ML18032A686
| ML18032A686 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 12/31/1985 |
| From: | Gridley R TENNESSEE VALLEY AUTHORITY |
| To: | Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| NUDOCS 8712310150 | |
| Download: ML18032A686 (66) | |
Text
s REGULA.
Y INFORMATION DISTRIBUTI SYSTEM (RIDS)
ACCESSION NBR:8712310150 DOC. DATE: 85/12/31 NOTARIZED:
NO FACIL: 50-259 Browns Ferry Nuclear Power Station>
Unit 1>
Tennessee 50-260 Browns Ferry Nuclear Power Station>
Unit 2.
Tennessee 50-296 Browns Ferrg Nuclear Power Station>
Unit 3>
Tennessee AUTH. NAME AUTHOR AFFILIATION GRIDLEY> R. L.
Tennessee Valley Authority REClP. NAME RECIPIENT AFFILIATION GRACE> J. N.
Region 2>
Ofc oF the Director
SUBJECT:
"Environ Radioactivitg Levels> Annual Rept for 1985. "
IrJ/860422 1 tr.
DISTRIBUTION CODE:
IE48D COPIES RECEIVED: LTR + ENCL Q SIZE:
TITLE: 50. 36a(a) (2) Semiannua'1 Effluent Release Reports NOTES: Q. Zech 3 cg.
1 cg.
ea to:
Ebneter> Axelrad> S. Richardson B. D. Liaw> K. Barr> Donohew> OI.
Q. Zech 3 cg.
1 cg.
ea to:
Ebneter> Axelrad> S. Richardson>
B. D. Liaw> K. Barr> Donohew> OI.
Q. Zech 3 cg.
1 cg.
ea to:
Ebneter> Axelrad> S. Richardson>
B. D. Liaw> K. Barr> Donohew> OI.
DOCKET 05000259 05000260 05000296 05000259 05000260 05000296 RECIPIENT ID CODE/NAME JAMERSON. C GEARS> Q lNTERN*L: ACRS AEOD/DSP/TPAB NRR/DEST/PSB NRR/PMAS/ lLRB RGN2 FILE 02 EXTERNAL:
BNL TICHLER> J03 NRC PDR NOTES:
COPIES LTTR ENCL 0
1 10 10 REC IP IENT ID CODE/NAME PD STANG> J AEOD/DOA ARM TECH ADV P/RPB REG F LE 01 RGN2/DRSS/EPRPB LPDR COP IES LTTR ENCL 5
5 1
1 1
1 4
1 1
1 1
1 TOTAL NUMBER OF COPIES REQUIRED:
LTTR 34 ENCL 33
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,i
TENNESSEE VALLEY AUTHORITY 5N 157B Lookout Place April 22, 1986 U.S. Nuclear Regulatory Commission Region II ATTN:
Dr. J.
Nelson Grace, Regional Administrator 101 Mariet ta Street, NW, Suite 2900 Atlanta, Georgia 30323
Dear Dr. Grace:
BROWNS FERRY NUCLEAR PLANT UNITS 1, 2, AND 3 ENVIRONMENTAL RADIOACTIVITY LEVELS ANNUAL REPORT 1985 Enclosed is a copy of the subject report prepared by the Tennessee Valley Authority pertaining to environmental monitoring at the Browns Ferry Nuclear Plant.
This monitoring program is specifically responsive to the recommendations and requests of the U.S. Fish and Wildlife Service.
We understand that NRC-NRR will transmit five copies of the report to the Secretary of the Interior.
Very truly yours, TENNESSEE V
LE A
HORITY R. L. Gridley, Director Nuclear Safety and Licensing Enclosure cc:
Director of Nuclear Reactor Regulation
(
Enclosure:
20)
Attn:
Mr. R.
M. Bernero, Director Division of BWR Licensing U.S. Nuclear Regulatory Commission Washington, D.C.
20555 An Equal Oppartunity Employer
I
ENVIRONMENTAL RADIOACTIVITYLEVELS BROWNS FERRY NUCLEAR PLANT ANNUAL REPORT " 1985 TVA/NUC SVS/RH 8712310150 851231 PDR ADQCK 05000259' PDR April 1986
-t
'k
CONTENTS List of Tables i11 List of.Figures.
Introduction iv Atmospheric Monitoring Terrestrial Monitoring
~
~
~
~
ll 23 Reservoir Monitoring 43 equality Control.
Data Analysis.
Conclusions.
57 57 58
LIST OF TABLES Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table Table 1
2 3
4 5
6 7
8 9
10ll 12 13 14 15 16 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 Environmental Radioactivity Sampling Schedule Atmospheric and Terrestrial Monitoring Station I,ocations - Browns Ferry Nuclear Plant Detection Capabilities for Environmental Sample Analysis Results Obtained in Interlaboratory Comparison Program Maximum Permissible Concentrations for Nonoccupational Exposure Radioactivity in Air Filter Radioactivity in Rainwater Radioactivity in Heavy Particle Fallout Radioactivity in Charcoal Filters Radioactivity in Milk.
Radioactivity in Vegetation Radioactivity in Soil Radioactivity in Well Water Radioactivity in Public Water Supply Environmental Gamma Radiation Levels Radioactivity in Cabbage Radioactivity in Corn Radioactivity in Green Beans Radioactivity in Apples Radioactivity in Potatoes Radioactivity in Beef Radioactivity in Tomatoes Sampling Schedule - Reservoir Monitoring Radioactivity in Surface Water Radioactivity in White Crappie (Flesh)
Radioactivity in Smallmouth Buffalo (Flesh)
Radioactivity in Smallmouth Buffalo (Whole)
Radioactivity in Sediment Radioactivity in Plankton Radioactivity in Clam Flesh Radioactivity in Clam Shell
~
~
~
13 14 15 16 17 26 27 28 29 30 31 32 33 34 35.
36 37 38 45 46 47 48 49 50 51 52 53 111
LIST OF FIGURES Figure l
- Tennessee Valley Region 9
Figure 2
- Atmospheric and Terrestrial Monitoring Network 18 Figure 3
Figure 4
Figure 5
- Local Monitoring Stations
- Annual Average Gross Beta Activity in Air Filters, Browns Ferry Nuclear Plant 19 20 21 Figure 6
- Annual Average Gross Beta Activity in Drinking Water, Browns Ferry Nuclear Plant Figure 7
- Direct Radiation Levels, BFN Figure 8
- Direct Radiation Ievels, BFN (4-Quarter Moving Average) 39 40 40 Figure 9
- Direct Radiation Levels, WBN Figure 10 - Direct Radiation Levels, WBN (4-Quarter Moving Average)
Figure ll - Reservoir Monitoring Network Figure 12 - Annual Average Gross Beta Activity in Surface Water 41 41 54 55
ENVIRONMENTAL RADIOACTIVITYLEVELS BROWNS FERRY NUCLEAR PLANT ANNUAL REPORT 1985 Introduction The Browns Ferry Nuclear Plant (BFN), operated by the Tennessee Valley Authority, is located on a site owned by TVA containing 840 acres of land in Limestone County,
- Alabama, bounded on the west and south by Wheeler Reservoir (see figure 1).
The site is 10 miles southwest of Athens,
The plant consists of three boiling water reactors; each unit is rated at 3,293 MWt and 1,098 MWe.
Unit 1 achieved criticality on August 17,
- 1973, and began commercial operation on August 1, 1974.
Unit 2 began commercial operation on March 1, 1975.
- However, a fire in the cable trays on March 22, 1975, forced the shutdown of both reactors.
Units 1 and 2 resumed operation and Unit 3 began testing in August 1976.
Unit 3 began commercial operation in January 1977.
The plant has been shutdown since March 1985.
The preoperational environmental radiological monitoring program established a baseline of data on the distribution of natural and manmade radioactivity in the environment near the plant site.
However, seasonal,
- yearly, and random variations in the data were observed.
In order to determine the potential increases in environmental radioactivity levels caused by the plant, comparisons were made between data for indicator stations (those near the plant) and control stations (those remote from the plant) in conjunction with comparisons with preoperational data.
Radiological Health (Office of Nuclear Power) and the Office of Natural Resources and Economic Development carried out the sampling program outlined in tables 1 and 23.
Sampling locations are shown in figures 2, 3, 4, and ll, and table 2 describes the locations of the atmospheric and terrestrial monitoring stations.
All the radiochemical and instrumental analyses were conducted in TVA's Western Area Radiological Laboratory (WARL) located in Muscle Shoals, Alabama.
Alpha and beta analyses were performed on Beckman Low Beta II, low background proportional counter or a Tennelec LB-5100.
Nuclear Data (ND) Model 6700 system, in conjunction with germanium detection
- systems, were used to analyze the samples for specific gamma-emitting radionuclides.
Specific analysis for iodine-131 in charcoal filters was performed using NaI(Tl) well detector systems attached to single channel analyzers.
A TVA fabricated beta-gamma coincidence counting system was utilized for the determination of iodine-131 concentrations in milk.
Analysis for low-energy beta emitters such as tritium was performed using Packard Tri-Carb Model 3255 and 4000 series liquid scintillation systems.
Data were entered in computer storage for processing specific to the analysis conducted.
The 'data obtained by germanium detectors were resolved by the appropriate analyzer softwar'e and the software program routine HYPERMET.
The detection capabilities for environmental sample analyses given as the nominal lower limits of detection (LLD) are listed in table 3.
All photopeaks fo'und in germanium spectra were identified and quantified.
Many of the isotopes identified by germanium spectral analysis are naturally occurring or naturally yroduced radioisotopes, such as Be, K, 212Bi 214Bi
- 212Pb, Pb
'226Ra etc.
LLDs for radionuclides identified by Ge(Li) an'alysis were calculated for each analysis and'nominal values are listed in table 3B.
In the instance
'where an LLD h'as not 'been est'ablished',
an LLD value of zero was assumed.
A notation in a t'able of "
"values
<LLD" for an 'isotope with no established XLD does not imply 'a value less than 0; rather it indicates that "th'e isotope was 'not identified in that spec'itic
'group o'f samples.
For each sample type, 'o'nly the radionuclides 'for which values greater
'than 'the LLD we'e reported are li'sted in the data, tables.
TVA's WARL participates in the Environmental Radioactivity Laboratory Inte;comparison Studies 'Prog'ram 'c'onducted by 'EPA-Las Vegas.
This program 'provides per'iodic cr'oss-checks on samples of the type and
'radionuclide composi'tion normally analyzed in an 'environmental radio-logical monitoring p'rogram; Route'ne sample handling and analysis p"
cedures were employed in the 'eval'ua'tion o'f 'the's'e 'sa'mples.
The results received during calendar year 1985 are shown 'in table 4.
The
+3o'imits based on one 'measurement, were d'i'vided 'by the 'square roo't of 3 to correct for 'triplicate determinati'o'ns.
Station Location Table 1
EWIRONMENTAL RADIOACTIVITYSA!IPLIVC SCHEDLLE Air Charcoal Rain-Heavy P~rticle River Mell Public Aquatic Life pygmy rilt e
ill c
s il~VDci Milk I:c l4a 4
asdi I
1 di Huscle Shoals Lavrenceburg Rogersville Athens Decatur Courtland Site 1 (H)
Site 2 (NNE)
Site 3 (ENE)
Site 4'NNV)
Site 5
('WSM)
Farm B
Farm Bn+
Farm Poo Farm L Farm E Farm V Control Farms Onsite Mell Wheeler Dam Elk River Tennessee River Champion Paper Co.
Various Local Farms M
~
M II A
M M
M M
M
'V M
M V
M - Veekly H - Monthly (every 4 veeks)
Q - Quarterly
- Sampling commenced November 1985
<<eDiscontinued operation October 1985 S - Semiannually A - Annually
Table 2
Atmospheric and Terrestrial Monitoring Station Locations Browns Ferry Nuclear Plant
)
0 Sam le Station Approximate Distance and Direction from Plant LM-1 BF, North LM-2 BF., North-Northeast LM-3 BF, East-Northeast LM-4 BF, North-Northwest LM-5 BF, West-Southwest PM-1 BF, Rogersville, AL PM-2 BF, Athens, AL PM-3 BF, Decatur (Trinity),
1.0 Mile 0.9 Mile 1.0 Mile 1.7 Miles 2.5 Miles 13.8 Miles 10.9 Miles AL 8 '
Miles (1.6 kilometers)
N (1.4 kilometers)
NNE (1.4 kilometers)
ENE (2.7 kilometers)
NNW (4.0 kilometers)
WkW (22,2 kilometers)
NW (17.5 kilometers)
NE (13.2 kilometers)
SSE RM-1 BF, RM-2 BF, Muscle Shoals, AL (Control)
'awrenceburg, TN (Control)
PM-4 BF, Couri.land, AL 10.5 Miles 32.0 Miles (16.9 kilometers)
WSW (51.5 kilometers)
W 40.5 Miles (65.2 kilometers)
NNW Farm Bn>
Farm B
Farm L Farm P-'~
Farm E Farm W
Farm N (Control)
Farm J (Control)
Farm C (Control)
Farm Ca (Control)
Farm Cb (Control)
Farm M (Control) 4.g5 Miles 7.0 Miles 5.0 Miles 8.8 Miles 6.1 Miles 6.9 Miles 27.0 Miles 40.0 Miles 32.0 Miles 32 '
Miles 22,5 Miles 22.5 Miles (7.6 kilometers)
N (11.3 kilometers)
NW (7.0 kilometers)
NE (14.1 kilometers)
E
( 9.8 kilometers)
NE (11.0 kilometers)
NE (43.4 kilometers)
NW (64.4 kilometers)
NNW (51.5 kilometers)
N (51.5 kilometers)
W (36.2 kilometers)
E (36,2 kilometers)
ENE
>> Sampling commenced November 1985
>+"Discontinued operations October 1985
Table 3
DETECTION CAPABILITIES FOR ENVIRONHENTAL SAHPLE ANALVSIS A.
S ecific Anal ses NOMINAL LOWER LIHIT OF DETECTION (LLD)*
Air Particulates pCi/m Charcoal Fal lout Water
~Ci/n mCi/K pCI/i Vegetation and Grain pCi/<i, Dry Soil and Sediment
~CI/ ~Dr
- Fish, Clam Flesh,
- Plankton,
~C'/
De
- Foods, Heat, Clam Shells
- Poultry, Hilk
~Ci/
De
~Ci/K m Wee KClll Gross a Gross B
H-3 1-131 Sr-89 Sr-90 0.005 0.01 0.005 0.001 0.01 2
0.05 2
330 10 2
0.05 0.20 0.25 0.05 0'5 0.70 1.5
- 0. 15 0.1 0.1 0.5 0.1 0.7 0.7 5.0 1.0 25 40 8
0.5 10 2
- All LLD values for isotopic separations are calculated by the method developed by Pasternack and Harley as described in NASL-300.
