ML20054K909

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Environ Radioactivity Levels,Bellefonte Nuclear Plant, Annual Rept-1981
ML20054K909
Person / Time
Site: Bellefonte  Tennessee Valley Authority icon.png
Issue date: 06/30/1982
From:
TENNESSEE VALLEY AUTHORITY
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ML110840229 List:
References
NUDOCS 8207060275
Download: ML20054K909 (45)


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O O TENNESSEE VALLEY AllTHORITY ENVIRONMENTAL RADIOACTIVITY LEVELS BELLEFONTE NUCLEAR PLANT ANNUAL REPORT - 1981 TVA/0MS/0HS - 82/10 RADIOLOGICAL HEALTH STAFF 8207060275 820630 PDR ADOCK 05000 R

l ENVIRONMENTAL RADI0 ACTIVITY LEVELS BELLEFONTE NUCLEAR PLANT ANNUAL REPORT - 1981 TVA/0MS/0HS - 82/10 l

l June 1982

CONTENTS Page List of Tables . . . . . . . . . . . . . . . . . . . . . . . . . iii List of Figures . . . . . . . . . . . . . . . . . . . . . . . . . iv Introduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 Atmospheric Monitoring . . . . . . . . . . . . . . . . . . . . . . . 11 Terrestrial Monitoring . . . . . . . . . . . . . . . . . . . . . 21 Reservoir Monitoring . . . . . . . . . . . . . . . . . . . . . . . . 39 Quality Control. . . . . . . . . . . . . . . . . . . . . . . . . . . 45 Conclusions . . . . . . . . . . . . . . . . . . . . . . . . . . . . 45 11

LIST OF TABLES

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Page Table 1 - Environmental Radioactivity Sampling Schedule . . . . . . 3 Table 2 - Atmospheric and Terrestrial Monitoring Stations Locations . . . . . . . . . . . . . . . . . . . . . . . 4 Table 3 - Detection Capabilities for Environmental Sample '

Analysis. . . . . . . . . . . . . . . . . . . . . . . 5 Table 4 - Results Obtained in Interlaboratory Comparison Program . . . . . . . . . . . . . . . . . . . . . . . 7 Table 5 - Maximum Permissible Concentrations for Nonoccupational Exposure. .. . . . . . . . . . . .. 12 Table 6 - Radioactivity in Air Filter . . . . . . . . . . . . . . 13 Table 7 - Radioactivity in Rain Water . . . . . . . . . . . . . . 14 Table 8 - Radioactivity in Heavy Particle Fallout . . . . . . . . . 15 ,

Table 9 - Radioactivity in Charcoal Filters . . . . . . . . . . 16 Table 10 - Radioactivity in Milk . . . . . . . . . . . . . . . . . . 24 Table 11 - Radioactivity in Vegetation . . . . . . . . . . . . . . . 25 Table 12 - Radioactivity in Soil . . . . . . . .. . . . . . . . . . 26 -

Table 13 - Radioactivity in Well Water . . . . . . . . . . . . . . . 27 _

Table 14 - Radioactivity in Public Water Supply . . . . . . . . . . 28 Table 15 - Environmental Gamma Radiation Levels . . . . . . . . . . 29 Table 16 - Radioactivity in Cabbage . . . . . . . . . . . . . . . 30 Table 17 - Radioactivity in Corn . . . . . . . . . . . . . . . . . . 31 Table 18 - Radioactivity in Potatoes . . . . . . . . . . . . . . . 32 Table 19 - Radioactivity in Tomatoes . . . . . . . . . . . . . . 33 Table 20 - Radioactivity in Turnip Greens . . . . . . . . . . . . . 34 .

Table 21 - Radioactivity in Poultry . . . . . . . . . . . . . . . 35 Table 22 - Radioactivity in Surface Water . . . . . . . . . . . . .

40 Table 23 - Radioactivity in White Crappie (Flesh) . . . . . . . . . 41 =

Table 24 - Radioactivity in Smallmouth Buffalo (Flesh) . . . . . . . 42  ;

Table 25 - Radioactivity in Smallmouth Buffalo (Whole) . . . . . . 43 1

5 iii

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LIST OF FIGURES Page

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Figure 1 - Tennessee Valley Region . . . . . . . . . . . . . . . 10

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Figure 2 - Atmospheric and Terrestrial Monitoring Network . . . 17

_i a Figure 3 - BLN Site Monitoring Stations. . . . . . . . . . . . 18 ===

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Figure 4 - Annt.a1 Average Gross Beta Activity in Air --

(Particulate Filters), BLN . . . . . . . . . . . . 19 Figure 5 - Annual Average Gross Beta Activity in Drinking Water, BLN . . . . . . . . . . . . . . . . . . . . . 36 Figure 6 - TLD Locations, BLN . . . . . . . . . . . . . . . . 37 "

Figure 7 - Direct Radiation Levels, BLN . . . . . . . . . . . 38 Figure 8 - Direct Radiation Levels, BLN  :

4-Quarter Moving Average

. . . . . . . . . . . . . . 38 -

Figure 9 - Reservoir Monitoring Network . . . . . . . . . . . . 44

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iv

i ENVIRONMENTAL RADIOACTIVITY LEVELS BELLEFONTE NUCLEAR PLANT ANNUAL REPORT 1981 Introduction 1

The Bellefonte Nuclear Plant (BLN), being ccnstructed by the Tennessee Valley Authority, is located in Jackson County, Alabama, on a peninsula bounded on the west by Town Creek embayment and on the east by _

Guntersville Reservoir at Tennessee River Mile (TRM) 391.5 (see figure 1). --

The site is approximately 6 miles (10 kilometers) northeast of Scottsboro, Alabama. The plant will consist of two pressurized water reactors; each unit 2 is rated at 3,620 MWt and 1,271 MWe. Fuel load in unit 1 is scheduled for no earlier than 1983.

A preoperational environmental radiological monitoring program was implemented in August 1978. This program has the objective of establishing a baseline of data on the distribution of natural and manmade radioactivity in the environment near the plant site. This report presents the results obtained from that program during 1981.  :

a Staffs in the Radiological Health Staff and the Office of Natural Resources carried out the sampling program outlined in table 1. Sampling locations are shown in figures 2 and 3, and table 2 describes the locations of the atmospheric and terrestrial monitoring stations. All the radiochemical -

and instrumental analyses were conducted in TVA's Western Area Radiological Laboratory (WARL) located at Muscle Shoals, Alabama, and Eastern Area Radio- =

logical Laboratory (EARL) at Vonore, Tennessee, with WARL being the primary laboratory for processing samples from BLN. Alpha and beta analyses were performed on Beckman Low Beta II, Beckman Wide Beta II, and Tennelec LB5100 low background proportional counters. Nuclear Data (ND) Model 100 multi-channel analyzer systems employing sodium iodide, NaI(TE), detectors and ND Model 4420 Systems in conjuction with germanium, Ge(Li), detection systems were used to analyze the samples for specific gamma-emitting radionuclides.

At EARL an ND Model 6620 system is used with both types of detectors. Samples  ;

of water, vegetation, air particulates, food crops, and charcoal (specific analysis for 131 I) are routinely counted with NaI(TE) detection systems.

If significant concentrations of radioisotopes are identified, or if there is a reasonable expectation of increased radioactivity levels (such as during g 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. TVA-fabricated and -

Tennelec beta gamma coincidence counting systems are utilized for the determi-nation of tal l concentrations in milk. Tritium determinations are made with Beckman LS150, Beckman LS100C, and Packard Model 3250 liquid scintillation _

counting systems. -

1 mis-memmim n-ims

2 Data were entered in computer storage for processing specific to the analysis conducted. A computer, employing an ALPHA-M least-squares code, using multimatrix techniques was used to estimate the activities of the gamma-emitting nuclides analyzed by NaI(T2). The data obtained by Ge(Li) detectors were resolved by the appropriate analyzer sof tware and the metric minimization routine HYPERMET.

The detection capabilities for environmental sample analysis given as the nominal lower limits of detection (LLD) are listed in table 3. Samples processed by NaI(Tf) gamma spectroscopy were analyzed for 13 specific gamma-emitting radionuclides and radionuclide combinations". For these analyses, radionuclide combinations such as 1 3'l 6Ru and 95 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 7Be, 40K, 212Bi, 214Bi, 212Pb, 214Pb, 22cRa, etc. LLDs for the analysis of the radio-nuclides listed below" are given in table 3B. LLDs for additional radio-nuclides identified by Ge(Li) analysis were calculated for each analysis, and nominal values are listed in the appropriate data tables. In the instance where an LLD has not been established, an LLD value of zero was assumed. A notation in a table of "_ values <LLD" for an isotope with no established LLD does not imply a value less than 0; rather, it indicates that the isotope was not identified in that specific group of samples. For each sample sype, only the radionuclides for which values greater than the LLD were reported are listed in the data tables.

TVA's radioanalytical laboratories participate in the Environmental Radioactivity Laboratory Intercomparison Studies Program conducted by EPA-Las Vegas. This program provides periodic cross-check samples of the type and radionuclide composition normally analyzed in an environmental monitoring program. Routine sample handling and analysis procedures were employed in the evaluation of these samples. The results received during calendar year 1981 are shown in table 4. The i30 limits based on one measurement were divided by the square root of 3 to correct for triplicate determinations.

