ML110840228
| ML110840228 | |
| Person / Time | |
|---|---|
| Site: | Bellefonte  |
| Issue date: | 06/30/1982 |
| From: | Mills L Tennessee Valley Authority |
| To: | Adensam E Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML110840229 | List: |
| References | |
| NUDOCS 8207060273 | |
| Download: ML110840228 (51) | |
Text
TENNESSEE VALLEY AUTHORITY R-AGM~ATfTy MCMN?
RADIOLOGICAL HEALTH-STAFF
TENNESSEE VALLEY AUTHORITY CHATTANOOGA. TENNESSEE 37401.
400 Chestnut Street Tower II June 30, 1982 Director of Nuclear Reactor Regulation Attention: Ms. E. Adensam, Chief Licensing Branch No. 4 Division of Licensing U.S. Nuclear Regulatory Commission Washington, DC 20555
Dear Ms. Adensam:
In the Matter of the Application of ) Docket Nos. 50-438 Tennessee Valley Authority ) 50-439 Enclosed for your information are 20 copies of the report:
Environmental Radioactivity Levels Bellefonte Nuclear Plant Annual Report - 1981 The report presents the results obtained from TVA's preoperational environmental radiological monitoring program during 1981.
Very truly yours, TENNESSEE VALLEY AUTHORITY L. M. Mills, Manager Nuclear Licensing Enclosure (20) cc: U.S. Nuclear Regulatory Commission (Enclosure)
Region II Attn: Mr. James P. O'Reilly, Regional Administrator 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 8207060273 e206-30o-o PDR ADOCK 05000438 R
PDR An Equal Ooportunmty Empiover
REQULATORY T NFtOR MATIDN DIST LUTION SYSTEM.(RIDS)
ACCESSION NBR: 8207060273 DOC.DATE: 82/06/30 NOTARIZED: NO DOCK #
FACIL:eOZ4389 Bellefonte Nuclear Plant, Unit 1, Tennessee Vailejy Au 050 0438 50-439 Bellefonte Nuclear Plant, Unit 2, Tennessee Valley Au 05 00439 AUTH.NAME AUTHOR AFFILIATION MILLSL.M. Tennessee Valley Authority RECIP.NAME RECIPIENT AFFILIATION ADENSAME. Licensing Branch 4
SUBJECT:
Forwards "Environ RadioactivitM Levels, Bellefonte Nucle DISTRIBUTION CODE: IE25S COPIES RECEIVED:LTR L ENCL IZE:
_TITLE: Periodic Environ Monitoring Rept (50 DKT)-Annual/Semiannual/Effluent/
NOTES:
RECIPTENT tDPTES W>RECTPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL LIC BR #4 BC 04 7 7 INTERNAL: AEOD 1 1 IE FILE 01 1 1
. PIPA 1 NRR/DE/EEB 08 -~1 I
_ IRRZDS12ETSB 1. 1
0R/DS1LARAB, A EXTERNAL: ACRS 11 1 LPDR 03 1. 1 NRC-PDR . 02 1 NTIS 05 :1 -~
TOTAL NUMBER DF COPIES REGUIRED: LTTR 1B ENCL 18
ENVIRONMENTAL RADIOACTIVITY LEVELS BELLEFONTE NUCLEAR PLANT ANNUAL REPORT - 1981 TVA/OMS/OHS - 82/10 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 ii
LIST OF TABLES Page Table 1 - Environmental Radioactivity Sampling Schedule . . . . .. 3 Table 2 - Atmospheric and Terrestrial Monitoring Stations Locations .............. ... 44.....
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 iii
LIST OF FIGURES Page Figure 1 - Tennessee Valley Region............. . . . . 10 Figure 2 - Atmospheric and Terrestrial Monitoring Network . 17 Figure 3 - BLN Site Monitoring Stations. . . . .. .. . . . .. 18 Figure 4 - Annual 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 iv
ENVIRONMENTAL RADIOACTIVITY LEVELS BELLEFONTE NUCLEAR PLANT ANNUAL REPORT 1981 Introduction The Bellefonte Nuclear Plant (BLN), being constructed 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 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.
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, Nal(T2), 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 1311) 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 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 1311 concentrations in milk. Tritium determinations are made with Beckman LS150, Beckman LS100C, and Packard Model 3250 liquid scintillation counting systems.
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(TQ). The data obtained by Ge(Li) detectors were resolved by the appropriate analyzer software 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(Tk) gamma spectroscopy were analyzed for 13 specific gamma emitting radionuclides and radionuclide combinations a. For these analyses, radionuclide combinations such as lo3a106 Ru and gsZr-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 7 Be, 40 K, 2 12 Bi, Bi, 2 12 Pb, 1 Pb, 2 2 6 Ra, etc. LLDs for the analysis of the radio nuclides listed belowa are given in table 3B. LLDs for additional radio nuclides identified by Ge(Li) analysis were calculated for each analysis, and nominal values are listed in the appropriate data tables. In the instance where an LLD has not been established, an LLD value of zero was assumed. A notation in a table of " values <LLD" for an isotope with no established LLD does not imply a value less than 0; rather, it indicates that the isotope was not identified in that specific group of samples. For each sample type, only the radionuclides for which values greater than the LLD were reported are listed in the data tables.
TVA's radioanalytical laboratories 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 +/-3o limits based on one measurement were divided by the square root of 3 to correct for triplicate determinations.
a The following radionuclides and radionuclide combinations are quantified by the ALPHA-M least-squares com uter code: 41
, 44 Ce; 5 1 Cr; 1811. Ru 4 7 Cs; 9 5 13 Cs; '8 Zr-Nb; 58Co; Mn; 6 sZn; soCo; 4 0K; and 14 OBa-La.
3 Table 1 ENVIRONMENTAL RADIOACTIVITY SAMPLING SCHEDULE BELLEFONTE NUCLEAR PLANT Air Charcoal Rain Heavy Particle Well Public Surface U Station Location Filter Filter water Fallout Vegetation Milk Water Water Water Fish Site SW W w H M4 Q Site NE W W 1 M Q Scottsboro W W M M Q M Hollywood W W M 1Q Fackler W W M Q Stevenson W W M Q Pisgah W W 1 M Q Section W W 1 M Q Lim Rock (Control) W W M H Q Rainsville (Control) W W M M Q Farm S 1 Farm D (Control) M Farm C (Control) Q Well A (Control) H Onsite Wells (6) M Sand Mountain Water &
& Fire Protection Authority N Widows Creek Steam Plant (Control) 1 Wheeler Reservoir c a Guntersville Reservoir Q S Nickajack Reservoir b (Control)
W - Weekly M - Monthly (every four weeks) Q - Quarterly S - Semiannually aSamples collected as a part of the Browns Ferry Nuclear Plant monitoring program.
bSamples collected as a part of the Sequoyah Nuclear Plant monitoring program.
cSampling initiated in fourth quarter 1981.
4 Table 2 Atmospheric and Terrestrial Monitoring Stations Locations Bellefonte Nuclear Plant Approximate Distance Sample Station and Direction from Plant Indicator Stations LM - 1 BL, Southwest 3/4 mile (1-1/4.kilometers) SW LM - 2 BL, Northeast I 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 Farm S 5 miles (8 kilometers) w 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 SAMPLE ANALYSIS DETECTION CAPABILITIES FOR ENVIRONMENTAL A. Specific Analyses NOMINAL LOWER LIMIT OF DETECTION (LLD)*
Fish, Soil and clam flesh, Foods, meat, Vegetation Milk Air Sediment plankton, pCi/g,shells Clam dry poultry, pCi/k. wet. PCi/i Charcoal Fallout Water and grain Particulates 3 3 2 pCi/g, dry _pCi/g, dry pCi/. dry pCi/in pCi/in mCi/km pCi/l 1.5 0.4 0.01 Total a 0.35 0.1 0.7 2.0 0.05 0.1 25 Gross a 0.005 0.70 0.7 0.05 2.4 0.20 Gross 8 0.01 330 0.5 131 0.02 40 10 1.5 0.5 5.0 10 0.25 8 2
- Sr 0.005 0.3 0.1 1.0 2 0.05 SoSr 0.001 as described in RASL-300.
by the method developed by Pasternack and Harley
- Al LLD values for isotopic separations are calculated efficiency may vary for a given sample; these variations chemical yield, and counting week of the Factors such as sample size, decay time, all samples are analyzed within one sample. The assumption is made that may change the LLD value for the given 10-2 Bq; 1 mCi = 3.7 x 107 Bq.
collection date. Conversion factors: 1 pCi = 3.7 x U,
Table 3 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS B. Gamma Analyses NOMINAL LOWER LIMIT OF DETECTION (LLD)
Foods,(tomatoes Meat and Water Vegetation Soil and Clam f lesh Air Clam shells potatoes, etc.) poultrywe' pCi/k, and milk and grain sediment Fish and plankton part iculates pCi/g, dry pCi/g, dry pCi/kp, wet_
pCi/i pCi/g, dry pCi/g, dry pCi/g, dry NaI Ge(Li) NaI Ge(Li) pCi/n )* NaI Ge(Li) Nal Ge(Li) Na Ge(Li NaI* Ge(Li)** Nal Ge(Li) NaI Ge(Li) Nal Ge(Li).
