ML18025A824
| ML18025A824 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 04/30/1980 |
| From: | Mills L TENNESSEE VALLEY AUTHORITY |
| To: | |
| Shared Package | |
| ML18025A823 | List: |
| References | |
| RH-80-3-BF2, NUDOCS 8005050275 | |
| Download: ML18025A824 (54) | |
Text
RH-80-3-BF2 ENVIRONMENTAL RADIOACTIVITYLEVELS BROWNS FERRY NUCLEAR PLANT ANNUAL REPORT 1979 KhKNMl(0Ãt(gH(( NPy April 1980
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CONTENTS Introduction
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Figure 1
Table 1 Table 2
Table 3
Table 4
Tennessee Valley Region Environmental Radioactivity Sampling Schedule Atmospheric and Terrestrial Monitoring Station Locations - Browns Ferry Nuclear Plant Detection Capabilities for Environmental Sample Analysis Results Obtained in Interlaboratory Comparison Program 3
4 Atmospheric Monitoring.
Figure 2 Figure 3 Figure 4 Table 5
Table 6
Table 7
Table 8
Table 9
Atmospheric and Terrestrial Monitoring Network Local Monitoring Stations Browns'Ferry Nuclear Plant Site Monitoring Stations Maximum Permissible Concentrations for Nonoccupational Exposure.
Radioactivity in Air Filter Radioactivity in Rainwater Radioactivity in Heavy Particle Fallout Radioactivity in Charcoal Filters 13 14 15 16 17 19 20 21 Terrestrial Monitoring.
23 Table 10 Radioactivity Table ll Radioactivity Table 12 Radioactivity Table 13 - Radioactivity Table 14 Radioactivity Table 15 Environmental Table 16 Radioactivity Table 17 Radioactivity ln Milk'
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in Vegetation in, Soil in Well Water in Drinking Water Gamma Radiation Levels in Food Crops in Poultry 0
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25 26 27 29 30 31 32 34 Reservoir Monitoring 35 Table 18 Figure 5
Table 19 Tabid 20 Table 21 Table 22 Table 23 Table 24 Table 25 Table 26 Sampling Schedule Reservoir Monitoring.
Reservoir Monitoring Network Radioactivity in Surface Water Radioactivity in Whitw Crappie Radioactivity in Smallmouth Buffalo (Flesh)
Radioactivity in Smallmouth Buffalo (Whole)
Radioactivity in Plankton Radioactivity in Sediment Radioactivity in Clam Flesh Radioactivity in Clam Shell
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37 38 39 40'1 42 43 44 46 47 Quality Control Data Analysis
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49 49 Conclusions 49
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ENVIRONMENTAL RADIOACTIVITYLEVELS BROWNS FERRY NUCLEAR PLANT ANNUAL REPORT 1979 Introduction The Browns Ferry Nuclear Plant (BFN), operated by the Tennessee Valley Authority, is located on a.site owned by TVA containing 840 acres of land in Limestone County, Alabama, bounded on the west and south by Wheeler Reservoir'(see figure 1).
The site is 10 miles southwest of Athens,
The plant consists of three boil'ing water reactors; each unit is rated at 3,293 MWt and 1,098 MWe.
Unit 1 achieved criticality on August 17,'1973, and began commercial opera-tion on August 1, 1974.
Unit 2 began commercial operation on March 1, 1975.
- However, a fire in the cable trays on March 22, 1975, forced the shutdown of both reactors.
Units 1 and 2 resumed operation and Unit 3 began testing in August 1976.
'Unit 3 began commercial operation in January 1977.
The preoperational environmental monitoring program established a
baseline of data on the distribution of natural and manmade radioactivity in the environment near the plant site.
- However, seasonal,
- yearly, and ran-dom variations in the data were observed.
In order to determine the potential increases in environmental radioactivity levels caused by the plant, compari-sons were made between data for indicator stations (those near the plant) and control stations (those remote from the plant), in conjunction with com-parisons with preoperational data.
Field staffs in the Division of Occupational Health and Safety, the Division of Water Resources, and the Division of Natural Resources
- Services, carried out the sampling program outlined in tables 1 and 18.
Sampling locations are shown in figures 2, 3, 4, and 5, and table 2 des-cribes the locations of the atmospheric and terrestrial monitoring stations.
All the radiochemical and instrumental analyses were conducted in a central laboratory at Muscle Shoals, Alabama.
Alpha and beta analyses were per-formed on Beckman Low Beta II and Beckman Wide Beta II low background pro-portional counters.
Two Nuclear Data (ND) Model 100 multichannel analyzer systems employing sodium iodide, NaI(T1) detectors and one ND Model 4420 in conjunction with Germanium, Ge(Li) detection
- systems, wer'e used to analyze the samples for specific gamma-emitting radionuclides.
Samples of water, vegetation, air particulates, food crops, and charcoal (specific analysis for I) are routinely counted with NaI(T1) detection systems.
If signifi-131 cant concentrations of radioisotopes are identified, or if there is a
reasonable expectation of increased radioactivity levels (such as during periods of increased fallout), these samples are counted on the Ge(Li) system.
Identification of gamma-emitting radionuclides in all other types of samples is routinely performed by analysis on the Ge(Li) system.
A TVA fabricated beta-gamma coincidence'ounting system is utilized for the determination of I<<131 concentrations in milk.
Data were entered in computer storage for processing specific to the analysis conducted.
A computer, employing an ALPHA-M least squares
- code, was used to solve multimatrix problems associated With estimating the activities of the gamma-emitting nuclides analyzed by NaI(T1).
The data obtained by Ge(Li) detectors were resolved by the ND-4420 software.
The detection capabilities for environmental sample analyses
. given as the, nominal lower limits of detection (LLD) are liste'd in Table 3.
Samples processed by NaI(T1) gamma spectroscopy were analyzed for.13 specific gamma-emitting radionuclides and radionuclide combina-tions*.
For these analyses, radionuclide combinations such as 'u and Zr-Nb are analyzed as one radionuclide.
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 naturally produced radioisotopes, such as Be,
" K, Bi, "Bi, Pb, Pb y Ra y -etc.
LLD' for the analys is of the radionucl ides 1is ted below+ are given in Table 3B.
LLD's for additional radionuclides identified by Ge(Li) analysis were calculated for each analysis and nominal values are listed in the appropriate data tables.
In the instance where an LLD has not been established, an LLD value of zero was assumed.
A notation in a table of "
values
<LLD" for an isotope with no established LLD does not imply a value less than 0; rather it indicates that the isotope was not identified in that specific group, of samples.
For each sample type, only the radionuclides for which values greater than the LLD were reported are li'sted in the data tables.
TVA's Radioanalytical Laboratory participates in the Environ-mental Radioactivity Laboratory Intercomparison Studies Pro'gram conducted by EPA-Las Vegas.
This program provides periodic cross-check samples of the type and radionuclide composition normally analyzed in 'an environ-mental monitoring program.
Routine sample handling and analysis pro-,
cedures were employed in the evaluation of these samples.
Gamma spectral analyses were performed on Nal detectors.
The results received during calendar year 1979 are shown in table 4.
The +3a limits are corrected for triplicate determinations.
- The following radionuclides and radionuclide combinations are ~uantified by the ALPHA-M least-squares computer code:
" '"Ce; Cr; I;
lus~lo6Ru'Cs's'r-Nb'o suMn.
esZn.
6oCo soK and Ba-La.
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Table 1
ENVIRORfENTAL-RADIOACTIVITYSAMPLING SCHEDULE Air Charcoal Rain-Heavy Particle River Well Public Aquatic Life station tno tron titter tilt r ter patient dail
~oe etatioa Milk Mater aeter tinter aad dedinent deeda Huscle Shoals W
Lawrenceburg W
Rogersville W
Athens Decatur W
M W
M W
M W
M W
M A
Courtland Site NW-l W
Site'N-2 W
H W
H W
M A
A Site NE-3 W
Site NW-4 W
Site WSW-5 W'
W H
W M
A Pam B
Fam Bi Fary S Pam T
~ Farm L Control Farms Onsite Well Wheeler Daa Elk River Tennessee River Chanpion Paper Co.
Various Local Ferns W - Weekly H - Monthly 8-Saaiannually A-Annually
Table 2
Atmospheric and Terrestrial Monitoring Station Locations Browns Ferry Nuclear Plant Sam le Station LM-1 BF, Northwest LM-2 BF, North LM-3 BF, Northeast LM-4 BF, Trailer Park LM-5 BF, Davis Farm PM-1 BF, Rogersville, AL PM-2 BF, Athens, AL Approximate Distance and Direction from Plant 1.0 Mile N (1.6 kilometers)
'I 0.9 Mile NNE (1.4 kilometers) 1.0 Mile NE (1.6 kilometers) 1.7 Miles NNW (2.7 kilometers) 2.5 Miles WSW (4.0 kilometers) 13.8 Miles NW (22.2 kilometers) 10.9 Miles NE (17.5 kilometers)
PM-3 BF, Decatur (Trinity), AL 8.2 Miles SSE (13.2 kilometers)
PM-4 BF, Courtland, AL RM-1 BF, Muscle Shoals, AL (Control)
RM-2 BF, Lawrenceburg, TN (Control)
Farm S
Farm B.
Farm H
Farm T Farm Bi Farm N (Control).
Farm J (Control)
Farm C (Control)
Farm Ca (Control) 10.5 Miles WSW (16.9 kilometers) 32.0 Miles W (51.5 kilometers) 4.5 Miles ENE (7.2 kilometers) 27.0 Miles NW (43.4 kilometers) 40.0 Miles NNW (64.4 kilometers) 32.0 Miles 32.0 Miles N (51.5 kilometers)
W (51.5 kilometers)
'I 40.5 Miles NNW (65.2 kilometers)
I 4.75 Miles N (7.6 kilometers) 7.0 Miles NNW (11.3 kilometers) 3.75 Miles N (6.0 kilometers) 7.0 Miles ENE (11.3 kilometers)
Table 3
DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS A.
S eciiic Anal ses NOMINAL LOWER LIMIT OF DETECTION LLD e Air Particulates
~Ctl Charcoal Fallout Water
~Ctl oCt/k
~Ct t Vegetation Soil and and grain Sediment
>~et/ ~C
~ctl, ar Fish>
clam flesh,
- plankton, I>~Ci/ ~dr
- Foods, meat, Clam shells
- poultry, Milk I>~Ci/ ~dr gC~i/k ~gt ~il Total a Cross o Cross B
lill "Sr "Sr 0.005 0.01 0.005 0.001
- 0. 01 0.4 2.0
--'.05 330 10 2
0.01
- 0. 05
- 0. 20
- 0. 25
- 0. 05 0.35 0.70 1.5 0.3 0.1 0.1 0.5 0.1 0.7 0.7 5.0 1.0 1.5 25 40 8
0.5 10 2
- AllLLD values for isotopic separations are calculated by the method developed by Pasiernack and Harley as described in HASL-300.
