ML18024A777

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Environ Radioactivity Levels,Annual Rept 1978
ML18024A777
Person / Time
Site: Browns Ferry  
Issue date: 04/27/1979
From:
TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML18024A778 List:
References
EMR-781231-2, MRH-79-3-BF2, NUDOCS 7905030349
Download: ML18024A777 (48)
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Text

RH-79-3-BF2 ENVIRONMENTAL RADIOACTIVITYLEVELS BROWNS FERRY NUCLEAR PLANT ANNUAL REPORT 1978 V90SOS 03~~

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CONTENTS Introduction Figure 1 Table 1 Tennessee Valley Region Environmental Radioactivity Sampling Schedule Atmospheric Monitoring.

Figure 2

Figure 3

Table 2

Table 3

Table 4

Table 5

Table 6

Table 7

Table 8

Atmospheric and Terrestri'al Monitoring Network

- Local Monitoring Stations Detection Capabilities for Environmental Sample Analysis

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Maximum Permissible Concentrations for Nonoccupational Exposure.

Radioactivity in Air Filter Radioactivity in Rainwater Radioactivity in Special Rainwater Radioactivity in Heavy Particle Fallout Radioactivity in Charcoal Filters ll 12 14 15 16 17 Terrestrial Monitoring.

19 Table 9

Table 10 Table ll Table 12 Table 13 Table 14 Table 15 Table 16 Table 17 Table 18 Radioactivity Radioactivity Radioactivity Radioactivity Radioactivity Radioactivity

- Environmental Radioactivity Radioactivity Radioactivity in Milk e

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in Special Milk in Vegetation in Soil

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in Well Water in Public Water Supply Gamma Radiation Levels in Food Crops in Soybeans in Poultry 21 22 23 25 26 27 28 29 31 32 Reservoir Monitoring 33 Table 19 Figure 4 Table 20 Table 21 Table 22 Table 23 Table 24 Table 25 Table 26-Table 27 Sampling Schedule Reservoir Monitoring Reservoir Monitoring Network.

Radioactivity in Surface Water (Total)

Radioactivity in Fish (White Crappie, Flesh)

Radioactivity in Fish (Smallmouth Buffalo, Flesh)

Radioactivity in Fish (Smallmouth Buffalo, Whole)

Radioactivity in Plankton Radioactivity in Sediment Radioactivity in Clam Flesh Radioactivity in Clam Shell 35 36 37 38 39 40 41 42 43 44 Quality Control Data Analysis Conclusions

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45 45 45

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ENV1RONMENTAL RADIOACTIVITYLEVELS BROWNS FERRY NUCLEAR PLANT ANNUAL REPORT 1978 Introduction The Browns Ferry Nuclear Plant (BFNP), 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.

The plant consists of three boiling water reactors; each unit is rated at 3,293 MWt and 1,098 MWe.

Unit 1 achieved criticality on August 17,

1973, and began commercial operation on August 1, 1974.

Unit 2 began commercial operation on March 1, 1975.

However, a fire in the cable trays on March 22, 1975 forced the shutdown of both reac-tors.

Units 1 and 2 resumed operation and Unit 3 began testing in August 1976.

Unit 3 began commercial operation in January 1977.

The preoperational environmental monitoring program established a

baseline of data on the distribution of natural and manmade radioactivity in the environment near the plant site.

However, seasonal,
yearly, and random variations in the data were observed.

In order to determine the potential increases in environmental radioactivity levels caused by the plant, compari-sons were made between data for indicator stations (those near the plant) and control stations (those remote from the plant) in con)unction with comparisons with preoperational data.

Field staffs in the Division of Occupational Health and Safety, the Division of Water Resources, and the Division of Natural Resources

Services, carried out the sampling program outlined in tables 1 and 19.

Sampling locations are shown in figures 2, 3, and 4.

All the radiochemical and instrumental analyses were conducted in a central laboratory at Muscle

Shoals, Alabama.

Alpha and beta analyses were perfoxmed on Beckman Low Beta II and Beckman Wide Beta II low background proportional counters.

Two Nuclear Data Model 100 multichannel analyzer systems employing sodium iodide, NaI(Tl) detectors and one Nuclear Data Model 4420 in con)unction with Germanium, Ge(Li) detection

systems, were used to analyze the samples for specific gammaemitting radionuclides.

Samples of water, vegetation, air particulates, food crops, and charcoal (specific analysis for I) are 131 routinely counted with NaI(T1) detection systems.

If significant concen-trations 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.

Iden-tification of gammaemitting radionuclides in all other types of samples is xoutinely performed by analysis on the Ge(Li) system.

A TVA fabricated betagamma coincidence counting system is utilized for the determination of I-131 concentrations in milk.

Data wexe entered in computer storage for processing specific to the analysis conducted.

An IBM 370 Model 165 computer, employing an ALPHA-M least squares

code, was used to solve multimatrix problems associated with estimating the activities of the gamma-emitting nuclides analyzed by NaI(T1).

The data obtained by Ge(Li) detectors were resolved by the ND-4420 software.

The detection capabilities for environmental sample analysis given as the nominal lower limits of detection (LLD) are listed in table 2.

Samples processed by NaI(T1) gamma spectroscopy were analyzed for 13 specific gamma"-

emitting radionuclides and radionuclide combinations*.

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 (roduced radioisotopes, such as Be, K,

Bi,

'"Bi, Pb, "Pb, Ra, Rn, etc.

LLD's for the analysis of the radionuclides listed below're given in table 2-B.

LLD's for additional radionuclides identified oy Ge(Li) analysis were calculated for each analysis and nominal values are listed in the appropriate data tables.

In the instances where an LLD has not been established, an LLD value of zero was assumed.

For each sample type, only the xadionuclides for which values greater than the LLD were reported are listed in the data tables.

  • The following radionuclides and radionuclide combinations are quantified by the ALPHA-M least-squares computex code:

" 'Ce; Cr;

'I; Ru.

, "Cs

~ Cs; Zr-Nb'o; "Mn Zn; Co; " K and '" Ba-La.

1 I LL

~r g.+

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GEORG I A LEGEND

~-HARTSVILLENUCLEAR PLANT f/'-PHIPPS BEND NUCLEAR PLANT QlRK-LIOUIDuETALSar BREEDER REACTOR

~-WATTS BAR NUCLEAR PLANT

~- SEQUOYAH NUCLEAR PLANT

- BELLEFONTE NUCLEAR PLANT

- BROWNS FERRY NUCLEAR PLANT

~- YELLOWCREEK NUCLEAR PLANT

Table 1

ENVIR0%KNTAL RADIOACTIVITYSAMPLING SCHEDULE Air Charcoal Rain-Heavy Particle River Well Public Aquatic Life dtatioa lmeation tilter ritter eater radiant Soil

~re etation Milt litter litter lfater a

d Sediment Fonda Muscle Shoals W

Lawrenceburg Rogersville W

Athens Decatur Courtland Site NW-1 Site N-2 Site NE-3 A

Site NW-4 W

Site WSW-5 W

Parm B

Farm Bi A

Farm He Perm S*

Parm T Farm L W,

Control Parms Onsite Well Wheeler Dam Elk River Tennessee River Champion Paper Co.

Various Local Parms W - Weekly M - Monthly S-Semiannually A-Annually Pena H went out of the dairy business in May 1978; therefore milk samples were no longer available.

Perm S was substituted for Perm H in the same month.

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 quadrants of greatest wind frequency.

One additional station is located at the point of maximum predicted off-site concentration of radionuclides (see figure 3).

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 HV-70 particulate filter at a re'gulated flow of 3 ft /min.

In series with, but downstream of, the particulate filter is a charcoal filter used to collect iodine.

Each monitor has a collection tray and storage container to obtain rainwater on a continuous basis a'nd a horizontal platform that is covered with gummed acetate to catch and hold heavy particle fallout.

Thermoluminescent dosimeters are used to record gamma radiation levels at each remote and perimeter station.

Each of the local air monitors is fitted with a GM tube that con-tinuously scans the particulate filter.

The disintegration rate of the atmospheric radioactivity is continuously recorded at each station and radio-telemetered into the plant.

