( 2/ R) 1476 '0( 2/ 2)81-214 NOT ESTAB.
1302oOo" 88e84(
24 ddt 5/')
175'0 3'5 4e75 NILES THRASHER FARM Too MILES ENE N 1579 F 00>> 1705e00 3'5(
3be45>>
1/
36 F 45 1) 1450 F 00>> 1503 F 00 RO ~ 04(
17 '2>>
2/ R) 22eRS.
P 8!214 NOT ESTAB ,24 '2(
le 34 3/
36e47
- 6) SNITH FARM 4e75 MILES N 3be47(
36e47>>
1/.
$ 6 ~ 47 2)
~
15.81(
15 ~ 04>>
z/ =z) 16 ~ 57 Pb 212 NOT ESTAB id'8.( 2/ 6) 8 ITTING FARH R3 ~ 95( 1/ 2) 2 VALUES <LLD
-..8 81>>,
F 23 ~ 95 4eS HILES ENE 23e95>> 23 ~ 95 SR 89 10o000 65 .V4LUES CLLO 5$ VALUES elLLD 118 ANAiYSIS PERFORMED SR 90 2 F 000 4e ll ( 62/
9e08
- 65) BROOKS FARH 7'e0 MILES NNM 5 43(
3e36>>
12/
F 04
- 12) 5 '1(
06>>
43/
9e89 53)
( 118 2e04 RE
+
C '
- a. Noadnal Lower Liait of Detection-(LLD) as described in Table 3.
b., Mean and range based upon'detectable.measurecients only. Praction of-detectable measurenents of specified locations is indicated in parenthesis'-(P). ~
TABLE 11 "RADIOACTIVITY IN VEGETATlON PCI/G>> 0 ~ 037 BQ/G (DRY MEIGHT)
IL I TY~RRQMUS 296 NAHE OF FAC LOCATION OF FACILITY LIUESIOUE--
KERRY
-- - OLORO5O REPORTING PERIOD?Hg.26Qa DOCKET NQ ~ SQ 19SQ TYPE AND COMER LIHIT ALL CONTROL NUHBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCOIIOU MIIU UIGHESI AUUUOL HEAU- - LOCATIONS NONROUT INE OF At(ALYSIS DETECTION a MEAN (F) NAME HEAN (F)b HEAN (F)b REPORTED
-SFREORUEO CLLQX - ROUGE b OISIOUC.E OUQ QIRECIIOU ROUGE RAUGEb UEASUREUEUZS
'00 20/ 4/ 18.57( lb/
GROSS BETA GAHMA 36 (GELI) 0 23o56(
7o54 50 '220) THRASHER FARM 7 ' MILES ENE 31 ~ 14(
16,36 40 '8 o) 5o47 44o02 16) 36 144 '20 '0( 2/ 20) 0.44( 1/ 2/ 16) 0 0
'4 4) Oo38(
CE LOONEY FARM BA-140 0 ~ 3o0 Oe36 . 0 20 VALUES <LLD
'4 F 75 HILES ENE 0 F 44>> 0 Oe25.
0 '9( Oe50 1/ lb)
Oe59 Oe59 LA-140 0 F 080 0 ~ 10(
0 ~ 10 1/ 20) 0 ~ 10 THRASHER FARM 7 ' MILES ENK 0 '0(
0 ~ 10>>
1/
'0 4) Oe42(
Oe42>>
1/
0 '216)
.0 RU-103 0 '00 0 '8( 5/ 20) LOONEY FARH Oob5t 1/ 4) 0,35( 4/ 16)
CS 137 0.060 0 '1 0 ~ 11(
Oeb5 6/ 20) 5o75 MILES LOONEY FARM ENE 0.65>>
0 ~ 16( 1/
Oe65 4) 0 '4>>
0 ~ 12(
Oe50 6/ 16)
Oe07 Oo 17 5 ~ 75 HILES ENE 0.16 Oe 16 0 ~ 08>> Oe lb ZR 95 0 '10 -
0.44t Oe22 5/
Oe96
- 20) LOONEY FARH 5o75 MILES ENE 0
0
'6(
'6>> 1/
0 '6 4) Oe48(
0 '7>>
4/ lb)
Oeb8 NB 95 0.050 0 '4( 5/ 20) LOONEY FARM le00t 1/ 4) 0 '9( 4/ 16) 0 ~ 27- le00 5o75 HILES ENE le 00>> 00 Oe31 0.84 K>>40 NDT ESTAB 12 '4t le 37-20/ 20) 27e60 THRASHER FARH 7 ' HILES ENE 17e77(
be51>>
4/
27 1 ~
'0 4) 9 '9( 15/ 16) 22 '916)
F 12 Bl 214 0 F 100 0 '$ ( 17/ RO) LOONEY FARM
'5 0 '4(lr 4/ 0 '9( 12/
Dell Oe53 5 MILES ENE Oe 1 Oo53 Oe10>> Oe49 PS 214 NOT ESTAB OoR3( 18/ 20) LOONEY FARH Oe26( 3/ 4) 0.24( 13/ 16)
Oo08 De41 5o75 HILES ENE Oe12>> Oo34 De 12, Oe47'2/
PB 212 NOT ESTAB Oe15( 15/ 20) LOONEY FARH Oo23( R/ 4) Ool3( 16)
BE-7 Oe06 0 7ob9( 20/ 20)
'3 5 ~ 75.MlLES ENE Oe13>>
4/
Oe33 0 F 07>> 0
'3( 16/ 16)
'4 TL 208 NOT ESTAB NOT ESTAB 0 81
~
Oo07(
29e ll 6/ 20)
SITTING FARH 4~5 MlLES FARH ENE'OONEY 10e31(
Oe81>>
Oe08(
29e 2/
ll4)4) 9 2o 13, 0 '6(
2beR7 8/ 16)
AC-228 NOT ESTAB 0 03 F
0 '4(
0 '2 10/ 20) 5 '5 HILES ENE I.OONEY FARH Oo03>>
Oo54( 3/
0 ~ 12 4) oo04 Oo25t Oe10 7/ 16)
Oe14 0 '7 5 ~ 75 MILES ENE 0 '0>> 0 '7 Oo12>> 0 ~ 34.
- a. Nominal Lover Limit of Detection (LLD) as described in Table 3.
Mean and range based upon detectable neasurenents only. Fraction of detectable measurements of specified locations is indicated in parenthesis (F).