Factors such as sample size, decay time, chemical yield, and counting efficiency may vary for a given sample; these variations may change the LLD value for.the given sample.
The assumption is made that all samples are analyzed within one week of the collection date..
Conversion factors:
1 pCi 3.7 x 10 Bq; 1 mCi ~ 3.7 x 10 Bq.
Table 3 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS B.
Canna Anal ses NOMINAL LOWER LIMIT OF DETECTION LLD Vegetation and grain
~Ct/
dr Water and milk
~CL/L Air particulates
~ct/a NaI* ~Ge Li **
Nal ~Ce Li NaI
~Ge Li Soil and sedinent
~ct/
d Nal
~Ge Li Clam flesh Fish and plankton
~Cjl d
~ct/
dr Nai
~GLL)
Nai ~GLt
- Foods, tomatoes
- potatoes, etc.)
Ci/
vet Clan shells
~ci/
dr NaI
~Ge Li)
NaI C~eLi Meat ac=
poultry
~ci/k e:
NaI Ce(Li~
stalk lttttC
'"'Ce "Cr 1311 103 '06Ru 106Ru 134C 1370 oszr-Nb 3Szr "Nb
'oco.
6SZn ooCo oK o Ba-La 1 tk 0 Ba 140
- 0. 35 90 33 4C 44 200 90 8
50 20 150 40 90 26 40 50 '
40 15 40 10 20 5
15 5
55 15 5
40 15 9
70 20 5
30 15 400 50 25 7
38 38 0.35 0.06 0.60 0.10 0.20 0.02 0.45 0.11 0.12 0.08 0.12 0.02 0.12 0.03 0.01 0.20 0.01 0.15 0.01 0.23 0.02 0.11 0.01 0.90 0.15 0.07 0.02
- 0. 55
- 0. 22 1.10 0.47 0.35 ';09 0.65 0.51 0.20 0.33 0.20 0.06 0.20 0.11 0.05 0.23 0.05
'.20 0.05 0.25 0.11 0.17 0.06 2.50 0.68 0.34 0.08 0.03 0.02
- 0. 07
- 0. 03 0.01 0.01
- 0. 04 0.'03 0.01 0.02 0.01 0.01
- 0. 01 0.01
- 0. 01.
0.02 0.01 0.02 0.01 0.02 0.01 0.01 0.01 0.10 0.02 0.02 0.01'.35 0.06 0.60 0.10 0.20 0.02 0.45 0.11 0.12 0.08 0.12 0.02 0.12 0.03 0.01 0.20 0.01 0.15 0.01 0.23 0.02 0.11 0.01 0.90 0.15 0.07
- 0. 02 0.35
'.56 0.07
. 0.06 0.60 0.10 0.20 0.02 0.45 33 44 8
60 15 40 60 15 40 0.74 0.48 0.08 40 26 5
0.11 0.12 0.08 0.12 0.02 0.12 10 10
'0 10 10 10 0.15 0.07 0.07 0.08 0.17 0.08
- 0. 03
- 0. 01 0.01 0.01 0.02 0.01 10 5
5 5
9 5
15 10 15 10 150 15 0.20 0.15 0.23 0.11 0.90 0.15 15 10 15 10 150 15 0.30 0.10 0.07 0.02 25 7
50 15 Le
- The NaI(T1) LLD values are calculated by the method developed by Pesternack and Harley as described in HASL-300 and Nucl. Instr. Methods 91, 533-40 (1971).
These LLD values'are expected to very depending on the activities of the components in the samples.
These figures do not represent the LLD values achievable on a given sanple.
Water is counted in a 3.5-L Marinelli beaker.
Vegetation, fish, soil, and sediment are counted in a 1-pint container as dry weight.
The average dry weight is 120 grams for vegetation end 400-500 grams for soil sediment and
- fish, Meat end poultry are counted in a 1-pint container as dry veight, then corrected to vet veight using an average moisture content of
,702.
Average dry veight is Z50 grams.
Air particulates are counted in a veil crystal.
The counting system consists of a nultichannel
~ analyzer and either a 4" x 4" solid or 4" x 5" well Nel(Tl) crystal.
The counting time is 4000 seconds.
All calculations are performed by the least-squares.
computer progran ALPHA-M.
The assumption is made that all samples are analyzed within one veek of the collection date.
- oThe Ge(Li) LLD values are calculated by the method developed by Pasternack and Harley as described in HASL-300.
These LLD values are expected to, vary depending on the activities of the components in the samples.
These figures do not represent the LLD values achievable on given samples, Water is counred in either a 0.5-L or 3.5-L Marinelli beaker.
Solid samples such as soil, sediment, and clan shells are counted in a 0.5-L Marinelli beaker as dry weight.
The average dry weight is 400-500 grams.
Air filters and very small volume samples are counted in patrie dishes centered on the detector endcap.
The counting system consists of a ND-4420 multichannel analyzer and either a 252,
- 142, 16X, or 292 Ce(Li) detector.
The counting tine is normally 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
All spectral analysis is performed using the softvare provided with the ND-4420.
assumption is made that all samples are analyzed within one week of the collection date.
. Conversion factor:
1 pCi 3.7 x 10 3 Bq.
Table 4
Results Obtained in Interlaboratory Comparison Program A.
Air Filter (pCi/filter)
Gross Al ha
(+3a)
~Av.
(+3a)
~Av.
(+3a)
~Av.
Cesium-137 EPA value TVA
'(+3a)
~Av.
1/79 5
+
9 4
3/79 14 +
9 14 6/79 9 +
9 9
10/79
.10 + 9 10 18
+ 9 20 63
+ 9 64 30
+ 9 31 31
+ 9 33 6
+ 2.7 21
+ 2.7 10
+ 2.7 10 + 2.7 6
17 9
10 6+
9 21+9, 10+
9 12+9 7
18*
9
-11 Gross Al ha Gross Beta EPA value TVA EPA value TVA Date
(+3a)
~Av.
(+3a)
~Av.
B.
Mater (pCi/1)
~
(+3a)
~Av.
Strontium-90 EPA value TVA
(+3a)
~Av.
,TVA
(+3a)
~Av.
Iodine-131*
(+30)
~Av.
16
+
9 18 11/78 11,+
9 12 26
+ 9 27 12/78 1/79 6 + 9 7
16
+ 9 17 2/79 3/79 10 + 9 10 4/79 5/79 18 + 9 15 6/79 7/79 9 + 9 ll 8/79 9/79 5 + 9 8
40 +'
43 10/79 14
+ 9 14 6 + 2.7 6
23+
9 24 30
+ 2.7 26 3
+ 9 4
28
+ 2.7 25 1540+580 1480+580 1590 1300 26
+ 9 26 1560+640 1400 2030+400 2100 1280+570 1260 2270+400 2270 40
+ 7 40
- Specific analysis for I to test the procedures used for the analysis of '
in milk.
Table 4 (Contd)
Results Obtained in Interlaboratory Comparison Program C.
Gamma-Emitting Radionuclides in Water (pCi/1)
"Cr 60C 6SZn EPA value TVA EPA value TVA EPA value Date
(+3')
~Av.
(+3a)
~Av.
~Av.
(+30)
~Av.
13NCs 137Cs EPA value TVA EPA value TVA
(+3o)
~Av.
(+3a)
~Av.
10/78 2/79 6/79 10/79 117
+ 10 0+
9 0+
9 113'+ 10 150 0
0 108 23+9 9+9 47+9 6+9 24 9
48 7
82+
9 21+9 0 + 9 0+
9 78 25 0
0 46+
9 0-+ 9 0 + 9 0 +
9 42 0
0 0
25+
9 6+9 71+9 7+9 29 125
+ 10 6
12+
9 72..
0+
9
'9 11' 9
120 12 0ll D.
Tritium in Urine (pCi/1)
Date EPA value (e3al
~1VA av 12/78 3/79 6/79 9/79 2,150
+ 400 3,300
+ 600 1,610
+ 580 13,200
+ 710 2330 2350 1590 13350
Table 4 (Contd)
Results Obtained in.Interlaboratory Comparison Program E.
Milk (pCi/1) o Date 89sr EPA value TVA
(+36)
~Av.
(+3a)
~Av.
(+3a)
~Av.
137CS EPA value
(+3a)
~Av.
(+30)
~Av.
4 OK.
EPA value
-TVA
(+3o)
~Av.
1/79 4/79 7/79 10/79 33 9
38 -9 5-+9 25 +-9 33 38 5
25 19
+ 2.7 21 54
+ 5.2 61 11
+ 2.7 13 17
+ 3.5 22 105
+ 10 110 96
+
9 95 17
+ 9'1 637
+ 55'36 49
+-
9.
154
+ 14 12
+-
9 49
-+-
9 48 0-+9' 150 0+9 0
11 0+-9 0
45 0+-9 0
1560-135 1520 1560"-135 1450 1630-+3.45 1570 1470-125 1490 F.
Pood (pCi/kg wet weight) 3/79 48
+- 9 53 22
+ 2.7 27 90
+
9 91 74
+
9 73 7/79 8
+- 9 12 3
+ 1.1 7
18
+
9 16 33
+
9 35 11/79 Results not received at this time 0+9 0+-9 0
2700235 2810 0
2650225 3000
ATMOSPHERIC MONITORING The atmospheric monitoring network is divided into three groups.
Four local air monitors are located on or adjacent to the plant site in the general areas of greatest wind frequency.
One additional station is located at the point of maximum predicted off-site concentration of radionuclides based on preoperational meteorological data (see figures 3 6 4).
Four perimeter air monito'rs are located at distances out to 10 miles from the
- plant, and two remote air monitors are located at distances out to 45 miles.
These monitoring stations are shown in figure 2.
The remote monitors are used as control or baseline stations.
At each monitor, air 'is continuously pulled through a Hollingsworth and Voss HV-70 particulate filter at a regu-lated flow of 3 ft /min.
In series with, but downstream of, the particulate filter is a charcoal filter used to collect iodine.
Each monitor has a col-lection tray and storage container to obtain rainwater on a continuous basis and a horizontal platform that is covered with gummed acetate to catch and hold heavy particle fallout.
Thermoluminescent dosimeters are used to record gamma radiation levels at each remote and perimeter station.
Each of the local air monitors is fitted with a GM tube that con-tinuously scans the particulate filter.
The disintegration rate of the atmospheric 'radioactivity is continuously recorded at each station,and radio-telemetered into the plant.
Air filters are collected weekly and analyzed for gross beta activ-ity.
During this reporting period, one sample was lost. because o'f equipment malfunction.
No analyses are performed until three days after sample col-lection.
The samples are composited monthly for analysis of specific gamma-emitting radionuclides and quarterly for Sr, Sr analysis.
The results are combined for each station to obtain an annual average.
These data are presented in table 6.
