ML20100J463

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Environ Radioactivity Levels,Browns Ferry Nuclear Plant, Annual Rept - 1982
ML20100J463
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 12/31/1982
From: Mills L
TENNESSEE VALLEY AUTHORITY
To: James O'Reilly
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
NUDOCS 8504100500
Download: ML20100J463 (60)
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{{#Wiki_filter:_. l TENNESSEE VALLEY AUTHORITY } i I I l l 9 I 1 f i i i l i l l i I RADIOLOGICAL HEALTH STAFF 8504100500 821231 PDR ADOCK 05000259 R PDR I -m.-

y L ENVIRONMENTAL RADI0 ACTIVITY LEVELS . BROWNS FERRY NUCLEAR PLANT ANNUAL REPORT - 1982 TVA/ POWER /RHS J 4 1 ~ April 1983 'l 'j -l l 1 i

~ 4 CONTENTS - List.of Tables. iii List of. Figures...... iv Introduction. 1 i 11 Atmospheric Monitoring. Terrestrial Monitoring. 23 4 . Reservoir Monitoring. 41 i Quality. control............................ 53 Data _ Analysis. 53 Conclusions. 53 i e i r d h '.T. ii 1 (.

LIST OF TABLES Table 1 - Environmental Radioactivity Sampling Schedule. 3 t Table 2 - Atmospheric and Terrestrial Monitoring Station i Locations - Browns Ferry Nuclear Plant. 4 Table' 3 - Detection Capabilities for Environmental Sample Analysis. 5 Tab,le 4 - Results Obtained in Interlaboratory Comparison Program. 7 Table 5 - Maximum Permissible Concentrations for Nonoccupational Exposure. 13 Table 6 - Radioactivity in Air Filter. 14 Table 7 - Radioactivity in Rainwater. 15 Table 8 - Radioactivity in Heavy Particle Fallout. 16 Table 9 - Radioactivity in Charcoal Filters. 17 Table 10 - Radioactivity in Milk.................... 26 Table 11 - Radioactivity in Vegetation. 27 Table 12 - Radioactivity in Soil.................... 28 Table 13 - Radioactivity in Well Water. 29 1 Table 14 - Radioactivity in Public Water Supply............. 30 l' Table 15 - Environmental Gamma Radiation Levels 31 j Table 16 - Radioactivity in Corn. 32 Table 17 - Radioactivity in Green Beans. 33 Table 18 - Radioactivity in Potatoes. 34 Table 19 - Radioactivity in Tomatoes. 35 Table 20 - Radioactivity in Turnip Greens 36 Table 21 - Sampling Schedule - Reservoir Monitoring '- 43 Table 22 - Radioactivity in Surface Water. ............... - 44 Table 23 - Radioactivity in White Crappie (Flesh)............ 45-Table 24 - Radioactivity in Smallmouth Buffalo (Flesh)......... 46 i Table 25 - Radioactivity in Smallmouth Buffalo (Whole).... 47 Table 26 - Radioactivity in Sediment. 48 Table 27 - Radioactivity in Clam Flesh................. 49 Table 28 Radioactivity in Clam Shell................. 50 1 i 4 a \\ 111 1 f. r o -m2 -,,v..-,., r m - y

LIST OF FIGURES Figure 1 - Tennessee Valley Region. 10 Figure 2 - Atmospheric and Terrestrial Monitoring Network........ 18 Figure 3 - Local Monitoring Stations. 19 Figure 4 - TLD Locations, BFN 20 - Figure 5 - Annual Average Gross Beta Activity in Air Filters, Browns Ferry Nuclear Plant 21 Figure 6 - Annual Average Gross Beta Activity in Drinking Water, Browns Ferry Nuclear Plant 37 Figure 7 - Dire'et Radiation Levels, BFN 38 Figure 8 - Direct. Radiation Levels, BFN (4-Quarter Moving Average)... 38 Figure 9 - Direct-Radiation Levels, WBN 39 Figure 10 - Direct Radiation Levels, WBN (4-Quarter Moving Average)... 39 Figure 11 - Reservoir Monitoring Network 51 Figure 12 - Annual Average-Gross Beta Activity in Surface Water 52 P 9 9 l iv s w g

L I ENVIRONMENTAL RADI0 ACTIVITY LEVELS BROWNS FERRY NUCLEAR PLANT ANNUAL REPORT 1982 k Introduction 1 .The Browns Ferry Nuclear Plant (BFN), operated by the Tennessee Valley. Authority, is located on a site owned by TVA containing 840 acres of. land in' Limestone County, Alabama, bounded on the west and south by Wheeler Reservoir (see figure 1).. The. site is 10 miles southwest of Athens, Alabama, and 10 miles northwest of Decatur, Alabama. ~ Th'e plant consists of three boiling water reactors; each unit is rated at 3,293 fnit and 1,098 MWe. Unit 1 achieved criticality on August 17, 1973, and began commercial operation on i . August 1, 1974. Unit 2 began commercial operation on' March 1, 1975. However, i a fire in the. cable trays on March 22, 1975, forced the shutdown of.both reactors. Units 1 and 2 resumed operation and Unit 3 began testing in August 1976. Unit 3 began commercial operation in. January 1977. l The preoperational environmental monitoring program established a baseline of data on the distribution of natural and manmade radioactivity in-the environment near the plant site. Ilowever, seasonal, yearly, and random variations in.the. data were observed. In order to determine the potential increases in environmental radioactivity levels caused by the plant, com-paris.ons were made between data for indicator stations (those near the plant) and control stations (those remote from the plant) in conjunction with com-- parisons with preoperational data. .The Radiological Health Staff (Office of Power) and the Office of Natural Resources carried out the sampling program outlined.in tables 1 and 21. Sampling locations are shown in figures 2,'3, 4, and 11,.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 i . Radiological Laboratory (WARL) located at Muscle Shoals, Alabama, and Eastern -Area Radiological. Laboratory (EARL) at Vonore, Tennessee. Alpha and beta analyses were performed on Beckman Low Beta II and Beckman Wide Beta II low background proportional counters. Nuclear Data (ND) Model 100 multichannel l analyzer systems employing sodium iodide NaI(TI) detectors and ND Model 4420 systems in conjunction' with-Germanium Ge(Li) detection systems were used to analyze the samples for specific gamma-emitting radionuclides. Samples of water, vegetation, air particulates, food crops, and charcoal (specific analysis for I-131) are routinely counted with NaI(T1) detection systems. If significant _ concentrations of radioisotopes are identified, or if there is a i 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 t- + +-g--a, y r-y. -ww -.w---y

2 is routinely performed by analysis on the Ge(Li) system. A~TVA fabricated beta-gamma coincidence counting system is utilized for the determination of I-131 concentrations in milk. - Data were entered in computer storage for processing specific to the ^ analysis conducted..A computer, employing an ALPHA-M least squares code, using multimatrix techniques,,was used to estimate.the activities of the gamma-emitting nuclides analyzed by NaI(TI). 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 simple analyses;given as:the nominal lower limits of detection (LLD) are listi i in table 3. Samples processed by NaI(T1) gamma spectroscopy were analyzed 14 specific gamma-emitting radionuclides and radionuclide combinaticns or these analysen, radionuclide combinations such as 103'108Ru and 95Zr-Nb ace 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, 22sRa, etc. TLDs for the analysis of the radio-nuclides listed below* are given in table 3B. LLDs for additional radio-4 nuclides identified by Ge(L;)<. 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 1982 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. aThe following radionuclides ~ and radionuclide combinations -are quantified by 141'144Ce; 51Cr; theALPHA-Mleast-squarescoqutercode: 1311 103'106Ru; 137 4 II0 134 Cs; Cs, 95Zr-Nb; s8Co; Mn; 65Zn; 58Fe; 60Co;'40K; and Ba-La. l l r 7_-yw-- _._.,.-9, ,m s m

,o N, ^ s g r s do A A o F et f n ie Lm i cd ie tS S aud qn Aa cr ie lt M M M M b a y uW l P l r a l e u lt n ea M M n WW A E L rr U ee A D vt E ia M M H RW C S y k l G .l l N i W W W W W a L . M u I n P n n M o a A i i S .t m a Q Q Q Q Q e Y t S T e I g 1 V e I V S e T l C l b A i A A A A A A A A A A A a 0 o T I S DAR e y l l L c r A i e T tt t N ru r E ao a M Pl M M M M M M M M M M M u N l Q O ya R vF I a V e Q N H E - r ne ) it M M M M M M M M M M M s aa k Rw ee w lar 4 oe ct y rl r ai W W W W W W W W W W W e hF v C~ (e . r y e l t h rl t ii W W W W W W W W W W W n AF o M sm .o r n C a M o r F i e r t s s v e l a l g ) ) ) ) m i p a c a r e E E M W r l m R a c o o u l ) N N S a l a P o y L h b l d N N E W F e D r e L l S e i n ( ( ( ( ( W e e n k n c v r a l r v s o s e o e n s s u l 1 2 3 4 5 B S P L o e e i s i u e i l e r n t t r t l R e p o W t c r e e a r e e e e e m m a a t i e n m i a s w g h c u t t t t t r r r n s e k n r T Wa t u a o t e o i i i i i a a a a o n h l e a S M L R A D C S S S S S F F F F C O W E V W 4

4. Table 2 Atmospheric and-Terrestrial Monitoring Station Locations Browns Ferry Nuclear Plant Sample Station -Approximate ~ Distance and-Direction from Plant 1 1 LM-1 BF, North 1.0 Mile (1.6 kilometers) N-LM-2 BF, North-Northeast 0.9 Mile (1.4 kilometers) NNE LM-3:BF, East-Northeast 1.0 Mile (1.4 kilometers) ENE LM-4 BF, North-Northwest 1.7 Miles (2.7 kilometers) NNW LM-5:BF, West-Southwest 2.5 Miles (4.0 kilometers) WSW PM-1:BF, Rogersville,-AL-13.8 Miles (22.2 kilometers) NW PM-2 BF, Athens, AL 10.9 Miles (17.5 kilometers) NE PM-3 BF, Decatur (Trinity), AL 8.2 Miles (13.2 kilometers) SSE PM-4 BF,.Courtland, AL 10.5 Miles (16.9' kilometers) WSW RM-1 BF, Muscle Shoals,.AL 32.0 Miles (51.5 kilometers) .W-(Control) RM-2 BF, Lawrenceburg, TN 40.5 Miles (65.2 kilometers) NNW (Control) Farm S 4.75 Miles (7.6 kilometers) N Farm B 7.0 Miles. (11.3 kilometers) NNW Farm L 5.0 Miles (7.0 kilometers) NE Farn T (Out of business 7.0 Miles (11.3 kilometers) ENE after 1/18/82) Farm P 8.8 Miles (14.1 kilometiers) E Farm N (Control) 27.0 Miles (43.4 kilometers) 'NW Farm J.(Control) 40.0 Miles (64.4 kilometers)- NNW Farm C (Control) 32.0-Miles -(51.5 kilometers) N-Farm Ca '(Cont rol) 32.0 Miles (51.5 kilometers) W

+ ..r s V Table 3.. DETECTION CAPABILITIES FOR ENVIB000 ENTAL SAMPLE ANALYSIS - A. Specific Analyses NOMINAL IDWER LIMIT OF: DETECTION (LLD)* Fish,. Air Vegetation ' Soil and clan flesh, Food s,. nea t,'. Particulates. Charcoal Fallout Water and grain Sedinent

plankton,

.Clas shells poultry. Milk '_ pC1/e pC1/e eC1/ka pCi/1 pC1/a. dry pC1/a,' dry pCi/a. dry pC1/a, dry pC1/ka. wat: pC1/1 3 8 a Total a 0.4 0.01 '1.5 Cross a. 0.005 2.0 0.05' O.35 0.1 0.7 Cross 8 0.01 0.05 2.4 0.20 0.70 0.1 0.7 25 'N-330 0.5 8 1-0.02 "Sr 0.005 10 0.25 1.5 0.5 5.0 40. 10 "Sr 0.001 2 0.05 0.3 0.1 1.0 8 2 4