90 0.35 0.35 0.35 38 141,144Ce 0.03 38 0.55 0.35 33 0.22 0.06 0.06 0.06 14 4 Ce 0.02 33 0.10 0.60 0.10 60 44 200 90 20 44 1.10 0.47 0.60 0.60 0.10 0.56 0.02 15 8 s Cr 0.07 0.03 60 0.20 150 0.09 0.20 0.02 0.20 0.02 0.07 0.45 1311 0.01 0.01 15 8 0.35 40 103,10 6Ru 40 0.65 0.45 0.45 40 90 0.04 0.11 0.74 0.11 40 106 Ru 40 0.51 0.11 0.48 0.12 50 0.03 0.08 0.08 10 26 5 40 15 10 26 0.20 0.33 0.12 0.08 0.12 0.12 0.02 0.01 0.02 0.08 10 40 37 10 5 0.20 0.06 0.12 0.02 0.12 0.02 1 Cs 0.01 0.01 0.12 10 1 0.20 0.12 0.12
' Zr-Nb 0.01 10 0.03 10 20 0.11 0.03 0.03 0.15 9Sr 0.01 10 0.01 5 15 95 Nb 0.01 5 0.01 0.01 0.07 0.05 0.20 0.01 15 5 55 40 15 15 5 0.23 0.20 0.01 0.20 0.01 0.15 0.01 10 5 5 'Co 0.02 0.01 15 0.05 0.01 0.15 0.01 20 5 0.20 0.15 0.23 0.02 15 9 70 0.02 0.01 10 0.02 0.23 0.02 15 5
Zn 9 0.25 0.11 0.23 0.11 0.01 10 5 30 6
0.02 0.01 15 0.11 0.01 10 5 0.17 0.06 0.11 0.01 0.0 0.08 150 400 6 'Co 0.01 0.01 0.17 0.90 150 0.90 0.90 0.08 15 50 4oK 0.10 2.50 0.15 50 15 0.68 0.15 0.15 0.07 25 1'Ba-La 0.02 0.07 0.07 0.30 15 0.02 25 0.34 0.02 7 0.02 0.02 0.10 14 *La 0.01 7 0.08 91, Pasternack and Harley as described in HASL-300 and Nucl. Instr. Methods
- The NaI(T1) LLD values are calculated by the method developed by in the samples. These figures do not on the activities of'the components 533-40 (1971). These LLD values are expected to vary depending fi *sh, soil, and sediment represent the LLD values achievable on a given sample. average Water' is counted in a 3.5-1, Marinelli beaker.. Vegetation, container as dry weight. The dry weight is 120 grams for vegetation and 400-500 grams for soil sediment and are counted in a 1-pint then corrected to wet weight using an average moisture content of fish. Meat and poultry are counted in a 1-pint container as dry weight, in a well crystal. The counting system consists of a multichannel 70%. Average dry weight is 250 grams. Air particulates are counted analyzer and either a 4" x 4" solid or 4" x 5" well NaI(Tl) crystal. The counting time is 4000 seconds. All calculations are performed by The assumption is made that all samples are analyzed within one week of the collection date.
the least-squares computer program ALPHA-M.
Pasternack and Harley as described in HASL-300. These LLD values are expected
components in the samples. These figures do not represent the to vary depending on the activities of the sediment, and clam shells are counted in a 0.5-L Solid samples such as soil, Water is counted in either a 0.5-L or 3.5-L Marinelli beaker. are counted in petrie The average dry weight is 400-500 grams. Air filters and very small volume samples Marinelli beaker as dry weight. and either a 25%, 14%, 16Z, or 29% Ge(Li) system consists of a ND-4420 multichannel analyzer dishes centered on the detector endcap. The counting 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 />. All spectral analysis date.
one week of the collection assumption is made that all samples are analyzed within Conversion factor: 1 pCi = 3.7 x 10~ Bq.
&_- d
a A 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 (+/-3a) WARLaEARLb (+/-3cr) WARL EARL (+/-3cT) WARL EARL (+/-30) WARL EARL 12/80 21+/-9 22 23 19+/-9 24 26 0 2 <2 19+9 20 22 30+/-13 31 31 50+/-9 55 49 18+/-2.6 18 15 c 14+/-9 15 14 3/.81 28+/-12 29 32 54+/-9 62 59 19+2.6 19 23 c 16+/-9 17 18 6/81 25+/-11 26 25 51+/-9 61c 54 16+/-2.6 16 19 c 19+/-9 21 20 9/81
]B. Tritium in Urine (pCi/L)
Date EPA Value (+/-3a) TVA AVERAGE WARL EARL 3/81 810+549 713 390 6/81 1600+/-585 1637 1830 d 9/81 2050+/-599 2103 - e 11/81 2700+/-615 2573 2623
- a. Western Area Radiological Laboratory, Muscle Shoals, Alabama
- b. Eastern Area Radiological Laboratory, Vonore, Tennessee
- c. Efficiency curves were checked and known spikes were run. Everything found was within acceptable limits.
We are awaiting the next cross-check for further investigation.
- d. Results were mailed to EPA but not reported by them.
- e. Sample was lost in analysis. There was insufficierit time to obtain another sample from EPA-and reanalyze.
Table 4 (Contd)
Results Obtained in Interlaboratory Comparison Program C. Radiochemical Analyses of Water (pCi/L) f Gross Alpha Gross Beta Strontium - 89 Strontium - 90 Tritium Iodine - 131 EPA value TVA AVG. EPA value TVA AVG. EPA value TVA AVG. EPA value TVA AVG. EPA value TVA AVG. EPA value TVA AVG.
Date (+/-3a) WARL EARL (+/-3o) WARL EARL (+/-30) WARL EARL (+3a) WARL EARL (+/-3a) WARL EARL WARL EARL
(+/-30) 1/81 9+9 10 9 44+/-9 49 49 16+/-9 11 14 34+/-3.1 2/81 3 8g 2 8h 1760+/-591 . 1917 1753 3/81 .25+/-10 23 15i 25+/-9 26 29 4/81 2710+/-615 2467 2723 30+/-10 32 28 5/81 .21+/-9 21 14 14+/-9 14 16 36+/-9. 40 33 22+/-2.6 21 22 6/81 1950+596 1990 1947
.7/81 22+/-10 20 22 15+/-9 15 18 8/81
.i 2630+/-613 2623 2713 73+/-13 79 73 9/81 33+/-14 29 18 28+/-9 29 26 23+/-9 26 23 11+/-2.6 11 10 10/81 2210+/-603 2263 2197 11/81 21+/-9 21 13 23+/-9 18 24 12/81 2700+/-615 2717 2807 76+13 65 56 D. Gamma-Spectral Analysis of Water (pCi/L)
Chromium - 51 Cobalt - 60 Zinc - 65 Ruthenium - 106 Cesium - 134 Cesium - 137 EPA value TVA AVG. EPA value TVA AVG. EPA value TVA AVG. EPA value TVA AVG. EPA value TVA AVG. EPA value TVA AVG.
Date (+3(7) WARL EARL (+/-3a) WARL EARL (+39)
-- WARL EARL (+/-_y) WARL EARL (+/-3a)' WARL EARL (+/-3a) WARL EARL 2/81 0 <60 <60 25+/-9 25 25 85+/-9 84 83 0 <40 <40 36+9 39 35 4+/-9 6 10 6/81 0 <60 <60 17+/-9 18 17 0 <15 <15 15+/-9 <40 <40 21+/-9 23 21 31+9 27 30 10/81 34+/-9 <60 <60 22+/-9 25 22 24+/-9 26 21 0 <40 <40 21+/-9 21 24 32+/-9 35 32
- f. Specific analysis for 131I to test the procedures used for the analysis of milk.
- g. Investigations of the analytical procedure were conducted and new efficiency curves were determined. Results have been satisfactory since that time.
- h. New efficiency curves were determined subsequent to this analysis. Subsequent results were satisfactory.
- i. Excess humidity in counting room and a change in the amount of solid introduced into the sample by EPA are suspected in the difficulty with this sample type. Steps have been taken to correct or compensate for these items.
- j. Results are possibly due to an incorrect chemical form of the precipitate counted in this procedure. Investigations continue.
a, to.4)
Table 4 (Contd)
Results Obtained in Interlaboratory Comparison Program k
E. Milk (pCilL)
,Cobalt - 60 Iodine - 131 Cesium - 137 Barium - 140 Potassium TVA AVG.