With reference to table 5, which contains'the maximum permissible concentrations (MPC) recommended by 10 CFR 20 for nonoccupational
- exposure, it is seen that the maximum beta concentration is 0.15 percent MPC.
j Rainwater is collected monthly and a 3.5-liter sample analyzed for specific gamma-emitting radioisotopes and tritium.
The results are shown in'able 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.
'harcoal filters are collected and analyzed for radioiodine.
The filter is counted in a single channel analyzer system.
The data are shown in table 9, where the highest value reported is 0.04 percent MPC for
~I.
In this reporting period, two samples were accidently, destroyed, and one was lost dye to equipment malfunction.
t
13 Figure 2
ATMOSPHERIC 'AND TERRESTRIAL MONITORING NETWORK RM.2BF LAWRENCEBURB yPULASKI F AYETTEVILLE~
WILSON FLORENCE PM-IBF WHEELER ROBE SNL OAM ATHENS PM-2BF FFIEL MUSCLE SHOALS RM-IBF I.EIQHTON TUSCUMBIA COURTLANO PM-4 F
pRUSSELLVILLE BROWNS FERRY NUCLEAR PL NT OECAT R
PM-3BFO IO MILES HARTSELLE HUNTSVILLE UNT SVIL OAM 25 HALEYVILLE CULLMAN 45 MILES RAINWATER SOIL Q-ENVIRONMENTAL MONITORINB STATION NOTE: THE FOLLOWING SAMPLES ARE COLLECTED FROM EACH STATION:
AIR PARTICULATES RADIOIODINE HEAVY PARTICLE FALLOUT
LOCAL MONITORING STATIONS BROWNS FERRY NUCLEAR PLANT ATHENS U S HWY 72 BFN ALA. HWY 20 Legend Air Monitor Air Monitor 8 TLD Station TLD Station Automatic Well Sampler N
Dairy Farm N
0 I
DECATUR Scale 2
3 IMiles
Figure 4
BROWN'S FERRY NUCLEAR PLANT SITE MONITORING STATIONS
/:
/
LM-2BF LM-4BF o
X LM-IBF~
~ a l5 LEGEND
~ ATMOSPHERIC AND TERRESTRIAL MONITORS
~ TLD STATIONS.
--PLANT BOUNDRY ROADS
+ WELL E WELLS (NOT BEING SAMPLED)
IO yt
~ r
~
~
r r
~iL,~J l ~
~ ~
O A
WHEELER LAKE
/j'oI LM 5
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rrrr ter 8+ICrl ~r
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Table 5.
MAXIMUMPERMISSIBLE CONCENTRATIONS FOR NONOCCUPATIONAL,EXPOSURE Nonvolatile'beta Tritium 137CS 103$ 106R "Zr-"Nb luOBa 1uOLa
.1 31Z In Water
~Ci/1 30 3,000 3,000,000 200000 10,000 10,000 60,000 20,000.
300 MPC In Air
~Ci/m ~
100
,200,000 500
'i 200 200 1
1,000
~1,000 100 Zn
'"Mn
"-Co 88Sr 80Sr 01C 1 5uCs 5 8Co 1000000 100$ 000 308000 3,000 300 2,000,000 9,000 90,000 21000 1$ 000 300 300 30
. 80$ 000 400 2,000
'C TABLE 6 RADIOACTIVITYIN AIR FILTER PCI/M(3) 0.037 K/M(3) 7 NAME OF FACILITY BROWNS FERRY LOCATION OF FACILITY LIMESTONE ALABAMA DOCKET NO.
RH-80-3-BF-2 REPORTING PERIOD 1979 TYPE AND LOWER LIMIT TOTAL NUMBER
,OF OP ANALYSIS DETECTION PERPORMED (LLD)
ALL INDICATOR LOCATIONS MEAN ($)
RANGE NAME DISTANCE AND DIRECTION MEAN (F$
RANGE LOCATION WITH HIGHEST ANNUAL MEAN
'CONTROL LOCATION)
MEAN (P(
RANGE NUMBER OF NONROUTINE REPORTED MEASUREMENTS GROSS ALPHA 52 GROSS BETA 571 GQDiA (NAI) 122 CE-141,144 I-131 BA-140,LA-140 BE-7 GARE (GELI) 21 KWO BIr214 PB-212 "PB-214 AC-228 0.005 0.010 0.030 0.010 0.020 NOT ESTAB NOT ESTAB 0.020 NOT ESTAB NOT ESTAB NOT ESTAB
- 0. 03 (466/467) 0.01-0.15
- 0. 04 (
2/101) 0.03 0.04 0.02( 10/101) 0.01-0.04 0.02(
4/101) 0.02-0.02 0.09(100/101) 0.02-0.18 0.10(
6/ 16) 0.8-0.12 0.04(
7/ 16) 0.02-0.06 0.01(
4/ 16) 0.01-0.02 o 02( 12/ 16) 0.00-0.06 0.01(
1/ 16) 0.01-0.01 COURTLAND,, AL 10.5 MILES WSW LM-1 BFN, NORTHWEST 1.0 MILES N COURTLAND, AL 10.5 MILES WSW.
IA-3 BP NORTHEAST 1.0 MILES NE
'L$4 BP TRAILER P 1.7 MILES NNW Ikf-..3.'BF NORTHEAST 1.0 MILES NE ROGERSVILLE, AL 13.8 MILES NW LR-2 BF NORTH 0.9 MILES NNE LM-3 BP NORTHEAST 1.0 MILES NE LM-2 BF NORTH 0.9 MILES NNE 0.04( 52/ 52).
0 02-0.11 0.04(
1/ 13) 0.04-0.04 0.03(
2/ 13) 0.03-0.04 0.02(
1/ 13) 0.02-0.02 0.11( 12/ 12) 0.04-0.18 0.12(
1/
3) 0.12-0.12 0.06(
1/
4) 0.06-'. 06 0.02(
1/
3) 0.02-0.02 0.06(
1/
3) 0.06-0.06 0.01(
1/
3) 0.01-0.01 0.01(
4/ 52) 0.01-0.01 0.03(104/104) 0.02-0.09 21 VALUES <LLD 0.02(
1/ 21) 0.02-0.02 21 VALUES <LLD 0.09( 21/ 21) 0.03-0.16 0.08(
1/
5) 0.08-0.08 0.03(
1/
5) 0.03-0.03 0.01(
2/
5) 0.01-0.01 0.01(
4/
5) 0.01-0.02 5 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'easurements of specified locations is indicated in parenthesis (F).
TABLE 6 (CONTD)
RADIOACTIVITYIN AIR FILTER PCI/M(3) - 0.037 BR/M(3)
NAME OF FACILITY BROWNS FERRY LOCATION OF FACILITY LIMESTONE ALABAMA DOCKET NO.
RH-80-3-BF-2 REPORTING PERIOD 1979 TYPE AND TOTAL NUMBER OF ANALYSIS PERFORMED BE-7 SR-89 44 LOWER LIMIT OF DETECTION
~II3 NOT ESTAB 0.005 ALL INDICATOR LOCATIONS MEAN (g)
RANGE 0.09( 13/ 16) 0.03-0.16 ANALYSIS PERFORMED 36 VALUES <LLD NAME DISTANCE AND DIRECTION DECATUR, AL 8.2 MILES SSE MEAN (F)
RANGE
- 0. 11(
2/
2) 0.06.-
0.16 LOCATION WITH HIGHEST ANNUAL MEAN CONTROL LOCATION)
MEAN (F(
0.07(
4/
5) 0.05-0.09 8 VALUES <LLD NUMBER OF NONROUTINE REPORTED MEASUREMENTS SR-90 44 0.001 ANALYSIS PERFORMED 36 VALUES <LLD 0.00(
1/
8) 0.00-0.00 a.
Nominal Lower Limit of Detection (LLD) as described in Table 8.
b.
Mean and range based upon detectable measurements only.
Fraction of detectable measurements of specified locations is indicated in parentheses (F).
'C TABLE, 7 P
RADIOACTIVITYIN RAINWATER PCI/L - 0.037 BQ/L NAME OF FACILITY BROWNS PERRY LOCATION OF FACILITY LIMESTONE ALABAMA DOCKET NO.
RH-80-3-BF-2 REPORTING PERIOD 1979 TYPE AND TOTAL NUMBER OF ANALYSIS PERFORMED LOWER LIMIT OF DETECTION (LLD)
ALL INDICATOR LOCATIONS MEAN ($)
RANGE NAME DISTANCE AND DIRECTION MEAN (F(
- RANGE LOCATION WITH HIGHEST ANNUAL MEAN CONTROL LOCATION)
MEAN (F(
RANGE NUMBER OF NONROUTINE REPORTED MEASUREMENTS GAMMA (NAI) 135 I-131 BA-140,LA-140 BE-7 15.000 15.00 NOT ESTAB 24.95(
6/109) 17.90-32.70 21.10(
1/109) 21.10-21.10 46.55( 46/109) 11.60-102.40 ROGERSVILLE, AL 13.8 MILES NW LM-2 BF NORTH 0.9 MILES NE LM-1 BF NORTHWEST 1.0 MILES N 26.03
(
20.50-
'1.10(
21.10-58.45
(
12.70-3/ 12) 32.70 1/13) 21.10 6/ 10) 102.40 40.5(
1/ 26) 40.5-40.5 26 VALUES <LLD 35.79(
15/26) 7.60-61.20 GAMMA (GELI) 8 K-40 BI-214 PB-212 PB-214 BE-7 TRITIUM NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB
-93.87(
58.13-31.44(
12.97-18.81(
6.74-19.30(
6.31-65.72(
65.72-6/
8) 128.50 6/
8) 45.77 5/
8) 27.80 6/
8) 32.62 1/
8) 65.72 LM-3 BP NORTHEAST 1.0 MILES NE ROGERSVILLE, AL 13.8 MILES NW LM-1 BF NORTHWEST 1.0 MILES N ROGERSVILLE, AL 13.8 MILES NW LM-5 BF DAVIS F 2.5 MILES WSW 106.60
(
97.79-45'9 (
45.29-23.73 (
19.65-32.62
(
32.62-65.72
(
65.72-2/
2) 115.40 1/
1) 45.29 2/
3) 27.80 1/
1) 32.62 1/
1) 65.72 330.00 400.50(
2/109) 379.00-422.00 ROGERSVILLE, AL 13.8 MILES'NW 422.00
(
1/ 13) 26 VALUES <LLD 422.00-422.00 a.
Nominal Lover Limit of Detection (LLD) as described in Table 3.
b.
Mean and range based upon detectable measurements only.
Fraction of detectable measurements of specified locations is indicated in parentheses (F).