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

Factors such as sample size, decay time, chemical yield,' and counting efficiency may vary for a giv'en sample; these variations may change the LLD value for the given sample. The assumption is made that all samples are analyzed within one week of the

collection date. Conversion' factors: 1 pCi - 3.7 x 10 s sq; 1 aci = 3.7 x 10? Sq.

d

9 Tib12 3 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS B. Gansna Analyses NOMINAL LOVER LIMIT OF DETECTION (LLD)_ I Clam flesh Foods.(tomatoes'. Meat and Air.. Water Vegetation Soil and .particulates and milk and grain-sediment Fish and plankton- 'Clas shells potatoes, etc.) poultry. pCi/m pC1/1 pCi/a. dry. pC1/a. dry _ rC1/a." dry pC1/a. dry pCi/a. dry. pC1/ke_ wet PCi/kt. we* M

  • Ge(Li)**-

Nal,Ge(L1) Nal Ge(L1) Nat Ge(L1)- Na1 Ge(L1) NaI Ge(L1) ' Na! Ce(L1) Na1 Ge(L1). M Ge(Li)- s I'8'3" Ce 0.03 38 0.55 0.35 0'.35 0.35 38 90. Ce 0.02" 33 0.22 0.06 0.06 0.35 . 0.06 . 33. 4c . s:Cr 0.07 0.03 '60 44 1.'10 0.47' O.60l 0.'10 0.60' O.10 0.'56 0.69' O.10 60 44' 200 90 ' 883I 0.01 0.01 15 8 0.35 0.09 0.20' O.02 0.20 0.02 0.07 'O.2F 0.02 15 8 '50 20 tes.assau 0.04 40 0.65 0.45 0.45 0.45 40 150 lRu ' O.03 40 0.51 0.11 ^ 0.11 0.74 0.11 40' 90 138'Cs C.01 0.02-10 26 0.20 0.33 0.12. 0.08 0.12 0.08 0,48 0.12.0.08 10' 26 40 50 Cs 0.G1 0.01 10 5 0.20 0.06 0.12.0.02 0.12 0.02 0.08 0.12 0.02 10 5 40' 15 Zr-Nb 0.01 10 0.20 0.12 0.12 0.12 10 40 as7 esZr

0. 01 ~

10' O 11. 0.03 0.03 0.15 0.03 10 ' 20 es b' O.01 5 0.05 0.01 0.01 0.07 0.01 5 15 co 0.02 0.01 15 5 0.23 0.05 0.20 0.01 0.20 0.01 0.07 0.20 0.01 15 5. 55 15 N Mn 0.02' O.01 10 5 0.20 0.05 0.15 0.01 0.15 0.01 0.08 0.15 0.01. 10 5' 40 15 se Zn 0.02 0.01 15 9 0.25 0.11 0.23 0.02 0.23. 0.02 0.17 0.23 0.02 15 9 70 20 Co 0.01 0.01 10 5 0.17 0.06 0.11 0.01 0.11 0.01 0.08 0.11 0.01 10 5 30 15 K. 3.10 150 2.50 0.90 0.90 0.90 150 400 0.15 15 50 ieeBa-La 0.02 15 O.68 0.15 0.15 0.30 0.07 25 50 8Ba 0.02 25 0.34 0.07 0.07

    • 'La 0.01 7

0.06 0.02 0.02-0.10 0.02 7 15 -

  • The NaI(TI) LLD values are calculated by the method' developed by Pasternack and Harley as described' in HASL-300 and hurl. Instr. Methods 91~

These figures do not These LLD values are expected to. vary depending on the activities of the components in the samples. Vegetation, fish, soil, and sediment 533-40 (1971). represent the LLD values achievable on a given sample. Water is counted 'in a 3.5-L Marinelli beaker. are counced. in a 1-pint container as dry weight. The average dry weight is 120 grams for vegetation and 400-500 grams for soil sediment and then corrected to wet weight using an average moisture content of Meat and poultry are counted in a 1-pint container as dry weight. 70%. Average dry weight is 250 grams. Air particulates are counted in a well crystal. The counting system consists of a multichannel fish. The counting time is 4000 seconds. All 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 d the least-squares computer program ALPHA-M.

    • The Ge(Li) LLD values are calculated by the method developed by Pasternack and Harley as described in HASL-300. These LLD valu to vary depending on the activities of the components in the samples. Solid samples such as soil.. sediment, and clan shells' are counted in a 0.5-L Water is ceunted in either a 0.5-L cr 3.5-L Marinelli beaker.

Air filters and.very small volume samples are counted in petrie is 400-500. grams. The average dry weight 251.14.16%. or 29% Ge(L1) Marine 11'i beaker as dry weight. 1 The. counting system consists of a ND-4420 multichannel analyzer and either a dishe's centered on' the detector endcap. All spectral analysis is performed using the software provided with the ND-4420. The-detector..~he counting time is normally 8 hours. assumption is made that all samples are analyzed within one week of the collection date. Conversion factor: 1 pCi = 3.7 x 10-2 3,9

.m ~ _..

c.

{l' ~ ~ Table 4 or Y g ~ ~ ~ Results Obtained in Interlaboratory Comparison' Program A. ' Air FilterI.(pCi/ filter)'

Gross' Alpha Gross Beta-

. Strontium-90 ' Cesium-137 EPA value. TVA AVG. EPA value. TVA AVC. EPA value TVA AVG. EPA value-TVA' AVG. Date' ( 30)- WARL" EARL ( 30). WARL EARL' '( 30) WARL EARL ( 30)' WARL EARL ~ 3/82-27 12 231 28-55 9 63 56 16 2.6 16 15. '23 9 24 24: C d 9/82 32 14' 28 67 9 57 5'2 " 20 2.6 -17 '8148 .27 9 22. 22 B. Tritium.in Urine (pCi/L) Date EPA Value ( 30) TVA AVERAGE WARL EARL +

5/82' 1300tS75 1793'

.1650"' 12/82'. .!3830+641-3'i10 - 4023 i N b

p y 4 4 1 Table 4 (Continued), . an ' Results Obtained in Interlsboratory Comparison Program. C. Radiochemical Analysis of Water (PC1/L) Cross Alpha. Crons Beta ~ Strontiun Strontium - 90' Tritium Iodine -131 i ' EPA-value TVA AVG. EPA value TVA AVG. EPA value TVA AVG. EPA value TVA AVG. EPA value.4 TVA AVG. EPA value. TVA-AVC. ' Data-(t 3ci ' WARL, EARL (t l$) WARL EARL (f la) VARL EARL (t3al__ WARL EARL (t30) WARL EARL (237) WARL EARL 1/81 24i10 20 19 3219 33 28 21 9 20 22 -12t2.6 13 12 8.422.6h 8.7 7.3L , 2/82, 1820tS92 2007 1793 3/82 '1929 19 20 19!9 19 20 ~ '62:11 61 ' 61 4/82' 2860t624-2907 2923 5/82 27.5212-27 '38.3 29t9 26 33 22 9 24 22 1312.6 11 8" h 6/82 E 18301589 1620 1810 4.4:1.2 5.3 3.6 ~7/82-1629. 13 32f 23:9 20; 21 8/82 2890t624 2903 -2793 9/82: 29tl3 '26 -I 4029 - 38 -I 24.529 30 21 14.St2.6 13.8 14.3 87:15 93 79 '10/82 25601606 2690 '2510 .f '. 11/82 1919 19 15 ' 24t9 22 23 1990 598 1943 1993 37:10 37 39 '12/82. D. Camma-Spectral Analvsis of Water (pCi/L). + Chromium iS1 - Cobalt - 60 Zinc - 65 Ruthenium - 106 Cesium - 134' Cesium - 137 EPA value. TVA AVG. EPA vaine. TVA AVG. EPA value TVA AVG. EPA value TVA AVC. EPA value TVA AVG-EPA value TVA AVG. _ t3?) VARL. EARL. (23a) - WARL EARL (t30) WARL EARL (:37) . WARL EARL ( Date (t 3o) VARL EARL-(t36) WARL lAR,L 2/82 0- <44 <35 20!9' 21 22 - 15t9' 16 16. 20t9 <40 <30 2229 21 19 2319 24 22 ' 44 ' <35 29t9 32 .34- .26t9 '29' 26 0 <40 <30 35t9 31 32 2529 24 27 6/82: 2329-d 1 d 10/82 5129 55 -<35 ',n39 gg 21 24t9 25d-25 30t9 39d <36 19t9 19d 17 2029 20d 22 T 7 4 ~ n ---.a

~ s Tab 134(Coatinued). ~ Results obtained in IIt:rlaboratory' Comparison Program E. Hilk (pCi/L) a Strontium - 89 ~ Strontium - 90 Todine - 131-Cesium - 137 - Barium - 140 Potassiuml Coba'It ' ' EPA value TVA AVG. EPA value TVA AVG. EPA value TVA AVC. EPA value TVA AVG. EPA value TVA AVG. EPA value..TVA AVG. EPA value. TVA AVG. Date (t30) WARL EARL-(t3a) .WARL EARL (23o) 'WARL EARL, '(t30) WARL M (t'39) WARL EARL - - (t30) ' WARL EARL-(130) ' WARL EARL k 4/82 2529 29 28 '16t2.6 16 13 28t9[ 31 30 0 <25.<15 15002130 1590 1413 3026 32 29' . 7/82-5.4tl.4h 6.7 5.1 k 10/82 0 <10-<10' 18.6'22.6 19.5 12.8 42!10 ~43 42 34 9- -34 n. O <25. <20 15602135 1563 1639 e-F e-0 F. Foods (pCi/kg, Wet Weight) Strontium - 89' Strontium - 90 Todine - 13'1 Cesium 137 Barium - 140 Potassium EPA value TVA AVG. EPA value. U_ 'A AVG. EPA value TVA AVG. EPA value TVA AVG. EPA value TVA AVG. EPA value TVA AVG.' Date. (23o) WAPL EARL ( 37) WARL EARL (23o) WARL EARL (t30) WARL EARL (230) WARL EARL ($3a) WARL EARL 26.k ' 27k 7/82 2629 30 ' 28 20!2.6 8 94t15 98 '98 20t9 24 26 0~ <25' <14 2400t208 28109 27339 11/82 0 <10 <40d k 4k 27.8:2.6 30.6 24 25210 20 29 2729 28 27 0. <25 <14 2780t242 2670 2903. Western Area Radiological Laboratory, Muscle Shoals. Alabama b ~ Eastern Area Radiological Laboratory,'Vonore. Tennessee

  • . No known explanation. Investigation underway.