~ factors such as sample size, decay time, chemical yield, and counting efficiency may vary for a given sample; these variations may change the LLD value for the given sample.
The assumption Is made that all samples are analyzed within one week of the collection date.
Conversion factors:
I pCi mm 3.7 x 10 z Bq; 1 mCi mm 3.7 x 10 Bq.
Table 3
DETECTION CAPABILITIES FOR ENVIRONHENTAL SAHPLE ANALYSIS B.
Gamma Anal ses NOHINAL LOWER LIHIT OF DETECTION (LLDl Ce-144 Cr-51 I-131 Ru-106 Cs-134 Cs-137 Zr-95 Nb-95 Co-58 Hn-54 Zn-65 Co-60 Fe-59 Ba-140 La-14O Air particujates Ge LI
- 0.02 0.03 0.01 0.03 0.01 0.01 O.OI 0.01 0.01 0.01 0.01 0.01 0.02 0.01 Water and milk
~CI/
I Ge Li 33 44 8
30 5
5 10 5
5 5
9 5
5 25 7
Vegetation and grain
~pCI/
dr Ge Li 0.22 o.47 0.09 0.5I 0.33 o.o6 0.11 0.05 0.05 0.05 0.11 o.o6 o.34 0.08 Soll and sediment pCi/c dr GeYL~I o.o6 0.10 0.02 0.11 o.o8 0.02 0.03 0.01 0.01 0.01 0.02 0.01 0.07 0.02.
Fish pCi/<
dry
~Ge L~I o.o6
- 0. 10 0.02 0.11 0.07 0.02 0.03 0.01 0.01 0.01 0.02 0.01
- 0. 10 0.07 0.02 Clam flesh and plankton g>C I / i dr)/
~Ge L~i 0 ~ 35 o.56 0.07 0.74 o.48 o.o8 0.15 0.07 0.07 o.o8 0.17 o.o8 0.30 0.10 Clam shells pCi/<
dr~
Ge I~LI 0.06 0.10 0.02
- 0. 11 o:o8 0.02 0.03 0.01 0.01 0.01 0.02 0.01 0.07 0.02
- Foods, (tomatoes
- potatoes, etc.)
Cl/K, wet Ge Li 33 44 8
4o 26 5
10 5
5 5
9 5
25 7
Heat and poultry Ci/K wet Ge Li 40 90 20 90 40 15 20 15 15 15 20 I5 50 15
< The Ge(Li)
LLD values are calculated by the method developed by Pasternack and Harley as described in-HASL-300.
These LLO values are expected to vary depending on the activities of the components in the samples.
These figures do not represent the LLD values achievable on given samples.
Water is counted in either a 0.5-L or 3.5-L Harinelli beaker.
Solid samples, such as soil, sediment, and clam shells, are counted in a 0.5-L Harinelli beaker as dry weight.
The average dry weight is 400-500 grams.
Air filters and very small volume samples are counted in petri dishes centered on the detector endcap.
The counting system consists of a ND-6700 multichannel analyzer and germanium detector having an efficiency of 20 percent.
The counting time is normally 4-15 hours.
All spectral analyses are performed using the software program HYPERHET. 2The assumption is made that all samples are analyzed within one week of the collection date.
Conversion factor:
I pCI ~ 3.7 x 10 Bq.
Table 4
RESL'LTS OBTAINED IN INTERLABCFA.OPY COMPARISON PROGRAM A.
Air Filter (pCi/Filter)
Date
(+3c)
Avg.
(+3(r)
Avg.
Strontium-90 EPA value TVA
(+3a)
Avcv.
Cesium-137 EPA value TVA
~(t e)
Avc).
11/84 3/85 8/85 15+9 10+9 13+9 15
]1 12 52+9 61 36+9 40 44+9 45 21+3 21 15+3 16 18+3 16 10+9 6+9 8+3 10 6
9 Date 4/85 7/85 B.
Tritium in Urine (pCI/R)
EPA value
(+3a) 3056+622 2444+610 TVA AvcV.
2687 2280 C.
Radiochemical Analysis of Water (pCi/R) 12 Gross Alpha EPA value TVA 4/84 1/85 5+9 2/85 3/85 6+9 6
4/85 4/85'/85 12+9 9
6/85 7/85 11+9 8/85 9/85 8+9 8
10/85 15+9 15+9 72+9 11+9 8+9 8+9 19 17 69 14 12 Gross Beta EPA value TVA
(+3a)
~Av 10+9 39+9 9d 49 20+9 26 Strontium-89 EPA value TVA
(+3a)
Av(V.
23+9 22b 3+9 Stronium-90 EPA value TVA
(+3a)
~Av 26+3 26 30+3 29 Tritium EPA value TVA
(+3a)
AvcV ~
Iodine-131 EPA value TVA (t3e)
~Av 15+3 15+3 7+3 1974+598 1880 3796+634 3817 355"+630 3347 7.5+1.4 7.3 16 13 2416+608 2257 4480+776 4127 33.
+10 29
Table 4 (Continued)
RESULTS OBTAINED IN INTERLABORATORY COMPARISON PROGRAM (Continued)
D; Gamma-Spectral Analysis of Water (pCI/!I).
Date 4/84 2/85 4/85 6/Sc 10/85 48a9 4ir+9 21+9 45 IIOb 40 Chromium-51 EPA value TVA
(+3a)
~Av
~
3%9 2%9 15+9 14-9 2%9 30 20 16 14 21 Cobalt-60 EPA value TVA
(+3a)
~Av
~
5R5 53 47 9 19+9 48 20 Zinc-65 EPA value TVA
(+3a)
Av(V a Ruthenium-106 2%9 40b 62='9 20 9 53 25 EPA value TVA
(-3a)
AvcV Cesium=l 4
3%9 2/
35+9 32 15 9
15 35+-9 34 20+9 18 Ep!'alue TVA
(+3a)
~Av.
Cesium-13>
(+3a)
Ave ~
26+9 27 25+9 25 12+9 13 20+9 19 20+9 20 E.
Food (pC i/Kg; Wot We r ght)
Date 1/85 7/85 Strontium-89 EPA value TVA
(+3a}
~Av.
34+9 37 34 Strontium-90
(+ 3a)
Avg.
26+3 37 f 26+3 34 Iodine-131 EPA value
(+3 )
TVA AvcV a 35+10 33 35+10 36 Cesium-137 EPA value TVA
(+3a)
Ava.
29+9 28 29+9 31 Potassium-40
~ta
~Av 1382+208 1270 1514+132 1567 F.
Mi 1 k (pC I/vE!
Date 3/85 6/85 11+9 13 Strontium-89 tW
~
~
(+3a)
AvcV Strontium-90 EPA value TVA
(+3a)
AvcVe 11+3 11 EPA value
(+3a) 9+1
~ 6 11+10 TVA Avg.
llh 11 Iodine-131 11+9 12 Cesium-137 EPA value TVA
(+-3a)
I'vg.
(+-3a)
~Av.
1525+132 1680 t
a
~ Laboratory perfcrmance evaluation study.
Results received from EPA ir April '1985.
b.
Below LLD~
- c. Labortory performance evaluation study.
d.
The analysis was reviewed.
Cause for high results could not be identified.
e.
Values reported as mg K/kgb
- f. Possible error due to nonhomogeneity of sample.
EPA used dog food ccntaining bone
!real in the preparation of the food cross-check.
- g. Values reported as mg K/II Results were investigated'o source of error, was determined..
i'Igh bias on result due to broader ing of the peak used for identifying K-40.
The low abundance and low court'.-!"tt eff1ciency for the 1460 Kev line inflated th<< small. positive bias'aused by temperature-variations.
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Atmos heric Monitorin The atmospheric monitoring network is divided into three groups.
Four local air monitors are located on or adjacent to the plant site in the general areas of greatest wind frequency.
One additional station is located at the point of maximum predicted off-site concentration of radionuclides based on preoperational meteorological data (see figures 3 and 4).
Four perimeter air monitors are located in communities out to about 13 miles from the plant, and two remote air monitors are located at distances out to 45 miles.
These monitoring stations are shown in figure 2.
The remote monitors are used as control or baseline stations.
At each local monitor, air is continuously pulled through a Hollingsworth and Voss LB5211 glass fiber particulate filter at a flow rate of about 3 fthm/min.
At perimeter and remote monitors the system has been modified so that air is continuously pulled through a 1-7/8 diameter glass fiber particulate filter at a flow rate of about 2 fts/min.
In series with, but downstream of, the particulate filter is a charcoal filter used to collect iodine.
Each monitor has a collection tray and storage container to obtain rainwater on a continuous basis and a
horizontal platform that is covered with gummed acetate to catch and hold heavy particle fallout.
Thermoluminescent dosimeters are used to record gamma radiation levels at each remote and perimeter station.
T Each of the local air'onitors is fitted with a GM tube that continuously scans the particulate filter, The disintegration rate of the atmospheric radioactivity is continuously recorded at each station and radiotelemetered into the plant.
Air Filters Air filters are collected weekly and analyzed for gross beta activity.
Adequate time is allowed for decay of radon daughters between collection and analysis of samples.
This time is typically three days.
The samples are composited monthly for analysis of specific gamma-emitting radionuclides and quarterly for Sr and Sr analysis.
The results are combined for each station to obtain an annual average.
These data are presented in table 6.
During this reporting period, two samples were not obtained because of equipment malfunction, two samples were damaged beyond use, one sample was destroyed during
- analysis, and one sample was lost during sample change.
The annual averages of the gross beta activity in the air particulate filters at the indicator stations (local and perimeter monitors) and at the control stations (remote monitors) for the years 1968-1985 are presented in figure 5.
Increased levels due to fallout from atmospheric nuclear weapons testing are evident, especially in
- 1969, 1970,
- 1971, 1977,
- 1978, and 1981.
These patterns are consistent with data from monitoring programs conducted by TVA at nonoperating nuclear power plant construction sites.
Table 5 presents the maximum permissible concentrations (MPC) specified in 10 CFR 20 for nonoccupa-tional exposure.
12 Rainwater Rainwater is collected monthly and a 3.5-liter sample analyzed for specific gamma-emitting radioisotopes and tritium.
The results are shown in table 7.
During this reporting period, four samples were hot available due to insufficient rainfall and three samples were not'.
collected due to human error.
Fallout The gummed acetate that is used to collect heavy particle fallout is changed monthly.
The samples are ashed and counted for gross beta activity.
The results are given in table 8.
Charcoal Filters Charcoal filters are collected and analyzed for radioiodine, The filter is counted in a single channel analyzer system.
The results are shown in table 9.
During this reporting period, five samples were not taken because of equipment malfunction or filter damage and one sample was destroyed during analysis.
13 Table 5
tMXIMUM PERMISS IBLE CONCENTRATIONS FOR NONOCCUPATIONAL EXPOSURE Alpha Nonvolatile beta Tritium 1 37Cs 10 3 ~ 106Ru 144(
"Zr-"Nb Ba-La 131I 6SZ 4Mn 6 OCo "Sr 90Sr 51(.r "4C "Co In Water
~Ci/1*
30 3,000 3,000,000 20,000 10,000 10,000 60,000 20,000 300 100-,000 100,000 30,000 3,000 300 2,000,000 9,000 90,000 In Air
~Ci/m'*
100 200,000 500 200 200 1,000 1,000
. 100 2,000 1,000 300 300 30 80,000 400 2,000
- 1 pCi ~ 3.7 x 10 Bq.
NAME OF FACILITY989955 EEBBI LOCATION DF. FACILITY LIUESIQUE TABLE 6 RADIOACTIVITY IH AIR FILTER PCI/H(3)'
0 ~ 037 BQ/H(3)
DOCKET NO 59=222/2(IQc2.R REPORTI
~ IG PERIOD TYPE AHD
'OTAL NUMBER
)F AHAlYSIS PERFORMED
'GSS ALPHA 52
!OSS SETA 566 1HHA (GELI) 145 LOsIER LIMIT OF DETECTIOH (LLD)
XEE UQIE 1 5.00E-03 1.0GE-02 ALL INDICATOR LOCATIONS MEAH (F)
RANGE EE gQIE 1 '4E-GZ(
44 9/ 46Z).
OOE 02 4 33E 02 OECATURr AL 8 ~ 2 MILES SSE 2 ~ 13E-02 (
50/
52) 1.18E 5.o9E-02 L996IIQB III'IQUESI 65596l.