TYPE AND TOTAL NUMBER OF ANALYSIS PERFORMED TABLE 8 RADIOACTIVITYIN HEAVY PARTICLE FALLOUT MCI/KM - 3,7 K 10 BQ/KM NAME OP FACILITY BROWNS PERRY LOCATION OF PACILITY LIMESTONE ALABAMA LOWER LIMIT ALL OF Zggl~TOR ACTIONS TION WITH HIGHEST DETECTION MEAN ([)
NAME
~LU>
RANGE DISTANCE AND DIRECTION MEAN (F(
RANGE CONTROL LOCATION)
MEAN (F(
RANGB DOCKET NO.
RH-80-3-BF-2 REPORTING PERIOD 1979 NUMBER OP NONROUTINE.
~
REPORTED MEASUREMENTS GROSS BETA 143 0.050 0.25 (117/117$
0.06-1.29 LM-4 BP TRAILER P 1.7 MILES NNW 0.41 ( 13/ 13) 0.24 ( 26/ 26) 0.07-1.29 0.06-0.67 a.
Nominal Lower Limit of Detection (LLD) as described in Table 3.
b.
Mean and range based upon detectable measurements only.
Fraction of detectable measurements of specified locations is indicated in parentheses (F).
c.
A gamma spectral analysis utilizing a GeLi detector revealed only the presence of ~Be and the naturally occurring radioisotopes of bismuth and lead.
P
TABLE 9 RADIOACTIVITYIN CHARCOAL FILTERS PCI/M(3) - 0.037 BQ/M(3)
NAME OF FACILITY BROWNS FERRY LOCATION OF FACILITY LIMESTONE ALABAMA DOCKET NO.
RH-80-3>>BF-2 REPORTING PERIOD 1979 TYPE AND TOTAL-NUMBER OP ANALYSIS, PERFORMED LOWER LIMIT OF DETECTION
~I'D
. ALL INDICATOR LOCATIONS ICATION MM HIGHEST MEAN (g)
NAME RANGE DISTANCE AND DIRECTION MEAN (F(
RANGE CONTROL LOCATION)
MEAN.-(P)
NUMBER OP NONROUTINE REPORTED MEASUREMENTS Iodine in Air 569 0.010 0.02 ( 92/465) 0.01-0.04 LM-2 BF NORTH 0.9 MILES NNE 0.02 (
8/ 52) 0.01-0.03 0.02 ( 21/104) 0.01-0.03 a.
Nominal Lower Limit of Detection (LLD) as described in Table 3.
b.
Mean and ranEe based upon detectable measurements only.
Praction of detectable measurements of specified locations is indicated in parentheses (P).
t
23 Terrestrial Monitorin Milk Milk is collected from at least four of five.farms within a 10-mile radius of the plant (see figure 3), and from at least one of four control farms.
Raw milk is analyzed weekly for I,
and monthly for gamma-emitting isotopes and for radiostrontium.
The average results for each farm are shown in table 10.
Cow censuses were conducted in May and September 1979. It was determined that there are no dairy farms nearer the plant than the nearest farm being sampled.
Ve etation Vegetation is sampled quarterly at the farms from which milk is collected and analyzed for gamma-emitting radionuclides.
Approximately 1-2 kilograms of grass is broken or cut at ground level and returned for analysis.
Efforts are made to sample vegetation that is representative of the pasturage where cattle graze.
Table 11 gives the results obtained from the laboratory analyses of these samples.
Soil Soil samples are collected annually near each monitoring station to provide an indication of a long-term buildup of radioactivity in the environment.
An auger or "cookie cutter" type sampler is used to obtain samples of the top two inches (S cm) of soil. These samples are analyzed for gamma-emitting radionuclides and strontium-89 and -90.
The results are given in table 12.
Ground Water An automatic sequential-type sampling device has been installed on a well down-gradient from Browns Ferry Nuclear Plant.
A composite sam-ple from this well is analyzed for gamma-emitting radionuclides monthly and composited quarterly for determination of tritium.
A grab sample is also taken from a control well up-gradient from the plant.'he results of the analysis of well water are shown in,table 13.
Drinkin Water Potable water supplies taken from the Tennessee River in the vicinity of Browns Ferry Nuclear Plant are sampled and analyzed for gross
beta and gamma-emitting radionculides, and composited quarterly for tritium, Sr, and Sr analyses.
The first potable water supply downstream from the plant is equipped with an automatic sampler with composite samples collected and analyzed weekly.
Two additional supplies downstream and one public water supply upstream are collected by monthly grab'ampling.
Table 14 indicates the results from the analysis of drinking water samples.
The maximum beta concentration is 0.25 percent MPC.
Environmental Gamma Radiation Levels Thermoluminescent dosimeters (TLD's) are placed at nine stations around the plant near the site boundary and at the perimeter and remote air
. monitors to determine the gamma exposure rates at these locations.
The TLD's are changed every 3 months.
The quarterly gamma radiation levels determined from these TLD's are given in table 15.
Poultr and Food Cro s
Food crops and poultry raised in the vicinity of Browns Ferry Nuclear Plant and at control locations are sampled as they become available during the growing season, and analyzed for gamma-emitting radionuclides.
During this sampling period samples of corn, green
- beans, potatoes,
'tomatoes, and poultry were collected and analyzed for specific gamma-emitting radio-nuclides.
The results are given ig tables 16 and 17.
TABLE 10.
RADIOACTIVITYIN MILK PCI/L, 0.037 BQ/L NAME OF FACILITY'ROWNS FERRY LOCATION OF FACILITY LIMESTONE ALABAMA DOCKET NO.
RH-80-3-BF-2 REPORTING PERIOD 1979 TYPE AND TOTAL NUMBER OF ANALYSIS PERFORMED LOWER LIMIT OP DETECTION
~IID ALL INDICATOR LOCPIONS MEAN ($)
NAME RANGE DISTANCE AND DIRECTION MEAN (F)
CONTROL LOCATION)
MEAN (F)
RANGE NUMBER OF NONROUTINE REPORTED MEASUREMENTS GAMMA (NAI) 117 CS-137 10.000 K-40 150.00 IODINE IN MILK 0 500 456 11.01(
7/ 65) 10.20-12.80 1247.90( 65/ 65) 1047.40-1409.00 ANALYSIS PERFORMED 257 <LLD FARM T 7.0 MILES ENE FARM T 7.0 MILES ENE 11.40(
3/ 13) 11.90( '2/ 52) 10.30-12.80 11.80-12.00 1317.20(
13/ 13) 1264'i90( 52/ 52) 1208.30-1409.00 1059.62-1446.30 199 <LLD
, SR-89 117 SR-90 10.000 2.000 ANALYSIS PERFORMED 65
<LLD 4.76( 65/ 65) 2.24-9.14 PARM B 7.0 MILES NNW 5.77( 13/ 13) 2.78-8.36 52 <LLD 4.89( 41/ 52) 2.02'-
11.98 a.
Nominal Lower Limit of Detection (LLD) as described in Table 3.
b.
Mean and range based upon detectable measurements only.
Fraction of detectable measurements of specified locations is indicated in parentheses (P).
TABLE ll RADIOACTIVITYIN VEGETATION PCI/G - 0.037 +/G (DRY WEIGHT)
NAME OF FACILITY BROWNS PERRY LOCATION OP FACILITY LIMESTONE AIJQNMA DOCKET NO.
RH-80-3-BF-2 REPORTING PERIOD 1979 TYPE AND TOTAL NUMBER OP ANALYSIS PERFORMED LOWER LIMIT OP DETECTION
~IUl ALL INDICATOR ACTIONS
~TION MM HIGHEST MEAN ( )
NAME RANGE DISTANCE AND DIRECTION MEAN (P$
CONTROL LOCATION)
MEAN (F(
RANGE NUMBER OP NONROUTINE REPORTED MEASUREMENTS GROSS BETA 36 GAMMA (GELI) 36 CE-144 CE-137 K-40 TL-208 BI-214 PB-212 PB-214 AC-228 BE-7
- 0. 200 0.220 0.060 NOT ESTAB NOT ESTAB 0.100 NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB 33:13( 20/ 20) 10.51-65.55 0.35(
3/ 20) 0.31-0.39 0.10(
6/ 20) 0.07-0.14 17.82( 20/ 20) 3.33-40.56 0.10(
4/ 20) 0.09-0.12 0.42( 16/ 20) 0.11-0.82 0.14( 14/ 20) 0.02-0.33 0.28( 16/ 20) 0.02-0.68 0.29(
6/ 20) 0.18-0.57 6.75( 20/ 20) 3.92-12.65 FARM T 7.0 MILES ENE FARM S 4.75 MILES N FARM S 4.75 MILES N FARM L 5.75 MILES ENE FARM T 7.0 MILES ENE FARM L 5.75 MILES ENE FARM T 7.0 MILES ENE FARM L 5.75 MILES ENE FARM L 5.75 MILES ENE FARM BI 4.5 MILES ENE 0.39(
0.39-0.14(
0.14-21;02(
4.59-0.12(
0.12-0.52(
0.28-0.20(
0.06-0.35(
0.26-0.48(
0.39-7.46(
4.00-1/
4) 0.39 1/
4) 0.14 4/
4) 40.56 1/
4) 0.12 3/
4) 0.66 2/
4) 0.33 3/
4) 0.41 2/
4) 0.57 4/
4) 12.65 0.24 (
0.24-0.08(
0.06-18.70(
3.05-
- 0.06(
0.02-0.49(
0.16-0.12(
0.03-0.30(
0.06-0.25(
0.17-7.96(
0.52-I/ 16) 0.24 5/ 16) 0.12 16/
16) 42.38 4/ 16) 0.10 12/
16) 1.02 11/ 16) 0.23 15/ 16) 0.62 5/ 16) 0.31 16/
16) 19.22 37.37(
4/
4) 31.13( 16/ 16) 16.11-'8.26 11.07-58.96 a.
Nominal Lover Limit of Detection (LLD) as described in Table 3.
b.
Mean and range based upon detectable measurements only.
Fraction of detectable measurements of specified locations is indicated in parentheses (P).
TABLE 12 RADIOACTIVITYIN SOIL PCI/G - 0.037 BQ/G (DRY WEIGHT)
NAME OF PACILITY BROWNS PERRY LOCATION OF FACILITY LIMESTONE ALABAMA DOCKET NO.