TABLE I2 RADIOACTIVITY IN SOIL PCI/G>> 0 ~ 037 BQ/G tORY MEIGHT)
NAME OF FACILITYRRQNt(S KERR)( DOCKET NO ~ KQaRRRa26Qa~
LOCATION OF FAC IL I TY LIHKSIO((K REPORTING PERIOD 1RRQ TYPE AND LOMER LIHIT ALL CONTROL NUHBKR OF TOTAL NUHBER OF INDICATOR LOCATIONS LQCAZIQI( MCTV VZQUESZ au((UAL t(Eau LOCATIONS NONROUT INE OF ANALYSIS DETECTION a HEAN (F)b NAHE MEAN (F) < HEAN (F)b REPORTED REBEORHEQ CLLQl BANQE3 QlSIAI(CE AUQ QIRE(iZIOtt RA((GE RA((GEb t)KASURE((EhlZS GAHHA (GEL I )
137 ll '20 Oe4lt 9/ 9) ATHENS'L CS 0 ~
De86( 1) 0.60( 2/ 2)
K>>40 0.250 0 ~ 18-5 '2(
De86 9/ 9) 10e9 MILES LHl NE BF NORTHWEST
. De86>>
8 '4( 1/
0 '6 1)
Oe45>>
4.51(
Oe75 2/ 2) l>>214 Os050 3e49-le04(
8 '4 9/ 9) le0 HILE N Be04>> 8 04 F 4e)9 4e83 B LH2 BF NORTH 39( 1/ 1) Oe91( 2/ 2)
BI 212 0 ~ 100 0 '5 0 '7t 1
9/
~ 39 9) 0~9 NILE NNE 1 ~
ls39>> lo39 0 '2>> F 01 LH4 BF TRAILER P Oe97( 1/ 1) 0 F 78( 2/ 2) 214 0.050 0 '0 1.10t 0
9/
'7 9) 1~7 H ILES NN)( 0 '7>>
le43(
De 97 Oe77 De78 PB LH2 BF NORTH 1/ 1) Oe99( 2/ 2) 0,73- 1~ 43 0~9 NILE NNE 1,43 le 43 0 F 89 F 09 PB>>212 NOT ESTAB leR4( 9/ 9) DECATUR'L 1e56( 1/ 1) 1 'R( 2/ 2)
Oe71 1 ~ 56 8 ~ 2 HILES SSE 1.56 le56 1 00>> F 04.
0 '50
~
RA-226 1 e04 ( 9/ 9) LH2 BF NORTH 1 ~ 39( 1/ 1) 0 ~ 91( 2/ 2) 0 '5>> =
1 39 Oe9 HILE NNE 1 ~ 39>> le 39 Oe82>> le01 RA 223 NOT ESTAB 0 '9( 6/
~
'8 9)9) LH2 BF NORTH 0 '8( 1/ 1) VALUES <Ll.D
'20 0 28 0 '2(
F 0 0 ~ 9 NILE NNE F 51>>'/1/
0 48>> 0 '8 1) R TL 208 0
'6 9/
0 '2 DECATUR'L 0 'R( 0 '9( 2/ 2)
AC 228 0.-060 0
le22( 9/ 9) 8 ~ 2 HILES SSE LHl BF NORTHWEST Oe5R le5),( 1/
Oe52 1)
De37>>
loll(
0 '1 2/ 2)
Oe77 . le51 le0 HILE N le 1e51 1<<04>> le18 SR 89 1 ~ 500 .9 VALUES <LLO 2 VALUES <LLD 11 ANALYSIS PERFORHED SR 90 Os300 9 VALUES <LLD 2 VALUES <LI.D ll ANACYSIS PERFORHED
- 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 parenthesis (P).
TABLE 13 RADIOACTIVITY IN MELL MATER PCI/L - 0.037 80/L NAME OF FAC ILITY BRQMUS KERRY DOCKET NO. SQn252c26Qc2M LOCATION QP FACILITY LIHESIOUE REPORTING PKRIOD 198Q TYPE AND iOHER LIHIT ALL CONTRDL NUHBER OF TOTAI. NUHBER OF INDICATOR LOCATIONS (F)b LOC4XIOU-MIIU hII(3)1ESI 4WMAL ()E48, b I.OCAT IDNS HEAN (F)b NONROUT INE OF ANALYSIS DETECTIONa I'IEAN NAHE HEAN (P) REPORTED PEREORBEQ ZLLQX R4HQEI w w w QISI4HCE 4((Q QIRECIIOU RAt(GE~ - ((EASUREBEhlIS GAHHA (NAI)
RAGE'1 22 11 VhLUES <LLD VALUES <LLD .
ANAiYSIS PERFORHED GAHHA t GEL I ),
4 K 40 NOT ESTAB 67.32(
66.53-2/ .
68.11
- 2) BFN MELL 0.02 HILES
¹6 M
67 '2(
bbo53r 2/
68ell
. 2) 68.70(
69i70<<
1/ 2) 1/ BFN HELL ¹6 1/ 2) 69'e70'bi04(
81 214 NOT ESTAB $ 3 ~ 63( 2) 13a63( 1/ 2)
PB-214 NOT ESTAB 13,63 12.5lt 13 1/
'3 2) 0 ~ 02 HILES W BFN HELL ¹6 13 ~ 63>>
12e51(
13 ~ 63 1/ 2) 16 '4~
11 ~ 53 (
16 F 04 1/ 2)
PS~212 NOT ESTAB i2 5i<<
2 VALUES <LLD 12 51 0 '2 HILES M 12 ~ 51~ 12 F 51 11 53 13.35(
~
ll 1/, 2) 53 13 '5~ 13+35 TR IT IUH 330 F 000 VALUES <LLD 4 VALUES <L(.0 ANALYSIS PERFORHED
- 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 lri parenthesis (P).