Analysis completed after report date. Equipment malfunction, analysis' completed after report date I Poor analysis.. Equipment taken out of service for recalibr'ation. Further result's satisfactory. 8 ' Previous and Subsequent resslts satisfactory. No known explanation. IRC/ EPA Iow-level 1311 study. I Experimental detection limit is being reviewed. Potassium values are ug/l or og/kg. Review of procedure is in progress. k

u-.,

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- YELLOW CREEK, NUCLEAR PLANT ~

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~ 11 Atmospheric Monitoring The atmospheric monitoring network is divided into three. groups. Four local air monitors are located on or adjacent. to the plant site in the general areas of greatest wind frequency. One additional station is located at the point of maximum predicted offsite. concentration of radionuclides based on preoperational meteorological data (see figures 3 and 4). Four perimeter air monitors are located.'at distances out to 10 miles from the plant, and two remote air monitors are located at distances out to 45 miles. These monitoring stations are shown in figure 2. The remote monitors are used as control or baseline. stations.. At each monitor, air is continuously pulled through a Hollingsworth and Voss LB5211 glass fiber filter at a fl.ow of 3 ft / min.' In 3 series.with, but downstream of, the particulate' filter is a charcoal filter used to collect iodine. Each monitor has a collection tray and storage container to obtain rainwater on a continuous basis and a horizontal platform .that is covered with gummed acetate to catch and hold heavy particle fallout. Thermoluminescent dosimeters are used to record gamma radiation levels at each remote and' perimeter station. ~ Each'of the local air monitors is fitted with a GM tubegthat con-j tinuously scans the particulate filter. The disintegration rate of the atmospheric radioactivity is continuously recorded at each station and radio-telemetered i.nto the plant. Air filters-are collected weekly and analyzed for gross beta activ-ity. No analyses are performed until three days after sample ~ collection. The samples are composited monthly for analysis of specific gamma-emitting radio-nuclides and quarterly for 89 5r and 90Sr analysis. The results are combined for each station to obtain an annual average. During this reporting period, one sample.was not obtained because of equipment malfunction. These data a're 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 1968-1982 are presented in figure 5. Increased levels.due to fallout from atmospheric nuclear weapons testing are~ evident, especially in 1969, 1970, 1971, 1977, 1978, and 1981. These patterns are consistent with data from monitoring programs conducted by TVA at nonoperating nuclear power plant construction sites. Table 5 presents the maximum permissible c'oncentrations (MPC) specified in 10 CFR 20 for non-occupational exposure. Rainwater is collected monthly and a 3.5-liter sample analyzed for specific gamma-emitting radioisotopes and tritium. The results are shown in table 7. i The gummed acetate that is used to-collect heavy particle _ fallout is changed monthly. The samples are ashed and counted for gross beta activity. The results are given~in table 8. Thirteen samples were lost, destroyed, or damaged and analysis was not performed.

12 Charcoal. filters are. collected and-analyzed for radioiodine.

The. filter is. counted in a single channel analyzer system. The results are shown in. table 9. During this reporting period, three samples were not taken because of equipment malfunction or-filter damage. 4 m Y 8 f 4 ) h

i 7 o 7 13 Table,. 5 l l i MAXIMUM PERMISSIBLE CONCENTRATIONS l ( FOR NONOCCUPATIONAL EXPOSURE i~ l ' MPC -In. Water -In Air 3 pCi/1* pCi/m

  • I i

Alpha f 30 t Nonvolati,l.e, bet. a i. 3,000 100 ' Tritium t 3,000,000 200,000 337Cs 20,000 '500 383'38'Ru. '10 000 '200 3""Ce 10,000 200 "Zr "Nb ~ 60,000~ 1,000 3"0Ba 3"'La I 20,0'00 1,000 1 333 1 300 100 '5Zn 100,000 .'2,000 5"Mn l 100,000~ 1,000 "Co l 30,000 300. i '"Sr 3,000 300 "Sr 3 300 30 ' ' 8I Cr 2,000,000 80,000 33"Cs-9,000 400* "Co 90,000 2,000 2

  • 1 pCi = 3 7 4 10 gp h

s 3

.. _.. - _ -~_ _m -4 f TOCLE 6 - 4 RADI0 ACTIVITY.IN AIR FILTER. PCI/M(3) - 0.037 PQ/M(3) COCKET No.' 58-259 260 296 E' NAME OF FACILITY _889WNS_EERRY LOCATION OF FACILITY __LIFEST050__ ALABABA REPORTING

  • PERIOD 1982 s-CONTROL NUMBER OF TYPE AND

. LOWER' LIMIT ALL TOTAL NUMBER' 0F. INDICATOR LOCgTIONS _ LOCATION WITH Higg[11_ ANNUAL MLAN. LOCATIONg-

NONROUTINE,

a NAME MEAN ( MEAN (F REPORTED OF ANALYSIS' DETECTION MEAN.(Fg RANE((,f b L RANEL g[1}yg[t[311__ __ PERFORMED (LLD)- R ANj[__ DISTANCE AND DIRECTION 0.014 -1/- 51) GROSS ALPHA 0 005 51 0.01-0.01' ' GROSS BETA 0.010 0.02( 426/ 468). DECATUR. AL 0.02( 47/ 52) 0.02( 96/'103) 571-0.01-0.04 8.2 MILES SSE 0 01. 0.04 ' O. 01 - ' O.04 GAMMA (NAI) .83 "CE-141,144' O.030' O.05( 2/ 67) LM2'BF NORTH 0 054 1/ 73-

16. VALUES (LLD-C.04-0.05 0.9 MILE NNE-0.05-0.05'

'i r-C.12(' 1/.16 ) K 0.100 67 VALUES <LLO -0 12-0 12 + FE-59 NOT ESTAB 0.004 6/ 673 DECATUE, AL 0.00( 1/ _ 81 16 VALUES <LLO 0.00-0.00 A.2 MILES SSE 0 00-0 00 'I-131 0.010 0.02( 4/ 67). DECATUA, AL 0.02( '1/' 8) 16 VALUES (LLD 0.01-. .0.02 8 2 MILES SSE 0.02-0 02 BC-7 NOT ESTAB 0.074 67/ 67) ATHENS, AL 0.08( 8/ ' ' - 81 0.07( -15/.16) 10.01-0.10 10.9 FILES NE 0.C5-0.10 0.05. 0 11 GAhnA (GELI)- 60 'K-40 NOT ESTAB-0.02( 32/ 50) LM4 BF TRAILER P 0.02( 3/ 5) 0.02( 8/ 103 0.00- . 0.04 -1 7 MILES flNW 0.02-0.04l' O.00-0 03 8I-214 0.020' O.05 (. 3/ 50) ROGERSVILLE, AL 0.054 .1/- 73 0 034 1/ 10) 0.04-0.05-13.8 MILES NW 0.05-0 05 0.03-0.03 P8-214 0.020 0.046 3/ 503' ROGERSVILLE, AL O.04( 1/- 7)' 10 VALUES <LLD 0.03-: 0.04 '13.8 MILES'hW 0.C4-0.04 0.00( 26/ 50) DECATUR, AL 0.00( 2/' 53 0 004 4 /... 10) PB-212' NOT ESTAB ~ 0.00-0.00 8 2 MILES SSE 0.00-0.00 0 00-D.02 NOT ESTAB 0.02( 5/. 50) COURTLAND, AL .0.044 1/' -) 10 VALUES (LLD -RA-226 0 00-0.04 10.5 MILES WSW. 0.04-0.0' BE-7 0.050 0.06(' 20/ 50) LM5 BF DAVIS F. 0 074 1/ 5). 0.06( 5/ 101 0.05-0.07 2.5 MILES WSW 0.07-0.07 0.05-0.10 TL-208 NOT ESTAB .0.00(. 15/- 50) LM4 EF TRAILER P 0.00( 1/ 5) G.00( 5/ 103 0.00 - 0.00 1.7 MILES NNW 0 00- 'O.00 0.00-0.00 . o AC-228 NOT ESTAB 0.01( 2/.503-ATHENS, AL 0.01( 1/ 5)

10. VALUES CLLD 0.00-

-0.01 10 9 MILES NE-0.01-0.01 1 8 VALUES (LLD i ' SR 89-0.005 36 VALUES <LLD ' 44 AN ALYSIS ' P ER FORMED 8 VALUES.<LLD ^ SR 90 O.001 36 VALUES.<LLD 44 ANALYSIS. PERFORMED 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. 1 +

m.m_ TABLE.7 RADI0 ACTIVITY IN RAIZWATER-PCI/L - 0,037.80/L. NAME OF. FACILITY _ BROWNS _hgaRY . DOCKET No. 50-259.260 291 LOCATION OF'FACILITT__LIMESTQHE_' ALABAMA REPORTING PERIOD 1982 TYPE AND ' LOWER LIMIT ALL CONTROL ~ NUMBER OF TOTAL NUMBER OF INDICATOR LOCA{ IONS. LOCATION WITH HIGHEST ANNUAL'MEAN _ LOCATIONg' h0NROUTINE-0F ANALYSIS DETECTION

  • MEAN (

NAME MEAN (Fl" MEAN (F) REPORTED. 'RANAL{} DISTANCE AND DIPECTION RANGE RANG @ ELfSUREMENT}__ PERFORM (Q-(LLD) GAMMA ENAI) -119 FE-59 .NOT ESTAB' 2.76( '14/ 97) LM3 BF NORTHEAST 4.95( 2/ 103-5.65( 4/ 22) 0.10-' .5.50 1.0' MILE LNE.' 4.40-5 50' O.70 .,'9.50 BE-7 NOT EST AB 36.64( 54/ 97) LM5 BF' DAVIS F 45.714 7/ 103 45.95( 14/, 22) 1,. 7 0 - - 71.C0 2.5 MILES WSW. 30.00-66.20' 15.90. 84.60 SAMMA'(GELI) 24 M-40 NOT ESTAB 4.35( 2/ 20) ROGERSVILLE~e AL 6.71( 1/ 23 1 764. 1/. 43 1 48-6.71 13.8 MILES NW 6.71-6.71. 1.76-1.76 . BI-214 NOT ESTAB 'O.31( 1/ 20) ROGERSVILLE. AL 0.31(. 1/ 23 4 VALUES (LLD' O.31-0.31 13.8 MILES NW 0.31-0.31 AB-212 ' NOT EST AB 3 48( 12/ -20) LM2 BF NORTH 7.31( 1/ 1)

2.36 (-

2/- 4) 0.24-7.31 0.9 MILE NNE. 7.31-7.31 2.31-2.41 BE-7' NOT ESTAB 53.42( 3/ 20) ROGERSVILLE AL 75.36( 1/ 23 4 VALUES <LLD 31.55-75.36 13.8 MILES f4W 75.36-75.36 AC-228 15.000_ 17.90( 1/ 20) LM3 BF NORTHEAST 17.90( 1/ 31-4 VALUES <LLD '17.90-17.90 1 0 MILE ENE 17.90-17.90 TRITIUM 33G.000 117 VALUES <LLD 26 VALUES <tLD 143 ANALYSIS PERFORMED . a.' Nominal Lower Limit of Detection'O.t.D) as described in 7Able 3. b. Mean and range based upon ' detectable measurements only. ' Fraction of detectable measurements at specified locations, is indicated in parentheses (F). 1

TABLE 8 ,g RADICACTIVITY IN HEAVY PARTICLE FALLOUT MCI /KMt23 - 37000000.00 BQ/KMt2)' .5.. NAME OF FACILITY BROWgi. FERRY DOCKET NO.' 58-259 260.296- ~ LOCATION OF FACILITY LIMESTONE ALAgAMA . REPORTING PERIOD 1982 J CONTROL .huMBER OF TYPE.AND - LOWER LIMIT-ALL. 1 TOTAL NUMBER. OF. INDICATOR LOCA{ IONS LOCATIgh WITH HIGHEST ANNUALBElg ' LOCATIONg', -hChROUTINE REPORTED. MEAN ( NAME - MC AN tg' MEAN fg3 a. RANsr{3 '0F ANALYSIS-DETECTION DI!TANCE AND DIRECTION R ANGE RAgGE g[1}g3[g[ gig _ PERFORMED (Llos G%0SS BETA.. 0.050 0.21t 107/ 1073-COURTLAND, AL 0.318 12/ 12) 0.20t 23/ :25): ~

130 0.05-0.44.