Strontium - 89 Strontium - 90 *EPA value EPA value TVA AVG. EPA value TVA AVG.. EPA value TVA AVG. EPA value TVA AVG. A3a) WARL EARL EPA value TVA AVG. EPA value TVA AVG.
EARL (+/-30y) WARL EARL (+/-3u) WARL EARL (30W) WARL EARL (+/-3a) WARL EARL Date (+/-30) WARL EARL (3a) WARL 20 26+/-17 24 21 43+/-16 40 41 0 <25 <15 1550+/-232 1490 1453 1/81 0 <10 <10 20+/-5. 2 21 e 13 26+/-10 21 29 22+/-9 21 24 0 <15 <15 1559+/-135 1513 1674 4/81 25+/-9 e 28 11+/-2.6 14m 16 .01+/- <15 <15 31+9 32 32 0 <15 <15 1600t139 1623 1620 7/81 25+/-9 23 30 17+/-2.6 16 52+ 10 49n 47 25+9 27 27 1530+/-133 1620 1500 10/81 23+/-9 25 28 18+/-2.6 17 0
F. Foods (pCi/kg, Wet Weight) r 119+/-21 126 121 53t9 56 55 q 0 <15 <15 2640+/-229 2857 2917 3/81 47+/-9 42 44 29+/-2.8 38P 21 32 82+/-14 80 106 q 45t9 43 54 0 <25 <25 2640+/-229 2870 3437 q 7/81 44+/-9 53 51 31+/-2.8 31 49 54 23+/-2.6 25 22 None 33+9 29 35 0 <15 <25 2730+/-237 2 8 20 r 2720 30t9 25 32 11/81 38+/-9
- k. Values for potassium are reported as mg/liter of sample.
Subsequent results have been satisfactory.
M. Results were marginally out of limits. Efficiency curves were checked with no conclusive findings.
- n. Only two results were sent to EPA. Results were not included in their analysis.
- o. Values for potassium are reported as mg/kg sample.
- p. Investigation of this problem was initiated but no satisfactory conclusions have been reached. We suspect difficulties arising from sample inhomogeniety.
Further analysis destroyed the sample so that the correct weight could
- q. An incorrect weight was obtained in the gamma analysis of this sample.
not be determined.
are satisfactory.
- r. Investigation was conducted. No satisfactory explanation was found. Other cross-checks on this isotope in different media
TENNESSEE VALLEY REGIOI (V LOUISVILLE I N D.
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4
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 ft3 /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 monthl for analysis of specific gamma-emitting radionuclides and quarterly for 8 Sr, 9 oSr analysis. The results are presented in table 6.
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 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 (MPC) recom mended by 10 CFR 20 for nonoccupational exposure.
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 malfunction. The filter is counted in a single channel analyzer system. The data are shown in table 9.
12 Table 5 MAXIMUM PERMISSIBLE CONCENTRATIONS w
FOR NONOCCUPATIONAL EXPOSURE MPC In Water In Air pCi/1* pCi/m3*
Alpha 30 Nonvolatile beta 3,000 100 Tritium 3,000,000 200,000
'3 s 20,000 500 103, 1 06R 10,000 200 J4Ce 10,000 200 9 5 Zr- 9 5 Nb.
60,000 1,000 140Ba-1r4OLa 20,000 1,000 1311 300 100 6 5Zn 100,000 2,000 54 Mn 100,000 1,000 60 Co 30,000 300 89r 3,000 300 9 6Sr 300 30 5 Cr 2,000, 000 80,000 9,000 400 58 Co 90)0001 2)000
- 1 pCi = 3.7 x 102 Bq.
Y I
TABLE 6 RADIOACTIVITY IN AIR FILTER PCI/M.3) - 0.037 BQ/Mt3)
NAME OF FACILITY RELLEFONTE DOCKET NO. TVA/OMS/OHS-82/10 LOCATION OF FACILITY__ACKSON A -BAMA REPORTING PERIOD_1 TYPE AND LOWER LIMIT ALL CONTROL NUMBER OF TOTAL NUMSER OF INDICATOR LOCATIONS LOCATION WITH HIEUa1ANNUAL MEAN LOCATIONJ NONROUTINE OF ANALYSIS DETECTIONa MEAN (F)b NAME MEAN F)b MEAN (F) REPORTED
?ERFORMED (LLD) RANGEb QI TAAUQg1!g.QjN RANGP_ RANGE KLIgggLMENTSg GROSS BFTA 0.010 0 38( 403/ 413) LMI BL SOUTHWEST 0.09t 49/ 50) 0.08( 98/ 100) 513 0.01- 0.34 0.8 MILE SW 0.01- 0.29 0.01- 0.34 GA44A (NAI) 45 CE-1419144 0.030 0.05( 3/ 30) PM4 STEVENSONvAL 0.07t 1/ 4) 0.07£ 1/ 15) 0.03- 0.07 11.0 MILES NNE 0.07- 0.07 0.07 0.07 BA-140,LA-140 0.020 30 VALUES <LLD 0*02£. 1/ 15) 0.02 0.02 RU-1039t06 0.340 0.05( .1 30) PM4 STEVENSONAL 0.*05( 1/ 4) 0.064 2/ 15) 0.05- 0.05 11.0 MILES NNE. 0.05 0.05 0.05 0.06 zR-95,NBC-95 0. 10 0.04( 13/ 30)' PM4 STEVENSONeAL 0.09£ 2/ 4) 0.05t 5/ 15) 0.02- 0.15 11.0 MILES NNE 0.03- 0.15 0.03 0.12 1-131 0.010 30 VALUES <LLD 0.01 2/ 15) 0.01 0.01 BE-7 NOT ESTAB 0.07£ 27/ 30) PM4 STEVENSDNAL 0.09£ 4/ 4) 0.074 14/ 15) 0.03- 0.19 11.0 MILES NNE 0.05- 0.19 0.02- 0.19 GAMMA (GELII 85 CE-141 0.010 0.01t 7/ 74 PM5 PISGAHAL 0.01t 1/ 9) 0.020 1/ 11) 0.01- 0.01 4.3 MILES. ESE 0.01- 0.01 0.02- 0.02 CE144 0.020 0.04 16/ 741' PM3 FACKLERsAL 0.06£ 2/ 9) 0.02£ 1, 11 0.02- 0.07 5.2 MILES N 0.04- 0.07 0 02- 0.02 RUi103 NOT ESTAB 0.01£ 35/ 74) PM5 PISGAHiAL 0.02 5/ 9) 0.01£ 7/ 11) 0.01- 0.03 4.3 MILES ESE 0 01- 0.03 0.00- 0.02 Z00010 0.03( 36/ 74) PM5 PISGAHqAL 0.05( 3/ 9) 0.03( 4/ 11) 0.01- 05 4.3 MILES ESE 0.03- 0.06 0.02- 0.03
- 0.010 0.06t 40/ 74) PM5 PISGAHAL 0.09( 4/ 9) 0.04£ 8/ 11 0.01- 0.13 4.3 MILES ESE 0.04- 0.13 0.01- 0.08 K-40 NOT ESTAB 0.12( 491 74) LM1 BL SOUTHWEST 0.15£ 7/ 8) 0.14£ 6/ 11) 0.06- 0.22 0.8 MILE SW 0.11- 0.22 0.03- 0.30 B1-214 0.020 0.04£ 50/ 74) PM1 SCOTTSBOROA 0.064 6/ .9) 0.04( 7/ 11) 0.02- 0.12 5.6 MILES *SU 0.03- 0.11 0.03- 0.07 P3-214 0.020 0.53£ 35/ 74) PM6 SECTIONtAL 4.36( 4/ 11) 0.03£ 6/ 11 0.02- 17.22 9.2 MILES SSW 0.34- 17.22 0.02- 0.05 P3-212 NOT ESTAB 0.02( 31/ 74) PM5 PISGAHAL 0.02( 3/ 9) 0.02£ 5/ .11) 0.00- 0.03 4.3 MILES. ESE 0.01- 0.03 0.00- 0.04 3E-7 0.050 0.08( 33/ 74) PM5 PISGAH9AL 0.09£ 3/ 9) 0.07( 5/ 11) 0.05- 0.13 4.3 MILES ESE 0.06- 0.11 0.05- 0.09 TL-208 NOT ESTAB 0.01( 13/ 74) PM2 HOLLYWOODAL 0.01t 1/ 9) 0.01( 4/ 11 0.00- 0.01 1.8 MILES WNV 0.01- 0.01 0.01- -0.02 SR 89 0.005 0.01( 16/ 32) LML BL SOUTHWEST 0.01£ 2/ 4) 0.0it 4/ 8) 0.01- 0.01. 0.8 MILE SW 0.01- 0.01 0.01- 0.01 SR 90 0.001 0.00( 8/ 32) LM2 BL ENV DATA 0.00 1/ 4) 0.00( 1/ 8) 0.00- 0.00 1.0 MILE NE 0.00- 0.00 0.00- 0.00
- a. Nominal Lower Lidit 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).