TABLE 14 RADIOACTIVITY IN PUBLIC MATER SUPPLY PCI/L 0 ~ 037 BQ/L NAHE OF FACILITY BROMhlS LOCATION OF FAC IL ITY LIHESIOUE EERRY -
'L464I)4 REPORTING DOCKET NO 5Rn2$ Ra26QaMS PERIOD 1MQ TYPE AND LONER LIMIT ALL CONTROL NUHBER OF TOTAI NUHBER OF INDICATOR LOCATIONS LOC4IIOU-MIXU UI(1)1ESZ 4((OVAL WE48-- LOCATIONS NONROUTINE OF ANALYSIS DETECTION a BAN (F) b NAHE MEAN (F)b MEAN (F)b REPORTED REREORIIEQ LLLQ1 - 8486%--b QISIAUCE 4UQ RIRECIIOU R4(IGE R4(IGE b IIEASUREHEHZS GROSS BETA F 400 3.69( 46/
ll 9978) '3( 4/ 3/
GAHHA (NAI) 91 2 ~ 41~ ~
5 2 '9>> 11 '913) Se05(
2 F 49~ 3e80 13) 84 72 VALUES <LLD 12 VALUES <LI.D ANACYSIS PERFORMED GAHHA (GEL I )
7 K~40 NOT ESTAB 76e44(
74e65 2/
78 '2 6) CHAMPION PAPER 282eb 78 '2(
78e22~
1/
78'e 22
- 3) 102 F 80( 1/ 1)
TRH 102 F 80~ 102 F 80 BI 214 NOT EST~8 19 F 88(
9e09-3/ 6) 26 F 20 llHEELER OAHi AL TRH 274 '
26 '0(
26 F 20~
1/ 3) 9 ~ 15( 1/ 1)
Z6 ~ 20 9e15 9 ~ 15 P 8~214 NOT ESTAB ( 2/ 6) CHAMPION PAPER 24 '5( 1/ 3) '3( 1/
'3 1) 21e6 13 PB 212 NOT ESTAB i8.86 1
$ 5e03(
24,35 2/ 6)
TRH 282 F 6 CHAHPION PAPER Zhe35~
19e43(
24 1/
'5 3) 13 '3>> 13 1 VALUES <LLD i0,6i-... 19.4S TRH 282 ' 19 '3~ 19e 43 SR 89 10 ~ 000 1Z VALUES <LLD 4 VALUES <LLD 16 ANALYSIS PERFORHED SR 90 F 000 $ 2 VALUES <LLD 4 VALUES <LLD 16 ANALYSIS PERFORMED TRITIUM 330 F 000 34S.29( 1/ 12) SMEFFIELOiAL ROB 343e29( 1/ 4) 4 VALUES <LLD 16 343e29- 343 F 29 TRH 254 ' 343 '9~ 343e29
- 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 parenthesis (p).
28 Table 15 ENVIRONMENTAL GAMMA RADIATION LEVELS Environmental Gamma uarter Location I ~i Radiation Levels January-April 1980 On-Site (8)-b
.Maximum, 10.6 23.1 Minimum c
7.3 15. 9 Average 9.4 + 2.3 20.7 + 5.0 Off-Site (7)
Maximum 12. 5 27.4 Minimum 6.9 15.2 Average 8.6 + 3.7 18.9 + 8.2 May-July 1980 On-Site (8)
Maximum Minimum Average 9.0 10.
7.4
+
0,2.0
- 21. 9 16.3 19.8 + 4.4 Off-Site (7)
Maximum ll. 1 24.3 Minimum 6.8 14.9 Average 8.1 + 2.8 17.8 + 6.1 July-September 1980 On-Site (9)
Maximum 10.3 22.6 Minimum 7.9 17.3 Average 9.5 + 1.8 20.9 + 4.0 Off-Site (7)
. Maximum 11.0 '24.2 Minimum .' ~ 3 16.0 Average 8.5'+ 2.5 18.6 + 5.5 October-December 1980 On-Site (9)
Maximum 11.5 25. 1 Minimum 7.8 17.2 Average 10.0 x 2.3 21.9 + 5.0 Off-Site (7)
Maximum 12. 0 26.3 Minimum 7.4 16. 3 Average 8.7 + 3.1 19.1 + 6.8 bData normalized to one quarter (2190 hours0.0253 days <br />0.608 hours <br />0.00362 weeks <br />8.33295e-4 months <br />)
Number of stations (normally three TLD's at each station)
All averages reported +2a (95% confidence level)
TABLE 16 RADIOACTIVITY IN FOOD CROPS PCI/KG >> 0 '37 80/KG (WET WEIGHT)
NAHE OF PACtLITY 4BQWQS EEBBY--- DOCKET NOo SOm25%E260a29E LOCATION OF FACILITY LISESZOHE- AL444I)4 REPORTING PERIOD aR41)
TYPE AND LOWER LIHIT ALL CONTROL NUMBER OF TOTAL NUHBER OF INDICATOR LOCATIONS LOCAZIOu M2ZI( VIGIIESZ 4((((MAL uE4N LOCATIONS NONROUTINE OF ANALYSIS DETECT IONa HEAN (F)b NAHE MEAN (F) > MEAN (F)b REPORTED eEBEOBIIEO --CLLQ2--- RANGE3r OlSZ4((CE 480 QIBECIIO((=- B48GEb - BAI(GE b SEASUBEBEHIS RADIOACTIVITY IN CABBAGE GROSS SETA 25 000 44i3o59( 1/
GAHHA (GELI) 2 4413 '9 4413 '9 1) SHI TH FARH 4 ~ 75 HILES N 4413 o 59 ( 1/
4413 ~ 59>> 4413o59
- 1) 4338 ~ 21(
4338 F 21>> 4338 1/
'1 1) 2 K>>40 NOT ESTAB 174So00( 1/ 1) SHITH FARH 1748.00( 1/ 1) 1646,00( 1/
1748o00 1748 F 00 4 '5 MILES N 1748.00>> 1748;00 1646.00- 1646.00 1)
PS 212 NOT ESTAB 16 ~ 52(
16 ~ 52 1/
16o52
- 1) SHITH FARH 4 ~ 75 MILES N 16 '2(
16 52 1/ 1) 1 VALUES (LLD 16o52 RADIOACTIVITY IN CORN GROSS BETA 2
25 F 000 3535o84(
3535 F 84 1/
3535 F 84
- 1) SHITH FARH 4 ~ 75 MlLES N 3535.84(
9535o84>>
1/
353'4
- 1) 3247 '7( 1/ 1)
GAHHA (GEL I )
3247,77>> 3247o77 2
K>>40 NOT ESTAB 2440o00( 1/ 1) SHITH FARM 2440o00( 1/
00- 2440 ~ 0()
- 1) 1758 o00( 1/ 1) 2440 ~ 4o75 HILES N 2440 F 00>> 2440 F 00 1758 F 00>> 175'0 RADIOACTIVITY IN GREEN BEANS GROSS SETA 25 F 000 4817 18( 1/ 1) SHITH FARM 4817 18( 1/ 1) 4638ob3( 1/ 1) 2 4817o18>> 4817 ~ 18 4 ~ 75 MILES N 4817 ~ 18>> 4817olS 4638o63>> 4638o63 GAHHA (GELI) 2 K>>40 NOT ESTAB 29i6.00( SMITH FARH 2916 ~ 00( 1/ 1) 2310 F 00( 1/ 1) 29i6.0o;, 2916o00 4 ~ 75 MILES 'N 2916 ~ 00>> 2916 ~ 00 2310o00>> 2310o00 PB '212 NOT ESTAB llo17( 1/ llo17( 1/ 1)
- 1) SHITH FARH lo,zs( 1/
11 o 17- 11 ~ 17 4o75 HILES N 11 ~ 17>> ll ~ 17 10 'S>> 10 '8
- 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 parenthesis (F).