10.5' MILES WSW 0.14- .0 44 0 07-0.41-i s a 2 L b t w Nominal' Lower Limit of Detection'(LLD) as described in Table 3.' c. Mean and range based upon-detectable measurements only'.. Fraction of detectable measurements at 'specified locations is indicated.in parentheses (F). b. 1 g

i. TABLE 9 ,RADI0' ACTIVITY IN CHARC0AL. FILTERS PC IIP!(3 ) - 0.037 BQ/M(3) q NAME OF' FACILITY _RgaMN1_((#RY DOCKET No. 50-259 260 296 LOCATION OF. FACILITY LIMESlgNE ALABAMA REPORTING. PERIOD 1982 TYPE AND .-LOWER LIMIT-ALL TOTAL NUMBER OF CONTROL ' NUMBER 0F 0F ANALYSIS ~ DETECTION" INDICATOR LOCg}TIONS [gCATION WITH HIGHEST ANNUAL MEAN R ANj[_{ ' MEAN.(g7 _ .LOCATIONg 'NONROUTINE' MEAN ( NAME MEAN (Fl R EPOR TED DISTANCE AND glr [gl10N RAgg[ _Ryg[ b g[Algg[g[g T}_ PERFORM [Q (LLD) IODINE IN AIR 0.020 0.03t 39/-467) ROGERSVILLE, AL O.038 12/ 52) 0.034 10/ 1023 .569, 3.02-3.07-13.8 MILES NW. 0.02-0.07 0.02-0.06 f a. Nominal Lower Limit of Detection (LLD) as described in Table 3. 1 b. Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (F). h I v 4 O t 4 u

18 ? Figure 2 ATMOSPHERIC AND TERRESTRIAL MONITORING NETWORK RM-28F LANRENCE8URG gPULASKI FAYETTEVILLE & i wlLSON WrtEELER DAM ROC V Le F FLORENCE OAM ATHENS -\\ PM-2 BF FFIEL MUSCLE HUNTSVILLE SH0ALS BROWNS FERRY NUCLEAR PLANT RM-IBF LEIGHTON TUSCUMBIA e COURTLANO DECAT \\ PM-38FO IO MILES g gRUSSELLVILLE T SVIL HARTSELLE DAM 4 25 MILES HALEYVILLE CULLMAN 45 MILES O--ENVIRONMENTAL MONITORINS STATION NOTER THE FOLLOWING SAMPLES ARE COLLECTED

FROM EACH STATION:

i AIR PARTICULATES RAINWATER

R ADIOlODINE SOIL

' HEAVY PARTJCLE FALLOUT I

3 . Figure.3 r LOCAL MONITORING STATIONS a 19 f_ BROWNS FERRY NUCLEAR PLANT M 4 3 p ATHENS _3 3 I N_ U.S. HWY 72 O i r -_m 5-n i a Si ^ ) 2= e Yp +e@ 0 = l O JEi m: e 3 e g 64 I g e. p L__N 1 Ma y w, M 5 ,f "A _t n y BFN c'E]G C

i-9 Jg

= + "'5B O fy [ i e#

s

[ ALA.' HWY 20 -J 1 J I -= t a gg \\ \\ min 4 Yi g f. -55B V p Legend "a -=in l-J N p 9 Air Monitor DECATUR g I A Autom'atic Well Sampler N -N pr i G Dairy Form m r 4 ( Scale. 0 1 2 3 4 5 3 e m a Miles 6 ( h 55

  • n air

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s. <

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,,,o., % 3 7 1 v.. 4 s n 9- ,., ;. n. a. x@(y :y- ',- 23 f 4.0../.Y f i e ;.. nr j Terrestrial Monitoring ${."j?u j @... " y. Milk 'g.,. c.. \\w.- W: .%o - t.. ?. 3. ; Milk is collected from four larms within a 10-mile radius of the

,8 1;p i,

.5 plant (see figure 3), and from at least one of four control farms. Raw milk ph. ' ikf.: 1 is analyzed weekly for 181 I, and monthly for gamma-emitting isotopes and for j.c w p; '. i radiostrontium. The results are shown in table 10. Q:.,,y:K s. n,..-w g., l( Cow censuses were conducted in May and September 1982. ;It was ).p.'ff O determined that there are no dairy farms nearer the plant than the nearest

J. c'Q.:.C..

farm being sampled. During this period however, one of the dairy farms being

f..~. c.y$

.1 e.' .[( sampled (farm T,. table 2) went out of business and all cows were sold.

h. i f

,f(y 5 F.e aV Vegetation n,.,.f

c. 1.l f, h

Vegetation is sampled quarterly at the farms from which milk is .N collected and analyzed for garma-emitting radionuclides. Approximately 1-2 y(';. -Q ..f - !.d kilograms of grass is broken or cut at ground level and returned for analysis. .;. l. - "~ f Q j/,' Efforts are made' to sample vegetation that is representative of the pasturage ?r where cattle graze. Table 11 gives the results obtained from the laboratory 7 l-E. analyses of these samples. p,3.; ~' 3 Ry:rk. ; 7 Soil _p y, m.q [b

,J. " ?

. j.?

  1. O.N

+ Soil samples are collected annually near each monit'oring station to gg r;;.g ,i provide an indication of a long-term buildup of radioactivity in the environ-An auger or. " cookie cutter" type sampler is used to obtain samples of pl@/ m:4. 7 ment. r.4 ? the top two inches (5 cm) of soil. These samples are analyzed for gamma-0 i. ? emitting radionuclides, 89Sr, and Sr. The results are given in table 12. ? Y J.+.I 80

-A d; c..n.

J q I u 2,: h Ground Water L. ?., 5* i?.b a&N'-?;hf

1.,

An automatic sequential-type sampling. device has been installed on a 4 i) /,1 2 y well downgradient from BFN. A composite sample from this well is analyzed for YT (,' p.?c 4 9 n gamma-emitting radionuclides monthly and composited quarterly for determination ./ f... of tritium. A grab sample is also taken from a control well upgradient from .gf ' k . t 4.7, li the plant. The results of the analysis of well water are shown in table 13. Ts..N,,,. i g* &i' %,, g Fpn.h -. -

f. ;

Drinking Water

  1. hD.'..."g-A.,s, 1,

Potable water supplies taken from the Tennessee River in the vicinity k[g.. e

e. rd of BFN are sampled and analyzed for gross beta and. gamma-emitting radionuclides,

%.,,s.MD (.-. and composited quarterly for tritium, 88Sr, and Sr analyses. The first MA., $.9 :-Y 80 p potable water supply downstream from the plant is equipped with an automatic {kf?.D;C i sampler with samples collected and analyzed weekly. The sampler is located on s, i:f.". the water intake structure and takes the sample from the river as the raw y f '$, j water is drawn into the water treatment facility. Two additional supplies ?h a :, ?%.3 "S %:k p S w l, 7,.. -. .w- ,Y 2, ~."p. ' ~ ;

f.,.. qs,,

h [f

  • W

%.3 f..;. n'$ j f %. ;a. n: W M y' ' Ej. a [ & , %#s %.W.

  1. ,, A 9 4Qm

. A. %...A, ? ?i .?+*r!JL i;^# +- "' #

  • 'i 'O '

' "~'

.."p.. 6 s~ l. 'l bl.Y J 7 @J,g 24 } q b downstream and one public water supply upstream are sampled by taking monthly f/' I J Q grab samples of treated water at user points. Table 14 indicates tte results YA N: .i from the analysis of drinking water samples. During this reporting period, one of the weekly samples was not taken because of the malfunction of automatic j(.J f,; E 9c.v..;'; 4 sampling equipment. Another sample was missed due to inaccessability caused m.d/ O i by bad weather. 1.! '.. A I R p. '.i " } Figure 6 shows the trends in gross beta activity in drinking water . N. 36 - 2 ..f from 1968 through 1982. The annual average level from the raw water samples h,.- M. J. O tends to run slightly higher than the average for treated water samples; however, i c:.~-e v the levels are consistent with the activities reported in surface water samples [Sr,[j ,J. taken upstream from BFN (figure 12) and in samples taken from the Tennessee (g ? .3 River in preoperational monitoring programs conducted by TVA at other sites. 234 y y q >; R. Q.q ;.y ; 4 Environmental Gamma Radiation Levels i ?.. y. )p

v gr.,

Bulb-type Victoreen manganese-activated calcium fluoride (Ca2F: Mn) [ f' N thermoluminescent dosimeters (TLDs) are placed at sixteen stations around the 7,.u plant near the site boundary, at the perimeter and remote air monitors, and at f;7% 1 .?) nineteen additional stations out to approximately five miles from the site to j W D. E determine the gamma exposure rates at these locations. The dosimeters, in A.Q N. 4 energy compensating shields to correct energy dependence, are placed at approxi- .'9 7 D " g[ mately one meter above the ground, with three TLDs at each station. They are J N."...:. annealed and read with a Victoreen model 2810 TLD reader. The values are % i o ?E corrected for gamma response, self-irradiation, and fading, with. individual 5 yX' Y' gamma response calibrations and self-irradiation factors determined for each .%)%, ik TLD. The TLDs are exchanged every three months. The quarterly gamma radiation ~. M '. levels determined from these TLDs are given in table 15, which indicates that Wl n 7 average levels at onsite stations are approximately 3-5 mR/ quarter higher than ^i f c.J J Q 1evels at offsite stations. This is consistent with levels reported at TVA's '.h-{.l;:yp nonoperating nuclear power plant construction sites where the average radiation ,.f : ?.:.. M levels onsite are generally 2-6 mR/ quarter higher than levels offsite. The ei. R-[.M j K causes of these differences have not been completely isolated; however, it is Y postulated that the differences are probably attributable to combinations of Q.?; :- i.. i influences, such as natural variations in environmental radiation levels, ha.. J". q earth moving activities onsite, the mass of concrete employed in the' con-f )[ 'lM V struction of the plant, and other undetermined influences. j. 9 Figure 7 compares plots of the data from the onsite or site boundary e.4p.., m v a a.. i stations with those from the offsite stations over the period from 1976 through ,[.FQQ s {y To reduce the variations present in the data sets, a four quarter

-? :J';J f 1982.

moving average was constructed for each set. Figure 8 presents a trend plot

g.Sy' 1 W

of the direct radiation levels as defined by the moving averages. The data .g Q.' 2 M follow the same general trend as the raw data, but the curves are smoothed te V i 4 considerably. Mf.J.IH p p y.9.. A Prior to 1976 measurements were made with less sensitive dosimeters, L.D ? > 2 and consequently the levels reported in the preoperational phase of the moni-kDD. toring program are 1-2 times the levels reported herein. Those data are not pg$dt t, r.r9 included in this report. Therefore, for comparison purposes, figures 9 and 10 .Q;) M depict the environmental gamma radiation levels measured during the construction

z..; J.;

7Uf 6 O d of TVA's Watts Bar Nuclear Plant to the present. Note that the data follow a g similar pattern to the BFN data and that, as discussed above, the levels 4.t :;c j reported at onsite stations are similarly higher than the levels at offsite kQ' ~ ~ < Q [i Stations. [ bp p,.e;- o, p'f !h'.j')l 4/.f k. ,.I ll l, l, )% h,fN l s,=

c. b,...

y ;;.y. -

  • !I)..,,,, % ).h) y,, n :, _- Q..