RH-80-3-BF-2 REPORTING PERIOD 1979 TYPE AND TOTAL NUMBER OP ANALYSIS PERFORMED LOWER LIMIT OF DETECTION
~l10 ALL INDICATOR LOC)TIONS MEAN ($)
RANGE NAME DISTANCE AND DIRECTION MEAN (F$
LOCATION WITH HIGHEST ANNUAL MEAN CONTROL LOCATION)
MEAN (F$
RANGE NUMBER OF NONROVTINE REPORTED MEASUREMENTS GA)OQ. (GELI) 11 CS-137 K-40 TL-208
'BI-212
, BI-214 PB-212 PB-214 RA-226 AC-228 0.020 0.250 0.020 0.100 0.050 NOT ESTAB 0.050 0.050 0.060 0.56(
9/
9) 0.07-1.73 6.41(
9/
9) 4.18-9.19 0.41(
9/
9) 0.21-0.53 0.80(
9/
9) 0.42-1.03 1 ~ 15'(
9/
9) 0.75-1.50 1.00(
9/
9) 0.52-'
1.34
- 1. 17(
- 9/
9) 0.75-1.51 1.15(
0/
9) 0.75-1;50 1.24(
9/
9) 0.67-1.65 ATHENS, AL 10.9 MILES NE LM-1 BF NORTHWEST 1.0 MILE N LM-4 BF TRAILER P 1.7 MILES NNW DECATUR, AL 8.2 MILES SSE LM-4 BP TRAILER P 1.7 MILES NNW DECATUR, AL 8.2 MILES SSE IMA BF TRAILER P 1.7 MILES NNW LM-4 BF TRAILER P 1.7 MILES NNW DECATUR, AL 8.2 MILES SSE, 1.73(
l.73-9.19(
9.19-0.53(
0.53-1.03(
1.03-1.50(
1.50-.
1.34(
1.34 1.51(
1.51-1.50(
1.50-1.65(
1.65 1/
1) 1.73 1/
1) 9.19 1/
1) 0.53 1/
1) 1.03 1/
1) 1.50
~
1/
1) 1.34 1/
1) 1.51 1/
1) 1.50 1/
1) 1.65 1.44('/
2) 1.20-
, 1.67 5.86(
2/
2) 5.59-6.14 0.35(
2/
2) 0.31-0.38 0.65(
2/
2) 0.55-
. 0.76 1.05(
2/
2) 0.96-
.1.15 0.88(
2/
2) 0.82-0.94 1.07(
2/
2) 0.94-1.20 1.05(
2/
2) a,96-1.15 1.09(
2/
2) 0.99-1.20 a.
Nominal Lower Limit of Detection (LLD) as described in Table 3.
b.
Mean and range based upon detectable measurements only.
Fraction of detectable measurements of specified locations is indicated in parentlieses (F).
TABLE 12 (CONTD)
RADIOACTIVITYIN SOIL PCI/G 0.037 BQ/G (DRY WEIGHT)
NAME OF FACILITY BROWNS PERRY IAKATIONOF PACILITY LIMESTONE ALABAMA DOCKET NOi RH-80-3-BP-2 REPORTING PERIOD 1979 TYPE AND TOTAL NUMBER OP ANALYSIS PERFORMED LOWER LIMIT OF DETECTION
~IID ALL INDICATOR IggPZONS
~TION MM HI~ST MEAN ($)
NAME RANGE DISTANCE AND DIRECTION MEAN (F)
CONTROL LOCATION)
MEAN (F(
NUMBER OF NONROUTINE REPORTED MEASUREMENTS SR-89 11 SR-90 11 1.500 0.300 ANALYSIS PERFORMED 9 VALUES LLD 0.43(
1/
9) 0.43-0.43 LM-1 BF NORTHWEST 1.0 MILE N 2 VALUES <LID 0.43(
1/
1) 2 VALUES <LLD 0.43-0.43 a.
Nominal Lower Limit of Detection (LLD) as described in Table 3.
b.
Mean and range based upon detectable measurements only.
Fraction of detectable measurements of specified locations is indicated in parentheses (F).
TABLE 13 RADIOACTIVITYIN WELL WATER PCI/L 0.037 BQ/L NAME OP FACILITY BROWNS FERRY LOCATION OP FACILITY LIMESTONE ALABAMA DOCKET NO.
RH-80-3-BF-2 REPORTING PERIOD 1979 TYPE AND TOTAL NUMBER OF ANALYSIS PERFORMED GAMMA (NAI) 24 LOWER LIMIT OF DETECTION
~I1D ALL INDICATOR ~TIONS LOCATION ITH HIGHEST MEAN (g)
~ NAME RANGE DISTANCE AND DIRECTION ANALYSIS PERFORMED 11 VALUES <LLD MEAN (P)
RANGE CONTROL LOCATION)
MEAN (F)
RANGE 13 VALUES <LLD NUMBER OF NONROUTINE REPORTED MEASUREMENTS GAMMA (GELI) 2 K-40 BI-214 PB-214 NOT ESTAB NOT ESTAB NOT ESTAB 70.90(
70.90-13.80(
13.80-11.26(
11.26-1/
2) 70.90 1/
2) 13.80 1/
2) 11.26 BROWNS FERRY WELL 86 BROWNS PERRY WELL F6 BROWNS FERRY WELL t6 70.90(
70.90-13.80(
13.80-11.26(
11.26-1/
2) 70.90 1/
2) 13/80 1/
2) 11.26 TRITIUM 8
330.00 537. 00 (
1/
4) 537.00-537.00 BROWNS PERRY WELL 86 537.00(
1/
4) 361.00(
1/
4) 537.00-537.00 361.00-361.00 a.
Hominal Lover Limit of Detection (LLD) as described in Table 3.
b.
Mean and range based upon detectable measurements only.
Praction of detectable measurements of specified locations is indicated in parentheses (F).
TABLE 14 RADIOACTIVITYIN DRINKING WATER PCI/L 0.037 BQ/L NAME OF FACILITY BROWNS PERRY LOCATION OP FACILITY LIMESTONE ALABAMA DOCKET NO.
RH-80-3-BF-2 REPORTING PERIOD 1979 TYPE AND TOTAL NUMBER OF ANALYSIS PERFORMED LOWER LIMIT OF DETECTION
~LID
~IVOR ~PZONS MEAN (g)
NAME RANGE DISTANCE AND DIRECTION MEAN (F)
CONTROL LOCATION)
MEAN (F$
RANGE NUMBER OF NONROUTINE REPORTED MEASUREHENTS GROSS BETA 91 GAMMA (NAI) 86 GAMMA (GELI) 5 K-40 BI-214 PB-212 PB-214 SR-89 16 SR-90 16 TRITIUM 16 2.400 NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB 10.000 2.000 330.000 3.71( 48/ 78) 2.40-7.42 ANALYSIS PERFORMED 75 VALUES <LLD 153.70(
3/
3) 89.19-281.60 15.73(
1/ 13) 15.73-15.73 4.46(
1/
3)'.46-4.46 ANALYSIS PERFORMED 3 VALUES CLLD ANALYSIS PERFORMED 12 VALUES <LLD ANALYSIS PERFORMED "12 VALUES <LLD 403.67(
3/ 12) 377.00-453.00 CHAMPION PAPER TRM 282.6 CHAMPION PAPER TRM 282.6 CHAMPION PAPER TRM 282.6 CHAMPION PAPER TRM 282.6 SHEFFIELD, AL TRM 254.3 3.92( 38/ 52) 2.40-7.42 3.11(
4/ 13) 2.47-3.62 11 VALUES WLD 153.70(
89.19-15.73(
15.73-4.46(
4.46 3/
3) 281.60 1/
3) 15.73 1/
3) 4.46 96.07(
96.07-44.48(
44.48-24.72(
24.72-19.04(
19.04-1/
2) 96.07 1/
2)'4.48 1/
2) 24.72 1/
2) 19.04 4 VALUES <~LD 4 VALUES <LLD 453.00(
1/
4) 400.50(
2/
4) 453.00-
'453.00 330.00-471.00 a.
Nominal Lover Limit of Detection (LLD) as described in Table 3.
b.
Mean and ranEe based upon detectable measurements only.
Fraction of detectable measurements of specified locations is indicated in parentheses (P).
31 Table 15 ENVIRONMENTAL GAMMA RADIATION LEVELS uarter February-March 1979 Location On-Site (9)*
Maximum Minimum Average**
Environmental Gamma Radiation Levels
~/
~/
9 ~ 4
- 20. 5 6.4 14.1 7.9
+ 2.4 17.4
+ 5.2 Off-Site (6)
Maximum Minimum Average 9.4 5.9 7.9
+ 2.6
- 20. 6 13.0 17.2
+ 5.6 April-June 1979 On-Site (9)
Maximum Minimum Average 9.6 21.0 6.7 14.7 8.4
+ 2.0 18.4
+ '4.4 Off-Site (7)
Maximum Minimum Average 10.6 6.2 7.6
+ 3.0 23.2 13.5 16.6
+ 6.5 July-September 1979 On-Site (9)
Maximum Minimum Average'0.3 22.5 6.8 14.9 9.1
+ 2.6 20.0
+ 5.8 Off-Site (7)
Maximum Minimum Average October-December 1979 On-Site (9)
Maximum Minimum Average 11.6 6.8 9.1
+ 2.9
- 10. 0 7.8 9.0
+ 1.8 25". 3 15;0 20.0
+ 6.4 21.9 17.0 19.8
+ 3.9 Off-Site (7)
Maximum Minimum Average
- Number of stations (normally three
- +All averages reported
+2a 11.5 25.2 6.0 '3.1 8.0
+ 3.5 17.6
+ 7.7 TLD's at each station)
TABLE 16 RADIOACTIVITYIN FOOD CROPS PCI/KG 0.037 BQ/KG (WET WEIGHT)
NAME OF FACILITY BROWNS FERRY LOCATION OF FACILITY LIMESTONE ALABAMA DOCKET NO.
RH-80-3-BF-2 REPORTING PERIOD 1979 TYPE AND TOTAL NUMBER OF ANALYSIS PERFORMED LOWER LIMIT OF DETECTION
~IUI INDICATOR LOC)TIONS LOCATION WITH HIGHEST ANNUAL MEAN MEAN (g)
NAME MEAN (P)
RANGE DISTANCE AND DIRECTION RANGE RADIOACTIVITYIN CORN CONTROL LOCATION)
MEAN (P)
RANGE NUMBER OF NONROUTINE REPORTED MEASUREMENTS GROSS BETh 2
GAMMA (GELI) 2 K-40 25.000 NOT ESTAB 4868.'83(
1/
1) 4868.83-4868.83 1963.00(
1/
1) 1963.00-1963.00 FARM BI 4.5 MILES ENE PARM BI 4.5 MILES ENE 4868.83(
1/
1) 5228.90(
1/
1) 4868.83-4868.83 5228.90-5228.90 1963.00(
1/
1) 2349.00(
1/
1) 1963.00-1963.00 2349.00-2349.00 GROSS BETA 2
25.000 RADIOACTIVITYIN GREEN BEAHS 3669. 31(
1/
1)
PARM BI 3669.31-3669.31 4.5 MILES ENE 3669.31(
1/ 1), 4157.19(
1/
1) 3669.31-3669,31 4157.19-4157.19 GAD(A (GELI) 2 K-40 PB-212 NOT ESTAB NOT ESTAB 1711.00(
1/
1) 1711.00-1711.00 11.73( -1/
1) 11.73-11.73 FARM BI 4.5 MILES ENE FARM BI 4.5 MILES EHE 1711.00(
1/
1) 1782.00(
1/
1) 1711.00-1711.00 1782.00-1782.00 11.73(
1/
1) 11.73-11.73 1 VALUE <LLD a.