5E65 NAME MEAN (F)
DISTAHCE ANO DIRECTION RANGE BEE DQXE 2
CONTROL LOCATIONS McAN (F)
RANGE Kfi hQIE 2
6.73E-03(
1/
52) 6i?3E 5.738-03 2i09E"02( 103/
1~~~)
1 '0E 3 64E-02 NUMBER OF NONROUTINE REPORTED MEASUREMEHTS
'"40 sI-214 sI-212
>8-214
)8-21 2,
)E-7 rl-208 XC-228 89 R 90 NOT ESTAB 2.00E-02 HOT ESTAB'.GGE-GZ HOT EST'AS SPODE-02 NOT CSTAB rIOT-ESTAB 5.00E-03 44 1 ~ DOE-03 44 1 ~ 51c-02(
43/ 117) 4 'Gc 3 '3E-OZ 2.428-02(
2/ 117) 2 '6E-02. -
2 '8E-02 1+4?E-OZ(
1/ 117) 1 '?E 1 47E-02 2 72E-02(
2/ 1'17) 2+36E-OZ - 3.08E-OZ 3'6E-04(
19/ 117) 1.00E 1eOOE-03 8 '9E-02.(
94/ 117) 5 '0E 02 1 '5E 01 1 ~ SGE-04(
5/ 117) 1 '0c 2 'OE-04 2.72E-05(
12/ 117)
? ~ OOE 7.50E-03 36 VALUES <LLD ANALYSIS PERFORHED 36 VALUES <LLO ANALYSIS PERFORHED LH1 SF NORTHMEST 1 ~ 0 MILE N I.H3 SF NORTHEAST'
~ 0 HILE ENE LM3 SF NORTHEAST 1 ~ 0 MILE ENE LM3 BF NORTHEAST 1 ~ 0 HILE ENE LM3 BF NORTIiEAST 1 ~ 0 HIL'E ENE DECATURr Al 8 ~ 2 HIlES SSE ROGERSVILLEr AL 13 ~ 8 MIlcS NSI ATHENSr AL 10 ~ 9 MILES NE 2 42E"02(
7/
13) 9'0c 5 '6E"02 Zo68E-02(
1/
13) 2.68E-02 2.68E-02 1 '7E-02(
1/
13) 1.47E-02 1 '7E-02 3'3E-02(
1/
1'3) 3.08E 3.083-02 5.008-04(
1/
13) 5.00E-04. -
5 'OE-04 1.02E"01(
11/
15) 5.76E 1.34E-01 2.00E-04(
1/
13) 2'OE 2.00E-04 SoOGE-05(
1/
15) 5 ~ GOE-03 5 ~ ODE-03 3oGOE-04 2 'OE-04 1 '1E-01 oo31c-'02 g.OCE-04 1 'GE-04 9o5CE-04 9 ~ GOE-04 8
VAL
(
3/
26) 5 DG -04
(
22/
25)
-'.43c-"1
(
2/
25)
?.OOE-04 2/
26) 1.0GE-G3 UES
<I.LD VAlUES <LLO Bo18E-03(
11/
25) 1 '08-03 1 '38-02 25 VALUES <LLO 25 VALUES <I.LD 26 VALUES <LLD MOTE:
1 ~
NOHINAL LOSIER LIMIT OF DETECTION (LI.D) AS 0 SCRIBED IN TABLE 3 ~
NOTE:
2 ~
MEAN ANO RANGE BASED UPON DETECTABLE HEASUREMENTS ONLY ~
FRACTION OF DETECTABLE MEASUREMEIITS AT Sc CIFI 0 LOCATIONS IS INOICATEO IH PARENTHES "S (F) ~
NaHE OF FACILITY $ $ QUU5 EEBttI LOCATION OF FACILITY l IttHIQUE TABLE 7 RADIOACTIVITY IN RAINwATER PCI/L " 0.037 80/L DOCt(ET ttO ~ NQ:252c2094226 REPORTING cERIOD 19tih TYPE ANO TOTAL "tUHSCR OF ANALYSIS PERFORMED GAM"ta (GcLI) 136 t("40 8I-214
>8-21 4 P8-21 2 3E-7 TRITIUM 136 l.OWER LIMIT OF OETcCTION (LLO)
Xff UQIE 1
NOT ESTAB'OT ESTAo NOT ESTAB NOT ESTAB NOT
=STAB S30+00 ALL I'tOICATOR LOCATIONS HEAlt (F)
RANGE Gff UQIE 2 20.64(
15/ 112) 4'2 -
os 94 5'2(
59/ 112) 0 56 -
29eSB 5'4(
35/ 112) 0 33 "
21 '5 1 '0(
29/ 112) 0.01 -
6.05 58.12(
24/ 112) 24.G9 -
197 7o 1'l2 VALUES <LLO ANALYSIS PcRFDR.'IED ATHENS'L 10 ~ 9 HILES NE LHS BF OAVIS F
2 ~ 5 HILES WSW'H5 BF DAVIS F 2 ~ 5 HILES WSW LH5 8F OAVIS F
2' MILES WSW LH1 SF NORTHWEST 1 ~ 0 MILE N
35.62(
5 ~ 30-9'3(
0'5 9 ~ 10(
1 ~ 58-2.83(
0.43 78'6(
37 82 2/
12) 65.94 o/
13)
- 29. 58 3/
13) 21 05 4/
13) o.05 6/
13) 197 75 IQQRIIQU BIIU UIQUEXI hUUQ&L, BEAU NAME MEAN (F)
DISTANCE ANO DIRECTION RattGE Gff UQIE 2
CONTROL LOCATIONS MEAN (F)
RANGc Sff UQIc 2
2m 1 8 (
2/
24) 0'9 -
3.67 bI60(
12/
24)
Oe04 -
20'2 5.58(
4/
24) 0'1 -
7'4 2.39(
7/
24) 0.05 -
5.97 54o56(
8/
24) 31 '2 -
106 '5 VALUES <LLO NUMBER OF NONROUTINE RcPORTEO HcASUREcHEVTS NOTE:
1 ~
NOMINAL LOWER LIHIT OF DETECTION (LLO)
AS DcSCRIBED Itl TABLE 3 ~
VOTE:
2.
HEAN ANO RA'VGE BASED UPON DcTECTASLE MEASUREMENTS ONLY.
FRACTION OF DETECTABLE MEASUREt ENTS aT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) ~
TABLE 8
RADIOACTIVITY IN HEAVY PARTICLE FALLOUT HCI/KH(2) - 37000000 F 00 BQ/KH(2)
NAHE OF FACILITY !!gQ!!g$ ff!!!!g LOCATION OF FACILITYl,j!!g5XQHg Ai!!!!!!!!
8 DOCKET NO.
2{i=202cRCQc'if'EPORTING PERIOD -gP!!$
TYPE AND (OTAL NUHBER
)F ANALYSIS PERFORHED ROSS BETA 143 LOMER LIHIT OF DETECTION (LLD)
Gff (!QEf 1 0 ~ 05 ALL INDICATOR LOCATIONS HEAN (F)
RANGe See 8QIE 2
0 16( 108/ 117) 0.06 -
0 F 88
! 964IIQU !!I15 VIQ!!ESI hU!!!!6! 5ESU NAHE HEAN (F)
DISTANCE ANO DIRECTION RANGE GPE 5Q..R
?
LH4 BF TRAILER P
0.31(
13/
13) 1 ~ 7 HILcS NtlM 0.06 -
0.88 C04TROL LOCATIONS HEAN (F)
RANGE RER 5QIE 2
'.11 (
25/
26) 0 F 05 -
0.20 NUHBcR OF NONROUTI4E REPORTED HEASURE<EMTS NOTE NOTE:
1 ~
NOHINAL LONER LIMIT OF DETECTION (LLO)
AS DESCRIBED IN TABLE 3 ~
2 ~
H AN AND RANGE BASED UPON DETECTABLE HEASUREHENTS ONLY FRACTION OF DETECTABLE H EASUREHENTS AT SPECIFI D LOCATIONS IS INOICATEO IN PARENTHESES (F) ~
TASLE 9 RADIOACTIVITY It( CHARCOAL FILTERS PCI/H(3) - 0 ~ 037 8Q/H(3)
NAHE OF FACILITY ilgQWlig EfililI LOCATIOtl OF FACILITY l.Il)EKIQHE 8! 8EhL8 DOC!(ET "lO 2Q:222'?(tQc?2E RcPORTING PERIOD gPgS TYPE A!lO TOTAL NUMBER OF ANALYSIS PERFORHEO IODINE-1 31 566 LONER LIMIT OF OcTECTION (LLD) gfc iiQIE 1 0.01 ALL IhOICATOR LOCATIOtlS HE Atl (F )
RAttGc EEE tiQIE 2 0 02(
68/ 452) 0.01 -
0'3*
!.QQAIIQB ttIIl! ~I%i)EKI 8(tt!M8!. 5=!!L3 NAME HEAtl (c)
DISTANCE AND DIRECTION RANGE REE ilQIE ?
LF1 dF NORTHNEST 0.02(
12/
52) 1.0 MILE N
0.01 -
0.13" CONTROL LOCATIONS MEAN (F)
RAtlGE SEE 5QIE 2
0 ~ 01(
15/ 104) 0.01 -
0 ~ 02 NVHSER OF NONROUTINE REPORTED EASUREHcNTS NOTE:
NOTE:
1 ~
tlOHINAL LONE'R LIHIT OF DETECTION (LLD)
AS OCSCRIEEO It( TA8LE 3 ~
2 ~
MEAN ANO RANGc BASED UPON OETECTASLc HcASURcHENTS ONLY'RACTION OF DETECTASLE MEASUREMENTS AT SP CIFI 0 LOCATIONS IS INDICATEO IN PARENTHESES (F) ~
- This valve is inflated because of radon interference.
18 Figure 2
ATMOSPHERIC AND TERRESTRIAL MONITORING NETWORK RM.2BF LAWRENCEBURG yPULASKI FAYETTEVILLE WII.SON FLORENCE PM-IBF WHEELER ROBE SVIL OAM ATHENS PM-28F FFIEL MUSCLE SHOALS RM-IBF LEIGHTON TUSCUMBIA COURTLANO PM-4 F
pRUSSELLVILLE BROWNS FERRY NUCLEAR PL OECAT PM-38F 0 IO MILES HARTSELLE 4
HUNTSVILLE GUNT SVIL OAM 25 HALEYVILLE
~CULLMAN 45 MILES RAINWATER SOIL O-ENVIRONMENTAL MONITORING STATION NOTE: THE FOLLOWING SAMPLES ARE COLLECTED FROM EACH STATION:
AIR PARTICULATES RADIOIODINE HEAVY PARTjCLE FALI OUT
LOLL MONITORING RATIONS BROWNS FERRY NUCLEAR PLANT 19,I ATHENS U S HWY 72 C3 0
BFN ALA. HWY 20 Legend h
Air Monitor AUtomatic Well Sampler Dairy Farm Other Fnrms DECATUR Scale 0
I 2
3 4
6 Miles
Yi
~>X
-~ %e-~=~M
'kN.".',.- @e5Ãw.-,.
-:, P pj's'~i "4
%@@le
. ~~~w~~-
~
~
, ~
~8
~ma~a
!&~~
~is
"-= --~
~~~IBeseei'a=
~aRR,"
'Ill Vi
~t
Figure 5
.30 25 Preoperational Phase Operational Phase AQANL AVERAGE GROSS BETA ACTIVITY III AIR FILTERS HRGWS FERRV Hmae Purr
.20
.15 o
tÃtC Jl o 1J iJ v'
4J V5 il C
Avcrafm:
Preonerational Phase
.10
.05 1968 1969 971 1970 1
1972 1973P 19730 1974 1975 1976 1977 1978 1979 1980 1981 1 82 1983 1984 Io85
I
23 Terrestrial Monitorin Terrestrial monitoring is accomplished by collecting environ-mental media within the general area of the plant for indicator locations, and at remote locations for controls.
These media sampled include milk, vegetation, soil, ground water, drinking water, and food crops.
In'ddition, environmental gamma radiation levels are determined by strategic placement of thermoluminescent dosimeters.'wice each year a land use survey is conducted'to determine milk producing animal census and location.
Land Use Surve The land use surveys were 'conducted in June and September of 1985.
The fall survey revealed that a dairy operation had resumed at a location previously used as a milk sampling point.
This location was added to the environmental sampling program.
After the land use survey was completed and during routine sample collection run, a dairy operation from which samples had routinely been collected ceased operation.
This location was removed from the sampling schedule.
In compliance with plant technical
,specifications, a Special Report was submitted to the Nuclear Regulatory Commission on November 26, 1985.
Milk Milk was collected from three farms within a 10-mile radius of the plant (see figure 3), and from at least one of six control farms.
During this report period, one indicator dairy farm ceased operation with the last sample being collected October 28, 1985., At about the same time, operations were resumed at a dairy formerly used as an indicator location.
This location was added to the milk sampling program with the first sample collected on November 4, 1985.
Raw milk samples are collected from indicator and control
- farms, and are analyzed weekly for iodine-131 and monthly for gamma-emitting isotopes and radiostrontium.
Analytical results are summarized in table 10.
During the 1985 reporting period, 7 samples were not available for collection, and one sample was inadvertently destroyed prior to analysis for radiostrontium.
V~e etation Vegetation is sampled monthly at five indicator farms (three dairies and two farms with one milk-producing animal),
and at each air monitoring station, quarterly vegetation samples are collected at four control farms (one control farm ceased operation in August).
The monthly samples are analyzed for iodine-131 and gamma-emitting isotopes with analysis for radiostrontium performed on the last monthly sample of each quarter.
Samples collected quarterly are analyzed for gamma-emitting isotopes.
Table ll summarizes analytical results.
'uring this reporting period, three samples were inadvertently destroyed before iodine analysis was done.
Soil Soil samples are collected annually near each monitoring station to provide an indication of long-term buildup of radioactivity in the environment.
An auger or a "cookie cutter" type sampler is used to obtain samples of the top two inches (5
cm) of soil.
These samples are analyzed for gamma-emitting radionuclides, strontium-89, and strontium-90.
The results are given in table 12.
Ground Water An automatic sequential-type sampling device collects groundwater from a well downgradient from BFN.
A composite sample from this weli is 'analyzed for gam'ma-emitting radionuclides monthly and composited quarterly for determination of tritium.
A grab sample is also taken monthly from a control well upgradient from the plant.
The results of the analysis of well water are shown in table 13.
During this report period one sample was not available for gamma analysis.
Potable water supplies taken from the Tennessee River in the vicinity of BFN are sampled and analyzed for gross beta and gamma-emitting radionuclides, and composited quarterly for tritium, Sr, and Sr analyses.
The first potable water supply downstream from the plant is equipped with an automatic sampler with samples collected and analyzed weekly.
The sampler is located on the water intake structure and takes the sample 'from the river as the raw water is drawn into the water treatment facility.
Two additional supplies downstream and one public water supply upstream are sampled by taking monthly grab samples of treated water at user points.
In addition, the surface water sample collected by an automatic water sampler upstream from the plant is included as a control for drinking water.
Table 14 indicates.
the results from the analysis of drinking water samples.
During this reporting period, two weekly samples were not collected because of automatic sampling equipment malfunction.
Figure 6 shows the trends in gross beta activity in drinking water from 1968 through 1985.
The annual average level from the raw water samples tends to run slightly higher than the average for treated water samples;
- however, the levels are consistent with the activities reported in surface water samples taken upstream from Bl'N (figure 12) and in samples taken from the Tennessee River in preoperational monitoring programs conducted by TVA at other sites.
Environmental Gamma Radiation Ievels N
Bulb-type Victoreen manganese-activated calcium fluoride (Ca~F:
Mn) thermoluminescent dosimeters (TLDs) are placed at sixteen stations around the plant near the site boundary,"at the perimeter and remote air monitors, and at nineteen additional stations out to approx~
imately five miles from the site to determine the gamma exposure rates at these locations, The dosimeters, located inside energy compensating shields to correct for energy dependence, are placed at approximately one meter above the ground, with three TLDs at each station.