3 (.s. ] k' A4 r, - % . 'm h,Y. v'NT' A N '-' 'S N a. ? N

i 25 l l l. Food Crops l Food crops raised in the.v'cinity of BFN and at control locations - are sampled.as they become availahim Juring the growing season, and anal'yzed for gamma-emitting radionuclides. During this sampling period, samples of corn, green beans,. potatoes, turnip greens, and tomatoes were collected and analyzed for specific gamma-emitting radionuclides. Nousample.of turnip greens was taken from a control. location. The results are.given in tables 16, 17,-18, 19, and 20,. [ 0 e t e i

TABLE 10 RACI0 ACTIVITY In MILK E01/L - 0.037 BQ/L e NAME CF F ACILITY,3ROWNS FERRY 00CMET NO. 50-25212&g.296 REPORTING PERIOD 1982 LCCATIC% CF FACILITY __Ll"[5TONL 4 t,1;a u TYPE AND

  • L0kEP LIMIT aLL CONTROL NUMBER OF TCTAL NUMBES OF INDIEAioR LOCAg10NS LggAIIEk wilt _giqu[sf A33yAL_3[AN LOCATIONS NCNROUTINL a

f f}~~_ PEAN (F)b PEPORTED OF ANALYSIS DETECTION 'MEAN (g) NAME PEAN PERF0PM[g JLU RANjL MITANCE A NDJ1R((1 T ON pa%gg oANggb pggggggg_ GAMMA (NAI) 63 CS-137 10 000 11.108 1/ 42) PAGE FARM 11 108 1/ 10) 41 VALUES (LLD 11 10-11 10 9 75 "ILES E 11 10-11.10 0-90 150.000 1306.328 42/ 42) DAGE FARM 1373.916 10/ 103 1297.164 41/ 41) 10 DINE-131 0.500 212 VALUES (LLD 1036.80- 1451 60 954.00- 1553.60 6.75 "ILES E 1156.80- 1455.50 204 VALUES (LLD '416 ANALYSIS PEaFORMED GAM 94 (GEL 18 2C CS-137 5.000 6.31f 3/ 113 PAGE FARM 6.72f 2/ 33 9 VALUES (LLD 5.50-7.51 ?.75 "!LES E 5.93-~ 7.51 M-40 NOT ESTAB 126#.10t' 11/ 11) LOCNEY FAR* 135*.464 2/' 21 1256 578

  • /

9) 747.91-1989.83 5.75 MILES ENE 1209.10- 1994.63 1175.66-1362.45 PI-214 NCT ESTAB 48.994 2/ Ill 5"ITH FAR* 49.998 2/ 3)- a VALUES (LLD 3e.29- -61.69 4.75 MILES N 39 29-61.6* PP-214 NOT EST AD 41 258 2/ 11) Sw!TH F ARM 91 258 2/ 3? F.028 2/

  • )

70.76-E1 74 4.75 FILES N 20.76-61 74 7.22-6.02 P0-212 60T ESTae 1.64f 6/ 11) E800N5 FAR" 2.E3t 2/ 33 3.446 3/ c) 0.06-4.09 7.0 MILES NNW 1 58-4.08 1 94-5.89 AC-228-NOT ESTAB 11 VALUES (LLD 3.03t 2/' 93 2 85-3 21 SR 89 10.000 53 VALUES (LLO 50 VALUES CLLD 103 ANALYSIS PERFORMED S2 93 2.009 4.3Pt 49/ 53) S4tTH FARM 5.658 12/ 13) 3.698 46/ 50) 103 2.09-10.14 4.75 MILES N 3.26-10.14 2.08-c.72 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).

~ - P TadLE 11 RaDI0 ACTIVITY IN WEGETATION PCI/G - 0.037 BC/G (ORY WEIGHT 1 ~* N&#E OF FACILITY _ARDWNS FERRY LJCKET teG. 50-214221122*1 LocayIcy or FACILITY __klML}TCNE AL82aMa REPORTING FERIOD 19EP TYPE aND LcgER LIw!T ALL. CCNTROL NUPBER OF TOTAL NU" sea cF INDICATOR LCCATICNS LOCATIGN blTH HIEg{ST ANNutL *[AN LOCATIONS NONROUTINE OF ANALYSIS DETECTION

  • MEAN EF) b NAME wCAN (Fili _

PEAN (F # REPORTED b b PERFOR'[2-(LL2) _RANGL gygyggg g p_gypggggpq nA3EE qaqqgb ggggy_ GR OSS BE T A 0.200 23 424 17/ 173 . THRASHER FARM 69.438 1/ 13 30.e3t 16/ 163 33 3.29-69.43 7.0 MILES ENE 6*.43-65.43 3.e0-57.24 CAMMA (GELI) 33 CS-137 'O.060 0 136 4/ 173 SMITH FARM 0.164 1/ 45 0.074 3/ 163 0.07-C.19 4.75 MILES N C.le-0.le C.07-0.06 K-40 NCT ESTAB' 14.?24 17/ 17) THRASHER FARP 46.288 1/ 13 '20 708 15/ 16) 1 97-46.29 7 0 MILES ENE 46 29-46 29 4.95-46.06 BI-214 0.100 0.108 1/ 173 SMITH FARM-0.108 it 43 0 164 1/ '16) 0 10-0.10 4.75' MILES N 0 10-0.10 0.16-0.16 BI-212 NOT ESTA9 17 VALUES <LLO 0 31t 1/ 163 0.31-D.31' Pe-214 .NCT ESTAE 0.048 '/ 173 SMITH FARM C.12t 3/ 4) 0.C7f 6/ 16) 0.01-0.13 4.75 "ILES N 0.00-C.13 0.00-0.1F PB-212 NOT ESTAP 0.064 15/ 17) SMITH FARu .0 07t

  • /

45 0.06t 12/ 16) 0 00-0.16 4.75 MILES N 0.00-0.16 0.02-0 11 RA-226 NOT EST AS 0.116 h/ 175 PAGE FARM 0.26f 2/ 41 0.07t 9/ 163 0.02-0.50 BE-7 NCT ESTA9 5.86t 17/ 17), 9 75 "ILES E O.02-0.50 0.01-0.16 BROOKS F AR M 7.22t 4/ 43 4.87t 15/ 16) 0.33- -15.56 .7.0 MILES NNW 2.35-15 06 0.92-9.e9 TL-209 NOT ESTA9 0.028 11/ 17) THDASHER FARM 0.048 1/ 1) 0.044 1C/ 16) -0.00- .0 06 7.D MILES ENE C.04-0.04 0.01-0.06 AC-228 NOT ESTAB 0.178 12/' 173 THRASHER FARM 1.158 1/ 13 0 14t et 161 0.02-1.15 7.0 MILES ENE. 1.15-1.15 0.03-0.26 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). ~~

TL8LE 12 RADI0 ACTIVITY IN SOIL PCI/G - 3.037 EG/G (ORY, WEIGHT) NAME OF FACILITY _ BROWNS FERRY DOCKET NO. 50-259 260 296 LOCATION OF FACILITY LIMESTONE A(AGAMA REPORTING PERIOD 19A2 TYPE AND LOWER LIMIT. .ALL CCNTROL NUMBER OF TOTAL NUM8ER OF INDICATOR LOCA ICNS LOCATION WITH HIGHEST ANNUAL M[Ah ~~~ LOCATIONg NONROUTIhE MEAN ( } NAME MEAN (FY MEAN ( REPORTED R A Ng({_ _ R Ahg[(* OF ANALYSIS DETECTION" Q111ANCE A%C gl3L(110N RA3g _ g[A1QR[g[gI}__ PERFORMED (LLD) GAMMA (GELI) 11 CE-144 0.060

9. VALUES CLLD 0.124 1/

2) .0 12-0.12 CS-137 0.020' O.40( 9/ 9) ATHENS, AL 1.17E 1/ 1) 1.174 2/ 2) 0.05-1 17 10.9 MILES NE 1.17-1.17 1.01-1.33 K-40 0.250 .5.52( 9/ 95 LM4 BF TRAILER P 8.13t 1/ 13 4.57( 2/ 23 3 36-8.13 1.7 MILES NNb 8.13-8.13 4.07-5 07 MN-54 0.010 0.02( 2/ 93 LM5 BF DAVIS F 0.02( 1/ 13 2 VALUES CLLD 0.01-0.02 2.5 MILES hSW 0.02-0.02 BI-214 0.050 0.91( 9/ 9) LM4 BF TRAILER P~ 1 18( 1/ 13-0.81( 2/ 2) 0.55-1.18 1.7 MILES N4m 1.18-1.18 0.73-0.89 81-212 0.100 1 33E 9/ 9) LM4 BF TRAILER P 1 78( 1/ 13 1.03( 2/ 2) 0.68-1.78 1.7 MILES NNW 1.78-1.78 0.91-1 15 P8-214 0.350 1 02( 9/ ?) LM2 BF NORTH 1.33( 1/ 13 0.90( 2/ 23 0.65-1.33 0.9 MILE hhE .1.33-1.33 0.83-0.97 PB-212 NOT ESTAB-1.09E 9/ 9) LM4 BF TRAILER P 1 454 1/ 1) 0.86( 2/ 2) 0.62-1.45 1 7' MILES kNW 1.45-1.45 0.80-0.92 RA-226 0.350 0.914 9/ 9) LM4 BF TRAILER P 1.12( 1/ 13 0.81E 2/ 2) 0.55-1.18 1 7 MILES Nhm 1.18-1.18 0.73-0.89 C&-223 NOT EST AB 0.314 6/ 9) LM3 BF NORTHEAST 0.37( 1/ 13 1.974 2/ 2) RA-224 NOT EST AB 0.99( 4/ 9) LM4 8F TRAILER.P, 0 37-0.37 0.30-3 64 0.24-0.37 1 0 MILE ENE 1 424 1/ 1) 2 VALUES (LLD 0.53-1.42 1.7 MILES kN. 1.42-1.42 BE-7 0 160 9 VALUES (LLD 0.21( 2/ 23 0.20-0.22 TL-208 0'.520 0.364 9/ 9) LM4 BF TRAILER P 0.458 1/ 11 0.30( 2/ 2) 0.20-0.45 1.7 MILES NNW 0.45-0.45 0.28-3.33 AC-228 0 060 1.12( 9/' 9) LM4 8F TRAILER P 1.51t 1/ 1) 0.88( 2/ 23 0.60-1.51 1.7 MILES ANs 1.51-1.51 0.79-0.98 PA-234M NOT ESTAB 2.814 4/ 9) LM5 SF DAVIC F 3 15( 1/- 1) 1 388 1/ 2) 2.44. 3.15 2 5 MILES =SW 3.15-3.15 1.38-1.38 SR.89 1 500 1.824 1/ 9) ATHENS, AL 1.824 1/ 13 2 VALUES <LLD 11 1.22-1.82 10.9 MILES NE 1.82-1.82 $2 90 0.300 9 VALUES CLLD 2 VALUES (LLD 11 ANALYSIS PERFORMED 4 Nominal Lower Limit of Detection (LLD) as described in Table 3. b. & an and range based upon detectable measurements only, Traccian of detectable measurements at specified locations is indicated in parentheses (F), a. .1 4

TABLE 13 RADICAC'.IVITY IN WELL WATER PCI/L - 0.037 B3/L NAME OF FACILITY BROWN} FERRY DOCKET NO. 50-259.P60.P96 LOCATION.0F FACILITY LIMEST0gL, ALADAMA REPORTING PERIOD 1982 TYPE AND LOWER LIMIT ALL CONTR'OL NUMBER CF TOTAL NUMBER OF. INDICATOR LOCA{ IONS LQtATION WITH HIGHEST ANNUAL MEAN. LOCATIONg NCNRCUTINE OF ANALYSIS DETECTIOg a MEAN ( .NAME MEAN F)" RAN(({} RANGE {) MEAN ( REPORTED i PERFORMER (LLD) DISTANCE AND DIREC110N RANG ELA1URE*EN11,_ GannA (NAI)_19 t FE-59 NOT ESTAB 8 VALUES CLLD 4.354 2/ ll) 2.96-5.80 I-131 15.000 8 VALUES (LLD 15.20t 1/ 113 15.2C-15.25 CAMMA (GELI) 7 BI-214 NOT ESTAB 14.364 1/ 53 8FN WELL #6 14.364 1/ 5) 2 VALUES <LLD 14.36-14.36 0.02 MILES W 14.36-14.36 PB-212 NOT ESTAB 1.584 2/ 5) BFN WELL #6 1.584 2/ 53 0.998 2/ 2) 1.25-I.9C 0.t2 MILES W 1.25-1.90 0.78-1.20 TL-208 NOT ESTAB 2.658 2/ 5) 8FN WELL s6 2.654 2/ 53 2 VALUES <LLD 1 85-3.46 C.02 MILES W 1.85-3.46 TRITIUM 330.000 4 VALUES CLLD 4 VALUES (LLD 8 ANALYSIS PERFORMED a. Nominal Iower 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

TC;LE 14 RADISICTIVITY IN PUBLIC CATER SUPPLT PCI/L - 6.C37 EQ/L MAME OF FACILITT_ BROWNS FERRY DOCKET NO._11-21222k12226 LOCATION OF FACILITY LINESTOHL. ALABAMA REPORTING PERIOD 1982 TYPE AND LOWER LIMIT ALL CONTROL NUMBER CF TOTAL NUMBER OF INDICATOR LO C (TION S kgCATION WITH MIEHL11_AhhM&C.MEAN _ LOCATIONg NONECUTINE PEAN ( NAPE MEAN gF)" MEAN IFg REPORTED OF ANALYSIS . DETECTION *