TALE 7 RADIOACTIVITY IN RAINWATER PCI/L - S.037 B I4 NAME OF FACILITY BELEFOJTE DOCKET NO. TVA/Q/0HS-82 £10 LOCATI31% OF FA0.ILITY_-ACKa'ON ~.LA~AMA REPORTING PERIOD TYPE AND LOWER LIMIT ALL CONTROL NUMBER OF TOTAL NUM6ER OF INDICATOR LOCATIONS LOCA ITH H LOCATION% NONROUTINE OF ANALYSIS DETECTION a MEAN (F)b NAME MEAN (F) b MEAN ) REPORTEO
_ERFORMED (LLD) A GgEb _ AI N___ RAN b GAMMA (NAI)
CE-141,14A 38 .000 44.40t 1/ 72) PM4 STEVENSONqAL 44.401 1/ 6) 21 VALUES <LLD 44.40 44.4 0 11.0 MILES NNE 44. 0 44.40 RU-103,106 40.000 52.93( 3/ 72) PM3 FACKLERAL 59.50( 1/ 9) 21 .VALUES <LLD' 40.90 59.50. 5.2 MILES N 59.50 59.50 ZR-95sN8-95' 10.000 16.93(, 22/ 72) PM3 .FACKLERAL 20.70s 3/ 9) 14.634 6 21) 10.20 31.40 5.2.MILES N. 14.0.0 31.40 11.70 22.00 GE-7 NOT ESTAB 63.77i 45/ 72) PM2 HOLLYWOOD9AL 79.210 7/ 10) 53.694 17/ 21) 14.90 152.10 1.8 MILES WNW. 24.40 152.10 16.20 117.30 GAMMA GELI 35 10.000 37.66A 1/ 30) PM3 FACKLER9AL 37.66( 1/ 4) 10.33t 1/ 5) 3 7.66 3.7.656 5.2 MILES N 37.66 37.66 10.33 10.33 N -95. 5.000 33.85A, 4/ 3.0) PM3 FACKLERIAL 84.064 1/ 4) 13.021 :1/ 5) 5.2 MILES N 84.0 6 84.06 13.02 '13'.02
- -40 NOT EST AB 113.934 11/ 30) PM2 HOLLYGODAL 165.194 2/. 3) 72.90C 3/ 5) 68.49 255. 10 1.8 MILES 'ANW 75.2 7 255.10 5.4.43 86.64 BI-214' NOT STAB 20.824 19/ 30) LM1 BL 'SOUTHWEST, 33.39( 1/ 4)'* 18.42t. 3/ 5i
- .16, 44.90 0.8 MILE SW 33.39 33.39 '12.*41: .21.88 NOT ESTAB 18.82( 14/ 30) PM2 HOLLYWOOAL 33.524 2/ 3) 9.314 '2/ .5) 642 52.00' 1.8 MILES UNW 15.04 52.00 8.04 10.58 PB-212 NOT ESTAB 13.23t 5/ 301 PM2 MOLLYWOODgAL 18 .07 1/ 3), 9.65( 2/ 5) 7.21 18.07 1.8 MILES WNW 18 e 07 *4.68 14.62 BE-7 NOT ESTAB 62.590 ( 4/ '30) PM4 STEVENSDN9 A. 81.694 1/ 6) 80.7,8( '1/ ~5) ~
45.87- 81.69 11.0 MILES NNE 81.69- 81.69 80 .78- 80.78
- 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.
O0*
TABLE 8 RADIOACTIVITY IN HEAVY PARTICLE FALLOUT MCI/KM(2) - 373 0q00.00.0/KM12)
DOCKET NO. TVA/OMS/0HaE2/1Q N'AME OF FACILITY .ELLEFONT REPORTING PERIOD-12i ----------------
LOCITION OFFACILITY JACKSON-------------
CONTROL NUMBER OF TYPE AND LOiER LIMIT ALL LOCATIONS NONROUTINE OF INDICATOR LOCATIONS.. LOTION HHIGHEST ANNUAL MEAN TOTAL NUMBE'_ 'MEAN OF)b MEAN MEAN (F)b REPORTED DETECTION a NAME RANGE D ANALYSIS hNGEb MEALSU R !EN1U_
R ANG Eb A.ND_ QL.R C ION 0,j At[CE _
E1FORMED (LLD) 1.15( 26/ 26) 0.* 5 PM4 STEVENSON,.AL 1.22( 13/ 13)
GlOSS BETA 3.26 0.07- 3.35
. .I I . 1 13 , 0.06- 3.26 11.0 MILES NNE 0.11-
- a. Nominal Lower Limit-of Detection (LLD) as described in Table 3.
at specified locations is indicated in parentheses (F).
- b. Mean and range based upon detectable measurements only. Fraction of detectable measurements
- 4
TABLE 9 RADIOACTIVITY IN C4ARCOAL FILTERS PCI/M(3) - 0.C37 BG/M(3)
NAME CF FACILITY BELLEFONTE ---.- __ DOCKET NO._AQ Q:E 11.
LOCATION OF FACILITY JACKSON-------- A --- -
_ REPORTING PERIOD 121 --
ALL CONTROL NUMBER OF TYPE AND LOWER LIMIT NONROUTINE OF INDICATOR LOCAbTIONS LOCATION WIH HIGHEST ANNUALE AN LOCATION%
TOTAL NUMBER REPORTED MEAN IF) NAME MEAN (F v MEAN ()
O= ANALYSIS DETECTIO a tEASUREMENIj...
11.AMLE NE 0.02- 1ANGEb RANGE DC -. LL:
513ORMED *0N2Eb 1
- 52) 0.03( 183/ 100)
IODIN~E IN AlI, C3( 65/ 413) PM4 STEVENSON*A- 0.04 ( 14/
0 .32- 0.16 0.02- 0.06 C9 2 3.1 ; 11.0 MILES NNE
- a. Nominal Lower Limit of Detection (LLD) as described in Table 3.
is indicated in parentheses (F).
- b. Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations
17 Figure 2 BELLEFONTE NUCLEAR PLANT ATMOSPHERIC AND TERRESTRIAL MONITORING NETWORK 20 miles NOTE THE FOLLOWING SAMPLES ARE COLLECTED FROM EACH STATION AIR PARTICULATES RAINWATER RADIOIODINE SOIL HEAVY PARTICLE FALLOUT VEGETATION
18 Figure 3 BELLEFONTE NUCLEAR PLANT SITE MONITORING STATIONS
19 4
0.20.
0.15 Annual Average 0m Gross Beta Activity a0
- a En CO In Air (Particulate Filters) p ma 0 0.10 Bellefonte Nuclear Plant 0.05 0
1978 1 1979 1981
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 13i, 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 9 oSr in milk samples from farms producing milk for private consumption only are up 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 9 oSr-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 9 oSr 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, 89 Sr, and 9 oSr. The results are given in table 12.
aHansen 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.
22 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, 89 Sr, 9 OSr, and tritium. The results are shown in table 14. Figure 5 shows the trends in gross beta activity in drinking water from 1978 through 1981.
Environmental Gamma Radiation Levels Bulb-type Victoreen Manganese-activated calcium fluoride (CaF 2: 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 near the site boundary and TLIs were placed at 18 stations located in the different meteorological sectors 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.
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 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 averages. The data follow the same general trend as the raw data, but the curves are smoothed considerably.
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.
TABLE 10 RADIOACTI.VITY IN MILK PCI/L - 0*037 30/L IN' NAME OF FACILITY BELLEFONTE DOCKET NO. j1A/0mS/OH-82L..
LOC'TION OF FACILITY JACKSON- ALABAMA REPORTING PERIOD 1981 TYPE AND LOWER LIMIT ALL CONTROL NUMBER OF TOTAL NUMBE2 OF INDICATOR LOCAbTIONS L~ALLON WITHl MIGHEST ANNUAL MEAN LOCATIONS NONROUTINE OF ANALYSIS DETECTION a MEAN (F) NAME MEAN (F)b MEAN (F)b REPORTED 1
P1 1 L2_L TL, RAN GE' 22 CS-137 10.000 13.31( 9/ 10) SISK FARM 13.31( 9/ 10) 12 VALUES <LLD 10.10- 17.80 4.9 MILES SW 10.10 17.80 K(-40) 1177.711 10/ 10) SISK FARM 1177.71( 10/ 10) 1231.97( 12/ 12) 10.000 ?29.60- 1413.49, 4.9 MILES SW o29.60 1413.40 1138.00- 1356.50 IODINE IN MILt K 050 13 VALUES <LLD 13 VALUES <LLD 264 ANALYSIS PERFORMED GAMMA (GELI)
CS-137 5.000 17.16( 3/ 3) SISK FARM 17.16( 3/ 3) 1 VALUES <LLD
- 14.75 18.44 4.9 MILES Sw 14.75 18.44 K-4 0 NOT ESTAB 1366.00( 3/ 3) SISK FARM 1366.00f 3/ 3) 1682.00( 1/ 1) 1333.00 1400.00. .4.9 MILES SW 1333. 00 1400.00 1682.00- 1682.00 3-214 NOT ESTAB 37.57,( 2/ 3)0 SISK FARM 37.574 2/. 3) 40.64f 1/ 1) 29.31 45.83 .4*9 MILES SW 2,9.31 45.83 40.64- 40.64.