They are
25 annealed and read with a Victoreen model 2810 TLD reader.
The values are corrected for gamma
- response, self-irradiation, and fading, with individual gamma response calibrations and self-irradiation factors determined for each TLD.
The TLDs are exchanged every three months.
The quarterly gamma radiation levels determined from these TLDs are given in table 15, which indicates that average levels at onsite stations are approximately 2-5 mR/quarter higher than levels at offsite stations.
This is consistent with levels reported at TVA's nonoperating nuclear power plant construction sites where the average radiation levels onsite are generally 2-6 mR/quarter higher than levels offsite.
The causes of these differences have not been completely isolated; however, it is postulated that the differences are probably attributable to combinations of influences, such as natural variations in environmental radiation levels, earth moving activities onsite, the mass of concrete employed in the construction of the plant, and other undetermined influences.
Figure 7 compares plots of the data from the onsite or site boundary stations with those from the offsite stations over the period from 1976 through 1985.
To reduce the variations present in the data
- sets, a four-quarter moving average was constructed for each set.
Figure 8 presents a trend plot of the direct radiation levels as defined by the moving averages.
The data, follow the same general trend as the raw data, but the curves are smoothed considerably.
Prior to 1976 measurements were made with less sensitive dosimeters, and consequently the levels reported in the preoperational phase of the monitoring program are up to 2 times the levels reported herein.
Those data are not included in this report.
Therefore, for comparison purposes, figures 9 and 10 depict the environmental gamma radiation levels measured during the construction of TVA's Watts Bar Nuclear Plant to the present.
Note that the data follow a similar pattern to the BFN data and that, as discussed above,.the levels reported at onsite stations are similarly higher than the levels at offsite stations.
Food Products Food products raised in the vicinity of BFN and at control locations are sampled as they become available during the growing
- season, and analyzed for gross beta activity and for gamma-emitting radionuclides.
During this sampling period, samples of apples,
- cabbage, corn, green beans,
- potatoes, beef, and tomatoes were collected-and analyzed for specific gamma-emitting radionuclides.
The results are given in 'tables 16 through 22.
TABLE 10 RADIOACTIVITY IN HILK PCI/L - 0 ~ 037 BQ/L NAME OF FACILITY QQQltgg EEEEI LOCATION -OF FACILITY LZHESIQHE 8l89858 DOCKET NO 29=252c20Qc225 REPORTING PERIOD 1252 TYPE ANO TOTAL NUMBER OF ANALYSIS PERFORMED ODINE-1 31 434 AHHA (GELI) 108 LONER LIHIT OF OETEC. ION (LLD)
SEE 5QIE 1
0'0 ALL INDICATOR LOCATIONS LQG8IIQU lllIU UIQUEGI 855081-df 88------
MEAN (F)
NAHE MEAN (F)
RANGE DISTANCE AND DIRECTION RANGE SEE UQIE 2
Sff 9Q'lE 2
156 VALUES <L'LO ANAL'YSIS PERFORMED CONTROL LOCATIONS MEAN (F)
RANGc E
HQIE 2 278 VALUES <LLO NUMBER OF NONROUTINE REPORTED MEASUREMENTS CS-137 K-40 BI-214 PB-214 PB-212 TL-ZOB AC-228 R 89 107 R 90 107 5.00 NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB 10 00 Z.OO 8 41(
6/
39) 6'9 -
9'8 1193 '9(
39/
59) 768.95 -
1686 '7
? ~ 41 (
31/
39) 0+59 -
35e98 7.65(
13/
39) 1 '6 "
26'5 2.00(
8/
39) 0 39 -
3'0 1 '5(
6/
39) 0 12 -
3 63 8'2(
3/
39) 5 08 -
13 26 39 VALUES <LLD ANALYSIS PERFORHEO 3'0(
38/
39) 2.05 -
5'4 PAGE FARH 8 75 HILES E
LOONEY FARM 5 ?5 MILES ENE SMITH/BENNETT FA 4 ~ 75 HILES N
LOONEY FARM 5 ~ 75 MILES ENE LOONEY FARM 5 ~ 75 NILES ENE PAGE FARM 8 ?5 MILES E
PAGE FARH 8 ~ 75 MILES E
SMITH/8ENNETT FA 4 ~ 75 MILES N
8 41(
6e29 1264 '3(
1058.34 9 98(
8'1 10 02(
1 ~ 36 F 00(
3.00 2'5(
0.87 10'3(
7.21 6/
11) 9+98 13/
15) 1435o68 2/
2) 11 '5 4/
13) 26'5 1/
13) 3 ~ 00 2/
11) 3ob3 2/
11) 13'6 4 ~ 12(
2/
2) 3 77-4 ~ 48 8'9(
2/
69) 5'4 11 '4 1297 44(
69/
69) 781 '3 -
1925.94 6.93(
38/
69) 0'2 -
21 F 87 7'8(
27/
69) 0'4 -
29 F 05 1 '8(
12/
69) 0'6 -
6+27 0.97(
13/
69) 0.01 -
2.78 5 20(
9/
69) 0'2 -
11 '6 68 VALUES <LLO 3.?0(
56/
68)
F 00 -
6'1 NOTE:
NOTE:
1 ~
NOHINAL LONER LIHIT OF DETECTION (LLO)
AS DESCRIBED IN TABLE 3 ~
2 ~
MEAN AND RANGE BASED UPON DETECTABLE MEASUREHENTS ONLY~
FRACTION OF DETECTABLE MsASUREHcNTS AT SPECIFIcD LOCATIONS IS INDICATEO IN PARENTHESES (F) ~
TABLE 11 RADIOACTIVITY IN VEGETATION PCI/G
~ 037 BQ/G (ORY MEIGHT)
NAME OF FACILITY EBQHUX EEBBI LOCATION OF FACILITY l,I5EBIQBE BLBEBLB DOCKET NO ~ gg:2$ Pc2$ QA2$ 0 REPORTING PERIOD SR 89 SR 90 65 65 TYPE ANO TOTAL NUHBER OF ANALYSIS PERFORMED IODINE-131 208 GAMMA (GELI) 226 C0-60 CS-137 K-40 BI-214 BI-212 PB-214 PB-212 BE-7 TL-208 AC-228 LONER LIMIT OF DETECTION (LLO)
BEE UQIE 1 NOT ESTAB 0'6 0 06 NOT ESTAB 0 ~ 10 NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB 0'5 0~05 ALL INDICATOR LOCATIONS HEAN (F)
RANGE GEE BQIE 2
0 00(
85/ 183) 0.00 -
Oe02 0'9(
1/ 185) 0'9 -
0 F 49 0'3(
14/ 185) 0 07 -
0'7 15+56( 182/ 185) 1 '4 -
43'1 0'2(
93/ 185) 0'0 -
0'0 0'8(
2/ 185) 0'7 -
0'0 0.16( 167/ 185) 0 F 00 -
0'6 0 07( 126/ 185) 0.00 -
0'3 7 13( 184/ 185) 0 61 -
25 22 0+04(
78/ 185) 0 ~ 00 -
0 ~ 14 0'0(
73/ 185) 0'2 -
0 79 5?
VALUES <LLD ANALYSIS PERFORHED 0'0(
53/
57) 0'6 -
0'6 LH1 BF NORTHllEST 1 ~ 0 MILE ti PAGE FARH 8 ~ 75 MILES E
PAGE FARH 8 ~ 75 MILES E
PAGE FARM 8 75 MILES E
PAGE FARH 8 ~ 75 HILES E
EVANS FARH 6 ~ 1 MILES NE EVANS FARH 6 ~ 1 HILES NE SMITH/BENNETT FA 4 75 MILES N
EVANS FARM 6.1 MILES NE PAGE FARM 8'5 MZLES E
Oo49(
0'9
' '7(
0.27 25.86(
5'6 0'9(
0 ~ 13 0.50(
0'0
'0 21(
0 ~ 06 0'3(
0 01 10'8(
6'7 0 F 07(
0'1 0'9(
0'3 1/
1/
11/
4/
1/
12/
9/
5/
6/
2/
13) 0 49 11) 0'7 11) 43 ~ 21 11) 0.60 11) 0 F 50 13) 0'2 13) 0+30 5) 15 ~ 56 13) 0 ~ 11 11) 0'5 ROGERSVILLEr AL 13 ~ 8 MILES NN 0 ~ 35(
4/
4) 0 ~ 16 -
0 ~ 56
!.QQBIIQU liIIU UIQUEBI BUUDBL ZEBU NAME HEAN (F)
DISTANCE ANO DIRECTION RANGE GEE BQIE 2
0 ~ 01(
6/
12) 0 F 00 -
0 02 COhTROL LOCATIONS HEAN (F)
RANGE 5EE BQIE 2
0 F 00(
10/
25) 0 ~ 00 -
-0 ~ 01 41 VALUES <LLD 0 12(
3/
41) 0'6 -
0'5 15'7(
40/
41) 1 43 -
40 34 0 ~ 20(
14/
41) 0'1 -
0'6 41 VALUES <LLO 0.12(
33/
41) 0 ~ 01 -
0 ~ 40 0 ~ 04(
18/
41) 0 ~ 01 -
0 ~ 11 7 ~ 44 (
41/
41) 0.97 -
18.75 0.02(
11/
41) 0 F 00 -
0.05 0'6(
12/
41) 0 F 05 -
0'0 8
VALUES <LLD 0.21(
8/
S) 0'9 -
0'1 NUMBER OF NONROUTINE REPORTED MEASUREMENTS 1
(Note 3)
NOTE:
NOTE Note:
1 ~
tiOMINAL LOttER LIMIT OF DETECTION (LLD)
AS DESCRIBED IN TABLE 3 ~
2a HEAN AND RANGE BASED UPON DETECTABLE HEASUREHENTS ONLY'RACTION OF DETECTABLE MEASUREMENTS AT SPECIFIEO LOCATIONS IS INDICATEO IN PARENTHESES (F) ~
3.
A report was submitted to the Nuclear Regulatory Commission on June 14, 1985, outlining the high value.
The single, tsolatect occurrence of cobalt-60 in vegetation, the absence of other fission and activation products in the sample, and the lack of an Increase in cobalt-60 releases from the plant prevented an identification of the causes for the presence of the isotope in the sample.
Subsequent samples showed no indication of the presence of cobalt-60.
TABLE 12 RADIOACTIVITY IN SOIL PCI/G - 0 ~ 037 BQ/G (DRY HEIGHT)
LOGATI TYPE AND TOTAL NUHBER OF ANALYSIS PERFORMED AMHA (GELI) 11 CS-137 1/
1) 1 ~ 43 1/
1) 7 ~ 24 1/
1 )
1 '3 1/
1) 1 ~ 55 1/
1) 1 ~ 48 1/
1) 1 35 1/
1) 1 ~ 43 1/
1) 1 ~ 47 1/
1) 0.24 LH5 Bf DAVIS F 2 ~ 5 MILES HSW LM1 BF NORTHNEST 1 ~ 0 MILE N LH2 BF NORTH 0 '
MILE NNE LH2 BF
- lORTH 0
9 HILE NNE LK1 BF HORTHHEST 1 ~ 0 MILE N OECATURr AL Be 2 MILES SSE LH2 BF NORTH 0 ~ 9 HIl.E NNE LH3 BF NORTHEAST 1 ~ 0 MIl.E "ENE DECATURr AL 8 ~ 2 MILES SSE 0 ~ 02 1 43(
1 '3 7'4(
7 24 1.43(
1 ~ 43 1 ~ 55(
1 ~ 55 1 ~ 48(
1 ~ 48 1 ~ 35(
1 '5 1 '3(
1.43 1.47(
1 '7 0.24(
0 24 0.46(
0 02 5'8(
2.89-1 '8(
0.63-1 ~ 21(
0.62 1 ~ 17(
0.67 1 '4(
052-1 ~ 08(
0 ~63-1 11(
0 62 0'1(
0.18 9
VALUES 9/
9) 1 ~ 43 9/
9) 7.24 9/
9) 1 ~ 43 9/
9) 1 ~ 55 9/
9) 1 '8 9/
9) 35 9/
9) 1 ~ 43 7/
9) 1,47 2/
9) 0 24
<LLD 2/
2) 0 57 2/
2) 4'9 2/
2) 0'4 2/
2) 0,04 2/
2) 1,04 2/
2) 0.87 2/
2) 0.94 2/
2) 0.93 1/
2) 0.22 1/
2) 0 11 2/
2) 0.29 2/
2) 0 F 87 2/
2) 3 33
<LLD 0.38(
020-4 ~ 03(
3 ~ 17 0 ~ 90(
- 0. 87 0 91(
0'9 0'6(
0 88 0 85(
0 ~ 83 0.90(
Oe87 0.8?(
0.80 0.22(
0.22 0 11(
0 11 Oe 28(
0 27 0.85(
0.83 2.69(
1 ~ 44 2
VALUES K-40 BI-214 BI-212 PB"214 PB-212 RA-226 RA-224 BE-7 TH-227 TL-208 AC-228 PA-234M 0'5 0 F 05 0.10 0'5 NOT ESTAB 0 F 05 NOT ESTAB 0.16 NOT ESTAB 0.02 1/
1)
- 0. 47 1/
1) 1'8 1/
1) 2'4 0 36(
9/
9) 0.19 -
0'7 1 '6(
9/
9) 0,55 -
1 '8 2.18(
4/
9) 1 '3 -
2'4 9
VALUES <LLD ANALYSIS PERFORMED 0 24(
4/
9) 0 20 -
0'8 DECATURr AL 8 ~ 2 HILES SSE OECATURr AL 8.2 MILES SSE ROGERSVILLEr AL 13.8 MILES NH 0 ~ 47(
0.47-1 38(
1 ~ 38-2.74(
2.74-0 ~ Oo NOT ESTAB R
89 1e50 2
VALUES <LLD 0 ~ 28(
1/
1) 0.28 -
0.28 R 90 0 ~ 15 LMS BF DAVIS F 2 ~ 5 MILES HSH NAME OF FACILITY gggjfgg fggQJ DOCl(ET ND ~ 29=?22c?09c?2k ON OF FACILITY ggggggggg
$ gQg$ Q$
REPORTING PERIOD LONER LIHIT ALL CONTROL NUHBER OF OF INDICATOR LOCATIONS.