"The following radionuclides and radionuclide combinations are quantified by theALPHA-Mleast-squarescomgutercode:

134 Cs; 137 Cs; 95 141,144Ce; SICr; 131 1; 103,1 6 Ru; Zr-Nb; 58Co; 4 Mn; 652n; coco; 40K; and 14"Ba-La.

3 Table 1 ENVIRONMENTAL RADI0 ACTIVITY SAMPLING SCHEDULE

~

BELLEFONTE NUCLEAR PLANT Air Charcoal Rain- Heavy Particle Well Public Surface Station Location Filter Filter _ water Fallout Vegetation Milk Water Water Water Fish Site SW W W M fl Q Site NE W W M M Q Scottsboro W W M M Q M Hollywood W W M 1 Q M Fackler W W M *1 Q Stevenson W W M M Q Pisgah W W M M Q Section W W H M Q Lim Rock (Control) W W M M Q Painsville (Control) W W M M Q Farm S Q M Fara D (Control) M Farm C (Control) Q M Well A (Control) M Onsite Wells (6) M Sand Mountain Water &

& Fire Protection Authority M Widows Creek Steam Plant (Control) M Wheeler Reservoir S' C

Guntersville Reservoir Q S*

Nickajack Reservoir b (Control) S W - Weekly M - Monthly (every four weeks) Q - Quarterly S - Semiannually

" Samples collected as a part of the Browns Ferry Nuclear Plant monitoring program.

b Simples collected as a part of the Sequoyah Nuclear Plant monitoring program.

Sampling initiated in fourth quarter 1981.

4 Table 2 Atmospheric and Terrestrial Monitoring Stations Locations Bellefonte Nuclear Plant Approximate Distance Sample Station and Direction fr:2 Plant Indicator Stations LM - 1 BL, Southwest 3/4 mile (1-1/4 kilometers) SW LM - 2 BL, Northeast 1 mile (1-1/2 kilometers) NE PM - 1 BL, Scottsboro, AL 5-3/4 miles (9-1/4 kilometers) WSW PM - 2 BL, Hollywood, AL 2 miles (3-1/4 kilometers) WNW PM - 3 BL, Fackler, AL 5-1/4 miles (8-1/2 kilometers) N PM - 4 BL, Stevenson, AL 11 miles (17-3/4 kilometers) NNE PM - 5 BL, Pisgah, AL 4 miles (6-1/2 kilometers) ESE PM - 6 BL, Section, AL 9 miles (14-1/2 kilometers) SSW Fa rm S 5 miles (8 kilometers) SW Control Stations RM - 1 BL, Lim Rock, AL 18 miles (29 kilometers) W RM - 2 BL, Rainsville, AL 14-1/2 miles (23-1/3 kilometers) SSE Farm C 11-1/2 miles (18-1/2 kilometers) SSW Farm D 1 mile (1-2/3 kilometers) W Well A 1-1/2 miles (2-1/2 kilometers) NNE

Table 3 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS A. Specific Analyses NOMINAL LOWER LIMIT OF DETECTION (LLD)*

Fish, clam flesh. Foods, meat, Vegetation Soil and Milk Air Sediment plankton, Clam shells poultry. '

Char coal Fallout Water and grsin pCi/kg. we t, pC1/1 Particulates 2 pC1/l_ PC1/R. dry PCi/R, dry PC1/g. dry gC1_/g, dry pC1/m 3 __pC1/m' mC1/km 1.5 0.4 0.01 Total a 0.05 0.35 0.1 0.7 ,

0.005 2.0 0.7 25 Cross a 0.05 2.4 0.20 0.70 0.1 Cross E 0.01

'H 330 0.5 0.02 0.5 5.0 40 10

I 10 0.25 1.5 2

Sr 0.005 0.05 0.3 0.1 1.0 8 2

Sr 0.001

  • All LLD values for isotopic separations are calculated by the method developed by Pasternack and Harley as described in KASL-300.

these variations Factors such as sample size, decay time, chemical yield, and counting ef ficiency may vary for a given sample;The assumption may change the LLD value for the given sample.

collection date. Conversion factors: 1 pC1 = 3.7 x 10 8 Bq; I mC1 = 3.7 x 10' Bq.

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' s Table 3 DETECTION CAPABILITILS FOR ENVIRONMENTAL SAMPLE ANALYSIS s

B. Cama Analyses NOMINAL LOER LIMIT OF DETECTION (LLR Foods,(tomatoes Meat ad Vegetation Soil and Clam flesh Air '4ater Clan shells potatoes, etc.) poultry sediment Fish and plankton particulates and milk and grain pCi/g, dry _ pCi/ke_ wet pCi/kg wet pCi/m 3 pC1/1 pC1/g. dry _ pCi/g, dry pCi/g. dry pct /g. dry _

Nat Ge(Lt' Na1 Ge(Li) Na1 Ge(L1) Na1 Ce(L1)_ Na! Ge(L1) NaI Ce(Li)

NaI* Ce(Li)** NaI Ge(L1) Nal Ce(L1) 0.35 38 90 3B 0.55 0.35 0.35 4c 8*3'*re 0.03 0.06 0.35 0.06 33 0.22 0.06 90

Ce 0.02 33 0.60 0.10 0.56 0.60 0.10 60 44 200 "Cr 0.07 0.03 60 44 1.10 0.47 0.60 0.10 0.07 0.20 0.02 15 8 50 20 0.35 0.09 0.20 0.02 0.20 0.02

'"1 0.01 0.01 15 8 0.45 0.45 0.45 40 150

"'*3"Ru 0.04 40 0.65 0.11 40 90 0.51 0.11 0.11 0.74

'"Ru 0.03 40 0.12 0.08 10 26 40 50 0.20 0.33 0.12 0.08 0.12 0.08 0.48

Cs 0.01 0.02 10 26 0.08 0.12 0.02 10 5 40 15 0.20 0.06 0.12 0.02 0.12 0.02

Cs 0.01 0.01 10 5 0.20 0.12 0.12 0.12 10 40 0.01 10 0.03 10 20

' Z r - Nb 0.11 0.03 0.03 0.15 0.01 10 0.01 5 15 "Zr 0.01 0.01 0.07 "Nb 0.01 5 0.05 15 5 55 15 0.20 0.01 0.20 0.01 0.07 0.20 0.01

" Co 0.02 0.01 15 5 0.23 0.05 0.08 0.15 0.01 10 5 40 15 0.20 0.05 0.15 0.01 0.15 0.01 70 20 5'Mn 0.02 0.01 10 5 0.23 0.02 0.23 0.02 0.17 0.23 0.02 15 9 "In 0.02 0.01 15 9 0.25 0.11 0,08 0.11 0.G1 10 5 30 15 "Co 0.01 0.01 10 5 0.17 0.06 0.11 0.01 0.11 0.01 0.90 150 400

  • sg o,in 150 2.50 0.90 0.90 50 .

0.15 15 15 0.68 0.15 0.15 25 50 8Ba-La 0.02 0.07 0.07 0.30 0.07 0.02 25 0.34 0.02 7 15

    • 'Ba 0.08 0.02 0.02 0.10 0.01 7 a eLa
  • The NaI(TI) LLD values are calculated by the method developed by Pasternack and Harley as described la HASL-300 and Nucl. Instr. Methods 9 533-40 (1971).

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 a given sample. Water is counted in a 3.5-L Marinelli beaker. Vegetation, fish, soil, and sediment are counted in a 1-pine container as dry weight. The average dry weight is 120 grams for vegetation and 400-500 grams for soil sediment and fish. Meat and poultry are counted in a 1-pint container as dry weight, then corrected to wet weight using an average moisture content of 70%. Average dry weight is 250 grams. Air particulstes are counted in Thea well crystal.

counting time The counting is 4000 system seconds. Allconsists of a multichannel calculations are performed by analyzer and either a 4" x 4" solid or 4" x 5" well NaI(TI) crystal.The assumption is made that all samples are analyzed within one week of the collection date.

the least-squares computer program ALPHA-M.

These LLD values are expected

    • The Ge(L1) LLD values are calculated by the method developed by Pasternack and Harley as described in HASL-300.These figures do not represent th to vary depending on the activities of the components in the samples. Solid samples such as soil, sediment, and clam shells are counted in a 0.3-L Water is counted in either a 0.5-L or 3.5-L Harinelli beaker.

Marinelli beaker as dry weight. The average dry weight is 400-500 grams. Air filters and very small volume samples are counted inorpetrie 25%,14%,163, 29% Ge(L1) dishes centered on the detector endcap. The counting All system consists of a ND-4420 multichannel analyzer and either a spectral analysis is performed using the software provided with the ND-4420. The detector. The counting time is normally 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

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

Conversion factor: 1 pC1 - 3.7 x 10-2 g, q

i.-...,.. l.,,

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

Gross Alpha Gross Beta Strontium-90 Cesium-137 EPA value' TVA AVG. EPA value TVA AVG. EPA value TVA AVG. EPA value TVA AVG.

Date ( 30) WARL EARL

( 3a) . WARL EARL ( 30) WARL EARL ( 30) WARL EARL' 12/80 21 9 22 23 19 9 24 26 0 2 <2 19 9 20 22 3/81 30 13 31 31 50 9 55' 49 18 2.6 18 15

  • 14 9 15 14 ,

6/81 28 12 29 32 54 9 62 59 19 2.6 19 23 " 16 9 17 18 c 16 2.6 19 9 21 20 9/81 25!11 26 25 51 9 61 54 16 19 B. Tritium in Urine (pCi/L)

Date EPA Value ( 30) TVA AVERAGE WARL EARL 3/81 .810 549 713 390 6/81 1600 585' 1637 1830 9/81 2050 599 2103 -

11/81 27001615 2573 2623

a. Western Area Radiological Laboratory, Muscle Shoals, Alabama
b. Eastern Area Radiological Laboratory, Vonore, Tennessee
c. Efficiency curves were checked and known spikes were run. Everything found was within acceptable limits.