These stations will detect any significant air-borne release from BFNP.

Air filters are collected weekly and analyzed for gross beta activ-ity.

During this reporting period, one sample was lost because of equipment malfunction and one was lost.

No analyses are performed until three days after sample collection.

The samples are composited monthly for analysis of specific gamma-emitting radionuclides and quarterly for Sr, Sr analysis.

The results are combined for each station to obtain a annual average.

These data are presented in table 4.

With reference to table 3, which contains the maximum permissible concentrations (MPC) recommended by 10 CFR 20 for nonoccupational

exposure, it is seen that the maximum beta concentration is 2.71 percent MPC.

This concentration occurred at a control station during a period of fallout from atmospheric nuclear weapon testing.

Rainwater is collected monthly and a 3.5-liter sample analyzed for specific gamma-emitting radioisotopes.

The results are shown in table 5.

In this sampling period, one sample was lost when its container burst, two were lost because of damaged equipment, and one sample contained insufficient water for analysis.

In addition to the regularly scheduled rainwater samples, three special samples were taken at the expected time of arrival of fallout from an atmospheric nuclear weapons test.

These data are presented in table 6.

The gummed acetate that is used to collect heavy particle fallout is changed monthly.

One sample was lost during this reporting period and three were damaged to the extent that insufficient material was left for analysis.

The sample is ashed and counted for gross beta

-activity.

The'results are given in table 7.

Charcoal filters are collected and analyzed for radioiodine.

The filter is counted in a single channel analyzer system.

The data are shown in table 8, where the highest value reported is 0.08 percent MPC for I.

In this reporting period, one sample was accidently destroyed, and two were lost due to equipment malfunction.

Figure 2

ATMOSPHERIC AND TERRESTRIAL MONITORING NETWORK RM.2BF LAWRENCEBURB yPULASKI FAYETTEVILLEQ WILSON FLORENCE PM-IBF WHEELER ROBE SVIL OAM ATHENS PM-2BF FFIEL MUSCLE SHOALS RM-IBF I EIGHTON TUSCUMBIA COURTLANO PM-4 F

pRUSSELLVILLE BROWNS FERRY NUCLEAR PL NT DECAT PM-3BF0 IO MILES HARTSELLE

~ HUNTSVILLE UNT SVIL DAM 25 HALEYVILLE

~CULLMAN 45 MILES RAINWATER SOIL 0- ENVIRONMENTAL MONITORINS STATION NOTE: THE FOLLOWING SAMPLES ARE COLLECTED FROM EACH STATION:

AIR PARTICULATES RADIOIODINE HEAVY PARTICLE FALLOUT

LOCAL MONITORING STATIONS BROWNS FERRY NUCLEAR PLANT ATHENS U S HWY 72 BFNP ALA. HV/Y 20 Legend 0

Air Monitor Air Monitor 8 TLD Station TLD Station A

AUtomatic Well Sampler 8

Dairy Farm DEC ATUR Scale O

i Z

S O

5 Miles

Table 2

DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS A.

S ecific Anal ses NOMINAL LOWER LIMIT OF DETECTION LLD

  • Air Particulates Ci/m3 Charcoal

~Ci/I Fallout Water mCi/Km

~Ci/I Vegetation Soil and and grain Sediment

/>~Cd/ ~dry

~Cd/

d.c

Fish, clam flesh,
plankton,

~Ci/ ~dr Foods

~ meat 1 Clam shells

poultry, Milk p~Ci/ ~dr

~i/Kgm wet

~Ci/1 Total a Gross a-Gross 9 H

1311 09Sr 90Sr

0. 005 0.01 0.005 0.001 0.05 0.4 2.0 2.3 330 10 2

0.01 0.05 0.20 0.25 0.05 0.35 0.70 1.5 0.3 0.1 0.1 0.5 0.1 0.7 0.7 5.0 1.0 1.5 25 40 8

0.5 10 2

'- eAll 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 given sample; these variations may change the LLD value for the given sample.

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

Conversion factors:

1 pCi 3.7 x 10 Bq; 1 mCi ~ 3.7 x 10 Bq.

Table 2

DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS B.

Caaaa Anal ses NOMINAL LOWER LIMIT OP DETECTION LLD Air particulates

~Ctl NaI>> ~Ce Li <<>>

Water

~

and milk

~Ct/1 NaI ~Ge Li Vegetation and grain

~Ci

~dr Soil and sediment Ncct//ddrr NaI

~Ge Li NaI

~Ce Li Clam flesh Pish and plankton N~Ct/.~dr

~Ci/

dr Nai

~Ge Li Nai ~Ge Li Clam shells

~Ct/

dr HaI

~Ge Li

Foods, tomatoes
potatoes, etc.)'i/

m wet Heat and poultry

~Ct/K et NaI G~eLi NaI

~Ce Li 111K 1IICe C

6 10r 131I 103N106Ru 106Ru 1 3ICs 137C 36Zr-Nb 062 "Nb "Co-6SZn 6 OCo I0K "0Ba-La 1 IOBa I IOLa 0.03

0. 02 0.07 0.03 0.01 0.01 0.04 0.03 0.01 0.02 0.01 0,01 0.01 0,01
0. Ol 0.02 0.01 0.02 0.01 0.02 0.01 0.01 0.01

~ 0.10 0.02 0.02

0. 01 38 33 60 44 15 8

40 40 10 26 10 5

10 10 5

15 5

10 5

15 9

10 5

150 15 25 7

0. 55
0. 22 1.10 0.47 0.35 0.09 0.65 0.51 0.20 0.33 0.20 0.06 0.20 O.ll 0.05 0.23 0.05 0.20 0.05 0.25 0.11 0.17 0.06 2.50 0,68 0.34 0.08 0.35 0.06 0.60 0.10 0.20 0.02 0.45 O.ll 0.12 0.08 0.12 0.02
0. 12 0.03 0.01 0.20 0.01 0.15 0.01 0.23 0.02 0.11 0.01 0.90 0.15 0.07
0. 02 0.35

~ 0.06 0.60 0.10 0.20 0.02 0.45 O.ll 0.12 0.08 0.12 0.02 0.12 0.03 0.01 0.20 0.01 0.15 0.01 0.23 0.02 0.11 0.01 0.90 0.15 0.07 0.02 0.35 0.56 0.07 0.74 0.48 0.08 0.15 0.07 0.07 0.08 0.17 0.08 0.30 0.10 0.35 0.06 0.60 0.10 0.20 0.02 0.45 0.11 0.12 0.08 0.12 0.02 0.12 0.03

0. 01 0.20 0.01 0.15 0.01 0.23 0.02 0.11 0.01 0.90 0.15 0.07 0.02 38 60 15 40 10 10 10 15 10 15 10 150 15 20 15 55 15 40 15 70 '0 30 15 400 50 25 7

50 15 90 33 40 44 200 90 8

50 20 150 40 90 26 40 50 5

40 15 40 10 5

5 5

9 5

>>The NaI(Tl) LLD values are calculated by the method developed by Pasternack and Harley as described in HASL-300 and Nucl. Instr. Methods 91, 533-40 (1)71).

These LLD values are expected to vary depending on the activities of the components in the samples.

These figures do not represent the LLD values achievable on a given sample.

Water is counted in a 3.5-L Marinelli beaker.

Vegetation, fish, soil, and sediment are counted in a 1-pint container as dry weight.

The average dry weight is 120 grams for vegetation and 400-500 grams for soil sediment and fish.

Meat and poultry are counted in a 1-pint container as dry weight, then corrected to wet veight using an average moisture content of 70X.

Average dry weight is 250 grams.

Air particulates are counted in a well crystal.

The counting system consists of a multichannel analyzer and either a 4" x 4" solid or 4" x 5" well NaI(T1) crystal.

The counting time is 4000 seconds.

All calculations are performed by the least-squares comput'r program ALPHA-M.

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

  • >>The Ge(Li) LLD values are calculated by the method developed by Pasternack and Harley as described in NASL-300.

These LLD values are expected to vary depending on the activities of the components in the samples.

These figures do not represent the LLD values achievable on given samples.

Water is counted in either a 0.5-L or 3.5-L Marinelli beaker.