Lgga?LOB IZING UIGUEII hUBLthl, BEh5 NONROUTINE DCT ECTION MEAN (F)
NAHE MEAN (F)
MEAN (F)
REPORTED (LLD)
RANGE DISTANCE ANO DIRECTION RANGE RANGE MEASUREHENTS RfE 5QIC 1
5EE UQIf ?
GEE SCIL
?
'EE hQIE 2
NOTE:
1 ~
NOHINAL LOWER LIHIT OF DETECTION (LLO)
AS DESCRIBED IN TABLE 3 ~
NOTE:
2 ~
MEAN,ANO RANGE BASED UPON DETECTABLE HEASUREHENTS ONLY~
FRACTION OF DETECTABLE MEASUREMENTS AT SPECIfIED LOCATIONS IS INOICATEO IN PARENTHESES (F)
TABLE 13 RADIOACTIVITY IN WELL WATER PCI/L - 0 037 SO/L NAtlE OF FACILITY ERQHUX EEEBI LOCATION OF FACILITYLIUESIQUE hLM8U6 DOCKET NO ~
1Q=222c25QA22!)
REPORTING PERIOD TYPL.
ANO TOTAL NUMBER OF ANALYSIS PERFORHEO LOWER LIMIT ALL OF INDICATOR LOCATIONS
!,QQGIIQU hIIU UIQUEKI BUUQSL UWU DETECTION HEAN (F)
NAHE MEAN (F)
(LLO)
RANGE DISTANCE ANO DIRECTION RANGE kEE UQIE 1
REE UQIE 2
GEE UQIE 2
CONTROL LOCATIONS tlEAN (F)
RANGE SEE UQIE 2
NUMBER OF NONROUTINE REPORTED MEASUREMENTS GAHHA (GELI) 25 K-40 BZ-214 PS-214 PS-212 TL-208 AC-228 TRITIUH NOT cSTAB NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB 550.00 8,92 (
1/
13) 8'2 -
8'2 9'6(
12/
15) 1
<<3 -
17'2 12 F 08(
9/
13) 2'7 -
18'7 F 80(
4/
15) 0'1 4'4 13 VALUES <LLO 7'9(
1/
15) 7'9 -
7'9 4
VALUES <LLO ANALTSIS PERFORHEO BFN WELL
%6 0 ~ 02 MILES k BFN
'WELL tt6 0 ~ 02 HILES X
BFN WELL tt6 0 ~ 02 MILES le BFN WELL tt6 0 ~ 02 MI!.ES W
8.92(
8.92 9.36(
1~43 12 08(
2'7 2 80(
Oe71 1/
12/
9/
4/
13) 8 92 13) 17'2 13) 18 ~ 27 13) 4'4 7 ~ 09(
1/
13) 7'9 -
7 F 09 F 57(
2/
12)
F 06 -
8.09 175 22(
12/
12) 40 F 97 -
680'5 177 10(
12/
12) 43'4 682 '2 3.77(
3/
12) 1 '3 -
6'6 0'3(
2/
12) 0.28 -
0'8 12 VALUES <LLD 4
VALUES <LLO NOTE:
1 ~
NOMINAL LOWER LIMIT OF DETECTION (LLO)
AS OESCRIBEO IN TABLE 5 ~
NOTE:
2 ~
MEAN AND RANGE BASED UPON DETECTABLE HEASUREHENTS ONLY~
FRACTION OF DETcCTASLE HEASUREMENTS AT SPECIFIEO LOCATIONS IS INOICATEO IN PARENTHESES (F) ~
TAB!.E 14 RADIOACTIVITY IN PUBLIC WATER SUPPLY PGI/L - 0+037 8(t/L NAME OF FACILITY EEQ$ 55 EEBBX LOCATION OF FACILITYL,?5i~5IQUE BLBE858 DOCKET NO 2Q"22212{iQc22B REPORTING PERIOD iR 90
'RITIUH 20 20 TYPE AND TOTAL NUHBER OF ANALYSIS PERFORHEO ROSS BETA 102 AHHA (GELI) 102 t(-40 BI-214 PB-214 PB-212 TL-208 AC-228 R 89 20 LOWER LIHIT OF DETECTION (LLD)
HE HQIE 1
F 00 NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB 10 F 00 F 00 330 F 00 ALL INDICATOR LOCATIONS tlEAN (F)
RANGE SEE MIE 2 3 23(
55/
76) 2.05 -
6.58 14'2(
12/
76) 2'2 -
42'6 5'5(
39/
76) 0'7 -
19'3 4'6(
24/
76) 0'8 -
17'9 76(
15/
76)
Oe01 -
8 F 28 1'2(
12/
76) 0 00 -
2'8 5.46(
9/
76)
Os13 -
11.59 12 VALUES <LLD ANALYSIS PERFORMED 12 VALUES <LLO ANALYSIS PERFORMED 12 VALUES <LLD wHEELER DAMr AL TRH 274 '
SHEFFIELDr AL ROB TRH 254 '
WHEELER OAHr AL TRM 274' CHAHPION PAPER TRH 282+6 SHEFFIELDr AL ROB TRH 254 '
23'6(
11 '0 7'9(
1 '1 7 29(
0'6 4'0(
4 ~ 10 1 ~ 05(
0 F 00 9'9(
9'9 3/
13) 42 16 7/
13) 14'2 3/
13) 17'9 1/
13) 4 ~ 10 8/
50) 2.38 1/
13) 9 ~ 49 LQQBI?QU t(IIU UIQUEEI BUUllBL HEBE NAHE HEAN (F)
DISTANCE ANO DIRECTION RANGE SEE UQIE 2
CHAHPION PAPcR 3'8(
40/
50)
TRH 282 6
F 08 -
6'8 CONTROL I.OCATIONS MEAN (F)
RANGE 5EE HQIE 2
2 ~ 93 (
22/
26)
F 04 -
5.62 0 ~ 47(
1/
26) 0 47 -
0.47 9'2(
12/
26) 0 ~ 13 -
47 ~ 47 5'2(
7/
26) 0'7 -
18'0 1.49(
6/
26) 0+29 -
2'2 26 VALUES <LLD 333o48(
333'8 1/
8) 333.48 8'8(
4/
26) 0.93 -
27.49 8
VALUES <LLO 8
VALUES <LLO NUMBER OF NONROUTINE REPORTED MEASUREMENTS NOTE:
1 ~
NOMINAL LOWER LIMIT OF DETECTION (LLO) AS OESCRIBEO IN TABLE 3 ~
NOTE:
2 ~
MEAN AHO RANGE BASED UPON DETECTABLE tlEASUREHcNTS ONLY FRACTIOtt OF OcTECTABLE MEASUREMENTS AT SPECIFIcO LOCATIONS IS INOICATEO IN PARENTHESES (F) ~
31 Table 15 FNVIRONMENTAL GAHHA RADIATION LEVELS Average External Gamma Radiation Levels at. Various Distances from Browns Ferry Nuclear Plant for Each Quarter - 1985 mR/Quarter Distance miles 0-1 1-2 2-4 4-6
>6 Avera e External Gamma Radiation Ievels b 1st Quarter 18.0
+ 2.5 16.2 + 2.6 15.1
+ 1.4 14.8 + 1,3 14.4 + 1.3 19.4 + 0.8 17.7 + 1.8 15.9
+ 1.5 16.1
+ 1.7 15.8 + 1.5 21.8 + 3.7 17.9 + 3.8 16.1
+ 3.0 16.5
+ 3.2 15.2 + 2.4 21.0 + 2.1 18.1
+ 2.4 18.2 + 2.7 17.6 + 2.2 17.4 + 1,9
- Average, 0-2 miles (Onsite)
- Average,
>2 miles (Offsite) 17.6
+ 2.5 14.8 + 1.3 18.9 + 1.3 15.9
+ 1.5 20.8
+ 4.0 16.0 + 2.9 20.3 + 2.4 17.6 + 2;2 a.
Data normalized to one quarter (2190 hours0.0253 days <br />0.608 hours <br />0.00362 weeks <br />8.33295e-4 months <br />).
- b. All averages reported +l(r (68 percent confidence level).
TABLE 16 NAHE OF FACILITY QBQUU5 EEBBI LOCATION OF FACILITY l,IUxgIQUE RADIOACTIVITY IN CABBAGE PCI'/KG' 0.03'7 BQ/KG- (ilET HEIGHT).
DOCKET NO ~
29=222c2ftQA29O REPORTING PERIOD 125>
TYPE AND
'OTAL NUHBER iF ANALYSIS PERFORMED
- OSS BETA 2
iHHA (GELI) 2
- -40 LONER LIMIT OF DETECTION
<LLO)
SEE UQIE I 25 F 00 NOT ESTAB ALL INDICATOR LOCATIONS MEAN (F)
RANGE SEE UQIE 4
3764 15(
1/
1) 3764 '5 -
3764 '5 1652 ~ 64(
1/
1)
PAGE FARM 1652.64 -
1652 ~ 64 B 75 HIt.ES E
1652 ~ 64(
1/
1) 1652 64 -
1652.64 l QQ8IIQU ViIIU UIQUE51 8UUll8l UE88 NAME HEAN (F)
DISTANCE AND DIRECTION RAilGE SEE UQIE 2 PAGE FARH S764 ~ 15(
1/
1)
B.75 MILES E
3764.15 -
3?64.15 CONTROL LOCATIONS MEAN (F)
RANGE
$ EE hQIE 2 ---
3440.65<
3440.65 -
3440.65 1559.45(
1/
1) 1569.45 15"9-45 NUMBER OF NONROUT INE REPORTED MEASUREMENTS lOTE:
1 ~
NOHINAL LOllER LIMIT OF DETECTION (LLO)
AS DESCRIBED IN TABLE 3 ~
lOTE 2 ~
MEAN ANO RANGE BASED UPON DETECTABLE l EASUREHENTS ONLY~
FRACTION OF DETECTABLE HEASUREHENTS AT SPECIFIED LOCATIONS IS INDICATED IN PARENTHESES (F) ~
TABLE 17 RADIOACTIVITY Ih CORtt PCI/KG - 0 ~ 037 BQ/KG (wET 4'EIGHT)
NAME OF FACILITY ggQggg PgllRI DOCKET NO ~ 2{}=222cRt)Q422(t--------
LOCATION OF FACILITY l,gg~cggQltf El,ggggg RcPORTING PERIOD TYPc AND TOTAL NUMBER OF ANALYSIS ccRFORHED GROSS BETA 2
GAHca (GELI) 2 K-40 PB-214 LOitER LIMIT OF DETECTION (LLO) 5aE BQI~
1 25 F 00 NOT FSTAB NOT ESTAB ALL INDICATOR LOCATIONS MEAN (F)
RANGE 0EE 8QIR 2
4152.67(
1/
1) 41 52 ~ 67 41 52 ~ 67 lLQQhlIQ9 h?ill UiQUZKI 68Ullhl NAME HEAN (F)
DISTANCE ANO DIRcCTION RAttGE XcR UQX:
2 7 HILES NNW 4152 ~ 67(
1/
1) 4152 '7 -
4152.67 CONTROL LOCATIONS MEAN (F)
RANGC KEc UQIC 2
3807 94(
1/
1) 3507 '4 -
3807 '4 2518 ~ 86(
1/
1) 7 MILES NNM 2518 '6 -
2518 F 86 10.58(
1/
1) 7 WILES NNW 10 ~ 58 "
10 ~ 58 2518 86(
1/
1) 2163 ~ 31(
1/
1) 251 Bo 86 251 8 ~ 86 2163
~ 31 21 63 ~ 31 10 58(
1/
1) 1 VALUES <LLD 10'o -
10 F 58 NUMBER OF NONROUT INE RcPORTED HEASUREHENTS
'ROTC 1 ~
NOHIiVAL LOWER LIMIT OF OETE CT ION (LLO)
AS DESC RI 8 0 IN TABLE 3 ~
NOTE:
2 ~
MEAN ANO RANGE BASED UPON DETECTABLE M ASUREHENTS ONLY ~
FRACTION OF DETECTABLE MEASUREMENTS AT SPcCIFIEO LOCATIONS IS. INOICATEO IN PARENTHESES (F) ~
TABLE 18 RADIOACTIVITY IN GREEN BEANS PCI/KG - 0 037 8Q/KG (MET itEIGHT)
NAME OF FACILITY EBQl(55 fEBBI LOCATION 'OF FACILITY l,jgESIOUE
-Al 8ll858 DOCKET NO ~ fg 22B4259c225 REPORTING PERIOD 1255 TYPE AND
'OTAL NUHBER IF ANALYSIS PERFORMED
'OSS SETA 2
<MHA (GELI) 2
- -40 sI-214
'8-214 LONER LIMIT OF DETECTION (LLO)
EE gQIE 25+00 NOT ESTAB NOT ESTAB NOT cSTAB ALL INDICATOR LOCATIONS HEAN (F)
RANGE KEE UQIE 2
3823 '7(
1/
1) 3823'7
3823'7 1659 ~ 47(
1/
1) 7 MILES NNH 1659 '7 -
1659 ~ 47 1
VALUES <LLD 1
VALUES <LLD 1659 ~ 47(
1/
1) 1659 47 -
1659.47 l 9GAIIQU llII"QIGUERI 8BHQEL BEBOP NAHE MEAN (F)
DISTANCE ANO DIRECTION RANGE SEE 991E 2
7 MILES NNN 3823.47(
1/
1) 3823 ~ 47 -
SB23 ~ 47 2003.71 (
20G3.71 3.70(
3 70 2.14(
2.14 1/
1) 2003o71 1/
1) 3 ~ 70 1 /
1) 2+14 CONTROL LOCATIONS HcAN (F)
RANGE GEE QQIE 2
5150 ~ 78(
1/
1) 5150 78 -
5150.73 NUMBER OF NONROUTINE REPORTED MEASURcHENTS lOTE:
1 ~
NOHINAL LONER LIMIT OF 0 TECTION (LLO)
AS DcSCRISEO IN TABLc 3 ~
IOTE:
2 ~
MEAN ANO RANGE BASED UPON DETECTABLE HEASUREMENTS ONLY ~
FRACTION OF OETECTASLE MEASUREMENTS AT ScECIFIEO LOCATIONS IS INDICATED IN PARENTHESES (F) ~
TABLE 19 RAOIOACTIVIT Y IH APPLES PCI/KG 0 '57 BO/KG
('AET HT)
NAME OF FACILITY QEQH55 EERBY LOCATION OF FACILITY gjgE/IQt1E 8L85858 oOCKET NO ~
20=212A21)QA220 REPORTIHG PERIOD TYPc ANO TOTAL HUHBER OF ANALYSIS PERFORMED GROSS BETA 2
AHHA (GcLI) 2 LONER LIMIJ OF OcTECTION (LLD)
SEE UQIE I 25 ~ 00 ALL INDICATOR LOCATIONS MEAN (F)
RANGE GEE 9QIE 2
1695 '2(
1/
1) 1695.72 -
1 695 '2 LQQBIIQB III'IQdEDI 85UQEL PERU NAME MEAN (F)
DISTANCE ANO DIRECTION RANGE EE 8QIE 2
PAGE FARM 1695 '2(
" 1/
1) 8.75 WILES E
1695.72 -
1695.72 CONTROL LOCATIONS HEAN (F)
RANGE Sic BQIE 2
1618.79(
1/
1) 1618 '9 -
1618 '9 NUMBER OF NONROUTINE REPO'RTED MEASUREMcNTS K-40 SI-214 PS-214 AC-228 NOT ESTAB NOT ESTAB HOT ESTAB NOT ESTAB 1080.23(
1/
1)
PAGE FARH 1080 ~ Z3 -
1080 23 8.75 MILES E
1 VALUES <LLD 1
VALUES <LLD 1
VALUES <LLO 1080 ~ 23 (
1/
1 )
1080 23 -
1080 ~ 23 862 ~ 72 (
862 AD ?2 8'7(
8'7 3'2(
5'2 2.70(
Zo?0-1/
1) 862 '2 1/
1)
Be47 1/
1) 3'2 1/
1) 2'0 NOTE:
1 ~
NOMINAL LOiiER LIHIT OF DETECTION (LLO)
AS OESCRIBEO IN TABLE 3 ~
NOTE:
2 ~
MEAN ANO RANGE BASED UPON DETECTABLE HEASUREHENTS ONLY'RACTION OF OETcCTABLE HEASUREHEHTS AT SPECIFIEO 1.OCATIONS IS INOICATEO IN PARENTHESES (F) ~
TABLE 20 RADIOACTIVITY IN POTATOES PCI/KG - 0 ~ 03l BQ/KG. ('AET. )(EIGHT,).