We are awaiting the next cross-check for further investigation.

d. Results were mailed to EPA but not. reported by them.
e. Sample was lost in analysis. There was insufficient- time to obtain another sample from EPA and reanalyze.

)

Table 4 (Contd) i -

Results Obtained in Interlaboratory Comparisoq

  • Program j.

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, < / C. Radiochemical Aulyse54of Water (pC1/L) e<

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Cross Alpha d Cross Beta . ' S t roo t ium - 89 Strontium - 90 Tritium _ T od tne - 131 ,

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EPA value TVA AVG. EPA value TVA AVG. EPA value TVA AVG. EPA value TVA AVG. EPA value TVA AVG. EJA value TVA . AVG. / -[

Date (133) WARL EARL (!33) WARi EARL ~ (t30) ,

WARL EARL", (230) WARL EARL (!3c) WARL EARL '(t37) WARL EARL /

i h * -'

1/81 9t9 10 9 44t9 49 49 j 16t9 11 14 34t3.1 388 28 2/81 1 17602591 1917 1753 '

3/81' 23t10 23 151 -,2529 26 29 '

- 7 4/81 y J 27102615 2467 2723 30 10 32 28 ' '

5/81 2129 21 4 14 ,1429 14 16 3629 40 33.

  • 22 1.6 21 22 ,

", I 6/81' , e 19502596 1990 1947 '

7/81 ,22 10 20 22 1529' a 15 18 . '

i 8/81 <i i 18, d28!9 2630t613 y / 4 2623 2713 73tt3 79 73 'f 533114 /

, 9/81 29 29 2P 23t9) 26 23 11!2.6 .11 10 _

s

/' 2210!603 2263, 2197 ,

'19/81 21 ' 13 , 23t9

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g - l ?./ 81 2129 18 24 } / t 2700!415 2717 2807 M+13 '

65 56 3 1 1 .'

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, -12/81 \.

  • 4 ,

D. Cane 5;:ectral Analysis of Water (pC1/L) ,

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Chromit=n - 51 Cobalt - 60 Zinc - W s ( Ruthenium - 106 Cesium - 134 Cesium - 137 ,

EPA value TVA AVO. EPA value TVA AVG. EPA value JVA AVG, ' EPA value TVA AVC. EPA value TVA AVG. EPA halue .TVA AVG.*

Date (t3n) VARL EARL _ t( M) WARL ; EARL J.t30) GARL EARL (t M) WARL EARL ( 37) WARL EARL , _ (t 31) 3 WARL,E3 _

2/81 0 <60 <60 25t9 25 25 8519 84 83 0 <40 <40 36t9 39 35 4t9 6 10 -

f6/81 < 0 <60 <b0 17t9 18 '17 0 <l 5 - <l5 15t9 <40 <40 2119 23 21 3129 27 30 10/81 34t9 <60 <60 22t9 25 22 24t9 26 21

  • O <40 <40 2129 21 24 32t9 35 32 Specifi<t analysis for " 8I to test the procedures used for.the analysis of milk.

f.

g. Investigations of the analytical procedure were conducted e.nd new efficiency curves were determined. Results have been satisfactory since that time. /
h. New efficiency curves were determined subsequent to this analysis. Subsequent results were' satisfactory.

3 j

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i. Excess humidity in counting room and a change in the amount of solid introduced into the sample by EPA are suspected in the difficulty with this '  !

sample type. . Steps have been taken to correct or compensate for these items. '

j. Results are possibly due to an incorrect chemical form of the precipitate counted in this procedure. Investigations continue.

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.s Table 4 (Conto)

Results Obtained in Interleboratory Comparison Program E. Milk (pC1/L) l Cesius - 137 Barium - 140 Potassium Cobalt - 60 Strontium - 89 Strontium - 90 Todice - 131 TVA AVC.

EPA value TVA AVC. EPA value TVA AVG. EPA value TVA AVG. EPA value TVA AVG. EPA value .

EPA value TVA AVG. EPA value TVA AVG. WARL EARL Dato (t h) JARL EAR? (t3c) WARL EARL (th) WARL EARL (th) WARL EARL (th) WARL EARL (t h) WARL F.ARL (? 34) _

20 26t17 24 21 43:16 'O 41 0 <25 <15 15501232 1490 1453 1/81 0 <10 <!3 2025.2 21*

  • 1122,6 13 26t10 21 29 22t9 21 24 0 <15 <15 1559t135 1583 1674 ,

4/81 25t9 28 1722.6 14* 16 .01t 3129 32 32 0 < 15 <15 1600t139 1623 1620 7/81 25t9 23 30 < 15 " < 15 15302133 1620 1500 23 9 25 28 18t2.6 17 16 52210 49 47 2529 27 27 10/81 F. Foods (pC1/kg, Wet Weight) 42 44 29t2.8 38 P 21 E 119221 126 5329 56 55 0 <15 <15 26402229 2857 2?!7 '

3/81 4719 121" 9 2640t229 2870 3437 4 31t2.8 32 82t14 80 106 45t9 43 54 0 <25 < 25 7/81 44t9 53 51 31 (25 27302237 2820' 2720 32 3329 29 35 0 <15 30*9 25 11/81 3829 49P $4P 23t2.6 25 22 None

h. Values for potassium are reported as ag/ liter of sample.
m. Results were marginally out of limits. Efficiency curves were checked with no conclusive findings. Subsequent results have been satisfactory. '
n. Only two results were sent to EPA. Results were not included in their analysis.
o. Values for potassium are reported as eg/kg sample.
p. Invtstigation of this problem was initiated but no satisfactory conclusions have been reactwd. We suspect difficulties arising from sample inhomogeniety,
g. An incorrect weight was obtained in 154 gamma ana!ysis of this sample. Further analesis destroyed the sample so that the correct weight could not be determined, *
r. Investigation was conducted. No satisfactory explanation was found. Other cross-checks on this isotope in dif ferent media are satisfactory.

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11 Atmospheric Monitoring The atmospheric monitoring network is divided into three subgroups.

Two local air monitors are located within the plant boundary. Six perimeter air monitors are located at distances out to 9 miles (14.5 kilometers) from the plant in the towns of Scottsboro, Hollywood, Fackler, Stevenson, Pisgah, and Section. Two remote air monitors are located at distances out to.18 miles (29 kilometers) from the plant in the Lim Rock community and the town of Rainsville (see table 2 and figures 2 and 3).

At each monitor, air is continuously pulled through a Hollingsworth and Vose LB5211 glass fiber particulate filter at a regulated flow of 3 fts/ min (0.085 m3/ 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 collect rainwater on a continuous basis, and a hori-zontal platform covered with gummed acetate to catch and hold heavy particle fallout.

Each of the local and perimeter air monitors is fitted with a GM tube that continuously scans the particulate filter. The disintegration rate of the atmospheric radioactivity is continuously recorded at each station. -

Air filters are collected weekly and analyzed for gross beta activity.

During this period seven samples were not collected because of equipment malfunction. No analyses are performed until three days after sample collection.

The samples are composited monthlg for analysis of specific gamma-emitting radionuclides and quarterly for a Sr, 90Sr analysis. The results are presented in table 6.

t 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 1978-1981 are presented in figure 4. Increased levels due to fallout from atmospheric nuclear weapons. s testing are evident in 1981. These fluctuations are consistent with data from monitoring programs conducted by TVA at other nuclear power plant sites.

Table 5 presents the maximum permissible concentrations (NPC) recom-mended by 10 CFR 20 for nonoccupational exposure.

I Rainwater is collected and analyzed for specific gamma-emitting isotopes. A gamma scan is performed on a 3.5-liter monthly sample. The results are shown in table 7. During this period two samples were not obtained because of equipment malfunction.

The gummed acetate that is used to collect heavy particle fallout is changed monthly. The sample is ashed and counted for gross beta activity.

The results are given in table 8.

Charcoal filters are collected weekly and analyzed for radioiodine.

During this period, seven samples were not collected =because of equipment calfunction. The filter is counted in a single channel analyzer system. The data are shown in table 9.

12 Table 5 4-MAXIMUM PERMISSIBLE CONCENTRATIONS FOR NONOCCUPATIONAL EXPOSURE  ?

MPC In Water In Air pCi/l* pCi/m3*

Alpha 30 Nonvolatile beta 3,000 100 Tritium 3,000,000 200,000 137Cs 20,000 500 103 10sRu 10,000 200 144Ce 10,000 200 85Zr 95Nb 60,000 .1,000 140Ba 140La 20,000 1,000 131I 300 100 65 2n 100,000 2,000 54Mn 100,000 1,000 60Co 30,000 300 88Sr 3,000 300 80Sr 300 30 51Cr 2,000,000 80,000 134Cs 9,000 400 58Co 90,000 2,000

  • 1 pCi = 3.7 x 10 2 Bq.