Solid samples such as soil, sediaentd and clam shells are counted in a 0.5-L Marinelli beaker as dry veight.

The average dry weight is 400-500 graas.

Air filters and very small volume samples are counted in petrie dishes centered on the detector endcap.

The counting systea consists of a ND-4420 multichannel analyzer and either a 8X, 14X, or 16X Ce(Li) 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 is performed using the softvare provided with the ND-4420.

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

COnVerSiOn faCtOr1 1 pCi ee 3.7 X 10 Bq.

Table 3

MAXIMUMPERMISSIBLE CONCENTRATIONS FOR NONOCCUPATIONAL EXPOSURE Alpha Nonvolatile 'eta TritiUm 137C 103$ 106RU 144Ce Zr-Nb 140Ba 1%0La 131Z 6'Zn

'4Mn Co asS 30S 51(

134C SSCo In Water

~Ci/i 30 37000 3,000,000 20,000 10,000 10,000 60,000 20 F 000.

300 1007000 1007000 307000 3,000 300 2,000,000 9,000 90,000 MPC In Air

~CX/m'00 2007000 500 200 200 1,000 1,000 100 2,000 1,000 300 300 30 807000 400 2,000

NAME OF FACILITY BROMUS EERRY LOCAT10N OF FAC ILI TY LIIIESIOUE TABLE 4 RADIOACTIVITY IN AIR FILTER PCI/N(3) - 0.037 BQ/H(3)

DOCKET ALABAIIA REPORTI hO ~ 'RHn29=3nBE2-----=---

NG PERIOD 1'RIB NUMBER OF NONROUTINE REPORTED IIEASUREHEMIS LOWER LIMIT OF DETECTION a CLLDZ 0.005 TYPE AND TOTAL NUMBER OF ANALYSiS II'EREORIIEO GROSS ALPHA 51 GROSS BETA 570 GAMMA (NAI) 114 I"131 CONTROL LCCATIONS ALL INDICATOR LOCATIONS HEAN (F)b RAUGE LPCAI108-MLITT BIGBESI-ABBVAL I)E48-NAHE HEAN (F)b OISIAUCE AUD DIRECIIOB RAIIGE b HEAN (F)b RAMGEb =

0 ~ 01(

24/

51) 0 ~ 01 0 ~ 09 0'2(

104/

104) 0 ~ 02 2'1 DECATUR'L Bo2 HILES SSE 52/

52) 2'6 0i14(

oe03-0 ~ 010 0 ~ 12( 466/ 466) 0 ~ 02" 2'7 0 ~ 010 NOT ESTAB 0

col

(

2/

21) 0 ~ 01 0 ~ Ol 0 ~ol (

21/

21) 0 F 01 0'2 1/

9) 0 ~ 02 11/

11) 0'2 LH3 BF NORTHEAST 1 ~ 0 HILE NE COVRTLANOz AL 10 ~ 5 MILES WS'M oeol(

4/

93) 0 F 01-0 ~ 02 oeol(

93/

93) 0 F 01 0 ~ 02 oi02(

oi02-oiol(

OiOle BE-7 GAHHA (GELI) 18 CE-141 NOT ESTAB oi08(

Oi08" Oi 13 (

Oe13 oi17(

oil7" Oi35(

Oi35-Oi07(

oioT-oi02(

0 ~02-oi02(

oi02-oiol(

0 i0 1" OiOB(

OiOB-Oi19(

Oil9 4i14(

oi02 oio?(

0'2" 2'8(

oiol DECATUR'L 8'

HILES SSE LN3 BF NORTHEAST loo HILE NE LN4 BF TRAIL'ER P

I, ~ 7 HII.ES NNM LN5 BF DAVIS F 2 ~ 5 MILES MSM ROGERSVILLEJ AL 13e8 MILES NM LN5 BF DAVIS F 2'

MILES MSW LH2 BF NORTH 0'

HILE NNE DECATUR'L Be2 HILES SSE DECATUR'L 8 '

MII.ES SSE LH4 BF TRAILER P le7 NILES NNM LH3 BF NORTHEAST loo HILE NE DECATUR'L 8 ~ 2 HILES SSE LH3 BF NORTHEAST loo HILE NE 0 ~ 04(

0'2" Oe05(

0 ~ 02" 0 ~ 12(

Oo09" 0 ~ 14(

0 ~ 09-oo06(

Oo05-0 ~ 02(

0 ~ 02-Oo02(

0'2 0 ~ 01(

0 F 01 oo07(

oo05" Doll(

oe08-1 ~ 40(

0 ~02-oo02(

Oo02-o.64(

oe 00-.

15 VAL 0 ~ 04(

2/

3)

OeO4-oe05 3

VALVES <LI,D 9/

15) 0 F 08 4/

15)

Oo 13 9/

15) 0 ~ 17 9/

15) oo35 9/

15)

Oo07 1/

15) oe02 1/

15) 0'2 2/

15) 0 ~ 01 4/

15) 0 F 08 9/

15)

Oe19 9/

15) 12e35 1/

15}

Oe02 12/

15) 7'0 UES

<LLD 1/

0 ~ 08 1/

0'3 1/

oe17 1/

oe35 1/

Oe07 1/

0'2 1/

0'2 1/

0 col 2/

0 F 08 1/

Oe19 3/

12e35 1/

Oe02 3/

7 ~ 40 3) 3)

CE-144 BA-140 LA-140 RU-103 CS-137 ZR-95 NB-95 K 40 I 131 81-214 8 I-212 PB-214 P8-212 Oo020 0'20 0.010 NOT ESTAB 0 ~ 010 0 ~ 010 0 F 010 NOT ESTAB 0 ~ 010 0,020 NOT ESTAB NOT ESTAB NOT ESTAB 0 ~ 15(

Oe ll oe 13(

Oe 10-0 ~ 07(

0 ~ 06 oe02(

oe02 0 F 01(

oeol" 0 ~ 01(

0 ~ 01 oe09(

0 ~ 09-0 ~ 13(

Dell 0 ~ 02(

Oo02>>

3 VALU 2/

3)

Oe20 2/

3) 0 ~ 15 2/

3) 0 F 08 1/

3) 0'2 1/

3) oool 1/

3) 0 ~ 01 1/

3) oe09 2/

3) 0 ~ 14 2/

3) 0 F 02 ES

<LLD 2) 2)

3}

3) 3)

3) oeol(

3/

3) oeoi>>

Oeol Oeol(

2/

3) oioo>>

Oeol Oiob(

3/

3) 0 ~ 0$

Oe09 3

VALUES <LI.O 3)

BEW 3) 39i55(

Oi0-9oi(

O,oB-2/

79o02 1/

0 F 08 of specified locations is indicated in parentheses (F).

actable neasurenents NOT ESTAB 6.66(

12/

15)

LHO BF NORTHEAST 0 F 05 79'2 1 ~ 0 NILE NE TE-132 NOT ESTAB 0 F 08(

1/

15)

ROGERSVILLEJ AL oo08>>

0 ~ 08 13e8 HILES NM

. a." Nominal Lower Liuit of Detection (LLD) as described in Table 2.

- =b.

Mean and range based upon detectable measurenents oniy.

Fraction of det

NAME OF FACILITY BEObtUS EEERY LOCATION OF FACILITY LIIIESIOHE TABLE 4 (CONTD)

RAOIOACTIVITY IN AIR FILTER PCI/H(3) 0'37 BQ/H(3) 4LARAHA DOCKET NOi RU=ZQ 3mRE2 REPORTING PERIOD 1975 TYPE ANO LOWER LIHIT ALL TOTAL NUHBER OF INOICATOR LOCATIONS OF ANALYSIS DETECTION HEAN (F) b OEEEORIIEQ CLLOI RANGE LOCAZIOi MIZU UIGUESZ ANNUAL REa(I NAHE HEAN (F) b QISIAHGE ANQ QIEECIIOU-EA(IGE b.-

CONTROL NUHBER OF LGCATIONS NONRQUT INE MEAN (F)

REPORTED Ea(IGEb

=

IIEAS((EEIIEHXS SR 89 SR 90 0 F 005 0 F 001 44 0 ~ 01(

9/

36)

LH4 BF TRAILER P 0+01-0 ~ 02 1 ~ 7 HILES NNW Oe00(

17/

35)

LH2 BF NORTH 0 F 00 Oo00 0'

NILE NNE Oq02(

I/

4) 0)02-0'2 0000(

2/

4) 0)00-0 F 00 Oi01(

2/

8) 0 ~ 01 0 ~ 02 0 F 00(

4/

8) 0 F 00 0 F 00 a.