P3-214 NOT ESTAS 28.34( 2/ 3) SISK FARM 28.34( 2/ 3) 42.79( 1/ 1) 13.77 42.50 4.9 MILES SW 13.77 42.90 42.79- 42.79 PB-212 NOT ESTAB 18.06( 1/ 3) SISK FARM 18.06( 1/ 3) 1 VALUES <LLD 18.06 18.06 4.9 MILES SW 18.06 18.06 SR 89 10.900 15.641 2/ 13) SISK FARM 15.64( 2/ 13) 10.42( 1/ 12) 10.15 21.14 4.9 MILES SW 10.15 21.14 10.42 10.42 2.000 14.741 13/ .13) SISK FARM 14.744 13/ 13) 4.50( 12/ 12) 3.79- 20.81 4.9 MILES SW 3.79-' 20.81 3.58- 5.75
- 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 *t specified locations is indicated in parentheses (F).
I
I, 44 TABLE 11 RADIOACTIVITY IN VEGETATION PCI/G - 0.037 B/3 (DRY WEIGHT)
DOCKET NO. TVA /0Mgfgg-82(1 NAME. OF FPCILITY VELLEFONTE REPORTING PERIOD 1981 -
LOCATION OF FACILITYJAC5 A A -------------
&MI ALL CONTROL NUMBER OF TYPE AND LOWER LIMI NONROUTINE I OCALION 11T IHS A Li~EA LOCAT 0 SO TOTAL NUMBER OF INDICATOR LOCATIONS MEAN (F REPORTED MEAN (F)b NAME M4EAN OF ANALYSIS DETECTIOT\ RANGEb
'EIFORMED ANr b PM3 FACKLER9AL 2.05( 1/ 4) 1.524 5/ 12)
CE-1414 0.200 1.314 17/ 36) 2.64 5.2 MILES N 2.05 2.05 0.30- 2.60 0.26 1.74( 10/ 12) 2.004 32/ 36) LMI BL SOUTHWEST 2. 96( 3/ 4) 0.220 0.23- 3.94 0.27 4.?3 0.8 MILE SW 0.99 6/ 36) PM3 FACKLERsAL 5.78( 1/ 4) 3.72t 3/ 12)
PR -144 NOT ESTAB 3.53(
5.7 5.2 MILES N 5.78 5.78 2.91- 4.21 1.42 9
U.. 1t 18/ 36) LM1 BL SOUTHWEST 1.08( 2f 4) 1.12t 5/ 12) 0.200 0.8 MILE SW 0.47 1.70 0.33- 1.99 0.22 1.70 0.95( 2/ 12) 0 *510 0*82( 3/ 36) SISK FARM 00894, 1/ 4)
RJ-106 0.89 0.89 0.64- 1.25 0.74 0.p9 4.9 MILES SW 0.32t 2/ 4) 0.154 7/. 12)
CS-137. 0.060 0.17 U 27/ 36) LMI BL SOUTHWEST 0.07 0.32 0.8 MILE SW 0.32 0*32 0.06- .0.26 PM6 SECTIONvAL 2.514 2/ 4) 2.00t 7/ 12) 0.110 1.77( 24/ 36) 0.13 3.91 9.2 MILES SSW 1.16 3.85 0.24-.. 4.79 3.914 3 4) 2.694 11/ 12)
N3-95 0.050 2. 44I 321 36) LMI BL SOUTHWEST 0.3 MILE SW 0.26 6.84 0.07- 9.27 0.09 8.27 8.911 36/ 36) PM4 STEVENSO.NiAL 11*71(4 4/ 4) 9.83t 12/ 12)
NOT ESTAB 2.96 19.13 2.57- 22.06 1.97 20.65 11.0 MILES NNE 0.09( 1/ 4) 0.07( 5/ 12)
MV-54 O0.050 0.084 6/ 36) LM2 BL ENV DATA 0.06 0.10 1.0 MILE NE 0.09 0.09 0.05- 0.09 0.064 36) PM2 IOLLYWOOAL 44 12 VALUES <LLD
- y-88 NOT ESTAB 2/ 0.074 0.05 1.8 MILES UN* 0.07 0.07 0.284 36) PM3 FACKLERAL 0.42( 1/ 4) 0.31( 7/ 12)
SI-214! 0.100 17/ 0.58 0.12 0.49 5.2 MILES N 0.42 0.42 0.12 7/ 12) 0.154 36) LMI BL SOUTHWEST 0.314 1/. 4) 0.12(
PB -2 14 NOT ESTAB 22/
0.31 I0.31 0.03 0.22.
0.02 0.54 0.8 MILE SW 0.164 8/ 12) 0.15 4 22/ 36) LM2 BL EN, DATA 0.32( 3/ 4)
Pa-212 NOT ESTAB 0 r500 0.34 0.66 1.0 MILE NE 0.03 0*66 0.03
- 7. 114 36/ 36) PM2 HOLLYWOOD9AL 8.41( 4/ 4) 7.65( 12/ 12)
BE-7 NOT ESTA8 2.37 15.83 1.11 13.62 1.8 MILES WNW 5.73 13.54 3/ 4) 0.06( 5/ 12)
NOT ESTAB 0.071 14/ 36) LM2 BL ENV DATA 0.12(
TL-20S 0.23 0.01 0.23 0*01 0.12 0.01 1.0 MILE NE LM2 BL ENV DATA 0.42( 2/ 4) 0.104( 4/ 12)
ACA-226 NOT ESTAB 0.194 24/ 36) 0050 0.15 0.04- 0.50 1.0 MILE NE 0.34- 0.08-
- a. Nominal Lower Limit ofDetection (LLD) as described in Table 3.
b.Mean and .range.based up'on'detectable mneasu rements ony rcinof'detecta .blemeasurements 'at specified locat -ions is indicated irnparentbss()
I'1
TABLE 12 RADIOACTIVITY IN SOIL PCI/G - 3.037 B2/G (DRY WEIGHT)
NAME OF FACILITY BELLEFONTE DOCKET NO. TVA/0MS/OHS -Qj/1 LOCATION OF FACILITY jA KSON---------- ALa8AMA REPORTING PERIOD 1981 TYPE .ND LOtER LIMIT ALL CONTROL NUMBER OF TOTAL NUMB3ER OF . INDICATOR LOCATIONS LOCATION WITH HI GHESTANNUAJ_ MLN LOCATION NONROUTINE OF ANALYSIS DETECTION a MEAN (F)b NAME MEAN (F) MEAN (F) REPORTED l~3FORMED ILL IN.ADIRECTION RANGEb RANGEb EAIURMEMNTS SAMA (GELI) 2 CE-1 44 0.10( 1/ 15) PM2 HOLLYV0Dw0AL 0.10( 1/ 2) 4 VALUES <LLD 0.10- 0.10 1. MILES WNW 0.10 RJ-103 NOT ESTABz 0.03c 1/ 16) PM1 SCOTTSB0RDA 0.31 1/ 2) 4 VALUES <LLD 0.03- 0.03 5.6 MILES WSW 0.03 0.03 CS-137 0.020 0.24( 16/ 16) PM4,STEVENSDNvA. 2/ 2) 00181 4/ 4) 0.04- 0.73 11.0 MILES NNE 0.52 0.73, 0.06- 0.28 ZR -935 u.04( 4/ 16)' PM1 SCOTTSBORD.,A 0.05( 1/ 2) 4 VALUES <LLD 0.03- 0.05 5.6 MILES 4S 0.05 0.05 0*010 0.04( 11/ 16) PM1 SCOTTS6OROA 0.0841 2/ 2) 0.034 3/ 4) 0.01- 0.12 5.6 MILES WSW 0.04 0.12 0.02- 0.04 0.250 5.34( 16/ 1:6) LM2 5L ENV DATA 10.81( 2/ .2) 4.99t 4/ 4 3.04- 16.80 1.0 MILE NE 4.82 16.PO 2.99- 9.68 MN- 54 0.010 *0.021 2/ 16) PM4 STEVENSONqAL 0.021 1 2) 0.01t 1/ 4) 0.02- 0.02 11.0 MILES NNE 0.02 0.02 0.01- 0.01 BI-2-14 O0.050 0 .861 16/ 16) PM1 SCOTTSBOROA 1.000 2/ 2) 0.68 4/ 4 0.48- 1.08: 5.6 MILES WSW 0'. 99 1.01 0.53- 0.82 BT-212 0.100 0.65( 15/ 16) L42 BL ENV DATA. 0.921 2/ 2) 0.40( 4/ 4) 028- 1*.0 1.0 MILE NE 0. 90 0.93 0.21- 0.82 PB -214 0.050 0.93t 16/ 16) RM1 SCOTTSBORkOA 1.094 2/ 2) 0.72( 4/ 4) 0.49- 1.19 5.6 MILES WSW 1.08 1.11 0.55- 0.86 PS-212 NOT ESTAB 0.99( 16/ 16) LM2 BL ENV DATA 1.44( 2/ 2) 0.83t 4/ 4)
.18- 1.49 1.0 MILE NE 1.40 1.49 0.57- 1.35 RA-226 0.050 0.864 16/ 16) PMi SCOTTSBOROA 1.00( 2/ 2) 0.68( 4/ 4) 0.48- 1.08 5.6 MILES WSW 0.99 1.01 0.53- 0.82 RA-223 NOT ESTAB 0 .341 6/ 16) PM1 SCOTTSBOROA 0.43t 1/ 2) 4 VALUES <LLD 0.16- 0.45 5.6 MILES WSW 0.43 0.43 B-7 0.160 0.21( 1/ 16) PM1 SCOTTS8OROA 0.21( 1/ 2) 4 VALUES <LLD 0.21- 0.21 5.6 MILES WSW 0.21 0.21 TL-208 0.020 0.331 16/ 16) LM2 BL ENV DATA. 0.471( 2/ 2) 0.261 4/ 4) 0.05- 0.49 1.0 MILE NE 0.46 0.48 0.18- 0.42 AC-226 0.0 61 0.98( 16f 16) LM2 BL ENV DATA 1.411 2/ 2) 0.84( 4/ 4) 0.20- 1.51 1.0 MILE NE 1.26 1.57 0.53- 1.55 PA-234M NOT ESTAB 3.30( 1 16) LM2 BL ENV DATA 3.304 1/ 2) 4 VALUES <LLD 3.30- 3.30 1.0 MILE NE 3.30- 3.30 SR 89 1.500 16 VALUES <LLO 4 VALUES <LLD 2 ANALYSIS PERFORMED SR 90 0.300 16 VALUES <LLD 4 VALUES <LLD 2 ANALYSIS PERFORMED
- 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).