  1. ANj[{ r QISTANCE AND DlR(gT10N RAkip_

RANiE M[A}yR[P[gl}__ PERF04MEO __iLLQ) G;LSS BETA 2.400 3.60t 51/ 76) CHAPPION PAPER 3.734 42/ 50) 2 874 3/ 13) 89 2.42-13.53 TRM 282.6 2.47-13 53 2.58-3.17 GOMMA (NAI) 70 FE-59 NOT EST A8 3.858 6/- 62) SHEFFIELD.AL RDB 6.6Gt 1/ 11) 8 VALUES CLLD 1 00-6 60 TRM 254.3 6.6C-6.60 GIMMA (GELI) 19 d-40 NOT ESTAB 1 048 1/ 14) CHAMPION PAPER 1.D*t 1/ 10) 9.268 1/ 53 1.04-1.C4 TRP 282.6 1.G4-1.04 9.26-9.26 F8-214 NOT ESTA8 8.474 1/ 14) CHAMPION PAPER 8.478 1/ 10) 5 VALUES (LLD 8.47-8.47 TRP 282 6 6.47-6 47 PB-212 NOT EST AB 3.588 .9/ 14) WHEELER CAM, AL 3.988 1/ 2) 1.788 3/ 5) 1.33-4.09 TRM 274.9 3.98-3 98 1 32-2.27 TL-228 NOT ESTAB 0.528 5/ 14) WHEELER DAM, At 0.63t 1/ 23 1.298 2/ 53 0.25-u.68 TRM 274.9 C.63-0.63 0.73-1.P8 4 VALUES (LLD SR E9 10.000 12 VALUES (LLD 16 ANALYSIS PEPFORPEC 53 93 2.000 12.WALUES CLLD 4 VALUES <LLO 36 ANALYSIS PERFORMED TQITIUM 330 000 395 054 2/ 12) CHAPPION PAPER 419.248 1/ 4) 4 VALUES (LLO 16 370.86-419.24 TR" 282.6 419.24-419.24 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). m

31 Table 15 ENVIRONMENTAL GAMMA RADIATION LEVELS Average External Gamma Radiation Levels at Varicus Distances from Browns Ferry Nucicar Plant for Each Quarter - 1982 mR/ Quarter

  • b l

Distance Average External Gasma Radiation Levels miles 1st Quarter. 2nd Quarter 3rd Quarter 4th Quarter 0-1 20.8 i 1.1 20.3 t 1.7 21.3 i 1.5 21.9 i 1.6 1 1-2 18.6 1 2.0 16.8 i 3.2 18.1 1 2.1-16.3 1 4.0' 2-4 17.9 i 1.7 16.3 i 1.5 17.5 i 1.8 15.8 i 3.8 4-6 17.4 i 1.6 16.1 i 1.4 17.6 i 1.6 .15.5 i 3.6 >6 17.4 1 2.6 16.4 i 3.0 17.3 1 3.3 15.6 3.2

Average, 0-2 miles (Onsite) 20.3 1 1.6 19.4 1 2.6 20.5 t 2.1 20.5 i 3.4
Average,

>2 miles (Offsite) 17.6i 1.9 16.2 1 2.0 17.5 1 2.2 15.6 1 3.4

a. Data normalized to one quarter (2190 hours).
b. All averages reported 110 (68 percent confidence level).

1

TC.8LE 16 RCDI3 ACTIVITY IN CORD PCI/MG - 0.037 BC/KG (WET WEIGHTl NARE OF FACILITY E qt3 Lf,[RRY DOCKET NO. 50-259n260e296 LOCATION OF FACILITY LINESTONL ALABARA REPORTING PERIOD 19RP TYPE AND LOWER LIMIT ALL CONTRCL NUMBER OF TCTAL NUMBER OF INDICATOR LOCA{ IONS LOCATIgN WITH HIGH[57 ANNMAL MEaN_ LOCATIONg NONROUTINE

f. F ANALYSIS DETECTION,

MEAN IF NAME MEAN (Ft MEAN ( REPORTED EANGE() b b M[g}gg[ gig _ PEDF0p*ED (LtD) 4ANGE g]} Igg {E AND DIRECTION PANGE G OSS PETA 25.800 3667.62( 1/ 13 7 MILES NkW 3667.628 1/ 13 4983.144 1/ 13 2 3667 62-3667.62 3667.62-3667.62 4983 14-4983.14 COMMA (GELI) 2 E-40 NOT EST AB 1990.356 1/ 11 7 MILES NNW 1990.354 1/ 19 2040.726 1/ 13 1990.35-1990.35 1990.35-1990.35 2040.72-2040 72 P3-212 NOT ESTAB 1.384 1/ 13 7 MILES NNW 1.38( 1/ 1) 1 WALUES <LLD 1 38-1 38 1.38-1.38 TL-20s NOT ESTAB 3.038 1/ 11 7 MILES NNW 0.036 1/ 17-1 VALUES (LLD O.03-3.03 6.03-3.03 s. 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). 9

_. _. -. = TAELE 17 RADI0 ACTIVITY IN GREEN BEANS PCI/4G - 0.037 B0/MG (WET WEIGHT) NAPE OF FACILITY E gg i l[RRY 00CKET No. 50-2122260 296 LOCATION OF FACILITY _(IMESl$3[_ ALABAMA . REPORTING PERIOD 1982 TYPE AND LOWEP LIMIT ALL CONTROL NUMeER CF TOTAL NUP8ER OF IND'CATOR LOCA{ IONS LSCATIgN WITH HIGHLET ANNUAL MEA 3 LOCATIONS-NONROUTINE CF ANALYSIS CETECTICN' MEAN ( NAME MEAN ( MEAN F)b REPORTEC RA3&L{} DISTANCE AND DIREC110N R AhEL{ ifERF0puED (LLS) RANG EL11MELE[h11_ GROSS BETA 25.300 4257.41t 1/.. 11 7 MILES NNW .4257.414 1/ 11 4751 82( 1/ 1) 2 4257.41 -4257.41 4257.41-4257.41 4751.82-4751.82 GAMMA (GELI) 2 K-40 NOT ESTA8 1900 304 1/ 13 7 MILES NNW 1900.30( 1/ 11 2034.02( 1/ 13 s 1900.30- 1900.30 1900.30- 1900.30 2034.02-2034.02 PB-232 NOT ESTAB 1.68( 1/ 13 7 MILES NNe 1.68( 1/ 13 4.08( -1/ 1) 1.68-1 68 1 68-1.68 4.08-4.08 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). s m-

-. _ _ _ _ ~ _ _ __ .s. m TABLE-18 RADICACTiv!TV IN POTATOES PCI/KG - 0.037 BC/KG (WET WEIGHTS MARE OF FACILITY.BROWgs rgARY 00CKET No. 50-219.268 2*6 LOCATION OF FACILITY LIMESTONE, ALABAMA REPORTIhG PERIOD _19M2 W TYPE AND LOWER LIMIT-ALL CONTROL NUMBER OF-TOTAL NUMBER OF Ih0!CATOR LOCA(IONS LOCATION WITH HIGHEST ANMUAL MEAN. -LOCATIOg$ 40hEOUTINE MEAN ( NAME MEAN Eg f MEAN gF r REPORTED OF ANALYSIS DETECTION

  • RANCE{}

DISTANCE AND DILL {Il0N RANGE PANGt gG}yg[gQ1}_ PERFORMED 'LLD) GJ.SS BETA 25.000 1373.008 1/ 11 .7 MILLS NNW 5373.004 1/ 13 7280 194 1/ 13 2 5373.00- 5373.00 5373.00- 5373.CC 7280.19-7283 19 C*MMA (GELI) 2-U-40 NOT ESTAB 3549.888 1/ - 11 '7 MILES NhW 3549.888 1/ 13 3337.574 1/ 13 -3549.88-3549.88 3549.88-3549.88 3337.57-3337.57 a. Nominal Immer Limit of Detection (LLD) as described in Table 3. b. Mean and range based upon detectable measurements only. Fraction of detectable measurer ants at specified locations is indicated in parentheses (F). a i i e y

~ ' T A B L E 19 RADIO CTIVITY IN TOIATOES PCI/KG - 0 037 HO/KG (WET EIGHT)' m NAPE OF FACILITY PROW 51_EERRY DOCMET N0. 50-?59 261g?96 LOCATIch 0F FACILITY. LImESTONL ALABAMA REPORTING PERIOD 19h? TYPE AhD LOWER LIMIT ALL CONTROL AUM"ER OF TOTAL NueSER OF INDICATOR LOCA{ IONS -Lgg TIgLj(ITH HJgNEST A7.NUA(JgAN LOCATIONS AD% ROUTINE l OF ANALYSIS DETECTION

  • PEAN I I NAME

.mEAN (F)" . PEAN ( b PANG [{3 EEFORTED l PERFORuED (LLD) 'RANC QISTANCE AND DIRECTION EANGEb l GROSS BETA 25.000 3987 898 1/ al. 7 MILES NNW 3987.898 .1/ 11 4577.958 1/ 13 MEASUPEMEN1}_ 2 3987.89-3987 89 3987.89-3987.89 4577.95-4577.95 2 K-40 NOT ESTAB 2172 528 1/ 19 7 MILES NNW 2172.528 1/ 1) 2158.948 ~1/ 1) 2172.52-2172 52 2172.52-2172.52 2158.94-2158.94 l PS-212 NOT ESTAB 2.548 1/ 13 7 PILES NNW 2.548 1/ 11 4.764 1/ 13 2 54-2 54 2 54-2.54 4.76-4.76 a. 3keinal 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). d

TiBLE 20 RADICACTIVITY Ik TURNIP GREEh5 PCI/uG - 0.037 BQ/MG (WET WEIGHT 3 DOCKET NO. 50-P59.260.P96 mapE OF FACILITY _8ROWh5 FERRY LOCATION CF FACILITY LIMESTONE ALABAPA REPORTING PERIOD 1982 CONTROL NUMBER CF TYPE AND LOWER LIMIT ALL TOTAL kUP8E8 0F~ INDICATOR LOCATICNS (g[Aligh WITH HIGHEST ANNUAL prah ___ LOCATIONS h0NROUTINE OF ANALYSIS DETECTION

  • MEAN IF N NAPE MEAN IFY MEAN (F)b REPORTED PERFOR=Ee (llc 3 oANgg_b p117ANgE Aho claECTION RANGEb RANG @