Nominal Lour Limit of Detection (LLD) as described in Table 3.
b.
Mean and range based upon detectable'measurements only.
Praction of detectable measurements of specified locations is indicated in parentheses (P).
TABLE 15 '(CONTD)
RADIOACTIVITYIN FOOD CROPS PCI/KG - 0.037 BQ/KG (WET WEIGHT)
NAME OF PACILITY BROWNS FERRY LOCATION OF PACILITY LIMESTONE ALABAMA DOCKET NO.
RH-80-3-BF-2 REPORTING PERIOD 1979 TYPE AND
LOWER LIMIT ALL TOTAL NUMBER OP INDICATOR LOC)TIONS OF ANALYSIS DETECTION
'EAN (g)
PEBFORMID
~LUl RANGE NAME DISTANCE AND DIRECTION MEAN (F)
RANGE LOCATION WITH HIGHEST ANNUAL MEAN CONTROL LOCATION)
MEAN (F(
RANGE NUMBER.OF NONROUTINE REPORTED MEASUREMENTS RADIOACTIVITYIN POTATOES GROSS BETA 2
GAMMA (GELI) 2 K<<40 BI-214 25.00 NOT ESTAB NOT ESTAB 3449.46(
1/
1) 3449.46-3449.46 3808.00(
1/
1) 3808.00-3808.00 ANALYSIS PERPORMED 1 VALUE
<LLD PARM BI 4.5 MILES ENE FARM BI 4.5 MILES ENE 3449.46(
1/
1) 7579.60(
1/
1) 3449.46-3449.46 7579.60-7579.60.
3808.00(
1/
1) 3704.00(
1/
1) 3808.00-3808.00 3704.00-3704.00 8.83(
1/
1) 8.83-8.83 RADIOACTIVITYIN TOMATOES GROSS BETA 2
GAMMA.GELI 2
K-40 PB-214 25.00 NOT ESTAB NOT ESTAB 2993.59(
1/
1) 2993.59-2993.59 2154.00(
1/
1) 2154.00; 2154.00 6.45(
1/
1)
'.45-6.45 FARM BI
~ 4.5 MILES ENE PARM BI 4.5 MILES ENE FARM BI 4.5 MILES ENE 2993.59(
1/
1) 5057.58(
. 1/
1) 2993.59-2993.59 5057.58-5057.58 2154.00('/
1) 2557.00(
1/
1) 2154.00-2154.00 2557.00-2557.00 6,45(. 1/ I}
6.45-6.45 1 VALUE <LID a.
Nominal Lover Limit of Detection (LLD) as described in Table 3.
b.
Mean and range based upon detectable measurements only.
Fraction of detectable measurements of specified locations is indicated
. in parentheses (P).
TABLE 17 RADIOACTIVITYIN POULTRY PCI/KG - 0.037 BQ/KG (WET WEIGHT)
NAME OP FACILITY BROWNS. PERRY LOCATION OF PACILITY LIMESTONE 'LABAMA DOCKET NON RH-80-3-BF-2 REPORTING PERIOD 1979 TYPE AND TOTAL NUMBER OF ANALYSIS PERFORMED LOWER LIMIT ALL OP INDICATOR ACTIONS LOCATION WITH HIGHEST DETECTION MEAN (g)
NAME
~UD
=
RANCE DIETANCE AND DIRECTION MEAN (P$
RANGE CONTROL LOCATION)
MEAN (F$
NUMBER OF NONROVTINE REPORTED MEASUREMENTS GROSS BETA 2
25.00 4171.80(
1/
1) 4171.80-4171.80 PARM D 2.5 MILES WSW 4171.80(
1/
1) 4430:82(
1/
1) 4171.80-4171.80 4430.82-4330.82 GlQSA (GELI) 2 K-40 BI-214 PB-212 PB-214 NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB 1750.00(
1750.00-11.22(
11.22-4.78(
4.78-10.25(
10.25-1/
1) 1750.00 1/
1) 11.22 1/
1) 4.78 1/
1) 10.25 FARM D 2.5 MILES WSW FARM D 2.5 MILES WSW PARM D 2.5 MILES WSW PARM D 2 ~ 5 MILES WSW 1750.00(
1750.00-11.22(
11.22-4.78(
4.78-10.25(
10.25-1/
1) 1750.00 1/
1) 11.22 1/
1) 4.78 1/
1) 10.25 1440.00(
1440.00-17.88(
17.88-6.06(
6.06-14.60(
14.60-1/
1) 1440.00 1/
1) 17.88 1/
1) 6.06 1/
1) 14.'60 a.
Nominal Lover Limit of Detection (LLD) as described in Table 3.
b.
Mean and range based upon detectable measurements only.
Fraction of detectable measurements of specified locations is indicated in parentheses (P).
35 Reser'voir Monitorin Samples are collected from the Tennessee River as detailed in table 18.
Samples collected for radiological analysis include plankton from three of these cross sections and bottom fauna and sediment from four cross sections.
The locations of these cross sections are shown on the accompanying map (figure 5) and conform to sediment ranges established and surveyed by the Data Services
- Branch, TVA.
Water
~
Water samples are collected automatically by sequential type sampling devices at thr'ee cross sections and composite samples analyzed monthly for gamma-emitting radionuclides.
Further composites are made quarterly for strontium and tritium analyses.
Sampling locations are shown in table 18.
In addition to these required
- samples, grab samples were also collected monthly from the vicinity of the plant discharge to the Tennessee River, and at a point on the Elk River, and analyzed for gross beta, gamma-emitting radionuclides, and strontium.
During this reporting period, gross beta analyses were not performed on three of these grab samples and strontium analyses were not performed on five of
, them.
Results are displayed in table 19.
Fish Radiological monitoring for fish is accomplished by analysis of composite samples of adult fish taken from each of three contiguous reser-voirsWilson, Wheeler, and Guntersville.
No permanent sampling stations have been established within'ach reservoir; this reflects the movement of fish species within reservoirs as determined by TVA data from the Browns Ferry Nuclear Plant preoperational monitoring program.
Two species, white crappie and smallmouth buffalo, are collected representing both commercial and game species.
Sufficient fish are collected in each reservoir to yield 250 to 300 grams oven-dry weight for analytical purposes.
All samples are collected semiannually and analyzed for gamma-emitting radionuclides.
The composite samples contain approximately the same quantity of flesh from each fish.
For each composite a subsample of material is drawn for counting.
Results are given in tables 20, 21, and 22.
Plankton As indicated 'in table 18, net plankton (all phytoplankton and zooplankton caught with a 100 p mesh net) is collected for radiological analyses at each of three stations by vertical tows with a 1/2-meter net.
At least 50 grams (wet weight) of material is necessary for analytical
36 t
accuracy.
Samples are collected semiannually and analyzed for gross beta activity, and when.quantities are sufficient, for gamma activity and Sr and Sr content.
During this reporting period, two samples did not con-tain sufficient material.for gross beta analysis and none contained suffi-cient material for strontium or gamma analysis.
Results are shown in table 23.
Sediment Sediment samples are collected from Ponar dredge hauls made for bottom fauna.
Gamma radioactivity and Sr and Sr content are determined
-semiannually in composite samples collected from each of four stations.
Locations of. these stations are shown in table 18.
Results are shown in table 24.
Bottom Fauna The flesh,and shells of Asiatic clams collected semiannually from the cross sections at four. stations (table 18) are analyzed for gamma-emitting radionuclides.
Levels of Sr and 'r are determined on the
- shells, and on the flesh when sufficient amounts were available.
A 50-gram (wet 'weight) sample provides sufficient activity for counting.
Results are given in tables 25 and 26.
Table 18 SAMPLING SCHEDULE RESERVOIR MONITORING Biolo ical sam les collected semiannuall River/river mile Zooplankton, chlorophyll, h to lankton Benthic fauna a
Sediment Fish Water samples (collected monthl Tennessee 277.98 Tennessee 285.2 Tennessee 288.78 Tennessee 291.76 Tennessee 293.5 X
X Tennessee 293.70 (discharge area)
Tennessee 305.0 b-Tennessee 307. 52 Elk 20.5 a.
Gill net and/or electroshocker will be used for collection.
from Guntersville,
- Wheeler, and Wilson Reservoirs.
b.
Automatic sampler.
c.
Samples of fish are collected
38 Figure 5
R ESERVOIR MONITORING NETWORK Elk River N
WHEELER DAIVI mile 274.90 mile 277.98 Rogersville 0
mile 282.6 mile 29l.76 Athens 0
~mite 285.2 B.F. NUCLEAR PLANT Champion Paper Co, Cour tland le 28878 mite 293.50 mile 295.70 0
Decatur mile 305.0
~ - Automatic Sam ler rnite 307.52 Scale of Miles
'6 TABLE 19 RADIOACTIVITYIN SURPACE WATER PCI/L 0.037 BQ/L NAME.OP FACILITY BROWNS PERRY LOCATION OF FACILITY LIMESTONE ALABAMA DOCKET NO.
RH-80-3-BF-2 REPORTING PERIOD 1979 TYPE AND TOTAL NUMBER OF ANALYSIS, PERFORMED LOWER LIMIT OP DETECTION
~IID)
ALL INDICATOR ACTIONS LOCATION WITH HIGHEST MEAN (g)
NAME RANGE DISTANCE AND DIRECTION MEAN (F)
CONTROL LOCATION)
MEAN (F$
RANGE NUMBER OF NONROUTINE REPORTED MEASUREMENTS GROSS BETA 23 2.400 GA%fA (NAI) 57 BA-140,LA-140 15.000 GAMMA (GELI) 3,05( 10/ 12) 2.41-3.77 ANALYSIS PERFORMED 34 VALUES <LLD TRM 293.7 2.97( 10/ 12) 2.41-3.77 4.56(
9/ 11) 2.41-
- 9. 11 15.00(
1/ 23) 15.00-15.00 K-40 BI-214 PB-212 PB-214 NOT ESTAB NOT ESTAB
~
NOT ESTAB NOT ESTAB 86.51(
78.67-20.52(
9.78-6.82(
6.82-17.54(
13.79-3/
5) 97.89 3/
5) 36.74 1/
5) 6.82 2/
5) 21.29 TRM 293.7 TRM 285.2 TRM 285.2 TRM 285.2 97.89(, 1/
1) 97.89-97.89 20.52(
3/
4) 9.78-36.74 6.82(
1/
4) 6.82-
,6.82 17.54(
2/
4) 13.79-21.29 169.65(
116.60-26:14(
18.77-18.94(
18.94 18.29(
15.85-2/
3) 222.70 2/
3) 33.50 1/
3) 18.94 2/
3) 20.73 SR-89 SR-90 TRITIUM 10.000 33 2.000 33 ANALYSIS PERFORMED 19 VALUES <LLD ANALYSIS PERFORMED 19 VALUES <LLD 14 VALUES <LLD 14 VALUES <LLD 8 VALUES <LLD 20 330.000 ANALYSIS PERFORMED 12 VALUES <LLD.
a.