Nominal Lover Limit of Detection (LLD) as described in Table 2.

b.

Mean and range based upon detectable measurements only.

Fraction of detectable measurements of specified locations is indicated in parentheses (F).

" 'TABLE NAHE OF FACILITY BBOBUS EEBBY LOCATION OF FAC ILITY Ll()ESIOHE RADIOACTIVITY IN RAINWATER PCI/L - 0'37 80/L ALaaa(Ia DOCKET NO BBmZQ=R=BE2 REPORTING PERIOD 1925 TYPE AND TOTAL NUHBER OF ANALYSIS fEBEOBHEO GAHHA (NAI) 99 I

131 BE-7 GAHHA (GELI) 29 CE-144 CS-137 K-40 81-214 PB-214 PB 212 BE 7 TRITIUH 60 LONER LIHIT OF DETECTION a LLLQ1 15 F 000 NOT ESTAB 33 F 000 5+000 NDT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB 330 F 000 ALL INDICATOR LOCATIONS HEAN (F) b BAHGE LOCaZlau )(IZU uiGUESZ AU((UaL BEa((

NAHE HEAN (F)

OISIAHCE AUO OIBECIIOB BA((GE CONTRDL LOCATION)

HEAN (()

BAHGE- ~

37+48(

3/

BQ)

CDURTLANOi AL 23e l5 58 ~ 54 10 ~ 5 HILES MSM 16'4(

29/

80)

ROGERSVILLEa AL 9 ~78-26+54 13 ~ 8 HILES NM hhe79(

1/

24) hhe79-hho79 24 VALUES <LLD 90.86(

23e80-19e 27(

7e69" 14.42(

10e68-9 ~ 13(

5 i $ 8-.

9'2(

64e09" 368 F 00(

334 ~ 00-8/

24) 243o10 11/

24]

33 F 06 6/

24)

IBe03 5/

24) 17e02 4/

24) i64 F 40 4/

48) 396 F 00 LH2 BF NORTH 0', NILE NNE LH2 BF NORTH Qe9 NILE NNE LH3 BF NORTHEAST leQ HILE NE LH2 BF NORTH 0 ~ 9 HILE NNE LH2 BF NORTH Qi9 NILE,NNE

(.H5 BF DAVIS F 2e5 HILES IfS'N LH5 BF DAVIS F 2 ~ 5 HILES MSM 44,79(

1/

2) 44i79-hhe79 243e10(

1/

2) 243(10- 24$ ~ 10 33)00(

1/

4) 33(00 33'6 18j63(

1/

2) 18i63-18,63 17'2(

1/

2) 17)02-17,02 104(40(

1/

3) 104)40 164 'Q 396t00(

1/

4) 396i00-396 F 00 5

VALUES <LLD 7e48(

F 48 95 '7(

92'0 16 ~ 60(

2 ~ 47 18 F 28(

18'8 8'3(

6e82>>

54'l(

54'}~

-414 ~ 00(

364 F 00 1/

5) 7'8 2/

5) 99'4 3/

5) 24 F 47 1/

5) 18'8 2/

5) 10'$

1/

5) 54 ~Ol 2/

12) 464 F 00 58'4(

1/

9) 19 VALUES <LLD 58'4" 58e54 20'5(

4/

9) 16'9( ll/

19) lli60" 24o22 11 '2>>

%1 ~ 72 NUHBER OF NONROUT INE '.

REPORTED BEASUBEHEHIS a.

Nominal Lover Limit of Detection (LLD) as described in Table 2.

b.

Hean and range based upon detectable measurements only.

Fraction of detectable measurements of specified locations is indicated in parentheses (F).

NAHE OF FACILITY BROUUS-EERRY I.OCAT ION OF FAC ILITY LIUESIOUE TABLE 6 RADIOACTIVITY IN SPECIAL RAINWATER PCI/L - 0'37 BQ/L DOCKET NO ~ RUnl3"SnBE2-aLABAUA REPORTII O'PERIOD aRZa TYPE AND TOTAL NUMBER OF ANALYSIS REBEORUEQ GAHMA (GELI) 3 BA-140 LA-140 RU-103 ZR-95 NB-95 I

131 81 214 TL 208 I 132

=

TE-132 TC-99H LOMER L IHI T OF DETECTION a LLLQ1 25 F 000 F 000 20 F 000 10 F 000 F 000 8 F 000 NOT, ESTAB 10 F 000 NOT ESTAB NOT ESTAB NOT ESTAB 77'1(

1/

2) 77 ~ 91 77 ~ 91 43e69(

2/

2) 43e61-43'6 39'6(

2/

2) 38e80-40'2 37'0(

1/

2) 37e90" 37'0 56'9(

2/

2) 47e82 65'6 63'9(

2/

2) 46'2" BOER 95 53'5(

1/

2) 5'5" 53e45 2

VALUES <LLD 233 F 00(

213 ~ 70-83,94(

71 e 39-52.68(

25,94" 2/

2) 252e30 2/

2) 96'9 2/

2) 79 ~ 41 ALL It(DICATOR LOCATIONS HEAN (F)b RAUGE LM1 BF NORTHMEST 1 ~ 0 HILE N

ATHENS'I.

10,9 MILES NE ATHENS@

AI, 10 ~ 9 HILES NE LHl BF NORTH)(EST leO MllE N I Hl BF NORTHMEST 1 ~ 0 NILE N ATHENS'L 10 ~ 9 MILES NE ATHENS>

AL 10e9 HILES NE 7719$ (

77y91-43(76(

43(76-40e52(

40e52" 37y90(

37)90 65196(

65)96-80(95(

80,95-53r45(

53)45 1/

1) 77'1 1/

1) 43,76 1/

1) 40 ~ 52 1/

1) 37'0 1/

1) 65'6 1/

1) 80 ~ 95 1/

1) 53e45 ATHENS'L 10 ~ 9 HILES NE ATHENS'L 10e9 MILES NE ATHENS'L 10 ~ 9 HlLES NE 252e30(

252i30-96 ~ 49(

96p49-79e41(

79e41 1/

1) 252'0 1/

1) 96'9 1/

1) 79e41 LOCAIIOU UXIU UIGUESI AUULlkL UEAbl NAME HEAN (F)b QISZAUCE AUQ QIBECIIOU BAUGEb CONTROL NUHBER OF LOCATIONS NONROUT INE HFAN (F)b REPORTED RAUGEh -

UEASOREUEUIS 1

VALUES <LLD 1

VALUES <LI.D 20 ~ 18(

1/

1) 20 ~ 18 20 ~ 18 1

VALUES <I.I.D 1

VAI.UES <LLD 60'9(

1/

1) 60'9 60'9 1

VALUES <LLD 26'4(

1/

1) 26e54~

26'4 195e60(

1/

1) 195e60 195'0 el'5(

1/

1) 41 ~ 75-41 ~ 75 VALUES <LI.D a.

Nominal Lover Limit of Detection (LLD) as described in Table 2.

b.

Mean and range based upon detectable measurements only.

Fraction of detectable measurements of specified locations is indicated in parentheses (F),

NAME OF FAClLITY BRQI(BS EERRX LOCATION OF FAC ILlTY Ll(IFSIOIIE TABLE 7

RADIOACTIVlTY IN HEAVY PARTlCLE FALLOUT MCl/KM(2) 37000000 F 00 80/KM(2)

DOCKET NO+

RUmZQ"3=BEE 4LSB455 REPORTlNG PERIOD 192B TYPE AND TOTAL NUMBER OF ANALYSIS EEREORHEQ GROSS BETA 12B LOHER LIMIT OF DETECTION a LLLOX 0 F 050 ALL INDICATOR LOCATIONS LQCarrQII }fIIU UIGUESI 45UlJAL 5EAU MEAN (F) b NAME MEAN (F) b RAUGE OZSIAIICE AGO QIRECIIOB RA E

0 90(

104/

104)

COURTLANO> AL ly2l( ll/ ll) 0 ~ 12 4 ~ 04 10 5 MII.ES WSM Os29 3s90 CONTROL LCCATION(

MEAN (F)

RAUGEb 2'3(

24/

24)

F 12 47'4 NUMBER OF NONROUTINE REPORTED HEOSUREIIEUIS--

a.