NAHE OF FACILLTY $3Q)l55 EEBBX'OCATION OF FACILITY l,Illa'IQ(lC ELBRBllk DOCKET NO ~ 59:?0 c?5QA225 REPORTING PERIOD 12llk TYPE ANO (OTAL NUHBER
)F ANALYSIS PERFORHEO LOSS BETA 2
LHHA (GELI) 2
- -40 LONER LIMIT OF DETECTION (LLD) 5
- E llQIi 1 25 F 00 ALL INDICATOR LOCATIONS MEAN (F)
RANGE SEE UQIc 2
6048 46(
1/
1) 6048.46 -
604e.,46 l QfchIIQ8 lfIIllUIQU~DI hUllllhl. 5PBU NAME MEAN (F)
DISTANCc AND DIRECTION RANGE BEf UQ) E 2-----
PAGE FARH 6048 '6(
1/
1) 8 ~ 75 MILES c 6048.46
6048.46 CONTROL LOCATIONS MEAN (F)
RANGE KfE UQXE
?
6564 '8(
1/
1) 6564.38 -
6564.38 3408.85(,
.1/
1) 3694.61(
1/
1) 3408.85 -
3408.85 3694 ~ 61 -
3694+61 NOT ESTAB 3408 F 85(
1/
1)
PAGE FARM 3408 ~ 85 -
3408 ~ 85 8 ~ 75 MILES NUHBER OF NONROUTINE RcPPRTEP MEASUREMENTS IOTE:
1 ~
NOHINAL LONER LIMIT OF DETECTION (LLD) AS OESCRIBEO IN TABLE 3 ~
<OTE P ~
MEAN AND RANGE BASED UPON DETECTABLE HEASUREMENTS ONLY ~
FRACTION OF DETECTABLE-HEASURcHENTS AT SPECIFIcD LOCATIONS IS INDICATcO IN PARENTHESES (F) ~
TABLE RADIOACTIVITY IN BEEF PCI/KG - 0 037 BO/KG (PET HEIGHT)
NAME oF FAGILITY EEQUU5 EEEBI LOCATION OF F ACILITY I.IUEPIQUE Bl BfBUB DOCKET NO ~ 09=222c26Q4225 TYPE ANO TOTAL NUMBER OF ANALYSIS PERFORHcD GROSS BETA 2
GAHHA (GELI) 2 K-4O PB-21 4 PB-212 LOAER LIMIT PF OETcCTION (LLD)
SEE UQXE 1
25.00 NOT ESTAB NOT ESTAB NOT cSTAB 1838.92(
1838'2 0 ~ 10(
0'0 0 33(
0.33 1/
1) 1838 92 1/
1) 0 ~ 10 1/
1) 0.33 ALL INDICATOR LOCATIONS MEAN (F)
RANGE Kff UQIE 2
4397. 55 (
1/
1) 4397 F 55 -
4397.55 LOONcY FARH 5
75 MILES ENE LOONEY FARH 5 ~ 75 MILES ENE LOONEY FARH 5 ~ 75 MILES ENE 1838.92(
1838 '2 0 ~ 10(
0 ~ 10 0.33(
0'3 1/
1) 1838 ~ 92
'1/
1) 0.10 1/
1) 0 ~ 33 LQQBIIQU uIIU UIQUEGI BUU!lBl UEBU NAHE HcAN (F)
DISTANCE ANO DIRECTION RANGE UQjs 2
LOONEY FARM 4397 '5(
1/
1) 5'5 MILES ENE 4397 '5 -
4397 55 1384 55(
1384 55 1 ~ 21(
~ 21 0.77(
0 ~ 77 1/
1) 1384 '5 1/
1) 1 ~ 21 1/
1) 0.77 CONTROL LOCATIONS HcAN (F)
RANGE Kff UQIE 2
3768 57(
1/
1) 3768 '7
'3768 ~ 67 NUHBER OF NONROUTINE REPORTED MEASUREMENTS NOTE:
1 ~
NOHINAL LONER LIMIT OF DETECTION (LLO)
AS DESCRIBED IN TABLE 3 ~
NOTE~e2
~
MEAN ANO R4NGE BASED UPON DETECTABLE MEASUREMENTS ONLY~
FRACTION OF DETECTABLE HEASUR MENTS 4T SPECIFIEO LOCATIONS IS INDICATED IN PARENTHESES (F) ~
TABLE 22 RADIOACTIVITY IN TOHATOES PCI/KG '037 BO/KG -(McT -MEIGHT)
NAHE OF FACILITY EllQlfUK CE HEI LOCATION Or. FACILITY l,ZIEEIQUE hl SE658 DOCKET No ~
NQ=?22c?(tQc2Rtt REPORTING PERIOD 1252 TYPE ANO foTAL NUHBER
)F ANALYSIS PERFORHEO ROSS BcTA 2
AHHA (GELI) 2 K-40 8 I'-21 4 PB-214 LOMER LIHIT OF DETECTION (LLD)
OEE UQIE 1
25 F 00 NOT ESTAB NOT ESTAB NOT ESTAB AI.L INDICATOR LOCATIONS HEAN (F)
RANGE SEE 8QIE 2
4228 87(
1/
1) 4228'7 -
4228 F 87 2103.35(
2103 '5 6.31 (
6.31 "
2.20(
2 20 1/
1) 7 HILES NNM 2103.35 1/
1) 7 MILES NNM 6 ~ 31 1/
1) 7 HILES NNk 2'0 2103 35(
2103 '5 5 31(
6 ~ 31 2 20(
2'0 1/
1) 2103. 35 1/
1)
- 6. 31 1/
1)'.20 I QChIIQ5 hII'll llIGUEEI 658!tel JE65 NAHE HEAN (F)
DISTANCE ANO OIRcCTION RANGc Eff 5Q:E?
7 HILES NNM 4228 ~ 87 (
1/
1) 4228.87 -
4228.87 2103. 69 (
2103. 69 8.97(
8 97 3+10(
3 ~ 10 1/
1) 2103.69 1/
1) 8 97 1/
1) 3.10 CONTROL;.
'OCATIONS HcAN (F)
RANGE SEE UQIE 2------
3786.61(
1/
1) 3786.61 -
3785 61 NUMBER OF NONROUTINE REPORTED HEASUREHENTS NOTE:
1 ~
NOHINAL LokER LIHIT OF DETECTION (LLD)
AS DESCRIBED IN TABLE 3 ~
NOTE 2 ~
HEAN AND RANGE BASED UPott DETECTABLE HEASURCHENTS ONLY~
FRACTION OF OcTECTABLE HEASUREHENTS AT SPECIFIED LOCATIONS IS INDICATED =IN PARENTHESES (F) ~
Figure 6
Cl CC CJ
'0 4J CJ 0 4J CC Cl '0 Cl 4J 44 C 00LI C0 tA C
CJ 0
4J 4J M 0 4JM 0
JJ 0 0
4J C
C 0 CJ Preoperational Phase Operational Phase AVNIAL AVERAGE 6ROSS HElA kTIVITY IN 8RI N<1t6 MATER SUPPLIES BmWrS FERRY NuCLEAR RP hT Averacrec Preonerational Phase 3
0 r
C 1
19 8 19 9
19 0 1
1 19 2
19 3P 19 30 19 4
1 5
19 6 1
7.19 8
19 9 19 0 1
1 82 1 83 1
4
)985
40 24.
22.
Fl uro 7
Direot Radiation Levels Browns Ferry Nuolear Plant Oneito
~ Offsets 14; 12'976 1 977 1 978, 1 979 1 980 1981 1 982 1 983 1 984.
1 985.
1 986.
22.
Figure 8 Direat Radiation Levels Browne Ferry Nuolear Plant 4-Quarter Hovine Averase
+
Onomato D Offsets 14.
12.
1 9 16 1 977 1 978.
1 979.
1 980 1 98 1 1 982 1 983 1 984 1 985.
1 986.
26 24.
22.
FlguFe 9
Direct Radiation Levels Watts Bar Nuolear Plant Onoito p Offoito 4i 20.
8 1 B.
16.
14 12.
1976.
1977.
1978.
1979 1980.
1981.
1982.
1983.
1984.
1985.
1986.
26 24.
22m Flguro j0 Direct Radiation Levels Watts Bar Nuclear Plant 4-Quarter Moving Average Onomato p Offoit 16.
14.
12.
1976.
1977.
1978.
1979 1980 1981 1982 1983.
1984.
1985.
1986.
43 Reservoir Monitorin Samples are collected from various Tennessee River cross sections as detailed in table 23.
Samples collected for radiological analysis include water and plankton from three of these cross sections and bottom fauna and sediment from four cross sections.
The locations of these cross sections are shown on the accompanying map (figure ll) and conform to sediment ranges established and surveyed by TVA.
Mater Mater samples are collected automatically by sequential type sampling devices at three cross sections and composite samples analyzed monthly for gross beta and gamma-emitting radionuclides.
Further composites are made quarterly for strontium and tritium analyses.
In addition to these required
- samples, grab samples were also collected monthly from the vicinity of the plant discharge to the Tennessee
- River, and at a point on the Elk River, and analyzed for gross beta, gamma-emitting radionuclides, and strontium.
Results are displayed in table 24.
Figure 12 presents a plot of the gross beta activity in surface water from 1968 through 1985.
No gross beta measurements were made in surface water samples in 1978.
The levels reported are consistent with gross beta levels measured in surface water samples taken from the Tennessee River in preoperational monitoring programs conducted by TVA at other sites.
Fish Radiological monitoring for fish is accomplished by analysis of composite samples of adult fish taken from each of three contiguous reservoirs--Wilson,
- Wheeler, and Guntersville.
No permanent sampling stations have been established within each reservoir; this reElects the movement of fish species within reservoirs as determined by TVA data from
'he BFN preoperational monitoring program.
Two species, white crappie and smallmouth buffalo, are collected representing both commercial and game species.
Sufficient fish are collected in each reservoir to yield 250 to 300 grams oven-dry weight for analytical purposes.
All samples are collected semiannually and analyzed for gamma-emitting radionuclides.
The composite samples contain approximately the same quantity of flesh from each fish.
For each composite a subsample of material is drawn for counting.
Results are given in tables 25, 26, and 27.
Sediment Sediment samples are collected semiannually from Ponar dredge hauls made for bottom fauna.
Gamma radioactivity and Sr and Sr content are determined in composite samples collected Erom each of four stations..
Locations of these stations are shown in table 23.
Results are shown in
'table 28.
I
44 Plankton Net plankton (all phytoplankton and zooplankton caught with a l00 p mesh net) is collected for radiological analyses at each of three stations by vertical tows with a 1/2-meter net.
At least 50 grams (wet weight) of mate'rial is necessary for analytical accuracy.
Samples are collected semiannually and submitted for gross beta analysis, and when quantities are sufficient, forI gamma activity and Sr and Sr content.
During this reporting period, samples collected during the first, half of the. year contained insufficient volume for any analysis.
During the second half of the year, sufficient quantities of plankton were collected for only one gross beta analysis.
Results're presented in table 29.
II Bottom Fauna The flesh and shells. of Asiatic clams collected semiannual.).y from the cross sections at four stations ]table 23) are analyzed for gamma-emitting radionuclides.
levels of Sr and Sr are determined on the shells',
and on the flesh when sufficient amounts were available.
A 50-gram (wet weight) sample provides sufficient activity for counting.
Results are given in tables 30 and 34.
Clams from one location were not available; and from two locations, insufficient quantities were collected to permit analysis of clam flesh.
Table 23
-SAMPLING SCHEDULE RESERVOIR MONITORING Biolo ical sam les (collected semiannuall
)
Zooplankton, chlorophyll, River/river mile phytoplankton Benthic fauna Water Samples Sediment Fish (collected monthly)
Tennessee 277.9 Tennessee 285.2 Tennessee 288.7 Tennessee 291.7 Tennessee 293.5 X
X b
Tennessee 293.7 (discharge area)
Tennessee 305.0 (Control)
Tennessee 307.5 (Control)
X Elk 20.5 (Control) a.
Gill net and/or electroshocker will be used for collection.
from Guntersville,
- Wheeler, and Wilson Reservoirs.
b.