TAOLE 6 4?DI0 ACTIVITY IN AI2 FILTER DC1/m433 - 0.037 90/283) 4A=E ?F FACILITv_g(LLLE23rE CCCMET NO. TVA/0*S/0MS-11L10 LOCATION OF FACILITY Jat<s0N akaga3a_ aEPCRTING PERIOD 1981 TYPE AND LOWER LIMIT ALL CONTROL NJ"6E4 0F T3faL NamSEg or INDICATC9 LOCATIONS L0cafl0N_g1TM 91ggggi ,agigaL_MLAN LOCATIONg NONRCUTINE ,

3F ANALYSIS DL T EC T I O Na MEAN IF3 b NAME =[AN gF 3 b MEAN (F) REPO4TED

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&a44a (NAI

  • S CE-141,144 0.03C 3.;58 3/ 30) PM4 STEVENS3N.AL 3 078 1/ 43 0.078 1/ 15) 3.03- 3.07 11.0 MILES NNE 3.07- 0.07 0.07- 0.07 9A-140,LA-140 0.L20 33 VALUES CLL3 0.02t 1/ 153 0.02- 0.02 AJ-103,106 0.340 3 358 1/ 303 PM4 STEVENS3N.A. 0.05f 1/ 43 0.06t 2/ 15) 0.05- 0.05 11.0 MILES NNE 0 05- 0.05 0 05- 0.06 .

24-35eNR-95 0.010 0.044 13/ 303 Pd4 STEVENs34.AL 0.09t 2/ 43 0.054 5/ 15) 3.02- 0.15 11.0 MILES NNE 0.03- 0 15 0.03- 0.12 1-131 0.010 2n VALUES (LLD 0.018 2/ 15) 0.01- 0.01 .

BE-7 NOT ESTAB 0.07t 27/ 509 PP4 STEVENS3NeAL 3 09t 4/ 43 0.074 14/ 153 0 03- 3 19 11.0 MILES NNE 0.05- 0.19 0.02- 0.19 5A*"A (GELI) 85 CE-141 0.010 0.01f 7/ 743 PM5 PISGAH,AL 0.01t 1/ 99 C.02t 1/ 119 0.01- 0.01 4.3 MILES ESE 0.01- 0.01 0.02- OcO2 CE-144 0 020 0.048 16/ 743 PM3 FACKLEReAL 0.064 2/ 93 0.02t 1/ 111 G.02- 0.07 5 2 MILES N 0.04- 0.07 0.02- 0.02 4J-103 NOT ESTAS 0 01t 35/ 743 PMS PISGAH,AL 0.024 5/ 99 0.01t 7/ 11) 3.01- 0.03 4.3 MILES ESE 0.01- 0.03 0.00- 0.02 Z4-95 0 010 0.336 36/ 74) PM5 PISGAHeAL 0.058 3/ 93 0.03t 4/ 11) 0.01- 0.06 4.3 MILES ESE 0.03- 0.06 0.02- 0 03 NS-35 0 310 0.064 40/ 74) PM5 PISGAH AL 0.098 4/ 93 0 048 8/ 111 0.01- 0.13 4.3 MILES ESE 0.04- 0.13 0.01- 0.08 E-40 NOT ESTAS 0.12t 49/ 74) LM1 BL SOUTHWEST 3.15t 7/ 63 0.146 d/ 11) 0.06- 0.22 0 8 MILE SJ 0 11- 0.22 0.03- 0 30 91-214 0.020 3.048 50/ 74) PM1 SCOTTSBORD.A 0.06 6/ 93 0.044 7/ 11) 3.02- 0.12 5.6 MILES WSW 0.03- 0.11 0.03- 0.07 P9-214 0.020 0.53 35/ 743 PM6 SECTION,AL 4.368 4/ 11) 0.03 6/ 113 0.02- 17.22 9.2 MILES SSW 0.34- 17.22 0.02- 0.05 P9-212 NOT ESTAS 0.02t 31/ 74) PM5 P1SGAN,AL 3.028 3/ 9) 0 024 5/ 11)

C.00- 0.03 4.3 MILES ESE 0.01- 0.03 0.00- 0.04 SE-7 0.050 0.00t 33/ 743 PM5 PISGAHeAL 0.094 3/ 91 0 074 5/ 111 0.GS- 3 13 4.3 MILES ESE 0.06- 0.11 0.C5- 0.09 TL-208 NOT EST A8 0.018 13/ 74) PM2 HOLLYWO3 DEAL 0.014 1/ 93 0.01t 4/ Ill 0.00- 0.01 1.8 MILES WNJ 0.01- 0.01 C.01- 0 02 SR 69 0.035 0.01t 16/ 323 LM1 8L SOUTHWEST 0.018 2/ 49 0.01t 4/ 88 4; 0.01- 3.01 0.9 MILE SW 0.01- 0.01 0.01- 0 01 SR 90 0.001 0.00f 9/ 32) LM2 BL ENV DATA O.004 1/ 43 0.00s 1/ el 4? 0 03- 0.03 1.0 MILE NE O.00- C.00 0.00- 0.00 g l a.' Nominal Lower Limit of Detection (LLD) as described in Table 3.

b. Mean and range based upon detectable measurements only. Traction of detectable measurements at specified locations is indicated in parentheses (F).

l

RA010 ACTIVITY IN RAINWATE9 FCI/L - 3.037 93/L E Na"E CF F 2 C I L I T Y_ ilk (E r na:TE _

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$E-7 16.20- 117.30 14.90- 152.13 1.8 MILES WNw 24.40- 152.10 GAMMA (GELI) 35 53 37.666 1/ 30) PM3 FACKLC4,AL 37.664 1/ 41 10.33t 1/

Z4-95 10 000 37.66- 37.66 5.2 MILES N 37.66- 37.66 10.33- 10.33 4/ 30) PM3 FACKLER AL 84.066 1/ 43 13.024 1/ 5) i NS-95 5 000 33.854 14.86- 84.06 5.2 MILES N 84.06- 84.06 13.02- 13.02 l DM2 HOLLYWC30,AL 165.198 2/ 3) 72.90t 3/ 5)

<-40 NOT ESTAB 113.338 11/ 30) 68.49- 255 10 1.8 MILES *NW 75 27- 255.10 54.43- B6.64 LM1 BL SOUTHWEST 33 398 1/ 43 12 42t 3/ 53 31-214 NOT ESTAB 2G.924 19/ 30) 9 16- 44.93 0.8 MILE SW 33.39- 33.39 12.41- 21 88 PM2 HOLLY'e000,AL 33.52t 2/ 3) 9.316 2/ 5)

P3-214 NOT ESTAB 18 62t 14/ 30) 10.58 6.42- 52.00 1.P MILES WNW 15.04- 52.00 8.04-5/ 30) PM2 H3LLYWO30,AL 18.07t 1/ 39 9.658 2/ 53 P8-212 NOT ESTAB 13.23t 7.21- 18.07 18 MILES WNW 18.07- 16.07 4.68- 14.62 4/ 30) PM4 STEVENS3N.AL 61.b94 1/ 6) 90.784 1/ 53 SE-T NOT ESTAB 62.59t 45.87- 21.69 11.0 MILES NNE 81.69- 81.69 60.78- 60.78

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

1 1

1 1 -

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%A*C JF FACILITv l ut[FONTE. ~

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3ElLEitL2 ikk21___. ^ ^ N G_L 1 15( 26/ 263' 34355 PffA 3 157 1 296 104/ 1:45_Put _ -STEVENS34,AL 21TtliNCE AND_211LETTON 1.22t 13/ 12) 3.26 C.07- 3.35 13: G.~6- 3.26 11 0 MI'_ES NNE 0.11-

+

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

a.

b. Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (F).

5

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

e #

17 Figure 2 BELLEFONTE NUCLEAR PLANT ATMOSPHERIC AND TERRESTRIAL MONITORING NETWORK south PITTSBURG N

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21 Terrestrial Monitoring Milk Although there are no commercial dairy farms within five miles of the plant site, milk was collected, when available, from one farm producing milk for private consumption (see table 2), and from one control dairy farm.

Raw milk was analyzed monthly for 181 1, gamma-emitting radionuclides, and for radiostrontium. The results are shown in table 10. During this reporting period, one sample was lost during strontium analysis.

As had been noted in earlier monitoring reports, the levels of 80Sr ,

in milk samples from farms producing milk for private consumption only are up I to six times the levels found in milk from commercial dairy farms. Samples of feed and water supplied to the animals were analyzed in 1979 in an effort to determine the source of the strontium. Analysis of dried hay samples indicated levels of 80 Sr slightly higher than those encountered in routine vegetation samples. Analysis of pond water indicated no significant strontium activity.

This phenomenon was also observed during preoperational monitoring at Sequoyah Nuclear Plant in samples taken from a farm where only one to two cows

' were being milked for private consumption of the milk. It is postulated that the feeding practices of these small farmers differ from those of the larger dairy farmers to the extent that fallout from atmospheric nuclear weapons testing may be more concentrated in these instances. Similarly, Hansen, et al., reported an inverse relationship between the levels of 80 Sr in milk and the quality of fertil-ization and land management."

Vegetation Vegetation samples were collected quarterly from the farms from which milk was collected, and from the vicinity of each atmospheric monitoring station and analyzed for gamma-emitting radionuclides. Approximately 1-2 kilograms of grass was broken or cut at ground level and returned for analysis.

Efforts were made to sample vegetation that was representative of the pasturage where cattle graze. Table 11 gives the results obtained from the laboratory analyses.