Nominal Lover Limit of Detection (LLD) as described in Table 3.
b.
Mean and range based upon detectable measurements only.
Fraction of detectable measurements of specified locations is indicated in parentheses (F).
TABLE 20 RADIOACTIVITYIN WHITE CRAPPIE PCI/G - 0.037 BQ/G (DRY WEIGHT)
-NAME OF FACILITY BROWNS PERRY LOCATION OP PACILITY LIMESTONE ALABAMA DOCKET NO RH-80-3-BF-2 REPORTING PERIOD 1979 TYPE AND TOTAL NUMBER OF ANALYSIS PERFORMED LOWER LIMIT ALL OF INDICATOR ACTIONS DETECTIONa MEAN (g)
NAME LUl RANGE DISTANCE AND DIRECTION MEAN (F(
RANGE CONTROL LOCATION)
MEAN (F(
RANGE NUMBER OP NONROUTINE REPORTED MEASUREKBiTS GROSS BETA 6.
- 0. 100 38.52(
4/
4) 36.00-42.42 WHEELER RESERVOIR TRM 275-349 39.21(
2/
2) 36.00-42.42 34.11(
2/
2) 30.38-37.83 GAMMA (GELI) 6 CS-137 K-40 BI-214 PB-212 PB-214 0.020 NOT ESTAB 0.020 NOT ESTAB NOT ESTAB 0.12(
0.07-17.63(
12.04-0.15(
0.05-0.03(
0.03-0.10(
0.04-4/
4)
- 0. 18 4/
4) 20.82 4/
4) 0.24 1/
4) 0.03 4/
4) 0.16 WHEELER RESERVOIR TRM 275-349 WHEELER RESERVOIR TRM 275-349 WHEELER RESERVOIR TRM 275-349 WHEELER RESERVOIR TRM 275-349 WHEELER RESERVOIR TRM 275-349 0.13(
0.07-19.96(
- 19. 10~
0.16(
- 0. 10-0.03(
0.03-0.11(
0.06-2/
2) 0.18 2/
2) 20.82 2/
2) 0.22 1/
2) 0.03 2/
2) 0.16 0.20(
0.13-17.72(
17 ~42-0.23(
0.19-0.11(
0.11-0.11(
0.10-2/
2) 0.28 2/
2) 18.03 2/
2) 0.28 1/
2) 0.11
=2/
2) 0.11 a.
Nominal Lover Limit of Detection (LLD) as described in Table 3.
b.
Mean and range based upon detect'able measurements only.
Fraction of detectable measurements of specified locations is indicated in parentheses (F).
TABLE 21 RADIOACTIVITYIN, SMALLMOUTH BUFFALO (FLESH)
PCI/G --0.037 BQ/G (DRY WEIGHT)
NAME OF PACILITY BROWNS FERRY LOCATION OF FACILITY LIMESTONE ALABAMA DOCKET NO.
RH-80-3-BP-2 REPORTING PERIOD 1979 TYPE AND TOTAL NUMBER'P ANALYSIS PERFORMED GROSS BETA 6
GA101A (GELI) 6 TL-208 CS-137 K-40 BI-214 PB-212 PB-214 LOWER LIMIT OF DETECTION
~IZJl
- 0. 100 NOT ESTAB 0.020 NOT ESTAB 0.020 NOT ESTAB NOT ESTAB ALL INDICATOR LOC)TIONS MEAN (g) 35.00(
4/
4) 25.39-41.56 ANALYSIS PERFORMED 4 VALUES <LLD 0.05(
4/
4) 0.04-0.06 13.20(
4/
4) 9.28-19.36
'.23(
3/
4) 0.14-0.32 0.08(
2/
4) 0.07-0.08 0.11(
4/
4) 0.05-0.16 NAME DISTANCE AND DIRECTION WHEELER RESERVOIR TRM 275-349 MEAN (F$
36.52(
2/
2) 33.92-39.11 WHEELER RESERVOIR TRM 259-275 WHEELER RESERVOIR TRM 275-349 WHEELER RESERVOIR TRM 275-349 WHFELER RESERVOIR TRM 275-349 WHEELER RESERVOIR TRM 275-349 0.05(
0.05-16.51(
13.65-0.23(
0.14-0.08(
0.07-0.14(
- 0. 12-2/
2) 0.06 2/
2) 19.36 2/
2) 0.32 2/
2) 0.08 2/
2) 0.16 LOCATION WITH HIGHEST ANNUAL MEAN CONTROL.
LOCATION)
MEAN (P(
NUMBER OF NONROUTINE REPORTED MEASUREMENTS
- 61. 39 (
2/
2) 26.79-96'2 0.04(
2/ ')
0.03-0.05 O.DQ(
2/
2) 0.09.
0.10 11.84(
2/
2) 11.22-12.47 0.20(
2/
2) 0.22-0.23 0.12(
1/
2) 0.12-0,12
,0.20(
2/
2) 0.15-0.25 a.
Nominal Lover Limit of Detection (LLD) as described in Table 3.-
b.
Mean and range based upon detectable measurements only.
Praction of detectable measurements of specified locations is indicated in parentheses (F).
TABLE 22 RADIOACTIVITYIN SMALLMDUTH BUFFALO (WHOLE)
PCI/G - 0.037 BO/G (DRY WEIGHT)
NAME OF FACILITY BROWNS FERRY LOCATION OF FACILITY LIMESTONE ALABAMA=
DOCKET NO.
RH-80-3-BF-2 REPORTING PERIOD 1979 TYPE AND LOWER LIMIT TOTAL NUMBER OF OF ANALYSIS ~
DETECTION PERFORHED
~llD ALL INDICATOR ACTIONS MEAN ($)
RANGE NAME DISTANCE AND DIRECTION MEAN (F$
LOCATION WITH HIGHEST ANNUAL MEAN CONTROL LOCATION)
MEAN (F)
NUMBER OF NONROUTINE REPORTED MEASUREMENTS GROSS BETA 6
0..100 BI-212 BI-214 PB-212 PB-214 AC-228 0.020 NOT ESTAB NOT ESTAB 0.020 NOT ESTAB NOT ESTAB NOT ESTAB GA101A(GELI) 6 CS-137 K-40 0.05(
0.06-8.96(
6 0.25(
0.25-0.17(
0.06-0.12(
0.07-0.12(
0.06-0.08(
0.07-1/
4) 0.06 4/
4) 13.86 1/
4) 0.25 4/
4) 0.36 4/
4) 0.24 4/
4) 0.21 2/
4)
- 0. 10 38,19(
4/ 14) 3.89-30.23 WHEELER RESERVOIR TRM 275-349 WHEELER RESERVOIR TRM 275-349 WHEELER RESERVOIR TRM 275-349 WILSON RESERVOIR TRM 259-275 WHEELER RESERVOIR TRM 275-349 WHEELER RESERVOIR TRM 275-349 WHEELER, RESERVOIR TRM 275-349 WHEELER RESERVOIR TRM 275-349 18.80(
2/
2) 7.36-30.23 0.06(
1/
2) 0.06-0.06 10.85(
2/
2) 7.84-13.96 0.25(
1/
2) 0.25-0.25 0.22(
2/
2) 0.08-0.36 0.16(
2/
2) 0.08-0.24 0.13(
2/
2) 0.06-0.21 0.10(
1/
2) 0.10-.
0.10 16.93(
2/
2) 13.02-20.84 0.04(
2/
2) 0'4-0.05 8.37(
2/
2) 8.13-8.61 2 VALUES< LLD
- 0. 16(
2/
2) 0.10-0.21 0.04(
2/
2) 0.04-0.04 0.09(
2/
2) 0.07-0.11 2 VhLUES<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 parentheses (F).
TABLE 23 RADIOACTIVITYIN PLANKTON PCI/G - 0.037 BQ/G (DRY WEIGHT)
NAME OF FACILITY BROWNS, FERRY LOCATION OF FACILITY LIMESTONE ALABAMA DOCKET NO RH-80-3-BF>>2 REPORTING PERIOD 1979 TYPE AND TOTAL NUMBER OF ANALYSIS PERFORMED LOWER LIMIT OF DETECTION
~IID ALL INDICATOR LOCATIONS MEAN ($)
RANGE NAME DISTANCE AND DIRECTION MEAN (F(
LOCATION WITH HIGHEST ANNUAL MEAN CONTROL LOCATION)
MEAN (F)
RANGE NUMBER OF NONROUTINE REPORTED MEASUREMENTS GROSS BETA
- 0. 100 28.39(
2/
2) 15.08-41.69 TRM 291.7 41.69(
1/
.1)
- 41. 69-
- 41. 69 44.05 (
2/
2) 34.83-53.77 a.
Nominal Lover Limit of Detection (LLD) as described in Table 3.
b.
Mean and range based upon detectable measurements only.
Fraction of detectable measurements of specified locations is indicated in parentheses (F).
I
TABLE 24 RADIOACTIVITYIN SEDIMENT PCI/G 0.037 BQ/G (DRY WEIGHT)
NAME OP FACILITY BROWNS FERRY LOCATION OF PACILITY LIMESTONE ALABAMA DOCKET NO.
RH-80-3-BF-2 REPORTING PERIOD 1979 TYPE AND TOTAL NUMBER OF ANALYSIS PERFORMED LOWER LIMIT ALL OF IOCATION ITH H CHEST DETECTION MEAN (g)
NAME
~IXB RANGE DISTANCE AND DIRECTION MEAN (F$
CONTROL LOCATION)
MEAN (F(
NUMBER OF NONROUTINE REPORTED MEASUREMENTS GAMMA (GELI)
CO-60 CS-137 K-40 TL-208 BI-212 BI-214 PB-212 PB-214 0.010 0.020 0.250 0.020
- 0. 100 0.020 NOT ESTAB 0.050 O.ll(
0.08-1;87(
1.42-
- 15. 86(
14.51-0.61(
0.56-1.14(
1.04-1.58(
1.40-1.90(
1 ~ 63-1.64(
1.49-4/
6) 0.12 6/
6) 2.40'/
6) 17.10 6/
6) 0.66 6/
6) l.24 6/6) l.72 6/
6)
- 2. 14 6/
6) 1.83 TRM 288.78 TRM 277.98 TRM 288.78 TRM 277.98 TRM 293.70 TRM 277.98 TRM 277.98 TRM 277.98 0.12(
0.12-2.30(
2.20-
- 16. 14(
15.18-0.65(
0.65-
- 1. 16(
- l. 16-1.60(
1.50-1.94(
1.92-1.66(
1.49-1/
2) 0.12 2/
2) 2.40 2/
2) 17.10 2/
2) 0.66 2/
2) 1.17 2/
2) 1.69 2/
2) 1.96 2/
2) 1.82 0.21(
0.12-15.38(
14 ~ 93-0.53(
0.47-0.95(
0.89-1.32(
1.15-1.70(
1.44-1.40(
1.29-2/
2) 0.29 2/
2) 15.83 2/
2) 0.59 2/
2) 1.00 2/
2) 1.48 2/
2) l.97 2/
2) 1.51 2 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 parentheses.(F).
c.