P{A1UREMENI1__ GROSS BETA 25.800 7719 474 1/ 13 7 MILES NNW 7719.474 1/ 13 1 7719.47-7719.47 7719.47-7719.47 cap 4A (GELI) 1 CS-137 5.000 '7.254 1/ 13 7 MILES Nhw 7.038 1/ 13 '7.C3-7 03 7.03-7.03 c-4 3 h07 ESTA8 3239.218 1/ Il 7 MILES NNW 3209.214 1/ 13 ~32C9.21-3229.21 32C9.21-3209.21 PO-212 NGT ESTAB 7.484 1/ Il 7 PILES NNW 7.484 1/ 13 7.48-7 48' 7 48-7.48 8E-7 NOT ESTAS 105 524 1/ 13 7 MILES NNW 105.528 1/ 13 '1:5.52-185 52 105.52-105.52 TL-208 NOT [ STAS 2 154 1/ 13 7 MILES NNW 2.15t' 1/ 11 2 15-2 15 2.15-2.15 %osiaal Eower 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). i

aa.- ee ._a a-- - - a-- -m._m4 2 .m.6 -a-. m_2 _._g,, .---a-- --wa .-...J----.. _. - - -.a 37 i I i l I en j2 l >ag I l $5j I, = 5 5 ~ Mm E mEng ag) PEAN (F)b REPCRTED b PERFCR*ED ELLO) Sani [b DISTANCE AND OIRECTION RANGE RANGE EMEUR E M E NIj_ tasSS PETA 2.400 3.698 5%# 393 TRP 285.2 4.214 32/ 13) 3.734 20/ 263 65 2.47-R.35 2.62-8.35 2 42-6.P5 6CM4A (NAI) 44 FE-59 NOT EST AB 5.404 3/ 24 TRM 293.5 10.TGt 1/ 73 4.388 5/ 20) 2.70-13.70 10.70-10.7C 3.00-7 50 I-131 15.500 16.7Ct 1/ 24) TRF 293.7 16.7CE 1/ 93 2C VALUES (LLD 16 7G-16.70 BF4 OISCHARGE 16.7C-16.70 GAn=A (GELI) 21 LA-140 7.000 13.64t 1/ 153 TAM 293 7 13.648 14 43 6 VALUES (LLD 13.64-13.64 BFN DISCHARGE 13.64-13.64 E-4C NOT ESTAB 19.684 2/ 15) TRM 285.2 22.768 1/ 53 13.754 1/ 61 16.63-22.76 22.76-22.76 13.75-13.75 61-214 NOT EST AB 4.255 1/ 15) TAM 293.5 4.254 1/ 67 2 514 1/ 63 4.25-4.25 4.25-4.25 2 51-2 51 11.964 1/ 6) PB-214 NOT ESTAS 15 VALUES (LLD 11 94-11.96 PB-212 NOT EST AB 2 16e 4/ 15) TRM 293.7 2.434 1/ 45 2.51( 5/ 68 1 55-2 59 PFN DISCHARGE 2.43-2.43 2.35-2.76 8 VALUES (LLD $4 83 13.000 12 WALUES CLLD 23 ANALYS15 PERFCRMED R VALUES (LLD SR 93 2.300 12 WALUES (LLD 20 ANALYSIS PERFCR=ED TRIT!UM 333 300 351.*84 5/ 12) TRM 293 7 362.22t 2/ 43 37C.938 2/ el 2G 336.93-37G.P6 BFN DISCHARGE 353.57-37C.86 351.86-390.00 Nominal Lower Limit of Detectaan U.LD) as described in Table 3. s. b. Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (F). .i (

TAELE23 RAD 12 ACTIVITY.IN EHITE CRAPPIE (FLESH) FCI/G - C.337 EG/G tDRY WEIGHT 3 NAME CF FACILITY EROWNSlLRRY 00ENET NO._11-Z59.260 7,1{t LOCATION OF FACILITY LI"ESTON(_ ALAPAPA REPORTING. PERIOD 1982 TYPE AND L0bER LIMIT ALL CONTAOL NUMBER OF - OF ANALYSIS DETECTION pggg gpg gg.g ANNUAL E 3,3 LOCATION! h0NR00 TINE TOTAL NUMBER OF INDICATOR LOCA(IONS kggAllgN WITH Hird![iT a MEAN (Fl" MEAN (F3b EEFORTED b _ E RFOR"E0 _1(LgL__ RANG {_b glSTANCE ANO DlE(( LION R ANg[b ,RAkCE PEASUREM[3T1 _ GROSS 9 ETA 0.100 34 35t 4/ el WILSON PESERVOIR 34.934 2/ 23 32.764 2/ 23 6 29.32-40.55 TP." 2S?-275 29.32-40.55 24.33-41.19 GAMMA (GELII 6 CS-137 0.020 0.13t 4/ 4) WILSON RESERVOIR. 0 144 2/ 23 0.134 2/ 23 C.10-0.17 TR" 259-275 0.10-3.17 0.13-0.16 E-43 NOT ESTAB 15 854 4/ 43 kHEELEP RES. 15.954 2/ 23 14.36( 2/ El 14.58-16.40 TRF 275-349 15.G4-16.86 13.45- -15.26 PB-212 NOT EST AP 0.018 3/ 41 kHEELER RES G. Cit 2/ 23 0.01t 1/- 23 C.C1-3.01 TRM 275-34* 0.G1-3.01 0.01 - 0.01 4A-226 NOT ESTA8 3.024 2/ 43 kHEELER RES 0.024 2/ 2) 2 VALUES (LLD 0 02-3.G2 TRM 275-349 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. Traction of detectable measurements at specified locations is indicated in parentheses (F). i

~ ~. ~. -. - .. ~ TABLE 24 RADI0 ACTIVITY IN SMALLPOUTH BUFFALO (FLESH) PCI/G - c.C37 PG/G ffRY WEIGHT) NAPE OF FACILITY _gR2Mhi_((nRY 00CKET NO._12-219 260e29t__ LOCATION OF FACILITY __LI" ESTOP.L__ ALABARA REFORTING PERIOD 1782 TYPE AND LCWER LIMIT ALL CONTROL NUMB [R CF TOTAL NUPBEP OF INDICATGk LOCATIONS LEC A T IO f_4_ W I T H Hist [if ANNUAL _t[1h_t__ LOCATICNg N0hAOUTINE b Na=E. PEAN (Fa MEAN (F) REPORTED OF ANALYSIS CETECTIONa PA%GE{3 PEA. t DISTig{E AND D13((110N RANG [jb R Agg[' g[A}UREP[Nig__ _. PERFORMED (LLD) GROSS BETA 3.100 22.568 4/ 4) WHEELER RES 24.4Pt 2/ 23 22.53E 2/ 23 6 1P.E9-29.21 TRM 275-349 19.76-29.21 21.26-23.77 GA MA EGELI) 6 CS-137 0.020 0.048 3/ 43 WHEELER R E' S 0.04t 2/ 23 0.07( 2/ '23 C.C4- .G5 TR" 275-349 0.04-3.G5 C.C6-0.C9 <-40 NOT ESTA9 11.048

  • /~

43 kHEELER RES 11.65t 2/ 23 9.574 2/ 2) 7.56-13.30 TAM 275-349 10.60-12.69 9.20-9.93 PP-214 NOT ESTAB G.314 1/ 4) kHEELER.RES C.C18 1/ -2) 2 VALUES (LLD C.01-0.01 TRM 275-349 0.31-3.01 PB-212 NOT ESTAB C.31( 3/ 4) kHEELER_RES 0.C2t 1/ 23 2 VALUES (LLD 0.C0-C.02 TRM 275-349 0.02-0.02 BE-7 'NOT ESTAB-0.328 1/ 4) WHEELER RES 0.328 1/ 2) 2 VALUES (LLD G.32-u.32 TAP 275-349 C.32-0.32 SR 89 3.500 2 VALUES <LLD 0 VALUES CLLD 2 ANALYSIS PEaFCRMED SR 93 0.100 2 VALUES (LLO O VALUES (LLD 2 ANALYSIS PERFCRmED a. Nominal Lower Limit 'f Detection (LLD) as described in Table 3. j b. Mean and range based u,on detectable measurements only. Traction of detectable measurements at specified locations is indicated in parentheses (F). i b

m .T ABLE 23 RADI0 ACTIVITY 13 SnALLOCUTH BUFFALC ('j HI L E ) PC5/G - C.037'80/G (DRY WEIGHT) ~ NAME OF FACILITY _ BROWNS F[RRY DOCKET NO. 50-259.260,29A LOCATION OF FACILITY __ LIMESTONE ALABAMA PEPORTING PERIOC 19AP TYPE AND LOWER LIPIT ALL CCNTROL. NUPEER OF TOTAL NUMBER OF INDICATOR LOCATIONS kggAT10h dITH nIGw[ST ANNgit HEah_B__ 'LCCATIGhg AGARCUTINE OF' ANALYSIS DETECTICN a MEAN (Fa ggpg gggg gry ptAN ( ) REFORTED b b PERFORu[Q. (LLD) RANggb _ 43 _hMEELE9 RES 20 134 2/ 23 17.694 2/ 23 OISTANCE APID DIRECTION RANGE RANGE MEASUREFEh11__. GROSS BETA 0 100 17.6Pt 4/ 6 14.94-23.43 TEF 275-349 19.83-20.43-16.el-18.56 GAMMA (GELI) 6 CS-137 0.020 3.03( 3/ 41-WHEELER RES 0.034 2/ 2) 0.04f 2/ 2) C.C2-0.C4 TRW 275-349 0.02-0.04 0.03-0.04 K-40 NOT ESTAB. 6.68 4/ 43 mnEELEA RES 7.684 -2/ 23 6.37( 2/ 2) .4.75-7.79 TAF 275-34* 7.56-7.79 5.42-7.33' BI-214 0.020 C.Cet 2/ 43' enEELEk RES 0.124 1/ 2) C.04( 1/. 2) C.03-0.12 TAM 275-349 0.12-3.12 0.34-3.04 l' PB-214 NCY ESTA8 3.024 1/ 4) hMEELEk RES C.028. 1/ 23 2 VALUES (LLD 0.02-0.02 TEM 275-349 0.02-3.02 PB-212 NOT ESTA8 C.01( 4/ 43 6 HEELER RES 0.02t 2/ 21 0.01( 2/ 2) C.J1-C.L3 TAM 275-349 0.01-0.05 0.G1-0.01 RA-226 NOT ESTAB 0.088 2/ 4) hMEELEh RES 0.12( 1/ 23 C.04( 1/ 2) 0.C3-0.12 TAM 275-349 0 12-0.12 -0.04-D.04 a, Nominal Lower Limit of Detectica (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).

TABLE 36 RADI0 ACTIVITY IN SE0! CENT PCI/G - 0.037 CQ/G (DR1 WEIGHT) NAME OF FACILITV_R*ghE1_fLERY DOCMET N06_11-212gZggzE2h LOCATION OF FACILITY LI"ESTON(_ A(aBAMA REPORTING FERIOC 1982 CONTROL NUMBER CF TYPE AND LOWER LIMIT ALL TOTAL NUMBER' 0F INDICATOR LOCATIONS La[111gh_g11M_H11tLST ANNUA (_g[A3 LOCAT10 S NONROUTINE MEAPI ( MEAN ( REFCRTIC FANQL{3 4 Ahg({ OF ANALYSIS DETECTION, PEAN f N8ME 4 ANj[,() glilig((_1g(_Q1L{(110N P(1}yE(d($11__ __PERF0awEQ __1((Q) GARRA (GELI) 8 CE-144 C.060 3.20t 2/ 6) TRM 293.7 .204 2/ 23 2 VALUES <tLG C.15-0.26 BFN.DISCHAhGE 0 15-0.26 CC-60 0.~510 0.234 6/ 6) TRP 288.78 0.32t 2/ 23 0.C35 1/ 23 c 0.C8-0.51 C.13-0.51 0.03-0.03 .CS-134 0.080 0.094 1/ 6). TRM 293 7 L.098 1/ 2) 2 VALUES (LLD C+09. 3.39 BFN DISCHARCE C.09-3.09 CS-137 0.020 1.355 6/ 6) TA" 277.96 1 964 2/ 23 G.168 2/ 23 c 0.91-2.79 1.10-2.79 C.14-0.18 R-40 NOT ESTAP 14.575 6/ 6) TEM 277.98 15.44t 2/ 2) 15.314 2/ 23 12.41-15.71 15.16-15.71 14.07-16.55 24-F5 0.023 L.C85 1/ 6) TRM 293.7 C.L84 .1/ 23 2 VALUES (LLD G.08-C.CE BFN DISCHARGE C.;B-0.C8 PI-214 0.020 1.304 6/ 6) TRF 277.98 1.358 2/ 23 1.224 2/ 21 1.13-1.45 1.25-1.45 1.05-1.4C BI-212 0.100 1.855 6/ 63 TRM 288.78 1.894 2/ 23 1.754 2/ 2) 1 61-2.06 1 78-2.01 1.39-2 11 FB-214 NOT EST AB 1.364 6/ 6) TR" 277.96 1 53t 2/ 2* 1.314 2/ 2) 0.97-1.57 1.*t-1 57 1.lb-1.46 PB-212 NDT ESTAB 1 564 6/ 6) TRM 277.98 1.784 2/ 23 1.474 2/ 23 1.20-1.89 1 67-1.89 1.30-1 64 RA-226 NOT ESTaB 1.304 6/ 63 TRP 277.98 1.358 2/ 23 1.224 2/ 2) 1.13-1.45 1 25-1.45 1.C5-1 40 RA-223 NOT ESTAB c.68: 3/ 6) TRM 293 7 0.734 2/ 2) 0.298 1/ ?> L.56-0.89 BFN DISCHARGE C.56-3.89 0.29-3.29 RA-224 NOT ESTA6 1 834 5/ 6) TAM 2?3.7 1 944 1/ 2) 1.72t 1/ 2) i 1.43-2 02 BFN DISCHARGE 1 94-1.94 1.72-1 72 TL-208 0.020 0.561 6/ 6) TRP 277.96 C.6CE 2/ 23 0.494 2/ 23 0.44-0.61 C.59-3.61 0.45-0.53 I AC-228 0.360 1.624 6/ 6) TRM 277.98 1.7Ct 2/ 2) 1.514 2/ 2) 1 37-1.75 1.65-1 75 1.29-1 73 PA-234M NOT ESTAB 3.204 1/ 6) TRM 293.7 3.208 1/ 23 4.648 1/ 2) 3.20-3.2C BFN CISCHARGE 3.2 - 3.20 4.64-4.64 SR 89 1.500 2 134 '1/ 6) TRM 293 7 2 134 1/ 23 2 VALUES (LLO 8 2.13-2.13 BFN GISCHARGE 2.13-2.13 C.344 1/ 23 SQ 90 0.300 6 VALUES (LLC 0.34-0 34 8 Ncainal Imer 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. ECCo and 337Cs between indicator and control locations' reported herein is comparable to the distribution reported in the c. The distribution of Treoperational monitoring program from 1968 to mid-1973. The levels reported are also comparable with levels reported in samples from the sennessee River in preoperational monitoring programs conducted by TVA at other sites.