i TABLE 13 RADIOACTIVITY IN WELL WATER PCI/L - 0.037 BQ/L E
NME. OF FACILITY_6ELLEFN0T ~DOCKET NO TVA/0MS/0HS REPORTING PERII0 198 LOCATION OF FACLITY JAC-SON-L oc ~ ~
OF-FACILITY---------- TIO -- AM----
CONTROL NUMBER OF TYE AND LOWER LIMIT ALL NONROUTINE THH1IG MAN --- LOCATIONS O INDICATOR LOCATIONS TOT NUBER AME MEAN (F)b MEAN ( ' REPORTED O. ANALYSIS DETECTIONa MEAN (F)b R AN GEb RAN EE < L L D AbL)
,3t,114A (jA I) 19 VALUES <LLD 53 4AAY VALUES <LL3O ANALYSIS PERFORMED GAMMA CGELI) 31 4) 80.87( 3/ 7) 84o27( 71 24) WELL #3 130.10( 1/
NOT ESTAB 38.39- 131.30 13.26- 130.10 ONSITE NW 130.10 130.10 WELL 144 36.96( 4/ 4) 39.854 4/ 7) 3I-214 NOT ESTAB 24.304 1/ 24).
ONSITE NNU 15.64 82.39 5.69- 64.53 2.45- R8.39 29*954 4/ 7) 67.621(
NOT ESTAB 30.23( 11/ 24) WELL 2.
P3-214. ONSITE WSW 67.62 67.621) 520 - 49.40 8.,783- 82.33 21 6) 15'394 1/ 7)
WELL #6 118.71j(
P -212 NOT ESTAB 14.51( 7/ 24) 4.38- 28-20 ONSITE N 13.96 23.46 15.39- 15.39 1/ 6) 7 VALUES <LLD 10.384 .2/ 24) WELL #6 11*84t TL-20 NOT ESTAB 11.84 83- 11.84 ONSITE N 11.84-B VALUES <LLD TRI YjUM 330.000 23 VALUES <LLD_
31 ANALYSIS PERFORMED a.Nmia ower LIto etto (LLD) as described in Table,3.
rcino eetbemaueet at specified locations is indiae nprnhss()
b eananragebased .upon detectable measurements only r'3
TABLE 14 RADIOACTIVITY IN PUBLIC WATER SUPPLY PCI/L - 0.037 BQ/L NvME OF FACILITY BELLEFONTE-_ DOCKET NO. TVA1O MS/OHS-82/10 LOC TION OF FACILITY JACKSON ALABAMA REPORTING FERiOD 1981 TYPE AND. LOWER LIMIT ALL CONTROL NUMBER OF TOTAL NUME OF INDICATOR LOCATIONS LOCATION% NONROUTINE OF ANALYSIS DETECTIO a MEAN OF)b NAME MEAN (Fb MEAN (F) REPORTED DERFORMED (LLD ) RANGEb Q RAN b____ ffASAL&MENTS R S BLTA 2.400 .3.53( ,19/ 39 SAND MT. WFPA 3.981 10/ '13) 3.284 5/ 13) 2.51- 10.30 TRM 362.1 2.51- 10.30 2.73- 4.05 GAMMA (NAI) 4G -9 VALUES <LLD 13 VALUES <LLD ANALYSIS PERFORMED GAMMA (GELI)
NOT ESTAB 94.79( 5/ 10) SAND MT. WFPA 115.60( 1/ 3) 82.83- 115.60 TRM 382.1 115.60 115.60 51-214 NOT ESTAB 22 .60 / 10) SCOTTSBOROvAL 25.91A 2/ 5) 16.07- 34.23 TRM 385.8 17.54 34.28
~3-214 NOT ESTAB 13.52A 7/ 10) SAND MT. WFPA 14.15( 3/ 3) 8 77- 18.T5 TRM 362.1 8.77 1 e. 95 SR 89 10.003 12 VALUES <LLD 4 VALUES <LLD 16 ANALYSIS PERFORMED SR 9 2.000 2.06( 1/ 12) SCOTTSBOROAL 2.06( 1/ 4). 4 VALUES <LLD 16 2.06- 2.06 TRM 385.8 2.06 2.06 TR-TH UM 330.000 32.914 2/ 12) SAND MT. ,FPA 402.651 1/1 4) 344.201 1 _4) 16 383.17- 432.65 TRM 382.1 402.65- 402.65 344.20- 344.20
- 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 at specified locations is indicated in parentheses (F).
29 Table 15 ENVIRONMENTAL GAMMA RADIATION.LEVELS Environmental Gamma Radiation Levels Monitoring Period Location ALtHour inRLQuarter January-March 1981 On-Site (15)b Maximum 12.5 27.4 Minimum 8.0 17.4 Averagec 9.4+/-2.3 20.5+/-5.0 Off-Site (8)
Maximum 8.0 17.5 Minimum 6.4 14.1 Average 7.2+/-1.2 15.7+/-2.6 April-June 1981 On-Site (14)
Maximum 14.9 32.6 Minimum 7.5 16.5 Average 9.4+/-3.6 20.6+/-7.8 Off-Site (8)
Maximum 9.0 19.8 Minimum 6.4 14.0 Average 7.6+/-1.9 16.6+/-4.1 July-September 1981 On-Site (13)
Maximum 13.0 28.5 Minimum 8.0 17.5 Average 9.2+/-2.6 20.2+/-5.7 Off-Site (8)
Maximum 8.2 17.9 Minimum 5.9 13.0 Average 7.1+/-1.6 15.5+/-3.5 October-December 1981 On-Site (17)
Maximum 12.5 27.3 Minimum 6.8 14.9 Average 8.5+/-2.8 18.7+/-6.1 Off-Site (27)
Maximum 8.8 19.3 Minimum 6.3 13.7 Average 7.1+/-1.2 15.6+/-2.7
- 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 +/-20 (95% confidence level)
TABLE 16 RADIOACTIVITY IN CABBAGE PCI/KG - 0.037 BQ/KG (WET WEIGHT) .w 0>
NAME OF FACILITY 9ELLEFCTE DOCKET NO. TVA/OMS/OHS LOCATION OF FACILITY JACKSON AAAA REPORTING PERIOD TYPE AND LOWER LIMIT ALL CONTROL NUMBER OF T3TAL NUMBER OF INDICATOP LOCATI-ONS LOCATION WITH HIGHEST ANNUAL MEAN LOCATION NONROUTINE OF ANALYSIS. DETECTIONa MEAN ( Pb NAME MEAN (F)b MEAN (F) REPORTED
~
111.LE_,j P ANGEb -RANGEb MEASUREMENTS-K-TM.4A(GEL!)