TABLE 16 (Contd}
RADIOACTIVITY IN FOOD CROPS PCI/KG 0 ~ 037 8()/KG (MET HEIGHT)
NAHE OF FACILITY BRQUUS EERBY- DOCKET NO ~ SQa259c26QcV6 LOCATION OF FACILITY LIUKSIOUK ALABAUA REPORTING PERIOD 19()Q TYPE AND LONER LIMIT ALL CONTROL NUMBER OF TOTAL NUHBER OF INDICATOR LOCATIONS LOCAIIOU MIIU UlGUESI AUUUAL VEAU LOCAT IONS NONROUT INE OF ANALYSIS DETECTION a MEAN (F)b NAME HEAN (F)b MEAN (F)b REPORTED EEBKORUEQ CLLQl RAUGK3 QISIAUCE AUQ QCBECIIOU -- BAUGEb BAUGEk UEASUREUEUIS RADIOACTIVITY IN PEACHES 25.000 5600 '4(
'4 -56901/ 5690 ~ 34( 1/ 6935 ~ 15 ( 1/
BETA
'4 1) SMITH FARM 1) 1)
GROSS GAHHA t GEL I) 2 5690 4 '5 HlLES N 5690 '4 5690 F 54 6935 ~ 15~ 6935 ~ 15 .
I 2
K+40 NOT ESTAB 2183 ~ 00 ( 1/ 1) SHITH FARH 2183 ~ 00( 1/ 1) 1888 ~ 00( 1/ 1) 2183 ~ Oo 2183 ~ 00 4 ~ 75 MILES N 2183 ~ 00 2183 ~ 00 1888 00, 1888 ~ 00 RADIOACTIVITY IN POTATOES GROSS BETA 25 000 7789.95( 1/ 1) 7789 ~ 95( 1/ 8228 ~ 30( 1/
'5 1)
HARGROVE FARH 1)
GAHHA (GELI) 2 7789.95- 7789.95 3 ~ 75 HlLES N 7789 '5~ 7789 8228 '0 822be30 2
K~40 NOT ESTAB 4121 ~ 00( 1/ 1) HARGROVE FARM 4121soo( 1/ 1) 3483 F 00( 1/ 1) 412leoo 4121 ~ 00 3 ~ 75 HlLKS N 4121 ~ 00~ 4121 ~ 00 3483 F 00~ 3483 F 00 RADIOACT1VITY IN TOHATOES GROSS BETA 25.000 487be55(
4876o55~ 4876 1/
'5 1)
SHITH FARH 4876 '5(
4876.55 1/
4876r55
- 1) 4844 '4(
4844.24 1/ 1) 2 4 ~ 75 H1LKS N 4844,24 GAHHA (GEL I )
2 K 40 NOT ESTAB 2485.OO( 1/ 1) SHITH FARH 2485 F 00( 1/ 1) 2456.00( 1/ 1) 2485.0O- 2485>00 4o75 MiLKS N 2485eoo~ 2485 F 00 2456eoo 2456 F 00
- 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 parenthesis (F).
TABLE 17 RAOlOACTIVITY IN SOYBEANS PCI/G ~ 0 '37 80/G tORY WEiGHT' NAHE OF FACILITY BRQWUS EEBRY- DOCKET NO ~ Spe25Ra26pa-LOCAT ION OF FAC IL I TV LIBEiZOUE ALARAHa REPORTING PERIOD 1RBO TYPE ANO LOWER LIHIT AiL CONTROL NUHBER OF TOTAL NUHBER OF INDICATOR LOCATIONS LOCAZIOU l(IZU )jIGNSZ auhlUAL HE4((
OF ANALYSIS OETECT ION a MEAN (F)b NAME ~ LOCATION)
NONROUTINE REREORBEO LLLQl= RAhlQE b QISIAHCE Ahlp QIBE{;ZIPU MEAN ($ ) HEAN ()) REPORTEO GROSS BETA 0.200 40 '9( 1/ 1)
RAQGE RABGE HEASUREHEUZS 40e89(
GAHHA (GEL I )
1 40 '9- 40 '9 HARGROVE FARH 3 '5 HILES N 40 89 1/
40 89 1) 1 K~40 NOT ESTAB 17 F 07( 1/ 1) HARGROVE FARH 17e07( 1/
BI 214 NOT'STAB 17 tOT 0 '6(
17e07 1/ 1) 3 '5 HILES N 17e07~ 17s07 1)
HARGROVE FARH Oo06( 1/
0 '6
'6(
0 '6 3e75 HILES N 0 '6~ 0 '6 1)
P B-214 NOT ESTAB 0 1/ 1) HARGROVE FARM 0 '6( 1/ 1)
Oe06 0 '6 3 '5 HlLES N 0' 06~ 0 '6
- a. Nominal Lower Limit of Detection (LLD) as described in Table 3.
- b. Mean and'ange based upon detectable measurements only. Fraction of detectable measurements of specified locations is indicated in parenthesis (F).