Hominal Lower Limit of Detection (LLD) as described in Table 2.

o i indicated in arentheses (P).

b.

Mean and range based upon detectable measurements only.

praction of detectable measurements of specified locations is indicated in parentheses P.

NAHE OF FAClLITY BBO)(US EEBEY LOCATION OF FAC ILI TY LI(IESIOUE TABLE 8 RADIOACTIVITY IN CHARCOAL FILTERS PCI/H(3) 0'37 BQ/H(3)

OOCKET NO ~

BI(mZQ"BmBE2 =

REPORTING PERIOO 1928 TYPE ANQ TOTAL NUHBER OF ANALYSIS PEBEOBIIEQ IODINE IN AIR 569 LONER L IH IT OF OETECT IONa LLLQX 0'10 ALL INDICATOR LOCATIONS LOcaziOII MIIu VIGUESZ a(IUUAL I)Eau HEAN (F) b NAHE HEAN (F) b BANGE QISIAIIGE AIIQ QIBECIIOH BAVGEb 0'2( 222/ 465)

LH3 BF NORTHEAST 0'2(

23/

52) 0'l-0 F 08 1'

HILE NE Oy01-0,07 CONTROL LOCATlONg HEAN (F)

'BANGEb 0'2(

46/

104) 0 F 01~

0 F 05 NUHBER OF NONROUTINE REPQRTEO HEOSUREIIEIIIS--

a.

Nominal Lower Limit of Detection (LLD) as described in Table 2.

b.

Mean and range based upon detectable measurements only.

Praction of detectable measurements of specified locations is indicated in parentheses (P).

19 Terrestrial Monitorin Milk Milk is collected from at least four of five farms within a 10-mile radius of the plant (see figure 3), and from at least one of four control farms.

Raw milk is analyzed weekly for I, and monthly for, gamma-emitting isotopes and for radiostrontium.

The average results for each farm are shown in table 9.

The operator of the farm located approximately four miles north of the plant went out of the dairy business and sold all his milk-producing animals in May 1978.

A dairy farm located approximately five miles north of the plant was added to the monitoring program in the same month.

In addition to the regularly scheduled milk samples, eight special samples were taken at the expected time of arrival of fallout from an atmos-pheric nuclear weapons test.

These data are presented in table 10.

Cow censuses were conducted in May and September 1978. It was determined that there are no dairy farms nearer the plant than the nearest farm being sampled.

Ve etation So that any relationship between fallout on pastureland and the presence of radionuclides in milk might be seen, pasturage is sampled quar-

terly at the farms from which milk is collected and analyzed for gamma-emitting radionuclides.

Table ll gives the results obtained from the laboratory analyses of these samples.

Soil Soil samples are collected'nnually near each monitoring station to provide an indication of a long-term buildup of radioactivity in the environment.

These samples are analyzed for gamma-emitting radionuclides and strontium 89 and 90.

The results are given in table 12.

Ground Water An automatic sequential-type sampling device has been installed on a well down-gradient from Browns Ferry Nuclear Plant.

A composite sam-ple from this well is analyzed for gamma-emitting radionuclides'monthly and composited quarterly for determination of tritium.

A grab sample is also taken from a control well up-gradient from the plant.

The results of the analysis of well water are shown in table 13.

Public Water Potable water supplies taken from the Tennessee River in the vicinity of Browns Ferry Nuclear Plant are sampled and analyzed for gross

20 beta and gamma-emitting,radionculides, and composited quarterly for tritium, Sr, and Sr analyses.

The first potable water supply downstream from the plant is equipped with an automatic sampler with composite samples collected weekly.

Two additional supplies downstream and one public water supply upstream are collected by monthly grab sampling.

Table 14 indicates the results from the analysis of potable water samples.

The maximum beta con-centration is 0.48 percent MPC.

Environmental Gamma Radiation Levels Thermoluminescent dosimeters (TLD's) are placed at nine stations around the plant near the site boundary and at the perimeter and remote air monitors to determine the gamma exposure rates at these locations.

The TLD's are changed every 3 months.

The quarterly gamma radiation levels determined from these TLD's are given in table 15.

Poultr and Food Cro s Food crops,

grains, and poultry raised in the vicinity of Browns Ferry Nuclear Plant and at control locations are sampled as they become available during the growing season, and analyzed for gamma-emitting radio-nuclides.

During this sampling period samples of tomatoes,

potatoes, green
beans, lettuce, turnip greens, soy beans, and poultry were collected and analyzed for specific gamma-emitting radionuclides.

The results are given in tables 16, 17, and 18.

No sample of lettuce or soybeans was taken from a control location.

NAHE OF FACILITY BRQUUS-EERRY LOCATION 'OF FACILITY LIUESXOUE TABLE 9 RADIOACTIVITY IN HILK PCI/L - 0 ~ 037 BQ/L QOCKET NO RUr29 BrBER---------

!LLABAU()

REPORTING PERIOD1925 TYPE ANO TOTAL NUMBER OF ANALYSIS fEREQRUEQ GAMMA (NAI) 10a IODINE IN HILK 436 SR B9 103 SR 90 103 10 F 000 5)72(

12/

12) 3q92-7.25 LOWER LIMIT ALL OF INDICATOR LOCAT IONS LQCAILOU-USXU-U~GUES>->USUAL-"EAU-b DETECTION HEAN (F)

NAME MEAN (F)

--l.LLOYD- -

ROUGE QISIAUCE-AUQ QIRECIIQU-- --R()UGEb----

ANALYSIS PERFORMED -- ALL VALUES BELOW LLD 0 ~ 500 I ~ 81(

13/ 245)

SITTING FARM Sq34(

3/

51) 0 51 6 04 4 ~ 5 HILES ENE Ot90 F 04 59 VALUES (LLD ANALYSIS PERFORHEO F 000 4'5(

56/

59) 2'2-9 66 CONTROL LQCATIONS MEAN (F)b RAUGEb 3106(

7/ 191) 0'7 8+86 44 VALVES <LLO 4'2(

36/

44) 2'l-10'6 NUHBER OF NONROUTINE REPORTEO UEASUREUEUIS-a.

Hominal Lover Limit of Detection (LLD) as described in Table 2.

b.

Mean and ranEe based upon detectable measurements only.

Fraction of detectable measurements of specified locations is indicated in parentheses (F).

TABLE 10 NAHE OF FACILITY BROUUS EERRY LOCATION OF FACILITY LIUESIOUE RADIOACTIVITY IN SPECIAL HILK PCI/L - 0'37 BQ/L DOCKET hO ~

RHmlB 3mRE2-4LABAU4

REPORTlhG PERIOD 1928 TYPE AND TOTAL NUHBER OF ANALYSIS EEREORUEQ GAHHA (NAI) b IODINE IN MILK b

LOWER LIHIT OF DETECTION a CLLQl 0 ~ 500 ALL INDICATOR LOCA)IONS HEAN (F)

BOUGE

ANALYSIS 15 'B(

5/

5)

I ~ 24-53e87 BITTING FARH 4 ~ 5 HILES ENE 53yb'7(

1/

1) 53)BT-53.87 LOCAZCOU UCZU UXGUESr AUU()AL UEAU G

NAME HEAN (F)

QISIAUCE 4UQ QCRECIIOU RQGE ---

PERPORMED -- ALL VALUES BELOW LLD CONTROL LCCATIONS HFAN (F) b EAU Gd'5 F 00(

3/

3) 3 ~ 12-29 ~ 12 NUHBER OF NONROVTINE REPORTED UEASUREUEUIS a.

Nominal Lower Limit of Detection (LLD) as described in Table 2.

b.

Mean and range based upon detectable measurements only.

Praction of detectable measurements of specified locations is indicated in parentheses (P).