The distribution of ~s Cs between indicator and control locations reported herein is comparable to the distribution reported in the preoperational monitoring program from 1968 to mid-1973.
TABLE 24 (CONTD)
RADIOACTIVITYIN SEDIMENT PCI/G - 0.037 BO/G (DRY WEIGHT)
NAME OF FACILITY BROWS FERRY LOCATION OF PACILITY LIMESTONE ALABAMA DOCKET -NO.
RH-80-3-BF-2 REPORTING PERIOD 1979 TYPE AND TOTAL NUMBER OF ANALYSIS PERFORMED LOWER LIMIT OP DETECTION (LLD)
ALL INDICATOR LOC)TIONS MEAN ($)
NAME DISTANCE AND DIRECTION MEAN (F)
LOCATION WITH HIGHEST ANNUAL MEAN CONTROL NUMBER OF LOCATION)
NONROUTINE MEAN (F(
REPORTED RANGE MEASUREMENTS RA-223 RA-226 AC-228 PA-228 SR-89 NOT ESTAB 0.050 0.060 NOT ESTAB 0.60(
1/
6) 0.60-0.60 1.58(
6/
6) 1.40-1.72 1 75(
6/
6) 1.60-1.89 0.07(
1/
6) 0.07-0.07 TRM 277.98
. TRM 277.98 TRM 277.98 TRM 288.78 0.60(
0.60-1.60(
1.50-1.83(
1.77-0.07(
0.07-1/
2) 0.60 2/
2) 1.69 2/
2) 1.89 1/
2) 0.07 2 VALUES <LLD 1.32(
2/
2) 1.15-1.48 1.56(
2/
2) 1.40-1.73 2 VALUES< LLD SR-90 1.500 0.300 ANALYSIS PERFORMED 6 VALUES <LLD 0.37(
2/.6) 0.32-0.42 TRM 293.70 0.42(
1/ 2)-
0.42-
- 0. 42 2 VALUES <LLD 2 VALUES <LLD a.
Nominal Lower Limit of Detection (LLD) as described in Table 3.
b.
Mean and range based upon detectable measurements only.
Fraction of detectable measurements of specified locations is indicated in parentheses (P).
TABLE 25 RADIOACTIVITYIN CLAM FLESH PCI/G 0.037 Bg/G (DRY WEIGHT)
NAME OF FACILITY BROGANS FERRY LOCATION OF FACILITY LIMESTONE ALABAMA DOCKET NO.
RH-80-3-BF-2 REPORTING PERIOD 1979 TYPE AND TOTAL NUMBER OF ANALYSIS PERFORMED GAMMA (GELI)
LONER LIMIT OF DETECTION
~IID INDICATOR-ACTIONS MOTION MM HIGHEST MEAN ($)
NAME RANGE DISTANCE AND DIRECTION MEAN (F)
CONTROL LOCATION)
MEAN (F(
NUMBER OF NONROUTINE REPORTED MEASUREMENTS CS-137 K-40 BI-214 PB-212 PB>>214 AC-228 TL-208 0.080 NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB NOT =ESTAB NOT ESTAB 0.33(
0.11-7.09(
5.35-1.24(
'0.77-0.68(
0.54-1.19(
0.66-0.85(
0;40-0.20(
0.16-4/
6) 0.74 6/
6) 8.07 6/
6) 1.80 6/
6) 0.86 6/
6) 1.90 4/
6)
- 1. 38 3/
6) 0.22 TRM 288.9 TRM 277.9 TRM 277 ~ 9 TRM 288.9 TRM 277.9 TRM 293.7 TRM 293.7 0.43(
0.11-8'3(
7,.98-1.29(
0.78-0.70(
0.54-1.34(
0.79-1.06(
0.74-0.22(
0.22-2/
2) 0;74 2/
2) 8.07 2/
2) 1.80 2/
2) 0.86 2/
2) 1.90 2/
2)
- 1. 38 1/
2) 0.=22 2 VALUES <LLD 9 ~ 47(
2/
2) 8.75-
- 10. 19 2.06(
2/
2) 0.88-3.24 0.58(
2/
2) 0.57-0.59 2.01(
2/
2) 1.02-3.00 1.09(
2/
2) 0.97-1.21 0.30(
2/
2) 0.14=
0.46 I
a.
Nominal Lover Limit of Detection (LUO as described in Table 3.
b.
Mean and ranEe based upon detectable measurements only.
Fraction of det'ectable. measurements of specified locations is indicated in parentheses (F).
"K-
TABLE 26 RADIOACTIVITYIN CLAM SHELL PCI/G 0.037 BQ/G (DRY WEIGHT)
NAME OF FACILITY BROWNS FERRY LOCATION OF FACILITY LIMESTONE ALABAMA DOCKET NO.
RH-80-3-BF-2 REPORTING PERIOD 1979 TYPE AND TOTAL NUMBER OF ANALYSIS PERFORMED LOWER LIMIT OF DETECTION
~LUl ALL INDICATOR LOCPIONS MEAN ($)
RANGE NAME DISTANCE AND DIRECTION MEAN (F)
LOCATION WITH HIGHEST ANNUAL MEAN CONTROL LOCATION)
MEAN (F(
NUMBER OF NONROUTINE REPORTED MEASUREMENTS GA10fA (GELI)
CO-60 CS-137 K-40 BI-212 BI-214 PB-212 PB-214 RA-226 AC-228 0.010 0.020 0.250 0.100 0.020 NOT ESTAB 0.050 NOT ESTAB 0.060 0.03(
0.03-0.04(
0.03-0.59(
0.47-0.32(
0.11-0.33(
0.17-0.37(
0.16-0.34(
0.18-0.33(
- 0. 17-0.43(
0.21-1/
6)'.03 6/
6) 0.05 6/
6)'.
90 4/
6) 0.47 6/
6) 0.66 6/
6) 0.69 6/
6) 0.65 6/
6) 0.66 6/
6) 0.78 TRM 293.7 TRM 293.7 TRM 277.9 TRM 293.7 TRM 293.7 TRM 293.7 TRM 293.7 TRM 293.7 TRM 293.7 0.03(
1/
6) 0.03-0.03 0.05(
2/
2) 0.04-0.05 0.73(
2/
2) 0.56-0.90 0.46(
2/
2) 0.45-0.47 0.58(
2/
2) 0.51-0.66 0.64(
2/
2) 0.60-0.69 0.59(
2/
2) 0.53-0.65 0.58(
2/
2) 0.51-0.66 0.77 (
2/
2) 0.77-0.78 0.03(
0.03-0.75(
0.66-0.24(
0.24-0.40(
0 ~ 39-0.36(
0.31-0.41(
.0.38-0.41(
0.41-0.44 (
0.44-1/
2) 0.03 2/
2) 0.84 1/
2) 0.24 2/
2) 0.41 2/
2) 0.42 2/
2) 0.'43 1/
2) 0.41 2/
2) 0.45 2 VALUES <LLD a.
Nominal Lover Limit of Detection (LLD) as described in Table 3.
b.
Mean and range based upon detectable measurements only.
Fraction of detectable measurements of specified locations is indicated in parentheses (F).
TABLE 26 (CONTD)
RADIOACTIVITYIN CLAM SHELL
. PCI/G - 0.037 BQ/G (DRY WEIGHT)
NAME OF FACILITY BROWNS PERRY LOCATION OF FACILITY LIMESTONE ALABAMA DOCKET NO.
RH-80-3-BF-2 REPORTING PERIOD 1979 TYPE AND TOTAL NUMBER OF ANALYSIS PERFORMED LOWER LIMIT OF DETECTION
~llJl INDICATOR LOCPIONS NAME DISTANCE AND DIRECTION MEAN (F(
RANGE LOCATION WITH HIGHEST ANNUAL MEAN CONTROL LOCATION)
MEAN (F$
NUMBER OP NONROUTINE REPORTED MEASUREMENTS TL-208 SR-89 8
SR-90 8
0.020 5.000 1.000 0.12(
6/
6) 0.06-
. 0.21 ANALYSIS PERFORMED 6
VALUES ~LLD
- 3. 91(
6/
6) 3.40-4.52 TRM 293.7 TRM 277.9 0.20(
2/
2) 0.20-0.21
=-
4.49 (
2/
2) 4'5-4.52
- 0. 13(
2/
2) 0.12-0.14 2 VALUES
<LLD 3.29(
2/
2) 2.52-4.06 a.
Nominal Lover Limit of Detection (LLD) as described in Table 3.
b.
Mean and range based upon detectable measurements only.
Fraction of detectable measurements of specified locations is indicated in parentheses (F).
ualit Control A quality control program has been established with the Alabama Department of Public Health Environmental Health Administration Laboratory and the Eastern Environmental Radiation Facility, Environmental Protection Agency, Montgomery, Alabama.
Samples of air, water, milk, and vegetation collected around the Browns Ferry Nuclear Plant are forwarded to these laboratories for analysis, and results are exchanged for comparison.
Data measured at the control stations for each medium were aver-aged for each sampling period.
In order to describe the di.stribution of control station data, a mean, standard deviation, and 3-sigma value were calculated.
We can expect, with 99 percent confidence, that background concentrations would be distributed within these limits.
This provides us the basis for comparing control and indicator data.
If the indicator data fall within the limits defined for control data, we can say, with 99 per-cent confidence, that the indicator data were not significantly affected by the nuclear plant.
If the data do not fall within the limits, we will perform further analyses to determine if the difference is attributable to the nuclear plant.
Conclusions A vast majority of the indicator station data were found to be within the distribution defined by the control station data.
The ALPHA-M least squares computer program identified concentrations slightly exceeding the limits of the control station data for a small number of radionuclides in samples from indicator stations.
Many of these values may be discounted because the error reported by the ALPHA-M program was greater than the cal-culated concentration.
The remaining isolated elevated concentrations may be the result of fallout, fluctuations in the existing environment, com-puter program artifacts, or analytical errors.
The same type of isolated high values occurred in the control station data and may be attributed to the same sources.
Dose estimates were made from concentrations of radioactivity found in samples of environmental media.
Media sampled include, but are not limited to, air, milk, meat, vegetation, drinking water, and fish.
Doses estimated for persons at the ind'icator locations were essentially identical to those determined for persons at control locations.
Greater than 99 percent of those doses were contributed by the naturally occur-ring radionuclide potassium-40, and by strontium-90 and cesium-137 which are long-lived radioisotopes found in fallout from nuclear weapon testing.
It is concluded from the above analysis of the data that there were no signif1cant increases in environmental radioactivity attributable to the. operation of Browns Ferry Nuclear Plant.