TABLE 18 RADIOACTIVITY IN POULTRY PCl/KG 0 ~ 037 BQ/KG (NET MEIGHT)
NAHE OF FACILITYRROilUS EERRY DOCKET NO ~ EQm25Ra26Qc295 LOCATION OF FACILITY LIHESIO5E ALABAMA REPORTING PERIOD 198O TYPE AND LOMER LIHIT'F ALL CONTROL NUHBER OF TOTAL NUHBER INDICATOR LOCATIONS LOCAZZOV )(IXV IIIGUESZ A((((UAL.VEAU'~ LOCATIONS NONROU TINE ANALYSIS DETECTION a (F)
OF REREORIIEO CLLOZ HEAN BAt)GEJ NAHE OISIAUCE-AHO QIRECZIOH -
HEAN (F) HEAN ([) b REPORTED RA((GE RANGE BEASVREIIEHZS GROSS BETA 25 F 000 45i4,98( 1/ 1) SHITH FARH 4514e98( 1/ 1) 2496o29( 1/ 1) 2 4514 ~ 98- 4514 ~ 98 4e75 MlLES N 4514e98~ 4514e98 2496 e 29~. 2496 ~ 29 GAHHA (GEL I )
2 CS-137 15 ~ 000 18 96( 1/
'6 1) SHITH FARH 18 '6( 1/ 1) llew 1 VALUESllew<L'LD K~40 NOT ESTAB le 96-1950 F 00(
18 1/ 1) 4 ~ 75 H ILES N SHITH FARH
, 18e96~
1950s00(
18 1/
'6 1) 2152 F 00( 1/ 1) 1980 F 00 1950 F 00 4e75 HlLES N 1950 F 00~ 1950 F 00 2152 ~ 00~ 2152 ~ 00 Bl 214 NOT. ESTAB 1 VALuES <LLD 19e74( 1/ 1)
PB 214 NOT ESTAB VALUES <LLD 19 '6~
lie 81(
19 1/
'6 1) 81~ 81 TL~208 NOT ESTAB 20e01( 1/ 1) SHITH FARH 20 ~ 01( 1/ 1) 1 VALUES <LLD 20 F 01 20 F 01 4~ /5'lLES N 20 ~ 01~ 20 ~ 01
- 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 of specified locations is indicated in parenthesis (P).
H Reservoir Honitorin Samples are collected from t'e Tennessee River as detailed in table 19. Samples collected for radiological analysis include plankton from three of these cross sections and bottom fauna and sediment from four cross sections. The locations of these cross sections are shown on the accompanying map (figure 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 three cross sections and composite samples analyzed monthly for gamma-emitting radionuclides. Further composites are made quarterly for strontium and tritium analyses. In addition to these required samples, grab samples were also collected monthly from the vicinity of the plant discharge to the Tennessee River, and at a point on the Elk River, and analyzed for gross beta, gamma-emitting radionuclides, and strontium. Results are displayed in table 20.
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.'o 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 Browns Ferry Nuclear Plant preoperational monitoring program. Two species, white crappie and smallmouth buffalo, are collected represent'ing both commercial and game species. Sufficient fish are collected in each reservoir to yield 250 to 300 grams oven-dry weight for analytical purposes. All samples are collected semiannually and analyzed for gamma-emitting radionuclides. The composite samples contain approximately the same quantity of flesh from each fish. For each composite a 'subsample of material is drawn. for counting.
Results are given in tables 21, 22, and 23.
Plankton As indicated in table 19, net plankton (all phytoplankton and 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 accuracy. Samples are collected semiannually and submitted for gross beta anal'ysis, and when quantities are sufficient, for gamma activity and Sr
34 and Sr content. During'his reporting period, all samples contained in-sufficient volume of material for gross beta, strontium, or gamma analyses.
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 19. Results are shown in table 24.
Bottom Fauna The flesh and shells of Asiatic clams collected semiannually from the cross sections at four stations (table 19) are analyzed for gamma-emitting radionuclides. Levels of Sr and Sr are determined on the shells, and on the flesh when sufficient amounts were available. A 50-gram (wet weight) sample provides sufficient activity for counting. 'During this reporting period, one sample of clam flesh contained insufficient volume for analysis. Results are given in tables 25 anl 26.
Table 19
. SAMPLING SCHEDULE RESERVOIR MONITORING Biolo ical sam les collected semiannuall Zooplankton, chlorophyll, Benthic a 'ater samples River/river mile fauna Sediment Fish (collected monthl )
Tennessee 277.9 Tennessee 285.2 Tennessee 288.7 X Tennessee 291.7 Tennessee 293.5 Tennessee 293.7 X (discharge area)
Tennessee 305.0 Tennessee 307.5.
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.
Figure 5 R ES ER VOI R MONITORIN 6 NETWORK Elk River WHEELER DAM mile 274.90 mile 277.98 Rogersvilte 0
rnite 29l.76 Athens mite 282.6 0
~mite 285.2 B.F. NUCLEAR PLANT A
Champion Paper Co.
te 288.78 mile 293.50 0
Cour tland mile 305.0 mile "295.70 0
Decatur mile 30752 Scale of Mites
~ - Automatic Sara ter 0
TABLE 20.
RADIOACTIVITY IN SURFACE MATER TOTAL PCl/L Qo037 BQ/L NAME.OF FACILITY,RRONUS KERRY LOCATION OF FAC IL ITY~LIHESIO9E 4L46454 REPORT DOCKET NO ~
ING SOaRSRaZlhOa~
PER IOb 1QBO TYPE AND LONER LIHIT ALL CONTROL NUHBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCAIIOB-MCIU hllGQESI-485UAL 5548 LOCATIONS NONROUT INE OF ANALYSIS DETECTION a MEAN (F) b NAHE MEAN (F)b HEAN (F)b REPORTED REREORUEO CLLQL 84blGKb OISI4((CK Auo RIKE(;Ital KaME b RaUGEb BEASUREHNIS GROSS BETA 2 '00 3o88(
'7" 6/
beb3
- 13) TRH 293 '
DISCHARGE 3e88(
'7r 6/ 13) 6 ~ 63 4 '2(
'4r 10/
12 '513) 26 2 BFN 2 2 GAHMA (NAI) 50 26 VALUES <LLD 24 VALUES <LLD ANALYSIS PKRFORHED GAHHA (GELI) 15 Kr40 NOT ESTAB 92e20( 6/ 13) TRH 293o7 10be54( 4/ 6) R VALUES <LLD 53 ~ 90 156 'D BFN DISCHARGE 64e34r 156eRD 81 214 NOT ESTAB 23.30( 9/ 13) TRH 293o7 24.50( 3/ 6) 13o99( 1/ 2)
To75 39 ~ 11 4/
BFN 01SCHARGE 12 '4r 30 ~ 93 6) 13o99r 13e99 P8-214 NOT ESTAB 18 F 04( 13) TRH 293o'7 19.91( 1/ R VALUES <LLD PB 212 NOT ESTAB ll 96
~
16 '0(
R 5/
e ~ 02 13)
BFN DISCHARGE TRH 285 '
- 19. 91r 18 ~ 62(
19 ~ 91 4/ 5) 2 VALUES <LLD
.Bo04- 24e93 12,09r R4 ~ 93 SR 89 10 ~ 000 21 VALUES <LLD 17 VALUES <LLD 38 ANALYSIS .PERFORMED
-SR 90 Ro000 g,l.VALUES <LLD 17 VALUES <LLD 38 ANALYSls PERFORHEQ TRIT IUH 33Q ~ 000 460,e44( R/, 1R} TRM R85 ~ 2 489elR( 1/ 4) 599e32( 1/ 8) 20 4%le 76 489e12 489 e 1Rr 489 e 1R 599 '2r 599e32'-
- a. Nominal Lower Limit of Detection (LLD) as described in Table 3.