Automatic sampler.
c.
Samples of fish are collected
NAKE OF FACILITY EEQ}tUE EERILY LOCATION OF FACILITY LIQEGIQQE TABLE 24 RADIOACTIVITY IN SURFACE
'WATER TOTAL PCI/L - 0 ~ 03?
BO/L DOCKET NO. )Q:252c25Qc22O REPORTING PERIOD 1255 TYPE AND TOTAL NUMBER OF ANALYSIS PERFORHED
- ROSS ALPHA 1
ACROSS BETA 65 iAMMA (GELI) 65 K-40 BI-214 PS-214 PS-212 AC-228
>R 89 20 1R 90 20 TRITIUM 20 LOWER LIMIT pc DETECTION (LLO)
Eff UQIE 1.
F 00 2 ~ 00 NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB 15e00 10 F 00 2.00 330. 00 ALL INDICATOR LOCATIONS MEAN (F)
RANGE Eff UQIE 2
0 VALUES <LLD ANALYSIS PERFORHED 3.13(
35/
39) 2'3 -
4 3?
11 '2(
1/
39) 11.52 -
11 52 7'2(
11/
39>
0.34 -
23.29 3.08(
6/
39)
Oe?8 -
6'0 1 '4(
6/
39) 0 12 -
3.47 39 VALUcS <LLO 12 VALUES <LLD ANALYSIS PERFORHED 12 VALUES <LLO ANALYSIS PERFORMED 334 '1(
1/
12) 334 '1 334 ~ 51 TRN 293.5
- 3. 27 (
12/
13) 2.37 -
4.31 TRH Z93 F 7 BFN DISCHARGE TRH 285 '
TRH 293.7 BFN DISCHARGE TRH 285 '
11 '2(
11.52 9'7(
0 34 4'6(
- 2. 07 3 47(
3.47 1/
13) 11.52 3/
13) 22,93 3/
13) 6 30 1 /
13) 3.47 TRN 285 '
334. 51 (
1/
4) 334.51 -
334 ~ 51 l.Qt'BIIQS hIIU UIQt!EKI AiBUQht 5E65 NAHc HEAN (F)
DISTANCE ANO DIRECTION RANGE GEE UNTIE 2
CONTROL LOCATIONS MEAN (F)
RANGE SEE 9QIE 2
1 VALUES <LLO 3'4(
22/
26)
F 07 -
5'9 27 04(
3/
26) 20.68 -
39~53 10.36(
17/
26) 0'3 -
44'9
'? 29(
15/
26) 0'7 -
18'0 1 '7(
10/
26) 0'9 3'1 27.49(
1/
26)
- 27. 49 -
27'9 8
VALUES <LLO 8
VALUES <LLD 333 '8(
1/
8) 333.48 -
333.48 NUNBcR OF NONROUTINE REPORTED HEASUREHENTS NOTE:
1 ~
NOMINAL LOWER LINIT OF DETECTION (LLO)
AS OESCRIBEO IN TABLE 3 ~
NOTE 2 ~
HEAN AND RANGE SASEO UPON DETECTABLE MEASUREMENTS ONLY~
FRACTION OF DETECTABLE MEASUREN NTS AT SPECIFI D LOCATIONS IS INDICATED IN PARENTHESES (F) ~
TABLE 25 RADIOACTIVITY IN @HITE CRAPPIE (FLESH)
PCI/G - 0 ~ 03?
BG/G (ORY HEIGHT)
NAHE OF FACILITY QEQli85 EfEBI LOCATION OF FACILITY l,ICE PIQUE
- -- ki BtlMk DOCKET NO ZQ=252c2i)Qc225 REPORTING PERIOD TYPE ANO TOTAL NUHBER OF ANALYSIS PERFORHED GROSS BETA 6
GAHHA (GELI) 6 CS-13?
K-40 BI-214 PB-214 PB"212 LOMER LIHIT OF DETECTION (LLD)
Bff UQIE I 0.10 0'2 NOT ESTAB
- 0. 02 NOT ESTAB NOT ESTAB 0'8(
0 F 06 14 03(
10 ~ 81 4
VALUES 0 ~ 02(
0 ~02-0 F 00(
0 ~ OG-4/
4) 0 ~ 11 4/
4) 16 ~ 81
<LLD 1/
4) 0 F 02 1/
4)
Oo00 ALL INDICATOR LOCATIONS HEAN (F)
,RANGE SEE 5QIE 2
32'6(
4/
4) 27 58 37'5 WILSON RESERVOIR TRH 259-275 WILSON RESERVOIR TRH 259-275 0 09(
2/
2) 0'? -
0'1 14 25(
2/
2) 13 F 88 14'2 RHEELER RES TRH 2?5-649 MHEELER RES TRH 275-349 0 ~ 02(
1/
2) 0 F 02 "
0 02 Oo00(
1/
2) 0.00 -
0.00 lQQSIIQ5 liIIU UIGUEGI 6UUMhl HEST hAHE HEAN (F DISTANCE ANO DIRECTION RANGE SEE 5QIE 2
WILSON RESERVOIR 32 ~ 67(
2/
2)
TRH 259-275 27.58 -
37.75 Oe09(
0'9 15 ~ 15(
14 ~ 59 0'2(
0'2 0'1(
0 ~ 01 2
VALUES 2/
2) 0'0 2/
2) 15 71 1/
2) 0'2 1/
2) 0 ~ 01
<LLO CONTROL LOCATIONS HEAR (F)
RANGE SEE hQIE ?
29+20(
2/
2) 28'7 -
29 '5 NUHBER OF NONROUT INE REPORTED HEASUREHENTS NOTF:
1 ~
NOHINAL LOAMIER LIHIT OF DETECTION (LLO)
AS DESCRIBED IN TABLE 3 ~
2.
HEAN AND RANGE BASED UPON DETECTABLE HEASUREHENTS ONLY. FRACTION OF DETECTABLE HEASUREHENTS AT SPECIFIED LOCATIONS IS INDICATEO IN PARENTHESES (F) ~
TABLE 26 RADIOACTIVITYIN SHALLMOUTH BUFFALO (FLESH)
PCI/G - 0 ~ 037 81/G (ORY WEIGHT)
NAME OF FACILITYEEQUUE EEE$ 7
DOCKET NO. Eg:2$ $c2ggc2$ ('t LOCATION OF FACILITY L,IUEEIQUE-------- -----BLBEBUB --- ------------
REPORTING PERIOD-1/55 TYPE AND TOTAL NUHBER OF ANALYSIS PERFORMED GROSS BETA 6
SAHMA (GELI) 6 C$ -137 K-40 BI-214 PS-214 PB-212 SR 89 SR 90 LOWER LIMIT OF DETECTION (LLO)
SEE UQIE 1 0 ~ 10 0'2 NOT ESTAB 0 F 02 NOT ESTAB NOT ESTAB 0
50 Oe10 ALL INDICATOR LOCATIONS HEAN (F)
RANGE SEE UQIE 2 19'3(
4/
4) 16'2 -
20 38 0'3(
2/
4) 0.03 -
0'3 9'5(
4/
4) 8'5 -
11 '0 4 VALUES <LLO 0'4(
1/
4) 0 F 04 -
0 F 04 0 F 00(
2/
4) 0.00 -
0'1 2
VALUES <LLD ANALYSIS PERFORMED 2
VALUES <LLO ANALYSIS PERFORHED WILSON RESERVOIR TRH 259-275 WHEELER RES TRH 275-349 0.03(
1/
2) 0'3 -
0 03 10 64(
2/
2) 9e37 -
11 90 WILSON RESERVOIR TRM 259-275 WHEELER RES TRH 275-349 0 04(
1/
0 ~04-0'1(
1/
0'1 2) 0 04 2)
- 0. 01 LQQBIiQU ttIIU UIQUESI BUUUBL UEBU NAME MEAN (F)
DISTANCE AND DIRECTION RANGE SEE UQIE 2
WHEELER RES 20 ~ 16(
2/
2)
TRH 275-349 ZO F 07 -
20'5 1 /
2) 0'3 2/
2) 1'0 2/
2) 0.10 2/
2) 0+08 1/
2) 0.00
<LLD 0 03(
Oe03-9.20(
7.49 0 07(
0 ~ 04 0'6(
0'4 0%00(
D.OC-0 VALUES 0
VALUES <LLD CONTROL LOCATIONS HEAtl (F)
RAttGE EEE HQIE 2
20.06(
2/
2) 18'9 -
21 22 NUHSER OF NONROUTINE REPORTED HEASUREHENTS NOTE.
NOTE:
1 ~
tiOHZNAL LOWER LZHIT OF DETECTION (LLD)
AS DESCRIBED IN TABLE 3 ~
2 ~
HEAN ANO RANGE BASED UPON OETCCTABLE MEASUREMENTS ONLY~
FRACTION OF DETECTABLE MEASUREMENTS AT SPECI"IED LOCATIONS ZS INOICATEO IN PARENTHcSES (F) ~
TABLE 27 RADIOACTIVITY IN SHALLHOUTH BUFFALO (WHOLE)
PCI/G - 0 ~ 037 BQ/G (ORY WEIGHT)
NAHc OF FACILITY EgQggg f EBB'OCATION OF FACILITY L,J5EJIQUE 8l 80858 DOCKET NO.
$ Q-7$ Pc2QQ! 2$ {j REPORTING PERIOD TYPE AND TOTAL NUHBER OF ANALYSIS PERFORMED GROSS SETA 6
GAHHA (GcLI 6
CS-137 K-40 SI-214 PB-214 PB-212 LOWER LIMIT OF DETECTION (LLO) 5 E HQIE 1
0 ~ 10 0.02 NOT ESTAB 0'2 NOT ESTAB NOT ESTAB 0'3(
0'2 7 F 08(
6'5 0'4(
0'4 0'3(
0.01 0.01(
0.00 2/
4) 0 03 4/
4)
F 00 1/
4) 0.04 4/
4) 0'4 3/
4) 0'1 ALL i
INDICATOR LOCATIONS HEAN (F)
RANGE Hf UQIE
?
17'9(
4/
4) 14.48 -
20 02 WHEELER RES TRM 275-349 WILSON RESERVOIR TRH 259-275 WHEELER RES TRM 275-349 WHEELER RES TRM 275-349 WHEELER RES TRH 275-349 WILSON RESERVOIR TRH 259-275 0 ~ 05(
0'2 7 49(
6 ~ 97 0 04(
0'4 0 05(
0'3 0.01(
Oe01 2/
2)
Oa03 2/
2) 8.00 1/
2) 0.04 2/
2) 0'4 1/
2) 0'1 LQQ8I?QU BIIU 5IQUEKI 8HBQ8L 5E85 NAHE MEAN (F)
DISTANCE ANO DIRECTION RANGE SEE 5QIE 2
17.95(
2/
2) 17 35 -
18'2 2
VALUES <LLD 11.04(
7.37 0'4(
0 04-2 VALUES 2/
2) 14.70 1/
2) 0 04
<LLD 2
VALUES <LLO CONTROL LOCATIONS HEAN (F)
RANGE Kff BQIE 2
19e59(
2/
2) 17'4 -
21,64 NUHBER OF NONROUTINE REPORTED MEASUREMENTS NOTc-.
1 ~
NOMINAL LOWER LIMIT OF DETECTION (LLO)
AS DESCRIBED IN TASLE 3 ~
NOTE:
2 ~
HEAth Ai40 RANGE BASED UPON DETECTABLE HEASUREHENTS ONl.Y ~
FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INOICATEO IN PARENTHESES (F) ~
TABLE 28 RADIOACTIVITY IN SEDIMENT PCI/G - 0 ~ 037 BQ/G (DRY biEIGHT)
NAME OF FACILITY QQQgggffBQI LOCATION OF FACILITY LI5fgIQHfhl.55555 Doc<ET No. 19=252c259c226 REPORTING PERIOD TYPE AND TOTAL NUHBER OF ANALYSIS PERFORHEO SAHHA (GELI) 14 C0-60 CS-134 CS-137 K-40 IN-65 8 I-21 4 8 I-21 2 PB-214 PB-212 RA-226 RA-224 BE-7 TL-208 AC-228 PA-234M SR 89 SR 90 LONER LIHIT OF DETECTION (LLD) ff gQIf 1 0 ~ 01 0 F 08 0'2 NOT ESTAB 0 ~ 02 0'2 0 10 NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB 0 02 Oe06 NOT ESTAB 1 '0 0'5 ALL INDICATOR LOCATIONS HEAN (F)
RANGE Nff HQIE 2 0 ~ 15(
9/
10) 0'2 -
0'3 0'1(
5/
10) 0 F 08 "
0'8 0'9(
10/
10) 0.04 -
1 '7 13 F 05(
10/
10) 7'2 -
16.'72 0 F 04(
2/
10) 0'2 D ~ 07 1%32(
10/
10) 0'6 -
1.91 1 '9(
10/
10) 0'8 -
1 '7 1 42(
10/
10)
Oe40 -
1 99 1o44(
10/
10) 0'3 -
1 '6 1 '2(
6/
10) 0 36 -
'1.34 1 ~ 20 (
5/
10) 0 ~ 35 -
1 ~ 8o 0.18(
2/
10) 0 ~ 16 -
Oe20 0.50(
10/
10) 0'5 -
0'8 1 '4(
10/
10)
Oo44 -
2.02 2o54(
2/
10) 2 18 -
2'1 6
VALUES <LLO ANALYSIS PERFORMED 0.35(
4/
6) 0.28 -
0'5 a~~ual.