TABLE 11 RADIOACTIVITY IN VEGETATION NAHE OF FACILITY RROUUS EERRY LOCATION OF FACILITY L]UESIOUE PCI/GH - 0 ~ 037 BQ/GH OLOROUO (ORY WEIGHT)

DOCKET NO ~

RUm29"3mBE2 REPORTING PERIOD

]QZR CONTROL LOCATIONS MEAN (F)

ROUGE b TYPE AND TOTAL NUMBER OF ANALYSIS PEREORUEO GAHHA (NAI) 19 RU-]03e 106 NUHBER OF NONROUTINE REPORTED UE4SUREUEUIS LOWER LIMIT ALL OF INDICATOR LOCATIONS DETECTION MEAN <F) b CLLOl ROUGE LOcazzOU xzlU U]GUESz OUUUOL UEOU NAHE-HEAN (F)

OISIOUCE OUO OlREczlOU ROUGd'ROOKS FARM 7 '

HILES NNW BROOKS FARM 7'

HII,ES NNW BROOKS FARM 7 ~ 0 HILES NNW 0.650 0.230 NOT ESTAB 0 F 80(

0 ~ 80-0'8(

oe28-0 ~ 61(

0'3" 1/

1 1) 0 ~ 80 1/

11) 0'8 11/

11) le42 Otbo(

0 ~ 80-Oe28(

0 ~ 28-Ot75(

0 ~ 35-1/

0 F 80 1/

Oe28 3/

le42 CO-58 BE-7 GAMMA (GEL I) 17 CE-]4]

1/

]coo 1/

3'7 1 ~ 00(

leOO-3e97(

3 ~ 97-Oe200 0'20 0'40 0 ~ 080 0 ~ 200 0'10 0 ~ 060 0 ~ 110 0'50 Oe050 NOT ESTAB 0'90 Oeloo NOT ESTAB NOT ESTAB NOT ESTAB Oe67(

4/

9) 0'4-1 ~ 00 2'4(

8/

9) 0'5-4'3 9

VALUES <LLD BITTING FARM 4 ~ 5 MILES ENE HARGROVE FARM 3'5 MILES N

CE-144 BA-140 LA-140 RU-103 RU-106 CS-137 ZR-95 NB-95 C0-58 K-40 1-131 8 I-214 PB-214 PB-212 RA-226 9

VALUES <LLD O.36<

3/

9) 0'3 0'S 1.05(

1/

9) 1 ~ 05-1 ~ 05 0.19(

7/

9) 0 ~ 07-0'8

] ~ 35(

4/

9) 0 ~ 91-le83 2 26(

5/

9) 0'9-3'1 0 07(

1/

9)

Oe07" Oe07 15e34(

9/

9) 3e32-29ell 9

VALUES <LLD 1/

0 F 48 1/

1 e05 1/

Oe3S 1/

le83 1/

3e31 1/

0 ~ 07 1/

21 ~ 72 BITT ING FARH 4 ~ 5 MILES ENE HARGROVE FARH 3 ~ 75 HILES N

LOONEY FARM 5e75 MILES ENE SITTING FARM 4e5 HILES ENE LOONEY FARM 5'5 MILES ENE HARGROVE FARM 3e75 MILES N

HARGROVE FARM 3 ~ 75 HILES N

Oe48(

0 ~ 48-

]e05

(

1 e 05-0%3&(

0 ~ 38"

]e83(

le83-3t3l(

3e31-Oq07(

Oq07-21t72(

2](72" 0'3(

6/

9)

Oel4-0'5 0'0(

5/

9)

Oe15-0.26 0 ~ 12(

4/

9) 0 F 08-Oi]6 Oe23(

6/

9)

Oe lt-0'5 9e72(

9/

9) 2.15-, 22,99 9 VALUES <LLD BITTING FARH 4 ~ 5 HII ES ENE LOONEY FARH 5'5 MILES ENE LOONEY FARM 5e75 HILES ENE SITTING FARH 4 ~ 5 MILES ENE HARGROVE FARH 3 ~ 75 MILES N

Oe45(

0 ~ 45-0'3(

Ot20-oe]5<

0 ~ 15-0'5(

Oj45-

]6 ~ 34(

lee34-1/

Oe45 2/

0'6 2/

o. ]e 1/

Oe45 1/

]6 ~ 34 BE-7 NOT ESTAB NOT ESTAB TL-208 a.

Nominal Lover Limit of Detection (LLD) as described in Table 2.

b.

Mean and range based upon detectable measurements only.

Fraction of detectable measurements 8

VALUES <LLD 8

VALUES <LLO 3) 3)

3) 0 ~5t(

8/

8) 0'7-1 ~ 05 2) 1)

0'4(

3/

8) 0 ~ 22 0'2 1 ~ 64(

5/

8) 0'9-3'2 0 ~t5('/

8) 0 ~ 45-0 ~ 45 0'7(

3/

8) 0 ~ 32-Oe73 0'2(

2/

8) 0 ~ 21 0 ~ 43 8

VALUES <LI.D 2) 1)

2) 2)

2) 1)

1) 0'2(

5/

8) 0 ~ 10" 0 ~ t2 0'0(

3/

8) 0 ~ 16-0'3 Oe72(

4/

8) o,]3-2.]e 8

VAI.UES <LLO 17 ~ 32(

8/

8) 9'0 32 ~ Ol 0'9(

3/

S) 0'9~

Oe47 0'4(

7/

8) 0 ~ 12-0 ~ 55 0'3(

6/

8) 0 ~ 13~

0 ~ 36 0'2(

5/

8) o,le-o.5o 0 '

t(

7/

8)

Oe]2 oe55 4 '0(

8/

8) le21

]0 F 44 0 ~ 14(

5/

8) 0 ~ 05-0']

2) 2)

2) 2)

of specified locations is indicated in parentheses (P).

-NAHE OF FACILITY BROUUS EERRY LOCATION OF FACILITY-LIUESIOUE TABLE ll (CONTD)

RADIOACTIVITY IN VEGETATION PCI/GH - Oe037 BQ/GM (DRY WEIGHT)

DOCKET hO RUm29nBmBE2 ALABAUA REPORTIhG PERIOD 1918 TYPE AND TOTAI. NUMBER OF 'ANALYSIS QEREORUEO GAHHA (GELI) 17 AC-228 NOT ESTAB Oo32(

I/

9) 0'2-0'2 LOWER LIMIT ALL OF INDICATOR LOCATIONS DETECTION MEAN (F)

CLLOl RAUGE BITT ING FARM 4o5 HILES ENE 0>32(

I/

2) 0'2-0'2 LOCAIIOU MIIU UIGUESI AUUlJAL BEAU NAME HEAN (F)

OISIAUCE-AUO-OIRECIIOU-- --RAUGEb----

CONTROL LOCATION)

HEAN (F)

BAUG&

0'4(

3/

B)

F 15-Oe29 NVHBER OF NONROUT INE REPORTED UE4SOREUEUIS a.

Nominal Lower Limit of Detection (LLD) as described in Table 2.

b.

Mean and range based upon detectable measurements only.

Fraction of detectable measurements of specified locations is indicated in parentheses (F).