- b. Mean and range based upon detectable measurements only. Praction of detectable measurements of specified locations is indicated in parenthesis (P).
TABLE 21 RADIOACTIVITY IN WHITE CRAPPIE (FLESH)
PCI/G>> Oe037 BO/G (DRY WEIGHT)
NAHE OF FACILITY BROWSES LOCATION OF FACILITY LIHESIOHE EERRY DOCKET ALaaDdD = REPORTING NQ ~ 5OmRKRB26Qa296 PERIOD 12()Q TYPE AND LOWER LIMIT ALL CONTROL NUMBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCDIIQt) )(DU UIGUESI D((UUDL I)ED(( LOCATIONS NQNRQUTINE OF ANALYSIS DETECTIONa MEAN (F)b NAHE MEAN (F)b MEAN (F) b REPORTED REEEQB1)EQ LLLQ? BDNGE b QISIDHEE D((Q QIRECXIQ(( - ED((GEb BASGE b ((EASUBEBEBIS GROSS BETA 0.100 33 '9( 4/ 4) WHEELER RES 35e32( 2/ 2) 46 '9( 2/ 2)
GAMMA (GELI )
6 28e97 36e75 TRH 275"349 33 '9>> 36 '5 43 '8 48 '1 6
CS 137 0 F 020 0.10( 4/ WILSON RESERVOIR Oe 10( 2/ 2) Oe09( 2/ 2) 0 F 08>> 0 ~ 11 TRH R59"275 0 '9>> Oell Oe08 0 ~ 10 K>>40 NOT ESTAB 15ell(
13e40" 4/
16,84
- 4) WHEELER RES TRH 275-349 15e12(
13e40>>
2/
16,84
- 2) 17 '5(
16 ~ 80>>
2/ 2) 18 ~ 10 BI 214 0 '20 Oe05( 2/ 4) '6( 1/
'6 2)2) 1/
WHEELER RES PB 214 NOT ESTAB Oe05 0 F 08( 3/
0 '6 4)- TRH R75-349 0
Oe06>> 0 Oe06(
0 '6 Oe06 2)
WILSON RESERVOIR 0 F 08( 2/ 0 F 05( 1/ 2)
Oe06" 0 ll
~ TRH R59 275 0 '6>> 0 ~ 11 Oe05 Oe05 PB 212 NOT ESTAB Oe03( 1/ 4) WILSON RESERVOIR Oe03( 1/ 2) 2 VALUES <LLD 0 ~ 03- 0 F 03 TRH R59-275 0 F 03>> Oe03 a.
b.
Nominal Lover Limit of Detection Mean and range based upon
(~) as described in Table 3.
detectable measurements only. Fraction of detectable measurements of specified locations is indicated in parenthesis (F) ~
TABLE 22 RADIOACTIVITY IN SMALLHOUTH BU"FALO (FLESH)
PCI/G>> 0 ~ 037 BQ/G (ORY MEIGHT)
NAME OF FACILITY &BOWLS EERRY OOCKET NOe EQn25Ra26Oa399 LOCATION OF FACILITY LIHESIOBE- - --- - --OL48484 REPORTING PERIOD 1980 TYPE ANO TOTAL NUMBER LOWER LIHIT OF
.. ALL INDICATOR LOCATIONS LOCOIIOU MIIU UIGBESZ OUULJAL I)EOU CONTROL LOCATIONS NUMBER OF NONROUTINE OF ANALYSIS OETECTIONa HEAN (F)b NAHE HEAN (F) HEAN (F) REPORTEO REREORBEQ ILLQl ROUGE QISIOHCE OUQ QIRECEIO(( R4t(GEb RO((GE ()EOSURE((EBLIS GROSS BETA 0 100 26 ~ 30( 4/ 4) MHEELER RES 30e91( 2/ 2) 31 ~ 17( 2/ 2) '
20 ~ 48 31 ~ 03 TRM 275 349 30 ~ 78>> 31 ~ 03 29 ~ 83>> 32 ~ 52 GAHHA (GELI) 6.
CS 137 0 '20 0 '4( 3/ 4) MHEELER RES 0 ~ 05( 1/ 2) 0 '5( 2/ 2)
K>>40 NOT ESTAB Oe03 llF 6670( 0 F 05 4/ 4)
TRH 275 349 0 ~ 05>> 0i05 0 '4>> Oe05 12 ~ 82 ( 2/ 2) 2/ 2)
BI 214 0.020 F
Oe07(
13 '3 3/ 4)
WHEELER RES TRM 275>>349 12 ~ 41>> 13e23 15e39(
15 ~ 08>> 15 ~ 69 MILSON RESERVOIR Oe08( 2/ 2) 1/ 2l 0 '9 0 ~ 14(
PB 214 NOT ESTAB Oe04-0 ~ 07( 2/ 4)
TRH 259 275 WILSON RESERVOIR Oe07>>
0 F 08(
0 1/
'9 2) 0 ~ 14 0 ~ 14 0 'd 0 F 08 TRH 259 275 0 F 08>> 0 F 08 Oelo(
Oe 10>>
1/
Oe10 2)
PB 212 NOT ESTAB 0 F 01(
0 '1 1/
0.01
- 4) MILSON RESERVOIR TRH 259-275 Oe01(
0 F 01>>
1/
0 ~ 01
- 2) 0 '7(
Oe04>>
2/
Oe09-2)
- 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 parenthesis (F).