K -4n NOT ESTAS 235^*00( 17 11 PM2 HOLLYWOODAL 2359.00t 1/ 1) 1764.00( 1/ 1) 2359.00- 2359.300 i.S MILES WNW 2359.00- 2359.00 1764.00- 1764.00 P3-214 NOT ESTAB 1 VALUES <LLD 12.22( 1/ 1) 12.22- 12.22 P3-212 NOT ESTAB I VALUES <LLD 8.30( 1/ 1) 8.30- 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).
- g
k-a-
TABLE 17 RADIOACTIVITY IN CORN PCI/KG - 1..37 83/I0 (WET WEIGHT)
MF FACILITY RELLEFONTE 1OCKET NO._TVA/OMS/CH Z/
LOC T1iON OF FACILITY JA oN -- ALABAMA REPORTING PERIOD 19 1 TYPE AND LOWFP LIYIT ALL CONTROL NUMBER OF TOTAL NCUM5 CF INDICATOR LCCATIINS LOCATION WITH HIGHEST ANNUAL MEAN LOCATION NONROUTINE OF ANALYSIS DETECTIONa MEAN (F)b NAMEAN (P MEAN REPORTED PERFO RED _EL) RANGEb DISTANCE AND DIRECTION RANGEb RANGE MEASU REMEN1a AMMA (G7LI)
K- 1 NOT ESTA3 1950 . C.( 1/ 1) PM? HOLLYWOODiAL 1 950,000 1 1/ 1) 1950.0* 1.'- MILES wNW 1950.*00 1950,.00 3-2 12 NOT ESTA3 7 .3? ( 1/ 1) PM2 HOLLY OD9A' 7.39' L/ 1) 7.3i- 7.3 ~ 1.8 MILES ;NW 7.39- 7.3c
- 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).
TABLE 18 RADIGACTIVITY IN POTATOES PCI/X(G - 0.037 8;/KG (WET wEIGHT)
N)ME OF FA:ILITY BELLEFON'TE DOCKET NO. TVA/OMaLQ-S -82/10 .
LOCtTION OF FACILITY JACKSON ALABAMA REPORTING PERIOD 1981 M
TYPE AND LOWER LI IT ALL CONTROL NUMEER OF TOTAL NUMbLR OF INDICATOR LOCATIONS L LOCATION NONROUTINE OF ANALYSIS DETECTIO.a (F)b bEAN NAME M AN MEAN (F) REPORTED GMFORMEL ILL2L. SPA 1__ InN 11b11 UlA NANG GAMMA (GELI)
K -4 0 NOT ESTAB 3378.000 1, 1) M2 HO LLY 00D, AL 337.00 1/ 1) 3115.00( 1/ 1 33 7 .100 3378.'" 1.0 MILES 4NW. 3378.00 378.*00 3115.00- 3115.00 1-214 NOT ESTAB 1/ .1) PM2 HOLLYWOODAL I 4.80( 14)8 1 VALUES <LLD 1.8 MILES wNW 14.80
'3-212 NOT ESTAB 14.90- 1/ 1 PM2 HOLLYWOOD, AL 18. 904 1/ 1) I VALUES <LLD 18.301 1.8 MILES W 18.90- 18. 90
- 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 qt specified locations is indicated in parentheses (F.
0- 4-
TABLE 19 RADIOACTIVITY IN TOMATOES PCI/KG - 0.037 BG/KG ( ET WEIGHT)
NAME OF FACILITY wELLEFO E DQCKET NO. TVA/0MS/0HS-j2/jQ LOCtTION OF FACILITY JACKSON ALABAMA REPORTING PERIOD 1951 TYPE AND LOWER LIMIT ALL CONTROL NUMBER OF TOTAL NUMBER OF INDICATOR LOCA IONS T ON WITH HI ST ANNUAL M-AN LOCATION§ NONROUTINE OF ANALYSIS DETECTIONa MEAN (F) NAME MEAN ( MEAN (F) REPORTED
> CLD)RANGEb
_ _EAFORML __TAgLAN RANGEb RGb MAU ENTS GAMMA . L K-4 . NOT ESTAB 2634.00( 1' 1) PM2.HOLLYVOODsAL 2634.'0( 1 1) 2527.00( 1/ 1) 2654.00-.2634.IM 1.9 MILES WNW 2634.00- 2634.O0. 2527.0G- 2527.00 31-214 NOT ESTA3 1 VALUES CLLS 25.10( 1/ 1) 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).
TABLE 20.
RADIDACTIVITY IN TURNIP GRrENS PCI/KG - 0.037 84/KS (WET WEIGHT)
NAME OF FACILITY RELLEFONTE DCCKET NO. TA/0MS/0H-i2/j .
LO.CTIDN OF FACILITY JACKSON ALABAMA REPORTING PERIOD 1981 TYPE !NO LOWER LIMIT ALL CONTROL NUMBER OF TOTAL NUMBER OF INDICATOR LOCATIONS LOCAT1 WIH -ISHEST ANNUAL MEAN LOCATION NONROUTINE 01 ANALYSIS DETECTIONa MEAN (F)b NAME MEAN (F)b MEAN (F) REPORTED
-- 3 12 La iLL.) RANGEb AND QIRECTION RANGEbbSAN RANGEb dLASUR~tLgig_
SAMM4 (GELI)
NOT ESTAB 2617.00( 1/ 1) PM2 HOLLYWOODAL 2r17.00( 1/ 1) 3824.00( 1/ 1) 2617.3C- 2617.00 1.3 MILES WNW4 2617.00 2617. C 3824.C- 3824.00 P 3-212 NOT ESTAB 21.14 1/ 1) PM2 HOLLYWOO0AL 21.15( 1/ 1) 1 VALUES <LLD 21.15- 21.15 1.9 MILES WNW 21.15- 21 .15 3E-7 NOT ESTAB 1 VALUES <LLD 87.684 1/ 1) 87.68- 87.68
- 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).
br--
V_ f TABLE 21 .
RADIOACTIVITY IN 'OULTRY PCI/KG - 2.037 R/KG (iET WEIGHT)
NAME OF FACILITYELLFONTE - ---------- ---------- DOCKET NO. TVA/OMS/OHS-82/10 LOCATION OF FACILITYJA (--N------------- ALABAMA REPORTING PERIOD 1981 TYPE AND LOWER LIMIT ALL CONTROL NUMBER OF TOTAL NUMBE . CF INDICATOR LOCATIONS LOCATION WITH HIGHEST A UAL MAN LOCATIOIV NONROUTINE OP ANALYSIS DETECTIONa MEAN (F) b NAME MEAN (F)T MEAN (t) REPORTED
'EiFORMED _(LL?) -ANGEb OISTANCL AND 2IRCTION RANGEb RANGE MEjASVRL[MEN~a GAMMA (GFLI)
S-42 NOT ESTA3 2561. 0( 1/ 1) SISK FARM 2561.00( 1/ 1) 1988.00( 1/ 1) 2561.D- 2561 .00 4.9 MILES SW 2561.00 2561.0 G 1988.0O- 1988.00 31-214 NOT ESTAS 8.52t( 1/ 1) SISK FARM 8.52( 1/ 1) 15.50( 1/ 1)
S.52 4.9 MILES SW 8.52 15.50- 15.50 PB-214 NOT ESTAB 14.43t 1/ 1) SISK FARM 14.43( 1/ 1) 15.07( 1/ 1) 14.4S- 14.48 4.9 MILES Sli 14.48- 14.48 15.07- 15.07
- 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).
U'
36 Figure 5 C O 5 L- -W' Annual Average o0 Gross Beta Activity CO 0 U p
.H co 4.t In Drinking Water 4 Bellefonte Nuclear Plant 3
0 1978 1979 1980 1981
w C.'
38 Figure 7 Direct Radiation Levels
- 24 Bellefonte Nuclear Plant 4
22 20 L
18
.0 CI S16 14 12 Figure 8 Direct Radiation Levels 24 Bellefonte Nuclear Plant 4-Quarter Moving Average 22 20 L
18 C
Offsi te 16 10 14 A-12.
1 y/y 1980 1981 1978 1979 1980 1981
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 semiannually 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-emitting radionuclides.
In addition, 89 Sr and 90 Sr concentrations are determined in one smallmouth buffalo flesh sample and in two whole smallmouth buffalo samples. The data from the analysis of these samples are included herein in tables 23, 24, and 25.