Soil Soil samples were collected semiannually near each monitoring station to provide an indication of any long-term buildup of radioactivity in the environment. An auger or " cookie cutter" type sampler was used to obtain samples of the top two inches (5 cm) of soil. These samples were analyzed for gamma-emitting radionuclides, 89Sr, and 90 Sr. The results are given in table 12.

"Hansen, W.G. , et al. , Farming Practices and Concentrations of Emission Products in Milk, U.S. Department of Health, Education, and Welfare; Public Health Service Publication No. 999-R-6, May 1964.

l 22 l

Ground Water Well water was obtained monthly from two farms in the area and from six onsite wells. All samples were analyzed for gamma-emitting radio-nuclides and a quarterly composite was analyzed for tritium. The results are shown in table 13. During this period 14 samples were not collected because the stations were inaccessible.

Public Water Potable water supplies taken from the Tennessee River in the vicinity of BLN are sampled and analyzed for gross beta, gamma-emitting radionuclides, 89Sr, 90Sr, and tritium. The results are shown in table 14. Figure 5 shows I

the trends in gross beta activity in drinking water from 1978 through 1981.

Environmental Gamma Radiation Levels Bulb-type Victoreen Manganese-activated calcium fluoride (CaF2: Mn) thermoluminescent dosimeters (TLDs) are placed at 15 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 (see figures 2 and 3). In October 1981 three additional stations were established nesr the site boundary and TLDs were placed at 18 stations located in the different meteorological sectors I around the plant at a distance of approximately 5 miles (figure 6). The dosimeters, in approximate energy compensating shields, are placed at approxi-mately one meter above the ground, with two to three TLDs at each station.

l They are annealed and read with a Victoreen Model 2810 TLD reader. The values are corrected for gamma response, self-irradiation, and fading, with individual gamma response calibrations and self-irradiation factors determined for each TLD. The TLDs are exchanged every three months. The quarterly gamma radiation levels determined from these TLDs are given in table 15. It should be noted that even during the preoperational phase of the monitoring program, the average radiation levels onsite are generally 2-5 mR/ quarter higher than the levels offsite. This is consistent with levels reported in other preopera-l tional monitoring programs conducted by TVA 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 1978 through 1981. To reduce the variations present in the data sets, a four-quarter moving average was constructed for each set. Figure 8 presents a trend plot of the direct radiation levels as defined by the moving averagec. The data follow the same general trend as the raw data, but the curves are smoothed considerably.

__a

23 Poultry and Food Crops Food crops and poultry raised in the vicinity of BLN are sampled annually as they become available during the growing season. During this sampling period samples of cabbage, corn, potatoes, tomatoes, turnip greens, and poultry were collected and analyzed for specific gamma-emitting radio-nuclides. No sample of corn was taken from a control station. The results are given in tables 16 through 21.

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%N% e % C % ==e% O % G % M % 4 % M %O%O%O%O %C% ort %C%O 8 mm 3 ) 2e 7' ee fG e9 Pe we Pe N M e we ** *e .9 ** erl e se al N y

>= 04 4 g nF I fw4 S LJ E9 as s 3 &

w 0

  • 0 =* I w 0 # 1 to 0 w $ w 0 w I ep I w 1 w 0 up I w 0 to 0 w I , g be ee e.e 3 e- y oart @ @ @ @ m P=t e N N em J e4 4 esQ O'O P=P= N N esce N M emot r N ** N e g as s #$ g

>= er O. O. O.' O.. P= 5. u. e. e. cD. r.) w.1 e. a. U.S . N. P= C'.6O. e O. r3. O e. e. er.)e M. e M. o. e. P= ** O. p e. a.1 L.J > 70 t'J N N r3 O O ** O O O O c3 N es M o ** N O O O O O C3 O O O c3 cc c O O O O n O or ] > 01 *e 8 i.J ri I e .0 4

> w I w W- 1 J3 1 I of at 7 tab e O tJ >= >= >= 0= _0 _J >= .J W M M d 4 4 4 U e.*  % 01 **$ sa $ e/1 M t/: af. as at

",,, re as' Il e4 .J 4.1 .J t.J i.J J 4J e L.a >=

  • J >= * >= b

> a> > I

! cs < > s 2 i =3= w2. O== u.= = 0i< < h.

bJ >= 4' is L.4 0

  • I
  • I "E I *MT ft 2 O O2
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  • al D rrn as ==0 at 7 t.J ") M W 3M 3 M Ft/1 > Z'B 4.J 0

JMO EMO L.A i.a 2 >MJMO 2 >MZ 2 me ==

>= >= e .4 as J

% 2 asls e $

.J ut O ** t/1 O E tw M w w t.A M W ed I.J M L.J 0= L.J M L.J > J I.J W .J I.J Y LeJ M W I.J LJ .J L.A t.s y e.J L.J g u o FG 4. 6 UJ JuJ .J e .J J u .J .J L.J == J .J J u .J J J .J .J .J .J O as of =e me .J == as ** J ** 6 ** J == kJ == .J m > E .J e* O == at a.= .J == J == Q ** .J e-o a e.* * * *

(4 M *J O I M 7los s 63 al 3 4 E to E E E2 1 M E to E (/l IC E I E w E a) I CC 1 I E CD E EJ K u

== o- t

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l M $ am = = am m a en am ,= an an en = an an en as g I 0 7 0 =ft 4 4 4 4 @ J J J @ @ @ J J @ 4 4 'O O -

0 -1 0 0 w e er) are vi e >> O w1 m er> N er) er) P. w3 m wi O es >= w1 er., w) 4 w1 e ai N M en M O ed j ,

l >= 0 4 Pm P= or)

c. g y 8 >- J3 0 o #. e . G.+ . at. N. A. c.e o. e. 4.) e. .O. o g,, c '

we me a= l %N%e% 0%ee%Q% O%er)% 1.%O% O%O%LD%e'S% 3 % w) % r3 % O u b

>- I U44l P= rJ A *L M P= e N i.O N 4 N P= N N sL en e e a S

.* Ow le 4 es M M N rJ M er) ** N N M ee N  %%

OI J .4 t'4 $

66 17 .J 2 21

=e ma w IC as w =a el me 0 w 0 =e 6 w 0 w 0 == 0 w I w I w I w 0 w 1 w I w 0 w I w 0 w I 8 at et J1i.94 O t.1 n ** @ es P= T N ce P P= or3 e p ,e P= m 4 .D A (D N O N o i:'l ce em P* ** tb e W

^ O J.JJw H3 . N. .i. N. o. e. g. N er)

N.Nw. e. r=.e r%

p.. . .J P.=og. T. O. P. 0.% 63. O. C.s o. N. **. *.* O e ese o. e .e ce. O. O. *.* O.

3 i all e

u ce O N O al ce "J O O O O O e.4 C3NO@ e.e C1 O O O O O O r3 O O Pm ee CD O O O s,,a4 4 21 == w .O

> 0 O 4 e- l f cw

-> w 0 J ** M u

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  • 8 3

O O O F3 O t1 O O O a) O @ O cn (O al G3 51

$h g3.

L6 46 J LL >= m O N us O ** 4 e.e O W O at O at g as as at g.e 3 O O U C.l >= Q >= >= re >= >= >= >= >= Q

'O h.L. m 4.J .J1 N. N. M N. nf. O. c.e . 4/t O. M . M M s/1 t/l M LJ O La >= Jl O O L.J O O O O O u O kJ O t.a L.J t.a L.J a. s ,",4 $

t i w ** >= >= >= >= >= ,se .O =

  • E 7 C O l D= >= >= '
  1. O .J l O O O O O O O O .J H 2 2 7 Z 2 2 7 2 G

.t rr , y LJ tJM * *

  • Q be O J i 3 L *o C4 == 9

.J #5 M a.m .J 4 > 3 a. h

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>= O at u (3 CL rr W u N p y y ). rt) ik Q d) >= 4 e .

lO a f6 J3 s

26 m

b w

1 4

  • W W w I.

k2O A OMW w

> > 3l C w3EJ y WOOul g WELN &

K W W V4 7 0 a 48 C EE 4

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w N 9 4

i1 1 a e

a e

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j l y v, 1 s O O eJ O e m a N N @ p NO O N 00 O O c 1 4 J J NJ o & o e m 2 n DJ J e DJ J J w G ml J J ed e o e e e e e eJ J e e4 J J Nas V V %OV %n%e%C%c%o%cNM%oV V %c%MV V V 8 M& Ao e n e H e e e e e e e I l J2m M M M M M M M M e C o 00w4 W W W W W W W W C

% O E=wd 3 3 3 3 3 3 3 p O e w >> d J J w . J w . w . w . w . w . w . w . w J J w . w . J J J

  • D a 2422 4 4 WJ4 MW@@wMOMOMNOMMeM4 4 @meM4 4 4 g

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/E q M

g w

Wa

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=

N N

[

e Ga la U M M D N o N N A n G m n H O > G de w4 M o 6 Q M E o o e e e u e N e O A M 4{ w u e o e e e o e e e e e e o e e e e 9

-J d %rs%c%o% 0%n% 4%n%m%u%e%e%m%7%n%c%e%"

= 187 M M a N M N NMM N N N N N m e

a N N d u

> 14 41 C E JJ VI k o  :

4 a I 8

- l 3 w . w . w . w . w . w . w .w . w . w . w . w . w . w . w . w . w .