Sfau MEAN (F)
RANGE LQQSIIQU l!IIU UIQUEH NAHE DISTANCE ANO DIRECTION TRM 293 '
BFN DISCHARGE TRH 293 '
BFN DISCHARGE TRM 288 '8 TRM 288 '8 TRH 293 '
BFN DISCHARGE TRH 288'8 TRH 288 ~ 0 TRM 288 78 TRM 288.78 TRH 288 0
TRH 288 '
TRM 292.7 TRM 288'8 TRH 288'8 TRH 291 '6 TRH 277'b Xff BQIE 2-----
0 ~ 21(
0 17 0,12(
0 F 08 1 ~ 08(
0 ~ 89 1o.23(
15.73 Oo07(
0 F 07 1 ~ 81(
1 79
- 1. 89(
1 '9 1.o6(
1 93 1.78(
1 ~ 60 1.34(
1e34 1 86(
1eBo 0 20(
0.20 0065(
0 63 1 ~ 79(
1eo7 2'1(
2'1 3)
OQ 23 3) 0 ~ 18 3/
2/
2) 1 ~ 27 2/
2) 1 6.72 1/
3)
- 0. 07 2/
1/
2/
2/
1/
1/
1/
2/
2/
1/
2) 1.82 1) 1 39 2) 1s99 2) 1,96 1) 1 ~ 34 1) 1 ~ 86 1)
- 0. 20 2) 0.68 2) 1 ~ 91 1)
- 2. 91 0 41(
0 3o 2)
Oo45 0 F 30(
0 ~ 17 13.00(
11 76 4
VALUES 1 ~ 12(
- 0. 98
~ 35(
1 F05 1 ~ 19(
1 ~ 01 1 ~ 27(
1 ~ 1 7 1.09(
0'8 1 ~ 50(
1e48 0 ~ 27(
0 ~ 17 0 ~ 44(
0'2 1.32(
1
~ 15 4'7(
3'6 2
VALUES Oo34(
0.34 4/
4) 0.51 4/
4) 13'9
<LLD 4/
4) 1 ~ 22 4/
4) 1.47 4/
4) 1.40 4/
4) 1~36 3/
4) 1 ~ 2 2 2/
4) 1e51 3/
4) 0 46 4/
4) 0'7 4/
4) 1 ~ 41 2/
4) 4 87
<LLO 1/
2) 0.34 CONTROL LOCATIONS HEAN (F)
RANGE fEf HQIE 2 O.OS(
2/
'4) 0.02 -
0.03 4
VALUES <LLD NUMBER OF NONROUTINE REPORTED HEASUREHENTS NOTE:
1 NOMINAL LONER LIMIT OF, DETECTION (LLO)- AS OESCRIBEO IN TABLE 3 ~
NOTE:
2 ~
HEAN AND RANGE BASED UPON DETECTABLE MEASUREHENTS ONLY~
FRACTION Ol=
IS INDICATED IN PARENTHESES (F) ~
DETECTABLE HEASUREMENTS AT SPECIFIED LOCATIONS
NAHE OF FACILITY QBQUUB EEBBI LOCATION OF FACILITY LIUEGIQUE TABLE 29 RADIOACTIVITY IN PLANKTON (SAHPLE 1)
PCI/G - 0 ~ 03?
SQ/G (ORY HEIGHT)
DOCKET NO ~ 19=222c2DQ/.225 REPORTING PERIOD TYPE AND TOTAL NUHBER OF ANALYSIS PERFORHEO GROSS SETA 1
LOAER LIHIT OF OET ECTION (LLD)
GEE UQIE 1
NOT ESTAB ALL" INDICATOR LOCATIONS HEAN (F)
RANGE BEE UQIE 2
SEE LQQSIIQU BIIU UIQUEAI 6UUMSL UEBU NAHE HEAN (F)
DISTANCE AND DIRECTION RANGE SEE UQIE 2
NOTE 3 CONTROL LOCATIONS HE AN (F)
RANGE SEE UQIE 2
34 ~ ?1 (
1/
1) 34'1 -
54.?1 NUHBER OF NONROUTINE REPORTED MEASUREHENTS NOTE:
1 ~
NOHINAL Loi(ER LIHIT OF DETECTION (LLO)
AS OESCRIBEO IN TABLE S ~
NOTE 2 ~
HEAN ANO RANGE BASED UPON DETECTABLE HEASUREMENTS ONLY~
FRACTION OF OET CTABLE HEASUREHENTS AT SPECIFIEO LOCATIONS IS INDICATED IN PARENTHESES (F) ~
NOTE:
3.
Insufficient saryle available for analysis.
TABLE 30 RADIOACTIVITY IN CLAM FLESH PCI/G - 0 ~ 037 8(4/G (ORY NEIGHT)
NAME OF FACILITY Eilgggg Efllilx LOCATION OF FACILITY l.15fggggf
ilLilg5$8 DOCKET NO ~
RQ=Z22A2kgc22g REPORTING PERIOD 1gfy TYPE ANO TOTAL NUMBER OF ANALYSIS PERFORHEO iAHHA (GELI) 12 C0-60 Z-40 ZN-65 BI-214 PB-214 P8-212 Tl.-208 AC-228 LONER LIMIT OF DETECTION (LLD)
RfE SQIE 1
0.08 NOT ESTAB 0 ~ 17 NOT cSTAB NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB 0'6(
0 ~16-4 00(
0'9 1 09(
0.64 2 40(
033-2.11 (
0 ~30-0.10(
Oi 04 0 03(
0'2 0 16(
0 15 1/
8) 0'6 5/
8) 12'3 4/
8) 1 ~ 81 8/
8) 7 ~ 42 8/
8) 6'6 5/
8) 0 21 3/
8) 0 F 05 2/
8) 0 ~ 17 TRM 293 F 7 BFN DISCHARGE TRH 288a78 TRH 293 '
BFN DISCHARGE TRH 288 '8 TRM 277'8 TRH 277 '8 TRH 291 76 TRH 293 '
BFN DISCHARGE 0.16(
0.16-12'3(
1 2 ~.43 1053(
1 ~ 24-4'0(
4 ~90-2'6(
296-0 21(
0 21 0 F 05(
0.05 Oo16(
0 ~ 15 1/
3) 0 16 1/
1) 12 43 2/
3)
-1 ~ 81 1/
1 )
4'0 1/
1) 2'6 1/
1)
- 0. 21 1/
1) 0 F 05 2/
3) 0 ~ 17 ALL INDICATOR LOCATIONS l,ggilj?Q8 itIIU PIQUE KI 4lUU!liiL 5E 8U MEAN (F)
NAHE HEAN (F)
RANGE DISTANCE AND DIRECTION RANGE off UQIE 2 Sff Ogrf 2
CONTROI.
LOCATIONS MEAN (F)
RANGE off UQXE 2
4 VALUES <LLO 1 ~ 45(
0'~
1 '0(
0 12 0'0(
0.11 0.02(-
0+02 Oe14(
0 ~ 14 4/
4) 4'6 4/
4) 4'8 3/
4) 0 25 1/
4) 0,02 1/
4) 0.14 F 82(
4/
4) 0.90 -
5.49 4
VALUES <LLD NU'IBER OF NON ROUTINE REPORTED MEASUREMENTS I
(Note 3)
NOTE NOTE:
NOTE:
1 ~
NO'IINAL LONER LIHIT OF DETECTION (LLD) AS DcSCRIBED IN TABLE 3 ~
2 ~
MEAN ANO RANGE BASED UPON DETECTABLE MEASUREMENTS ONLY ~
FRACTION OF DETECTABLE HEASUREH NTS AT SPECIFIEO LOCATIONS IS INOICATEO IN PARENTHESES (F) ~
3.
Zinc-65 in clam flesh reported to the Nuclear Regulatory Conmission on. June 25, 1985.
Samples collected in November contained no evidence of fission or activation products.
TABLE 3l RADIOACTIVITY IN CLAM SHELL PCI/G - 0 ~ 037 SQ/G (DRY FREIGHT)
NAHE OF FACILITY EBQH55 EEBBZ LOCATION OF FACILITY ggQESIQUE SL85888 DOC<ET NO ~ 29=222c25Qc225 REPORTIVG PERIOD
/PER TYPE ANO TOTAL NUHSER OF ANALYSIS PERFORMED LONER LIMIT ALL OF INDICATOR LOCATIONS DETECTION MEAN (F)
(LLD)
RANGE XEE UQXE 1 SEE UQIE 2
CONTROL LQQBIIQU eIXU tfZGuEDI 835Qhl.
HEST LOC~TI~NS NANE MEAN (F)
MEAN (F)
OIS T ANCE AND GIREC T ION RANGE RANGE SEE HQIE 2
E E UQIE 2 NUMBER OF NONROUTINE REPORTED MEASUREMENTS GAMMA (GELI) 12 CO-60 K-40 BI-214 BI-212 PB-214 PS-212 Ra-226 TL-208 AC-228 SR 89 SR 90 0 ~ 01 NOT ESTAB Oe05 OrlO 0.05 NOT ESTAB 0 F 05
- 0. 02 0'6 5 F 00 1 ~ 00 0 01(
1/
8) 0 01 -
0.01 0 ~ 13(
6/
3) 0.01 -
0 29 Oe16(
6/
3) 0'9 -
Oe28 0 ~ 12(
1/
8)
Oe12 -
0 ~ 12 0 17(
7/
3) 0'7 -
0 54 0'6(
8/
8) 0'1 -
0'6 0'1(
2/
S) 0 ~ 10 -
0 ~ 12 0 F 05(
3/
3) 0.02 -
0 F 08 0'0(
7/
8) 0 F 07 -
0'0 4
VALUES <LLD ANALYSIS PERFORNEO 1 ~ 09(
1/
4) 1 ~ 09 -
1 ~ 09 TRM 293 F 7 BFN DISCHARGE TRM 277'8 TRH 288.78 TRH 292.7 TRH 288'8 TRM 288 '8 TRH 293
'7 BFN DISCHARGE TRN 288o78 TRN 288 '8 TRH 293 '
BFN DISCHARGE 0 01(
1/
3)
Oe01 -
0.01 0.22(
1/
1) 0'2 -
0'2 0 ~ 25(
1/
1) 0'5 "
0.25 0 12(
1/
1) 0 ~ 12-0 ~ 12 0 ~ 27(
1/
1) 0.27 -
0'7 0.16(
1/
1) 0.16 -
0 ~ 16 0 ~ 12(
1/
3) 0 ~ 12-
~ 12 0.08(
1/
1)
O.OS -
0.08 0~40(
1/
1) 0'0 -
0'0 1 ~ 09(
1/
2) 1 ~ 09 "
1 ~ 09 4
VALUES <LLD 0'4(
0.09 0 ~ 19(
0'9 4
VALUES 0 ~ 17(
0.09 0 F 02(
0,01 4
VALUES 2/
4) 0.20 3/
4)-
0.35
<LLD 3/
4) 0'2 3/
4)
Oe04
<LLO VALUES <LLD 1 02(
1 02 r
1/
2) 1.02 0 13(
3/
4) 0'1 -
Or14 2
VALUES <LLD NOTE:
1 ~
NOMINAL LOWER LIMIT OF DETECTION (LLD)
AS OESCRISEO IN TABLE 3 ~
NOTE:
2 MEAN A'VO RANGE BASED UPON DETECTABLE HEASUREHENTS ONLY ~
FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATIONS IS INDICATEO IN PARENTHESES (F) ~
i54 N
Figure 11 R ESERVOIR MONITORING NETWORK Elk River N
WHEELER DAM mile 270.90 mile 277.98 Rogersville 0
mile 282.6 mile 29l.76 Athens
~mile 285.2 B.F. NUCLEAR PLANT Champion Paper Co.
0 Courtland ite 28878 mite 293.50 mile 293.70 mile 305.0 Decatur rnIle 307.52 e-Automatic Sam ler Scale of Mile8 0
Figure 12 CC 0
CCC CJ 0 CC ~
Cj Jk Cll Jl A CC 0
Cj CC 0 CJ C0 w V Preoperational Phase t
Operational Phase AHNNL AVERAGE 6ROSS SETA ACTIVITY IN SURFACE HATER BOWS FERRY i@CLEAR PLANT Average:
Preoperational Phase 6
1 77 1 78 1979 1980 1
1968 1969 1970 1971 1972 1973P 19730 1974 1975 197 9
hl 19 2 19 19 4
I9 5 a.
No gross beta measurements made in 1978.
0
57 ualit Control A quality control program has been established with the Alabama Department of Public Health Environmental Health Administration
~.
Laboratory and the Eastern Environmental Radiation Facility, Environmental Protection Agency, Montgomery, Alabama.
Samples of air, water, milk, and'vegetation collected around BFN are forwarded to these laboratories for analysis, and results are exchanged for comparison.
Data Anal sis i
The results from each sample are compared with the concentra-tions from the corresponding control stations and appropriate preopera-tional and background data to determine influences from the plant.
During this report period, concentrations in two samples were found to exceed the reporting levels as outlined in the plant Environmental Technical Specifications.
Cobalt-60 was identified in one vegetation sample collected near the site boundary in April.
No indication of the presence of cobalt-60 was observed either at the control stations or at any of the other stations around the plants.
Subsequent samples showed no indication of the presence of cobalt-60.
This single, isolated occurrence, the absence of other fission and activation products in
'the sample, and the lack of an increase in cobalt-60 releases from the plant prevented an identification of the causes for the presence of the isotope in the sample.
In May 1985, zinc-65 was identified in one sample of clam flesh taken from the Tennessee River approximately one-half 'mile downstream from the plant discharge.
No fission or activation products had been identified in this medium during the previous report period.
Followup samples collected in June revealed zinc-65 at these downstream
- stations, with highest value being about two-thirds and the other values about one-third of the concentration reported in May.
No fission or activation products were found in clam flesh samples collected in the November sample period.
The exposure to an individual consuming clam with the highest activity was calculated to be less than 0.01 mRem/year, or 0.03 percent of the annual exposure limit.
However, to the best of our knowledge clams from the Tennessee River are not harvested for human consumption, therefore, even this small exposure is unlikely to take place.
Dose estimates were made from concentrations of radioactivity found in samples of environmental media.
Media sampled include, but are not limited to, air, milk, food products, drinking water, and fish.
Inhalation and ingestion doses estimated for persons at the indicator locations were essentially identical to those determined for persons at control locations.
Greater than 95 percent of those doses were contributed by the naturally occurring radionuclide potassium-40, and by strontium-90 and cesium-137 which are long-lived radioisotopes found in fallout from nuclear weapons testing.
58 Conclusions It is concluded from the above analysis of the data and from the trend plots presented 'earlier that there were no measurable increases in the exposure to members of the general public attributable to the operation of BFN.
Indications of the presence of small quantities of fission and activation, products have been
- seen, especially in aquatic media.
Although the levels reported sometimes exceed the values reported at the corresponding control stations, they are similar to levels reported in samples co).lected in conjunction with preoperational monitoring programs being conducted by TVA at nuclear plant construction sites upstream from Browns Perry.
The radioactivity reported herein may be 'the result of fallout, fluctuations in the existing environment, or computer program artifacts, and may include small contributions from plant operations.
Any activity resulting from plant operations which may be present is generally difficult to distinguish from background.
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