TABLE 23 RADIOACTIVITY IN SHALLHOUTH BUFFALO (WHOI,E)
NAHE OF FACILITY BRPWh(S LOCATION OF FAC IL ITY LIBESIOhlE EERRY DOCKET PCI/G>>
Oo037 BQ/G (DRY WEIGHT)
-'LABAh(4 'EPORTING NO, 5Oa252r2lhOrWS PERIOD 1QBQ TYPE AND LOWER LIHIT. ALL CONTROL NUHBER OF TOTAL NUHBER OF INDICATOR I.QCAT IONS LQCAZIQhl-WIZII UCGHESX 4((hlUAI IIEAhl LOCATIONS NONRQUT INE OF ANALYSIS DETECTION a HEAN (F)b NAHE MEAN (F)b MEAN (F)b REPORTED REREQRHEO CLLQl RANGEb QISEAh(CE-A((Q-OCREGIlQh( RA((GE b RA((GE b hIEASURE)IEI(ZS-GROSS BETA 0. 100 i5.ex( WHEELER RES 19oll( 2/ 2) 13 '5( 2/ 2)
GAHHA (GELI) 6 10o86 20 '2 TRH 275>>349 17 '0>> 20e92 ll ~ 11>> 15 ~ 99 6
CS-137 0 '20 0.03(
0 '2 3/
De03
- 4) WILSON RESERVOIR TRH 259<<275 0 '3(
Oe03>>
1/
Oe03
- 2) 0 '3(
0 F 03>>
1/
Oo03 2)
K>>40 NOT ESTAB 7o63( 4/ 4) WHEELER RES 8 ~ 81( 2/ 2) 8o38( 2/ 2)
Bl 214 Oo020 6 ~ 25-0 ~ 11(
9 3/
'7 4)
TRH 275-349 WHEELER RES 7e95 0~ lb( 1/
9eb7 2) 7 0
'5>>
'7( ,8 ~ Bl 1/ 2)
'7
~
0 ~ 08" De lb TRH 275 349 De16>> 0 ~ 16 0 F 07>> 0 PB 214 NOT ESTAB Oo ll ( 3/
'1 4)
'WHEELER RES TRH 275 349 0 '1(
0 ~ 21>>
1/ 2) 0 F 03(
0 F 03>>
1/ 2) 0 '3 0 F 05 0 De 21 212 NOT ESTAB VAI.UES <LLD 0 F 03( 1/ 2)
PB SR 89 0 '00 2 VALUES <LLD 0 '3>> 0 0 VALUES <LLD
'3 ANALYSIS PERFORHED SR 90 0 ~ 100, 0 '2(
0 ~ 1) 2/
0 ~ 13
- 2) WHEELER RES TRH 275 349 0 ~ 12(
0~ ll>> 2/
13 2)
De
- 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 parenthesis (F).
TABLE 24 RADIOACTIVITY IN SEDIHENT PC I/G 0 ~ 037 BQ/G (DRY HEIGHT)
HAHE OF FACILITY BRQMHS EERBC DOCKET NO ~ EQn25Ra26Qa~
LOCATION OF FAC IL ITY LI((ESIOHE AL484(}4REPORTINGPERIOD 1RBQ TYPE AND LONER LIHIT ALL CONTROL NUMBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LQCAZIOU }(lEU HlG'UESX 4((((UAL BE48 LOCATIONS NDNROUTINC OF ANALYSIS DETECTION a MEAN (F) b NAME MEAN (g)b MEAN (i:)b REPORTED REREORBED LLLQ1 RANGE. QSSE4(ICE 4((Q QIRECZIOU = R4UGE RA((GEb t(EASUREHE((IS GAHHA (GELI) 8 60 0 ~ 010 0 10( 5/ 6) TRH 293e7 0.10( R/ 2) 0.07( ,1/ 2)
CO Oe06-le3?t 0 ~ 14 6/
BFN DISCHARGE TRH ZTT ~ 98 Oe06~
2 '8(
0 '4 2/ 2) 0 F 07~
'5( 2/
0 F 07 CS-137 0 ~ 020 0 '4~ 2 '6 6)6) 2 '0i 0
0~
2)
'l RE 36 K~40 NOT ESTAB 15o79(
8 '0>>
6/
25 '1 6) TRH 288 78 20 '9(
14e46i 2/
25 2) 0,11'3e67(
10 ~ 63~ lbe71 99'/
2)
SI 214 0 '20 leS3(
'3 6/
2 '7 TRM 277 '8 le63(
le45~
2/ 2) 1e25( 2/ 2) 0 1 85 le 10 1 ~ 41 81 212 0 '00 lo05t Oe51 6/ 6) 1 ~ 60 TRH RSB ~ 78 le24 t Oe87%
2/
~
leb0
- 2) 0 '7(
0 F 84~
2/
le 10 2)
PS 214 NOT ESTAB 1.58( 6/ 6) TRH 288 78 le91 t 2/ 2) 1e32( 2/ 2) 0 '982( 2e53 6/ R88.78 le 28~ 2o5S 2/ 2) 1 ~ 18~
le46t 2/
le47 PS RA 212 2Z6 NOT ESTAB NOT ESTAB 0 '9 1
'0( 2 6/
'9 6}6) TRH TRH 288 '8 2 ~ R4(
1~ 89~
1e80(
2e59 2/ 2) le29 le 25( 2/
leb3 2) 2)
1
'ebb
'3( . ROAST 3/ 6) 288 '8 le23~
Oe65t 2 '7 2/ 2) 1 o 0.56(
10~
1/
le41 RA 223 NOT ESTAB 0 TRH 2)
Oej0~ 0 F 80 Oe50r 0 F 80 De56, De56 SE 7 Oe22(. 1/ 6) TRH 293o7 Oe2Rt 1/ 2)
TL 208 NOT ESTAB 0 '20 0 '2 0.58t 0
6/
'2 6} BFN TRH 0 ISCHARGE 288 '8 OeRRi OeTlt OeRR 2/ 2) 2 VALUES <LLD De50( 2/ 2)
AC-Zas 0.060 0 '7 F 77(
0 6/
'0 6) TRH 288o78 0 '2>>
2 ~ 21(
0 R/
'0 2) 0 1~
'456( 2/
De56 2)
OeBZ Ze78 ]eb4e F 78 1 ~ 28 1~ 84 SR 89 lo500 6 VALUES <LLD 2 VALUES <LLD ANACYSIS PERFORMED 2/ 6) 1/
SR 90 0%300 Oe32(
0 '2 Oe32 TRH R93e7 BFN DISCHARGE Oe32(
0 F 32~ 0 '2 2) 2 VALUES <LLD
- a. Nominal Lover Limit of Detection (LLD) as described in Table 3.
- b. Mean and range based upon parenthesis (P).
detectable measurements only. Fraction of detectable measurements of specified loca tions is indicate d in
TABLE RADIOACTIVITY IN CLAM FLESH PC I/G 0 ~ 037 80/G (DRY 'HE IGHT)
NAME OF FACILITY,BRO)(US EERRY DOCKET NO ~ SQn259a26Qa&N LOCATION OF FACILITY L18ESZOUE ALABA(IA '
REPORTING PERIOD 1RBQ TYPE AND LOMER LIMIT ALL CONTROL NUMBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCAXIOU )(XIV ULGUESI auUUAL IIEJLII LOCATIONS NONROUT INE OF ANALYSIS DET(FACT ION a MEAN (F)b NAME MEAN tF) > MEAN I[) b REPORTED REREORMEO GAMMA (GEL?)