  • J sa i # noMMNNoce ewNNNorNoemeccenewwkewood 2 m a # mHMO@ coono@ e c c o m @ m o n e g as m e e N N e v e N M M e c 4 e e e e e o e o e e e e e e e e e e o e e o e e e e o e o e e e o e 4 M > 2 o c2 n o n n o p o n n e n o m a n n e w w M w o o n o n c o m w M F, p

a > a - f ci vi el e m w I I

QIs kj 64 M

A

> . d W J 4 . 4 4 J 4 4 4 4 4 9 N > - 1 1 ~ 6 4 4 4 4 4 4 4 a .

m a n l 41 Il M n 4. M O O > 4. W O > O k o O O > > > e D m 'El l CA O3& 1FFN 1W34 22W14 F34 E3ENM 24 4 4 a W M el Il w l O2OMnFOMOMO 070MC OMO OMOMOMO O O

  • J > > 1 28 > F rJ 03r3M 43% 3 WM mi We3 WC1T3m3 IJ W W T m u M 49 = 4 /t 4 M /MM M b?2MM DEM D/M M M D2D?>7 4

4 o q 3 7 4) >MW MWWWWWM2 WWp ME WM2 WM>MWMZ F 2 o

O e es i JWWWDJk WWWWWDJWWWWWWWW>WWWWWWWWWWW m n 7 Li JJOJWHOJOJ OJ JOJ JOJOJOJ J J J C O

4 .

C H 21 LA Omu=>3 u=umJa>

M3MEmEM J W "E u = J m u w s w u m u m u = J M J=J= ,0 I rerM MrmEMrmEerMEMEsimKmx mu

= H WI u o u o >l n'r-me ewam4Noe eg

% (

4)s C1 v4 s er er-s en er er-r e a cerNeEo or - 4etN es o -er4 - 4

  • e. NE oerWeroeN o a w

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N LenDLHLDLeJmLnLDJHLDJmLDLDLDJuJmJm k 1 p ch M 1 m a a a a a a a e a a a a e = m a WH z . e 4 e # 4 @ 4 4 e a e e e d 4 4 4 O O O . mo=M-M acemet.wmmemowem*wmac-wwe e>moOWOW y @

~

>o e. c.

c e e e. o. o. n.

. e. o. e. N. e.

0 m.Ja ,r Ja JE $e

-w W em %u%o%o%c%c%@%o%e%w%=%wsm%o%c%o%m%mvovo k C e-. u sy

  • H &
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/. Ow ud a w w w w m a a a w McMe L k ll g g Ol k i n_j JJ W WWWW q W J 2t' 3A34 3 Wl ta J.v4 M eddi OWn t w.w.w.w.w.w.w.w.w.w.w.w.w.w.w.w.w.s DCMMeeeMeme@ NN4WOTMPPm@ medWMM@mcGo4M4 M J ea 9 d

>1 M D- m JJ Ja 4 d. e. ne oe r.v o. oe oe n. oe me oe ce o. meeo@e N. eeeomeeemee eMemeNeNee eo e& G o em. M. > M l tl mal u M q 1% ~

LJ f 3 (1 f 3 O O C3 o O O O Dr) O g e3 o O O o o O o o o rJ O o n C a oOoMM4 > 4> wW J

l O eana4 4 * #"

> e P Z Z g3

>

4 4 oy JW M 9 mm au l

9 I

(# J 4 ~ ~

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gj l w*s 3 o u 4 = w o e n n o o o o o o c j o m o m n c n m o o 40 i 4 4 Jkka T e4 4 M M 4 m @ o O 4 O 4 @ N 4 4 o O A u ou.4 ea > c. >>

r2 N o n a <3 > o > m o <> > o M

  • 3 m e WJ e M e e e e o e e e M e M e e e M e e o Wo W > o W n o o o o o o o W o u o m o o W m n u e 3 's W d a 4 2 O O l > > > > E 9

/O J s O O O 3 O

- < E r 2 .

-f v b M a O C u We mN N N 34 O

J O e.-W m 9 =J ]b, 4 3 > 1th g g

? J ev t t* r MN W 4Gw e M > d G e N 4 m E b e C a J r ki e n M e c e a e e m N N o N n

  • C F 4 w.4 p- O > m O

- .4- a, m. M. M. m. . c. N. N. N. N. N. N. N. N. N. . e h zg n m oir u , M w m e. , - - O m 4 4 .. J u 4

>O 4 u & 43 N P Y r m m A A w a ld e

& T > d w M

w M q' ]

l T ABLE 13 4ADIDACT1d!TT IN WELL WATE4 DCI/L - 0. 37 93/L

%A"E OF FACILITY _i[(LLEONTE ___

00CrET NO. TVA/M1/0H5-12LlP L3CETION CF FAf!LITY__gi(S ON ____ SLASili__ ___

AtoCATING PLhl0D 1941 C0hTROL NUMeE4 0F TYPE A%3 LO.E6 LI"IY ALL N0hmouTIgE T3fAL NUMBEs OF INDICATOR LOCATIONS (OC A T I M_g11d_dlEHL11_ A 'th21L_"L A N LOCATICgS Na9E "LAN ( F h_.__ PCAN ( RLPO4TED 38 ANALYSIS OETECTION8 "EAN f m y gpEmE%I1__

1LL11 lihil() ___ llSTAN([ ,13Q,018tGION _4 a g g[b R a hEL{ i ,

EL

  • F O '_" L2 34994 (NAI) 19 WALUES CLL]

Si 4 WALUES <LL J ANALYSIS Pear 04"E3 3AM"A t^ELII 31 43 90.878 3/ 77

<-42 N37 ESTAB o*.278 7/ 243 DELL e3 133.138 1/

150.13 ONSITE Nd 130 10- 130 10 38 39- 131.30 13.26- 73 WELL 84 36.968 4/ 43 39.854 4/

31-214 N3T ESTA3 24.30s 1st 243 2 45- 48.37 3% SITE NNJ 15.64- se.39 5 69- 64.53 WELL s2 67.62t 1/ 11 29.951 4/ 73 33-214 NOT ESTA3 32.23E 11/ 243 49.40 H.79- 82 33 DNSITE WSm 67.52- 67.62 5.20-2/ 6) 15 394 I/ 73 73-212 NOT ESTAB 14.514 7/ 243 WELL sb 19.714 4.38- 28.23 ONSITE N 13.96- 23.46 15.39- 15.39 13.364 2/ 24) WELL 86 11.944 11 69 7 VALUES <tLD ,

TL-20e NOT ESTAB l 3 33- 11.e4 ONSITE N 11 64- 11.e4 l

23 VALUTS (LL3 9 V ALL'E S CLLD TRITIUM 330.300 31 ANALYSIS PEkF0amED l

l

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

l

ilI j'

,1jllllI! il1 5

)

F

(

s e

s e

3 h y t E

FNDg n 0I Eg e

r TT, a 4 UR( p oRP n EOOm

" NE UOR i

d NN e

( , t a

1 c

( i 1

t ,

. 7 )

d n

- , 3 4 i l , 15 O C D 0 s

a1 0 L L L 2 i EL L L L 11 / 4 C C < / 4 s

{ 5 14 n 11_

1 LN) S S S 3 o i

QD 0 O Fb E E E t U U U a

/

A 0

1 4I I TT gE - L L L 4 - c o

W 4 NANN 93 A A A 00 l

T OCAA 27 W V V 22

_C COEo d

.& L" 32 3 4 4 4 4 e OG 1 4 4 i 33 f NN i I

c TT e p

ES MO s CP 9 7 ) 3 1 3 CE 3 3 d 3 4 4 t

[ R # 0 S 5 6 5 a N F b _1 3C 6 2 9 6 s C.

Y L

a (

L g# 0 / 5/4/ e /212 t

n e

P 11 233l 1 10

,A 4 m P 1 e wNg01 1

U LE r S i* u g 6 - 4 4 - 8 s R y 31 001 457 6655 a y 669517 0066 e E 95 m T L s .

A /  % 32 555748 2222 e W 3 T 2 11211 00 l 9 s 1 1 1 44 b a

C _ i T t I 7 _ w ( c L 3 _ k ; e 4

1 5

J c.

_ A i g t d

e P 3 _

= d_ gA A L A L A E _a gE ,' P P P f

  • - a F A, F A, F o L

B I a 1A w 0 W 0 e n A

T Y T

L

/

I

_(

a 1M3F.

3 s_ N (T 2 1

T 2B5T2 4 *

1. 0 .

1 99 0

95T2 1

3t

.i o

1 S5M9 c v

C P 1 g" 3- = 9S3M e 3T3 3 T3 3 ea l r

! 1 D T D T D bF T A N" N" Om%M OMNM a A _

(

2 mO iST A o A A CaA A ST STST CO AR STST T

3 L n ny 1 _ ._ il n

3 __ d o A __ S ) 3 ) ) ) 3 e 4 _ , N 9 3 0 0 G D2 2 b s 3E 1; 1 3 I 33E1 615 i t

_ . 3 3 "

_. 1 3 L" 2 1 L9 0 6 rn

n. c e L

__ Tb A a /0 LR CO /5/ * /8CO/2/2 LR sm ee 1 Crb 4 1 F 516371 J1 22 d r 1 Og r 1 SR 1 SD 4 u g EE EE ss 2 . LL aa F 2 L Ni UP UP e L2 A4 A lt - L t t L 6 ) m L1 0Ed 3 t A S a3G727 AS6617 D

  • TM V I 0091 L e L

E E A

- 5. t. S 7. 6 6 0 5 7. WSI Ll (b

- i C 2 eY 4 226382Y2223 a I _3 2L a r21 1 1 L 2 h nt Y d_ D A A 33 oc T

I Y LT

_ N I _ N A

N A

i e t t ce ed II t 0L T a.

en 8 I I D op F C " 0' f u A I 1 J 9 B B 3 0 0 o F F LFT 1C A A A 0 0 3 d O 0C2* T T T 0 0 3 t e R EL. S S S i s E0 5

T L2 E E E 0 2 0 ma ib

' E. E 1 3 L

- ' O 3 1_ T T T 3 rg e

N3 L _ 3 O O 1 N N N en wa

f. - ' e 6 6 L or S 5 4 3 1 l 1 1 d O

L DMI NuSLA 2  !