T ABLE 27 / RADI0 ACTIVITY IN CLAM FLESH PCI/G - 0.t37 DG/G (DRY.EIGHT) NAME OF FACILITY _ BROWNS _EERRY DOCKET NO. 50-259 260 221 LOCATION OF FACILITY LIMESTONE. ALADAMA RFPORTING PERICD_19R2 TYPE AND LOWER LIMIT ALL CONTROL NumeER CF TOTAL NUMBER OF INDICATOR LOCATIONS Lg[AflgN_WITH High[ST AhEMAL_g[A3 LOCATIONS NONROOTINE-b I__ MEAN ( NaME MEAN EF MEAN F) b REPORTED 0F ANALYSIS DETECTION

  • RANG ({3 Q111[g((_{hg_Q1&(((1Q3 H Ahi[ b RA$E[

E[llQi[m[hil__ __ELEE21502 (LLD) GAMMA (GELI) 6 CO-60 0.080 C.384 2/ 4) TRM 293.7 0.53( 1/ 23 2 VALUES (LLD 'O.24-3.53 BFN DISCHARGE G.53-0 53 CS-137 0.060 0.174 1/ 4) TRM 288.76 0.174 1/ 13 2 VALUES <LLD 0.17-0.17 0.17-0.17 M-40 NOT EST AE 2.27: 4/ 4) TRM 293.7 2.82( 2/ 23 .2.348 2/. 23 1.11-4.53 EFN DISCHARGE 1.11-4.53 2.24-2.45 ZN-65 0.170 1.33( 2/ 43 TRM 293.7 1 671 1/ 23 2 VALUES (LLD 0.98-1.67 BFN DISCHARGE 1.67-1.67 BI-214 NOT ESTAB 0.42t 3/ 43 TRM 288.76 0.76( 1/ 13 0.194 2/ 2) 0.01-0.T6 0.76-0.76 0.02-0.37 PB-214 NOT ESTAB 0.494 4/ 43 inM 288.78 0.804 1/ 13 0.248 2/ 2) .21-0.80 0.8C-0.80 C.11-3.38 PB-212 NOT ESTAB 0.66( 2/ 4) TRM 288.78 6.87( 1/ 13 0.224 1/ 23 0.45-0.R7 0.87-0.87 0.22-9.22 RA-226 NOT ESTAB 0.394 2/ 4) TRM 288.78 0.76( 1/ 13 2 DALUES <LLD 0.01. 0.76 C.76-0.76 TL-208 NOT ESTAB C.13( 3/ 4) TRM 288.76 0.184 1/ 13 0.168 1/ 23 0.10-0.18 0.16-0.18 0.16-0.16 AC-228 NOT ESTAB 0.31( 2/ 43 TRM 288.78 0.414 1/ 13 2 VALUES <LLO 0.21-0.41 0.41-0.41 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 T AELE 28 RADICACTIVITY IN CLAM SHELL 4 PCI/G - 3.037 PG/G (DRY WEIGHT) 4 NAME OF FACILITY _g8QMh2_F{eRV COCMET ho._ig-213g260.?96 LOCATION OF FACILITY LIFEST03[, A(igAMA REPORTIhG PEnICD 1982 TYPE AND LohER LIMIT . ALL CONTROL NUPPER CF. NONROUTINE TOTAL NU*BER OF INDICATCR LOC (TICNS LOCsTION dITH HIGHLST ANNQA(_M[AN. __ LOCATIONg MEAN ( MEAN (F) REFORTED R ANg[g ) m ANc@

  • EASURENENT}__

PEAN ( NAPE R ANE[,{ } [11Tiy((_Agg,11(([Tigh 0F ANALYSIS DETECTION l __P[RFORMED 8LLO) G a rM A (GELI) 8 C0-60 0.010 0.0Rt 2/ 6) TPr 293 7 C.138 1/ 2) 2 VALUES (LLD C.02- 'J.13 bfN LISCHARGE 0.13-0.13 K-40 NOT ESTAB 0.2?( 3/ - 6) TR* 288.78 0.224 2/ 2) 1 514 1/ 2) i C.15-3.3: 0.15-0.30 1.51-I.51 B1-214 0.030 0.174 5/ 6) 78" 28R.76 0.264 2/ 2) C.674 1/ 2) C.97-0.95 0.10-0.*5 C.67-0 87 PB-214 0.555 G.228 5/ 6) TA" 286.78 0.408 2/ 23 0.474 2/ 2) 0.L7-0.68 C.13-C.68 0.07-0.87 PB-212 NOT EST AB 0.118 5/ 63 TRM 298.78 0.218 2/ 23 0.024 1/ 2) 0.09-0.29 0.12-0.29 C.G2-0.02 R4-226 0.050 0.176 5/ 6) TAP 288.78 0.264 2/ 2) 2 VALUES (LLD C.07-0 45 0.10-0.45 TL-234 0.020 0.058 5/ 6) TAM 2de.78 0 054 2/ 23 2 VALUES <LLD i C.02-0.06 0.05-J.06 AC-228 0.063 0.188 5/ 6) TR* 286.78 0.278 2/ 2. C.104 1/

)

0.0*- 0.30 J.24-3.30 C.10-0.1c SR 89 5 000 5 254 1/ 6) T6 F 277.96 5 25t 1/ 23 2 VALUES <LLD A 5.25-5.25 5.25-5.25 SR 90 1 000 1.664 6/ 6) Tar 288.76 1 864 2/ 2) 1.364 1/ 2) a 1.19-2.1C 1 63-2.10 1.36-1.36 I a. Nominal Lover Limit of Detection (LLD) as described in Table 3. b. Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (F). t-i e 4

Figure 11 51 RESERVOIR MONITORING NETWORK Elk River ) gWHEELER DAM I mile 274.90 mile 277.98 Rogersville O mile 291.76 mile 282.6 r Athens mile 285.2 B.F. NUCLEAR PLANT e j Champion [ A Paper Co. 'le 288.78 Q mile 293.50 mile 305. \\ Courtland mile 293.70 O l Decatur male 307.52 l l Scale of Miles ~ o-Automatic Sampler 5 O h

F Figure 12 a i i e e i e i i i s skMJAL AVERAGE ~ [ Pre erational Ope ional BR0bNS FERRY NtrtEAR PLANT 5 } ~ Average: l l Preoperational Phase 4 _ __j __ 1968 19'69 Id70 1571 1572 1573P197301$74 id75 1576 1577 Id78'1$79 19'80 1d811982 No gross beta measurements made in 1978. a.

53 Qua l_i_ t y _ con t ro l A quality control program has been established with the Alabama Department of Public Health Environmental. Health Administration Laboratory and the Eastern Environmental Radiation Facility, Environmental Protection Agency, Montgomery, Alabama.. Samples of air, water, milk, and vegetation collected around BFN are forwarded to these laboratories for analysis, and results are exchanged for comparison. Data Analysis l Data mea'sured at the control stations for each medium were averaged for each sampling period. In order to describe the distribution of control station data, a mean, standard deviation, and 3-sigma limits were calculated. We can expect that background concentrations would be distributed within these limits. This provides us the basis for comparing control and indicator data. l If the indicator data fall within the limits defined for control data, we conclude that the indicator data were not significantly affected by the nuclear plant. If the data do not fall within the limits, we will perform further analyses to determine if the difference is attributable to the nuclear plant. Conclusions i A vast majority of the indicator station data was found to be within t the distribution defined by the control station data. The data analysis software identified concentrations slightly exceeding the limits of the control station data for a small number of radionuclides in samples from indicator i stations. Many of these values may be discounted because the error' reported by the analysis program was greater than the calculated concentration. The remaining isolated elevated concentrations may be the result of fallout, fluctuations in the existing environment, computer program artifacts, or, analytical errors. The same type of isolated high values occurred in the control station data and may be attributed to the same sources. Dose estimates were made from concentrations of radioactivity found in samples of environmental media. Media sampled include, but are not limited to, air, milk, meat, vegetation, drinking water, and fish. Doses estimated for persons at the indicator locations were essentially identical to those determined for persons at control locations. Greater than 99 percent of those doses were contributed by the naturally occurring radionuclide potassium-40,

54 and by strontium-90 and cesium-137 which are long-lived radioisotopes found in fallout f rom nuclear weapon testing. It is concluded from the above analysis of the data and from the trend plots presented earlier that there were no measurable increases in the exposure to members of the general public attributable to the operation of BFN. Indications of the presence of small quantities of fission products have been seen in aquatic media (for example, Asiatic class). The levels measured were extremely low, for example near the nomimal lower limits of detection and several hundred times lower than the reporting levels outlined by the Nuclear Regulatory Commission. No increases of radioactivity have been seen in water samples. These media will be monitored closely for indications of increases. 1 ( l

f, bv .Q, piv - y: --- - y C:p wL TENNESSEE VAL f AUTHORI CH ATTA NOOGA. TENN ESSCE 3740 3 g 400 Chestnut Street Tower II May 3, 1983 U.S. Nuclear liegulatory Commissica g 6-65 j Region II 1 ATTN: James P. O'Reilly, Regional Administrator 101 Marietta Straet, NW, Suite 2900 Atlanta, Georg,ia 30303

Dear Mr. O'Reilly:

Enclosed is a copy of the following report prepared by the Tennessee Valley Authority pertaining the environmental monitoring at the Browns Ferry Nuclear Plant: Environmental Radioactivity Levels, browns Ferry Nuclear Plant, Annual Report 1982 This monitoring program is specifically responsive to the recommendations and requests of the United States Fish and Wildlife Service. We understand that the Office of Nuclear Reactor Regulation will transmit five copies of the report to the Secretary of the Interior. Very truly yours, TENNESSEE VALLEY AUTHORITY J .2 'l L. M. Mills, M rager Nuclear Licensing 2 Enclosure cc: Director of Nuclear Reactor Regulation (20) C Attention: Mr. Darrell G. Eisenhut, Director Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555 I8dp I /p sg. Y OFFICIAL C An Equal Opportunity Employer -.)}}

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