CLLQl b RAUGE---- OLSIAUCE AUO QlRECIIOhl-----RkhlGEb- - RA 1(GE IIEASUREIIEBIS 7
K~40 '$ 3/ '8 '6t '0(
'6 5)5)
NOT ESTAB 18 TRM 288 32 1/ 2) 10 '3 (
32 32 '6m 32 '6 21 2le40 1/
2le40 2) 8 I>>214 NOT ESTAB 2e26( 4/
'4 5) TRM 293 ' 2e39( 2/ 2) 'e5lt 2/ 2) le24- 3 BFN DISCHARGE ] 24i 3 '4 34>> 3eb7 PB-214 NDT ESTAB 3e41(
le54 3/
4 '3 TRM 288 '8 ~
4 '3(
4e93~
1/
4 '3 2) 1 ~
2 '3( 2/ 2) 30~.
277 '8 1~ 3e 37 PS~212 NOT ESTAB 52( 5/ 5) le 1/ 2/ 2) 2 '8 1 ~ TRM 75 ( 1) 2e64(
Oe47 75~ e75 le07 4e22 0 '8t 1 ~ 1 TL 208 NOT ESTAB 0 '8 1/
0 '8
Oe58~-
l/Oe58 2) 1 ~ 16(
lb+
1/ 2) 1 ~ 1 ~ 16
- a. Nominal Lower Limit of Detection (LLD) as described in Table 3.
- b. Mean and ranpe based upon detectable measurements only. Fraction of detectable measurements of specified locations is indi'cated in parenthesis (F).
TABLE 26 RAOlQACTIVITY IN CLAH SHELL PCI/G 0 ~ 037 BQ/0 (ORY )(EIGHT)
NAME OF FACILITY BBQ)t(IS EEBBY--
LOCATION DP FACILITY iXBESIQIIE
-- ---'AL454)I4 OQCKET NQ. St)iamaaZbaa224 REPORTI NG PERIOD:1M()
TYPE AND LDMER LIHIT ALL CONTROl. NUHBER OF TOTAL NUHBER OF INDICATOR LOCATIONS LQCAIIQ(t )(IIU BIGUESI AHW4L lt(48 LOCATIONS NONRQUT INE OF ANALYSIS DETECTION a HCAN (F)b NAME MEAN (P)b HEAN (F) b REPORTED REBEQBHEQ CLL()l: aAttGE OISIAUCE 4((Q QIBECIIQU B4QGE)t BA((GE )(EASUBE)(EHIS GAHHA (GELI) 8 CS-137 0.020 Oe04( 2/ 6) TRH R93e7 Oe05t 1/ 0 '3( 1/ 2)
K>>40 NQT.-ESTAB 0 '278( 0 6/
'5 6)
BFN DISCHARGE TRH 277 '8 Oe05>>
3 '9(
Oe05 2/ 2) 0 '3>>
~ 08(
0 F 03 2/ 2)
,0 '3 I, ~ 1 6 ~ 96 0,43>> be96 le 05>> lel2 81 214 0.050 0'e39( bt 6) TRH 277 '8 0 F 48( R/ 2) 0 F 44( 2/ 2) 0 ~ 18 0 79 0 ~ 18>> Oe79 0 '7>> 0 ~ Sl 81 212 0.100 0 ~ 28( 2/
~
- 6) TRH 293 ' Oe31( 1/ 2) 0 '5t 1/ 2)
PB 214 0.050 0 '5 Oe39(
0 '1 6/ 6)
BFN TRH 0ISCHARGE 277 '8 Oe 31>>
Oe51(
Oe31 2/ 2) 0 F 45>>
0 F 43(
0 ~ 45 2/ 2)
P8>>212 NOT ESTAB Oe14>>
OeR9(
0 F 88 6/ 6) TRH 293 '
0 ~ 14>>
Oe44(
0 F 88 2/ R)
Oe 3b.>>
0,36t 0
2I
'9 R) 0 ~ 11 0 ~ 47 BFN OISCHARGE Oe40>> Oe47 0 '6>> 0 '5 0.050 0'.39( 6/ 6) 277e98 Oe48( 2/ Oe44( 2/ 2)
RA>>226 TL 208 0 '20 0.18-0 ~ 10(
0,79 4/ 6)
TRH TRH 293 '
Oe18>>
F 14(
0 2/
'9 R)2) 0 '7>>
OelRt 0 '1 2/ 2) 0 F 05 0 ~ lS BFN OISCHARGE 0 ~ 13>> 0 ~ 15 0 '7>> Oe17 AC 2RB 0 '60 Oe46( 3/ 6) TRH 293 ' Oe53( 2/ 2) 0 '9( 2/ 2)
SR 89 5 F 000 0 '2 .
6,VALUES <LLO Oe58 8FN OISCHARGE 0 F 48>> Oe58 OeRB>>
2 VALUES <LLO Oe50 ANAiYSIS PERFORHEO 1.000 6/ 6) '8 '0( 2) 4 ~ 35( 2/
SR 90 3 ~ 11(
F 97 4e08 TRH 288 3 3 'l>> R/
F 08 3 '4>>- 4 '5 2)
- 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 parenthesis (P).
A quality control program has been established with the Alabama Department of Public Health Environmental Health Administration Laboratory and tPe 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 Anal sis Data measured at the control'stations for each medium were aver-aged for each sampling period. In order to describe the distribution 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 bjsis for comparing control and indicator data. If the indicator data fall w'ithin 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 pl'ant.
Conclusions A vast ma)ority of the indicator station data was 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.
Increased levels of radioactivity"were observed in milk, rain-water,air particulates, heavy particle fallout, vegetation, and in atmos-pheric radioiodine in October, November, and December following the atmo-spheric nuclear weapons testing conducted by the Republic of China in mid-October. This increase was seen in control stations as well as indicator stations, and was widely reported in the eastern portion of the United Stateh.
Levels; of I in milk as, high as 1.2 pCi/1 were observed. The primary radioi'sotopes identified in the'atmospheric media were 5Zr, 214Bi Nb, I,
" and 103Ru.
46 Dose estimates were'ade from concentrations of radioactivity found in samples of environmental media. Media sampled include, but, are not limited to, air, milk, meat, vegetation, drinking water, and fish.
Doses estimated for persons at the indicator locations were essentially identical to those determined for persons at control locations. Greater than 99 percent of those doses were contributed by the naturally 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 significant increases in environmental radioactivity attributable to the operation of Browns Ferry Nuclear Plant.