I L

l n aa A gY" T A E n in N L*

s t N G

( M ma E A O ( 4 4 oe f LNF 1 1 U NM f A A i 5 4 4 0 2 2 9 O I TT 5 = 4 4 - -  :  ? T . .

O8 = 4 - 1 3 1 T 0 d_0 _3 4 a G

a G

4 9 8 4 S

9 S

4 T

ab

\ )lfJ! llj

29 __

=

Table 15 _

ENVIRONMENTAL GAMMA RADIATION LEVELS m

Environmental Gamma Radiation Levels Honitoring Period _ Location _pR1 Hour _ A /_ Quarter" January-March 1981 On-Site (15)b jjjj Maximum 12.5 27.4 .===

Minimum 8.0 17.4 ====

Average" 9.412.3 20.515.0 Off-Site (8) _,,

Maxtmum 8.0 17.5 Minimum 6.4 14.1 ----

Average 7.211.2 15.712.6 -

April-June 1981 On-Site (14)

Maximum 14.9 32.6 -=

Minimum 7.5 16.5 Average 9.413.6 20.6 7.8

[]j Off-Site (8) 5-Maximum 9.0 19.8 - -

Minimum 6.4 14.0 Average 7.611.9 16.6i4.1 ____

July-September 1981 On-Site (13)

Maximum 13.0 28.5 --

Minimum 8.0 17.5 -

Average 9.2 2.6 20.215.7 -

Off-Site (8)

Maximum 8.2 17.9 ____

Minimum 5.9 13.0 ---

Average 7.lil.6 15.5i3.5 -

October-Deceaber 1981 On-Site (17) """

Maximum 12.5 27.3 Minimum 6.8 14.9 -- -

Average 8.5 2.8 18.716.1 -- ,- -

Off-Site (27) ---

Maximum 8.8 19.3 ---

Minimum 6.3 13.7 --

Average 7.1 1.2 15.6i2.7 -

a.  ;;

Data normalized to one quarter (2190 hours0.0253 days <br />0.608 hours <br />0.00362 weeks <br />8.33295e-4 months <br />) - - '

b. Number of stations (normally 3 TLDs at each station) --
c. All averages reported i20 (95% confidence level) _

N 9

h i -i--i .--m

T A B L E 16 RaDI3ACT1tITY I4 CARBAGE PCI/MG - 2.037 SQ/K3 teET WEIGHT) g N1"E OF FACILITY _iCLLEFC$ Q ,,________ ___ 70CMET %0.11ALQw1LE21-11L12.

LOC *T!Gv Or raC3LIry__gi @ % a(aaa=4_______ _

___ FTDOCTif.G PERIOD _lail_

Type AN3 L O '. F 4 Li'li ALL CONTROL NJMPE4 0F hohpouTINE T3fAL NJ"cE, Of INDICATCE LOCATICNS L O C A]{Qi,g{ld,d[Qgi1] {$$y AL,f[ A', LOCATIOhg b .; A =i t *EAN 4F3b *EAN (F) REPORTED 3r agaLT!!S OETECTIONa MEA % agt

__euwer __ m a____ "Nct ___ unu2_n2_netw n- e entb uset6 n u m us__

AM*A (SELII i

<-4: NOT Esta3 23%:.354 1/ Il P42 HOLLYWO3 DEAL 2359.008 1/ li 1764.0C4 1/ li 2359.3"- 2350.'? 1.4 MILES =Nw 2359.03- 2359.00 1764.CC- 1764.30 NOT ES'A3 1 VALUES (LL3 12.22t 1/ 13 D3-214 12.22= 12 22 93-212 NOT ESTA3 1 VALUES <LLD 8*308 1# II 8.3C- 8.30

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

l l

i

T A 9 L E 17 4A?!3ACT!blTv I *. C0;N rCI/4G '.??7 B^#43 (del *EIG*TI r ra:Itg7,_ _ x.t_; e.rr__C _. _T r .__ _ __ _ _ _ - " CatT

  • 0._11__/A E_'( _/ _M_ .* s _/11

. ={ - __

t;a- Oc rargLgry t a 6. - .', a. at a a a"; EEc0ETING r t 9 t C D _a'

  • _- 1____-

t-CONTPOL %umEE4 CF TfeE NO L:.Ea L!w!T ALL NONROUTINE

.' T 1%CICAT04 LCCAT11Ns (((1113_g11a__31Ed5 7 13hgaL_wLi' 4 ,__ LCCATIONg TOT.L ' . . * -

.4=E PEAN REPC41[C V ANALv: IS C T r C T I O N' " ( A *. frs

  • E a *. gg 7

_ m :.t____ matt ______ nturc_n2_entclus_____ nut a a st(F )___ -_ nuet-tm__

__eutu m 3awwa (,rt!)

g.,; ,07 ESTA3 I C r 1. , ;f 13 ow' WALLY.70D.AL 1 50.008 1# 13 2 a s; . ;, _ I M O. - - 1.- "ILES .Ne 1950 00- 155;.C#

2 3_ p 3 ;: DT ESTs} 7.331 I/ II D*2 '1CllT*000'A- 7'394 I/ I}

7.3r_ 7.43 1. d. "!Lfs .N. 7.59- 7.-

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

we

T A S L T 18 tacIDACTId!TY IN POTATOE5 rt!/4G - 0.237 % / r( 3 tuff .((GHT) "N C0CaET NO._

N3yr -

-r ra ILITy_ __ ra k r_ r_ _ _r _g -7 r_ _ _ _ - _ _ _ _ _- --- - - -- --- - - --- -- - - - - - - - -

_ , , , , , , , ,,_ _ , ,1 ( i l i "J , , __ _ _ _ . . _ _ _

E U NIINc L,3gg

,ly,11tog Bill.(gl-ilfil._

LUC?TI3N pr ra;ytIiy,,g g; ,3 3, .

CONTRCL huMEEE CF IfPE AND LOWEA LI"!T ALL NON800 TINE T3Tal NUMoEJ Cr INDIC ATM LOCATIONS (Q(11123_g11 1.311d[il.1 h g1L_g(th ,F _ LCCATIONg

,b NAME =EAN tr) MEAN (F REFORTED 3: ANALYSIS DETECTIO.a utan ( o a 3gg b) .gggggggg3tg _

_.1;1 eel m . 1LL;l - _ _

  • A %L 21111E L_132_211EC11ON __datiLd G A M u f. 4S[LI)

?

3379.0?c 1) 34? H3LLY 33D,A_ 3379.036 1/ 1) 3115.CGI 1/ 1)

<-o2 N]T ESTA3 1/

3375.33- 357e.7* 1.* PILES .Nd 3378.3C- 3376.0C 3115 00- 3115.00 N37 ESTAS 14.-04 1/ 1) PM2 HOLLYwG3 Deal 14.ect 1/ 13 1 VALUES CLLD 51-214 14.oJ- Ig.a0 1.* MILES .Nd 14.40- 14.6C NOT ESTAs 14.968 1/ 1) PM2 HOLLYWO3 DEAL 16.906 1/ 13 1 VALUES (LLD 33-212 16.93- 13. 3 1.8 MILES JNd 16.90- le.9C

a. Nominal t ower Limit of Detection (LLD) as described in Table 3.
b. Mean and range based upon detectable measurements only. Fraction of detectable measurements 4t specified locations is indicated in parentheses (F).