NAHE OF FAC ILIIY BBOWUS EEBBX LOCATION OF FACILITY LIUESIQUE TABLE lZ RADIOACTIVITY IN SOIL PCI/GH 0 ~ 037 BQ/GH (DRY WEIGHT)

DOCKET hO ~

BUm29=3mBE2 ALOBOUO REPORTIhG PERIOD 1928 LOWER LIMIT OF DETECT ION a LLLDl NOT ESTAB o.o60 0.020 NDT ESTAB 0'20 0 ~ 100 NOT ESTAB NOT ESTAB NDT ESTAB NOT ESTAB 0 ~ 020 NOT ESTAB o.o6o NOT ESTAB SR 89 SR 90 1 o 500 11 0'00 ll TYPE AND TOTAL NUMBER OF ANALYSIS BEBEOBUED GAMHA (GELI)ll CE-141 CE-144 CS-137 K-40 8 I-214 8 I-212 PB-214 PB-212 RA-226 RA-223 TL-208 TE-132 AC"228 PA-228 9

VALUES <LLD 0 ~ 20(

0 ~ 20-0 ~ 38(

oo07 5olg(

3e38" 0 ~ 97(

o,64-0 ~ 74(

oo51-1 ~ 03(

0 ~ 70" 1 e05(

0 ~ 54-0 ~ 97(

0 ~ 64-oe32(

0 ~ 20-oe39(

oo23-0.26(

oe26-1 ~ 13(

oo67-Oe04(

0 ~ 02" 9 VAL ANALYSIS oe35(

- oo31-1/

9)

Oo20 9/

9) oo94 9/

9) 6e80 9/

9) 1 ~ 27 9/

9) le09 9/

9) lo33 9/

9) 1 e36 9/

9) 1 ~ 27 6/

9) 0 ~ 48 8/

9) 0 ~ 51 1/

9) 0 ~ 26 9) 1 ~ 67 4/

9) oe08 UES

<LLD PERFORHED 3/

9) 0.37 ALL INDICATOR LOCATIONS HEAN (F)b BOUGE LH2 BF NORTH De9 MILE NNE LH5 BF DAVIS F

2 '

MILES WSW LH4 BF TRAILER P I.e7 MILES NNW LH1 BF NORTHWEST loo HILE N LH1 BF NORTHWEST 1 ~ 0 MILE N LH1 BF NORTHWEST loo HILE N DECATUR'L 8.2 MI(,ES SSE LH1 BF NORTHWEST leo HILE N LHl BF NDRTHWEsT 1 ~ 0 HILE N LMl BF NORTHWEST 1 ~ 0 MILE N LH5 BF DAVIS F

2 '

MILES WSW LH1 BF NORTHWEST 1 ~ 0 MILE N LM1 BF NORTHWEST leo NILE N Ouzo(

0020 Or94(

0)94-6e80(

6)80-1 e27(

lq27" lq09(

1 q09-le33(

1e33-l)36(

le36" lj27(

1 ~ 27-0'8(

oj48 oy51(

oy51-0 ~ 26(

oj26-1 ~ 67(

I ~ 67-0 ~ 08(

oq08-1/

1) 0 ~ 20 1/

1) 0,94 1/

1)

F 80 1/

1) 1 ~ 27 1/

1) 1'9 1/

1) le33 1/

1) le36 1/

1) le27 1/

1) oe48 1/

1) 0,51 1/

1) o,z6 1/

1) le67 1/

1)

Oe08 LH1 BF NORTHWEST 1 ~ 0 MlLE N 0 ~ 37(

0 ~ 37" 1/

1) 0,37 LOCOIIDU WiIU UIGh(ESI OUUUOL UEOU~

NAHE HEAN (F)

DISIAUCE AUD DIBECILOU BOUGE oe07(

0 ~ 07-0 ~ 16(

0 ~ 16 0 ~ 48(

oe38>>

4e53(

4'8 0 F 88(

oe73 oe55(

0 ~ 44 0 ~ 90(

oe74" 1 ~ 04(

0 ~ 94-0 F 88(

0 ~ 73 0 ~ 31(

oe23" oe32(

o.z6-2 VALU 1/

2) 0 ~ 07 1/

21 0 ~ 16 2/

2) oe58 2/

2) 4.68 2/

2) 1 ~ 02 2/

2) 0 ~ 67 2/

2) 1 06 2/

2) 1 ~ 14 2/

2) 1 ~ 02 2/

2) 0 ~ 40 2/

2) 0 ~ 37 ES

<LLD oe95(

2/

2) 0 ~ 78>>

1 ~ 13 oe04(

1/

2) 0 ~ 04" 0 ~ 04 2

VALUES <LLD oe36(

1/

2) oe36" 0 ~ 36 CONTROL NUMBER OF LCCATIONS NONROUT INE HEAN (F)b REPORTED BOUGEb UEASUBEUEUIS a.

Nominal Lover Limit of Detection (LLD) as described in Table 2.

b.

Mean and range based upon detectable measurements only.

Fraction of detectable measurements of specified locations is indicated in parentheses (p),

t)AHE OF FACILITY BROIIUS EERRY LOCATION OF FACILITY LIUESIOUE TABLE 13 RADIOACTIVITY IN WELL WATER PCI/L - Oi037 BQ/L DOCKET hO ~ '-RUmZR=SnBE2- ---->>----

ALABAUA REPORTING PERIOD 192B TYPE AND TOTAL NUMBER OF Ah'ALYSIS eEREORUEQ GAHHA (NAI) 23 GAMMA IGELI) 1 K-AD LOWER L IHIT OF DETECT IONa ALLO>

NOT ESTAB TR ITIUH 330 F 000 9

ALL INDICATOR LOCATIONS LOCAXlOU UIIU UIGUESI AUUUAI, UEAU HCAtl IF )b NAME MCAN IF)

ROUGE QISIAUGE AUQ QIRECXIOU RAUGEb ANALYSIS PERFORMED -- ALL VALUES BELOW LLD 4

VALUES <LLD CONTROL LGCATION]

MEAN (F)

RAUGEb 55 '0(

1/

1) 55)60<<

55'0 426 F 00(

1/

5) 126 F 00" 426 F 00 NUMBER OF NONROUTINE REPORTED UEASUREUEUIS a.

Nominal Lover Limit of Detection (LLD) as described in Table 2.

Mean and range based upon detectable measurements only.

Fraction of detectable measurements of specified locations is indicated in parentheses (F).

NAHE OF FACILITY 8BOUUS EEBRY LOCATION OF FACILITY LIUESIOUE TABLE l4 RADIOACTIVITY IN PUBLIC WATER SUPPLY PCI/L - 0'37 BQ/L DOCKET )'0 RU 19=3mBE2 ALABAUA REPORTING PERIOD 1928 TYPE AND TOTAL NUMBER OF ANALYSIS

()EREORUEO GROSS BETA 88 GAHHA (NAI )

84 GAHHA (GELI) 4 K-40 LOWER LIMIT OF DETECTION a CLLOl 2'00 NOT ESTAB 81-214 NOT ESTAB PB-214 NOT ESTAB P 8-212 NOT ESTAB SR 89 10 F 000 16

,SR 90 F 000 16 TRITIUM 330 F 000 16 73'2{

2/

4) 52'0-94'4 2Z ~ 96(

3/

4) 9'2-31e99 21 ~ 98(

2/

4) 13 ~ 80-30 e 15 be77(

1/

4) 6'7-6e77 10'1(

1/

12) 10 ~ 41 10 ~ 41 12 VALUES <LLD ANALYSIS PERFORHED 457 F 00(

4/

12) 415 ~ 00 48 t ~ 00 CHAHPION PAPER TRH 282e6 SHEFFIELD>AL ROB TRH 254 '

CHAHPION PAPER TRH 282 F 6 CHAMPION PAPER TRH 282 '

CHAHPION PAPER TRH 282 F 6 WHEELER DAHN'L TRH 274 '

73'2(

52i30-31t99(

31e99" 30ti5(

30ti$"

6)77(

be77-10 ~ 41(

10e41" 2/

3) 94'4 1/

1) 31 ~ 99 1/

3) 30e15 1/

3) 4 ~ 77 1/

4) 10e41 484 F 00(

1/

4) 484.00-484.00 ALL INDICATOR LOCA/IONS LOCAILOU 81IU UIGUESZ AUUUAL UEAU HEAN (F)

NAME MEAN {F)b RAUGE OlSXAUCE AUO OIBECIIOU RAUGE 4'2(

68/

76)

CHAMPION PAPER 4t54(

49/

52) 2'5-ltd 51 TRH 282e6 Zt55-14e51 ANALYSIS PERFORMED ALL VALUES BELOW LLD CONTROL LOCATION/

HEAN (F)

BAUGEb 2'8(

7/

12) 2e40 3'8 4

VALUES <LI,D VAI,UES <LI,D 474 F 00(

2/

4) 472 F 00 476,00 NUHBER OF NONROUT INE REPORTED UEOSUREUEUIS a.

Nominal Lover Limit of Detection (LLD) as described in Table 2.

b.

Mean and range based upon detectable measurements only.