TABLE 22 RADIOACTIVITY IN SURFACE WATER TOTAL L- .037 1Q/L CJ L 1 Y FELLL_0!jjLDCCKET NO..T-VA/0MS/0HS8j2/10___
NAME F FACILITY BELLFONTE--_-- _-----PORTING--- _ - N. D 1 40 LOCTION OF FACILITYJACKSON----------------- ALA A------
CONTROL NUMBER OF TYPE AND LOWER LIMIT ALL LOCATION% NONROUTINE TOTAL NUMBER OF INDICATOR LOCATIONS LOCATIZ.\E 11T 1 1IGHEST. - ME b --
-ANU-MEAN (F) REPORTED OF ANALYSIS OETECTIO Na MEAN (F)b DL QR TIN. RANGEb ANGEb NCEAND RANGEb - ftit"Ouis-
'ER FORMED (LLDT 3 AAIA (NAT) 1 VALUES <LLD C VALUES <LL0 ANALYSIS PERFORMED GAMMA (GELI) 53.224 1/ 2). TRM 3i6,31 93.22(
K-40 NOT ESTAB 1/ 1) 93 93.22 93.22 TRM 3'3.0 31.12(
BI-214 .NOT ESTAB 31.12( 1/ 2) 31.12-31.12- 31.12 31.12 2 VALUES <LLD 1 VALUES <LLD SIR k9 10.000 ANALYSIS-PERFORMED 1 VALUES <LLD 2.000 2 VALUES <LLD 3 ANALYSIS PERFORMED 1 VALUES <LLD TRITIUM 330 000 2 VALUES (LLD.
ANALYSIS PERFORMED
- a. Nominal Lower Limit of Detection (LLD) as described in Table 3. is indicated in parentheses (F).
- b. Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations
TABLE 23 RADIOACTIVITY IN WHITE CRAPPIE (FLESH)
PCI/G - .O37 SQ/G (DRY WEIGHT)
-OCKET NO. TVA/OMJ/OHS- 2 -/10
%!ME OF FACILITYRELLEFONTE JACKSON . ALABAMA REPORTING PERIOD 1981 LOC-TIDN OF FACILITY ALL CONTROL NUMBER OF TYPE AN~D LOWER LIMIT NONROUTINE 0F INDICATOR LOC!TINS ! WITH-i HI GSTAnUAL MEAN 2AL13N LOCATIONg TOTAL NUME MEAN (F)b MEAN REPORTED OF ANALYSIS CETECTIONa M4EAN (F) NASME M ANG b AN G Eb_ _ F)
PER~FORM~ED 1) 0.13 C 34. o 4/ 4) WHEELER RES 35.10( 2/ 2) 27.36( 1/
GROSS BETA 22.36 33.03- 37.15 TRM 275-34q -33.04- 37.16 27.36-5 GAMMA (GELI) 5 0.12( 4f 4) GUNTERSVILLE RES 0.14 2/ 2) 0.09( 1/ 1)
CS-137 0.0320 0._09 TRM 346-425 0.09 11. 18 0.09 0.09 15.70 41 4) GUNTERSVILLE RES 17.50( 2/ 2) 14.18( 1/ 1)
K-ye NOT £STA 3 12.72 19.51 TRM 349-425 15.49 19.51 14.18 14.18 61-214 0.020 0. ~ 2/ .4) WHEELER RES 0.094 1/ 2) 0.03( 1/ 1) 0.09 0.09 0.03 0.03 0 *06 C.09 TRM 275-349
-3*064 1/ 4) WHEELER RES 3*06( 1/ 2) 1 VALUE <LLD P3-214 NOT ESTAB TRM 275-349 0.06 0 . 06 0.02 2/ 4) GUNTERSVILLE RES 0.02t If 2) 1 VALUE <LLD PS-2-12 NOT ESTAB 0.02- 0.02 TRM.349-425 0.02- 0.02
- 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).
TABLE 24 RADIOACTIVITY IN SMALLMOUTH BUFFALO (FLESH)
OCI/G - 3.037 80/G (DRY WEIGHT)
LO ME F T FACILITY OLLEF0NTE LOC'-TT3.' OF FACILITY JACKSOQN- CCKET NO. TVA/OMS/OHS -a/1.
- - -ALA3AMA- - -- --- - REPORTING PERIOD-1a ---------
TYPE aD LOWER.LIMIT ALL CONTROL NUMBER OF TOTAL NU MBE OF a INDICATOR LOCATIONS LOCATION WITH HIGHEST ANNUAL MEAN LOCATIONJ NONROUTINE O ANALYSIS uTTECTION MEAN (F) NAME EAN (F) MEAN (g) REPORTED r'3 RANGEb DjSTANCE AND DJRE CT ION RANGEb RANGE MEASUREMENTJ DSS DETA 0.100 24.19( 4/ 4) WHEELER RES 25.97(. 2/ 2) 17.46( 1/ 1) 5 20.12- 27.20 TSM 275-3,.9 24.74- 27.20 17.46- 17.46 GAMMA (GELI) 5 CS-1 37 0 .20 0.06 4/ 4) GUNTERSVILLE RES 0.08( 2/ 2) 0.06( 1/ 1)
.*04- 3.03 TRM 349-425 0.07 G; a.* 0.06 0.06 0 NOT ESTAB 9.42c 4/ 4) WHEELER RES 11.03( 2/ 2) 9.56( 1/ 1) 7.00- I1. 6 TRM 275-349 10.49 11 .56 9.56 9.56 31-214 0.020 0.05( I/ 4) GUNTERSVILLE RES 0.14( 1/ 2) 1 VALUE <LLD
- .7- 0."9 TRM 349-425 3.09 09 0.01 0.01 P3-212 NOT ESTAB O.04( 1/ 4) WHEELER RES 0.04( 1/ 2) I VALUE <LLD G.04- 0.04 TRM 275-349 0.04 0.04 T;- -20C 0.020 '.02( 1/ 4) WHEELER RES .0.02( 1/ 2) 1 VALUE <LLD 0.02- 0.02 TRM 275-349 0.02- 0.02 SR S3 0.500 1 VALUES <LLD 0 VALUES <LLD ANALYSIS PERFORMED SR 912 0.100 1 VALUES <LLD 0 VALUES <LLD 1I ANALYSIS PERFORMED
- 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).
a- 0 ik-- It
VI 1 TABLE 25 RADLOACTIVITY IN SMALLMOUTH BUFFALO (WHOLE)
PCI/G .337 8:13 (0RY 6EICHT)
N OF FACILITY EELLEFONTE OME DOCET O. A/OMS/HS-2/10 LOC TI ON OF FACILITY JA _--------- -- ALABAMA PERIOD 981 RPOTI-----------------REPOTIG ALL CONTROL NUMBER OF TYPE fAND LOWER LIMIT OF INDICATOR LOCATI ONS LOCATION WITH HIGHEST ANNUAL MEAN -. LOCATIONC NONROUTINE TOTAL NUM;E OF ANALYSIS DETECTION a MEAN (F)b NAME MEAN (F)b MEAN (F) v REPORTED LiFORMED (LL-> RANG Eb DjST.N AND R ACTO NGE RANGE b TAR UU1 a__
ROSS BETA 0 .100 2 ^- 0;( 4/ 4) GUNTERSVILLE RES 20.94( 2/ 2) 12.49( 2/ 2) 6 14e97- 26,. 1 TRM 349-425 14.97- 26.91, 10.62- 14.35 GAMMA (GELIY 6 0 20 0 04C / 4) GUNTERSVILLIE ES 0 . 04 1/ 2)_ 0.04( 2/ 2)
CS -137 3.03 TRM 349-425i 0 .04-. .04, 0.03- 0.04
.- 4 NOT ESTAB 774 ( 4/ 4) WHEELER RES 8.20( 2/ 2) 5.48( 2/ 2) 5.10 9.57 TRM 275-349 7.50 R* 89 5.11- 5.84 31-214 0. 520 0.6s / 4) GUNTERSVILLE RES 0.06.( 2/ 2) 0.02( 1/ 2) 0.03 TRM 349-425, 0.*33 0.08 0.02- 0.02 ESTAB 0.35( 0.9-' GUNTERSVILLE RES 0.08( 17 2) 0.02( 1/ 2)
P3-214 NOT 0.04 TRM 349-425 0.08 0.02- 0.02 3/ 4), RHEELER RES. 0.3 3 1/ 2) 0.02( 1/ 2)
PB- 212 NOT ESTAB 0.03f
- 0. 03- 0.94 TRM 275-349 0.03- 0.03 0.02- 0.02 0.500 I VALUES <LLD 1 VALUES <LLD 2 ANALYSIS PERFORMED 0.100 VALUES DLLD 0.29( 1/ 1)
ANALYSIS PERFORMED 0.29- 0.29
- 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).
RESERVOIR
/ BELLEFONTE NUCLEAR PLANT 4 391.2 aQ i-I 0 Miles 5 DAM
-4
45 Quality Control I
A quality control program has been established with the Alabama Department of Public Health 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.