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TA9LE 19 48010 ACTIVITY IN T04AT0E5 P;I/4G = ;.037 t: G / 4 3 toCT W E 16'f T )

  • ! "E Cr rs;gtg;y,;g(r r c. t r

__ _____________ _ _______ CCCKEY NC,_TyAfgug[gri-ig[1g LCC TIO*. 3r F AC I L I T Y_,J A Q1% A(AgAwa FEPORT1%G PERIOD _lgil_

TTPE 2 ':0 LO.E; LIMIT ALL CONTROL kUPEE4 0F T3T L *.,usE- !F INDICATJa LCCA{ IONS Q{AM]3,mMd,gMg{$T 4 }$g{(,M r a 's LOCAflog NONROJTIhE 3r tNALytts ._ f Tr c y ;3g a uggy gp3 gagg .ggy gryo MEAN ( 4EPO4TED fil!.E15L2 __ ik k 21 _ . 'AN$l ___ 21 MAUL _132.21t G112h_____dE3 d b pagg((l _ _ _

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<-4: NOT ESTA3 2634.001 1# 13 P*2 HOLLY'03D.A'. . 2634.?Of 1/ 13 2527.C34 1/ 13 2634.;;- 2634.': 1.- MILES .NW 2634.03- 2634.0C 2527.CC- 2527.00 31-214 NOT ESTA3 ] VALUES <LL' 25.104 1/ 13 25.10- 25 10

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

1 1

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._ g T A LE 20 4A0!OACTIVITT IN TU4N GkTENS 3C1/*.G - 9.a37 P';/'J (.E! .E!GNT)  %

NA"E OF FACILit?,1(Qi(C11(___________ _

_ _ _ _ _ , , _ FfCafi *G._liiLQ11(($1-ilfl(==

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ivFE :N2 Ln.E8 LI*IT ALL CONT 40L NJPEE4 0F TOT 1L

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  • OF !NJ1;ATL4 LOC AT]CNS (2(1][Q ,g[lg,j[jg((1,jh(A(,"(AN LOCATIOM NCNRCLTINE 3 SNALvt!S 3ETECTIONa =EAN t & )b NA=E .f AN ( F )b "EAN afI b REPORTEC

__2L1Lai:L2 __1LL;1_ -- **%CI______ 21111EL_n2_;11ELII')N

  • A MEL___ " AML.6 EL11kEIEG11__
4**4 (LCLI)

<-4; "Of ESTA4 2A17."^( 1/ 13 D*2 HOLLTWOOC,AL 2617.004 1/ 1) If24.004 1/ 13 2611.):- 2617.: 14 "!LES .N. 2617.C0- 2617.C; 3P24.CC- 3*24.00 13 p" HOLLYd73 DEAL 21.154 1 VALUES (LLD 33-212 NOT ESTA3 21 158 1/ 1/ 1) 21 15- 21.15 1.d "!LES dN. 21 15- 21.15 l l

3E-1 NOT ESTA3 1 WALUES <LL3 87.664 1/ 1) 87.66- F7.66

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

TAaLE 21 4AD13ACTId1TV IN 830LTRY PCI/n; - .;37 8t '. / 9 3 f.ET =EIGHTl S2"E '#

- F$CILITY_;LkdLEML_________ _____________ ____-- 00CaEY ?. 0 . TvA/0mi gri-12(lt, LGraTION OF FACILITY,,fiZj M _ _ iLit!"i_ __ __

kr00ETING PEWI00,11tl ___ _

TyvE AND LOgra L!"If ALL C0% TROL NJMBER OF TOTAL *J"aE CF I ".D I C & T D ; LOCAT!3NS LCCATIOy NONROUTINE 3r ANALYS!s SETECTIONa .g A s g , 3 b (2C_ill22ygki,lt_di E hill,11Mik_"Lih(F "LAN T. MEAN t ) RE*0RTEC

__lL1EiltC __iLC _) -

11MLP______ 2111au;L_1$2.211LEIMN a A 4L b _, Asqt .tijgt c.g31g,_

JA"WA g3rL])

<-40 *3T EsTA1

. 26rl..Ct 1/ 1) SIsm rAR" 2561 03t 1/ Il 19s n.0 0 t 1/ 13 2561 00- ?561.s 4.G "ILES SW 2561.00_ 2561.60 19s*.CO- 19Pe.00 31-214 NOT EsTA6 a.52s 1/ 13 SISm rAq3 4,5;g gf 33 15,5c: t/ 13 S.52- e.b? 4.= "!LES Sw S.52- s.52 15.5C- 15.50 P3-214 NOT ESTAS 14.4st 1/ 13 SISK FAR" 14.43t 1/ 13 15.074 1/ 13 14.49- 14.42 4.= MILES S '. 14.4e- 14.4e 15 07- 15.07 l

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

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36 Figure 5 I I I l l l 8

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3 Annual Average _

r.n n g$ Gross Beta Activity No u

3 In Drinking Water c c MO Bellefonte Nuclear Plant _

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38 Figure 7 Otreet Radiotson Levels 2, Bellefonte Nuclear Plant 22 -

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1978 1979 1980 1981

k 39 Reservoir Monitoring Reservoir sampling at BLN was initiated in November 1981 with the collection of surface water. Surface water samples will be collected quarterly and samples of sediment, Asiatic clams, plankton, and aquatic macrophytes will be collected semiannually beginning in the spring of 1982. Because of the location of BLN between Browns Ferry Nuclear Plant (BFN) and Sequoyah Nuclear Plant (SQN), the reservoirs scheduled to be sampled for fish are already being sampled in the BFN and SQN monitoring programs.

Water Grab samples of surface water are taken quarterly at TRMs 388.0, 391.2, and 396.8 (figure 9) and analyzed for gamma-emitting radionuclides and for tritium. During this reporting period one sample was taken from each station. The results are shown in table 22.

Fish Radiological monitoring for fish is accomplished by analyses of com-posite samples of adult fish taken from each of three contiguous reservoirs--

the reservoir on which the plant is located and the reservoirs immediately upstream and downstream. No permanent sampling stations are established within each reservoir; this reflects the movement of fish species within reservoirs as determined by TVA data from the Brown Ferry Nuclear Plant preoperational monitoring program. Sufficient fish are collected in each reservoir to yield 250-300 grams oven-dry material for analytical purposes.

The composite samples contain approximately the same quantity of flesh from each fish. For each composite, a subsample of material is drawn for analysis.

Samples of white crappie and smallmouth buffalo are taken -asiannually from Guntersville and Wheeler Reservoirs and analyzed for gamma-emitting radionu-clides as a part of the BFN monitoring program. In the SQN monitoring program, samples of white crappie and smallmouth buffalo are taken semiannually from Nickajack Reservoir and analyzed for gross beta and gamma-cmitting radionuclides.

In addition, a9Sr and 90 Sr concentrations are determined in one smallmouth buffalo flesh sample and in two whole smallmouth buffalo samples. The data fron the analysis of these samples are included herein in tables 23, 24, and 25.

Ta?LE 22 aAD13ACT141ty 1% suaFACE .ATES TCTAL o;}/L - L.037 ^G/L

  • CCCMET No. Tv&/Cas/04 *1/10
      • f r rA !L:Tr_;(g(LFnNtr _____ ___________

FG8 TING & l s 1 C 0.1211___.. ._

_ __i( A ti a " A _

LOC Y!?- 0F F A C I L I T v __J1(w_(O N CONTROL NJMSE4 0F LIwIT ALL NCNRLJTINE TvPL f. N D L9 m E 't (23 T I % .ill*1_j lh(S_T _1Muk _* ( 2. 5 LOCATICN{ REPOETED T3TAL '. u M s E - UF IN lCATDA LCCAT!'NS *EA% fr)b PEAN (F)

  • 4 s - E =tiget=t311__

3r ANAtyt!S CETECT10Na utAN (F)

_______disfzLI______ llilliEL n2.2LiGil2L -lii@ c a uf_ __

__dLiME* G iLLit.___

5tega (NAI) 1 VALUES <LLD l 1

. VALUES <tL3 ANALvs15 PERFOR*E3 5A984 (GELI) yaw . 93 224 1/ II

_3.224 v 1f 3 3 -3.3 4.,; N3T ESTA3 93.22 - H.22 S3 22- 93.22 f 3, T** 3-s.1 3 31.12( 1/ 2) ag

' - ,14 NOT ESTAB 3 .1 31 12 31.12- 51 12 1 VALUES CLL3 sg -9 10.cc0 2 VALUES <LLD

~

ANALYSIS PERFOR4E3 1 VALUES CLLD 3, 4 2 000 2 VALUES (LL3 Ar4 A L V S I S PEeFOA"E3 1 VALUES (LLO TRITIUM 330.000 2 VALUES <LL3 ANALYSTS PERFOR*ED

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

l Ta9LE 23 aa0104071v!TY IN WHITE C4aPPIE (F LE H)

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4tPCFTING PERIOD ,1911 _ ,, _ _ _

TYPE isS LS.Ta LI"!T ALL CGNTROL NUMEE4 CF T3Tal %.e[- M I P.9 t C A T C 4 LScaTIONS (2;ill25,.lT 3_jlEH_(S T A33g;Lj[ah,__, LOCATIONg NCNROJTINE 0: ANAlft!s 2E f f C T 10 Na *EAN (F r NA*E "LAN (fib WEAN 3 REPO4TED ik g anNGd 21111h;(,a32,qli;(llgN kANQ@ PaMG M L A 12R LE.Lill,,

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05-137 C..?O C.12t */ 4) GJNTE'SVILLE 4ES 0.141 2/ 2) 0.09( 1/ 1) 0.O'- 3.la i4M 349-*25 0.09- 0 1A 0.09- 0.09

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3.;6t 1/ 4) .HEFLE8 #fS 3.36t 1/ 23 1 VALUE <LLD

!.6- 3 05 Ter 275-34s C.06- 0.C6 P3-212 N3T ESTAB 0.924 2/ 4) GUNTL45VILLE RES 0.326 1/  ?) 1 VALUE <LUD C.02- 0.72 Tag 3g9 425 0.02- 0.02

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

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45 Quality Control A quality control program has been established with the Alabama Department of Public Ilealth Radiological Laboratory and the Eastern Environmental Radiation Facility, Environmental Protection Agency, Montgomery, Alabama. Samples of air, water, milk, fish, and soil collected around nuclear plants are forwarded to these laboratories for analysis, and results are exchanged for comparison.

Conclusions Since BLN has not achieved criticality, there has been no con-tribution of radioactivity to the environment from the operation of the plant.

The levels of radioactivity being reported in this document are due to natural background radiation, fallout from nuclear weapons testing, or other nuclear operations in the area.

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