Fraction of detectable measurements of specified locations is indicated in parentheses (F).

28 Table 15 ENVIRONMENTAL GAMMA RADIATION LEVELS uarter January-March 1978 Location On-Site (9)*

Maximum Minimum Average~*

Off-Site (6)

Maximum Minimum Average Environmental Gamma Radiation Levels i

~l 0.011 23.5 0.005

11. 8 0,009

+ 0.003 18.9

+ 7.0 0.012 26.5 0.006 13.5 0.008

+ 0.005 17.6

+ 10.4 April-June 1978 On-Site (9)

Maximum Minimum Average Off-Site (4)

Maximum Minimum Average 0.011 0.005 0.008

+ 0.004 0.012 0.005 0.008

+ 0.006 24.2 11.0 17.6

+ 9.4 25.4 11.0 17.0

+ 13.0 July-September 1978 On-Site (8)

Maximum Minimum Average Off-Site (6)

Maximum Minimum Average 0.010

21. 7
0. 004 9.7 0.008

+ 0.004 18.0

+ 7.8 0.011 23.9 0.006 12.5 0.008

+ 0.004 17.5

+ 8.2 October 1978 January 1979 On-Site (8)

Maximum Minimum Average Off-Site (6)

Maximum Minimum Average 0.009 0.006 0.009

+ 0.003 0.010 0.006 0.008

+ 0.003 20.8 12.5 16.6

+ 6.2 22.8 12.8 16.7

+ 7.6

  • Number of stations (normally three TLD's at each station)
    • Allaverages reported

+20'

NAME OF FACILITY BROMUS EERRY LOCATION OF FACILITY LJUESIOUE TABLE 16

. RADIOACTIVITY IN POOD CROPS PCI/KGM - 0'37 BQ/KGH (MET WEIGHT)

DOCKET NO ~

RUmIBm3mBE2 ALABAUA REPORTING PERIOD LRIB IYPE AND LOWER LIMIT ALL TOTAL NUMBER OF INDICATOR LOCATIONS OF ANALYSIS DETECT IONa HEAN

( F ) b PEREORUEQ ILLQl

'ANGE LOCA,IIOU MIIU ULGUESI AUUVAL UEAU <

NAME HEAN (F)

QISIAUCE AUQ QIRECIIOU ENGELS RAOIOACTIVITY IN CORN CONTROL LCCATIONS MEAN (F)b BAUGEb NUMBER OF NONROUTINE REPORTEO UE4SUREUEUIS GAHHA (GELI) 2 K-40 NOT ESTAB 81-214 NOT ESTAB 1668 F 00(

1/

1) 1668 F 00-1668 F 00 11 '8(

1/

1) 11'8-lle38 LH5 BF DAVIS F

2 ~ 5 HILES WSK LM5 BF OAVIS F

Zr5 HILES XSW 1668 00(

1/

1) 2475 00(

1/

1) 1668 F 00 1668 F 00 2475 F 00 2475 F 00 llt38(

1/

1) 1 VALVES (LLO 11 ~ 38 11 o38 GAHHA (NAI) 1 K-40 RADIOACTIVITY IN GREEN BEANS 1583 ~'38 (

1/

1) 1583 '8 1583 '8 100 ~ 000 1583e38(

1/

1)

LH5 BF DAVIS F 1583 ~ 38 1583

~ 38 2 ~ 5 HILES WSW GAHHA (GELI) 1 K-40 NOT ESTAB RAOIOACTIVITY IN LETTUCE 1428 F 00(

1/

1)

L428 F 00 1428 F 00 81-214 BE-7 NOT ESTAB NOT ESTAB GAHHA (GEL I )

1 K-40 NOT ESTAB 2820 F 00(

1/

1) 2820 F 00-2820 F 00 22 ~ 21(

1/

1) 22'1-22o21 28 '3(

1/

1) 28'3-28 '3 2 MILES N

2 HILES N

2 HILES N

2820t00(

1/

1) 2820t00"2820 F 00 22t21(

1/

1) 22 ~ ZL 22 ~ 21 28t93(

1/

1) 28t93 28'3 RADIOACTIVITY IN POTATOES ANALYSIS PERFORMED -- ALL VALUES BELOW LLD GAHMA (NAI) 1 GAMMA (GELI)

K 1

40 NOT ESTAB 2437 F 00(

1/

1)

2437 F 00-2437 F 00 a.

Nominal Lover Limit of Detection (LLD) as described in Table 2.

b Mean and range based upon detectable measurements only.

Praction of detectable measurements of specified locations is indicated in parentheses (p),

NAHE OF FACILITY BRDBUS EERRY LOCATION OF FACILITY LIUESIOUE TABLE 16 (COMTD)

RADIOACTIVITY Ih FOOD CROPS PCI/KGH - Oe037 BQ/KGH (MET NEIGHT)

DOCKET NO. RU=29=3ndE2 4L4d4U4 REPORTING PERIOD 1RZd TYPE AND LOHER LIMIT ALL TOTAL NUMBER OF INDICATOR LOCATIONS OF ANALYSIS DETECTION HEAN (F) fEREORUEQ CLLQ1

&AUGE CONTRDL LOCAIIOU lflIU UIGUESI 4UUUAL UEAU LOCATIONS NAHE MEAN (F)b HEAN (F)

QZSIA((CE 4JQ QIRECIIOU R4UGE

-l4UGE--

RADIOACTIVITY IN TOMATOES NUMBER 0" NONROUTINE REPORTED UE4SUREUEblIS GAHHA (GEL I

)

2 K 40 NOT ESTAB 3035 ~ 00(

1/

1)

LH5 BF DAVIS F 3035>00(

1/

1) 2308 ~ 00(

1/

1) 3035e00"3035e00 2 '

HILES )(SN 3035e00-3035e00 2308e00 2308 F 00 RADIOACTIVITY IN TURNIP GREENS GAHHA (GEL I )

2 CE-144 CS-137 K 40 BI-214 PB"214 33,000 F 000 NOT ESTAB NOT ESTAB NOT ESTAB 34 ~ 54(

I/

I )

2 MILES N

34'4" 34e54 1

VALUES <LLD 2979 F 00(

1/

1) 2979 F 00-2979e00 F 04(

1/

1)

F 04-F 04 1

VALUES <LLD 2 HILES N

2 MILES N

34q54(

1/

1) 34)54-34'4 2979)00(

1/

1) 2979 F 00 2979e00 9~04(

1/

1) 9e04-9e04 PB-212 NOT ESTAB 1

VALUCS <LLD BE-7 NOT ESTAB 229,70(

1/

1) 2 MlLES N 229 '0(

1/

1) 229e70-229 F 70 229'0- 229 '0 1

VALUES <LLD 13 ~ 40(

1/

1) 13e40-13'0 2057 F 00(

1/

1) 2057 '0~2057 F 00 14'7(

1/

1) 14e77-14e77 12 '0(

1/

1) 12'0 12'0 12 '8(

1/

1) 12e98 12'8 1

VALUES <LLD a ~

b.

Nominal Lower Limit of Detection (LLD) as described in Table 2.

Mean and range based upon detectable measurements only.

Praction of detectable measurements of specified locations is indicated in parentheses (P).

NAME OF FACILITY 8BOUUS EEBRY LOCATION OF FACILITY LLUESIOUE TABLE 17 RADIOACTIYITY IN SOYBEANS PCI/GH 0 ~ 037 BQ/GH (DRY WEIGHT)

DOCKET hOe BU"793"8E2 OLOBOUO REPORTIhG PERIOD 1928 TYPE AND TOTAL NUMBER OF ANALYSIS QEREOBUEO GAHHA (GEL I )

1 LOWER LIMIT ALL OF INDICATOR LOCATIONS DCTECTIONa MEAN (F)b CLLQl BOUGE LOCOZZOU UrZU UZGUESZ OUUUOL UEOU NAHE HEAN (F)b OISIOUCE OUQ OLRECIIOU-BOUGE CCNTROL NUMBER OF LOCATIONS NONROUTINE MEAN (F) b REPORTED BOUGEh UEOSUREUEUIS K 40 8 I-214 PB-214 NOT ESTAB NOT ESTAB NOT ESTAB 16 ~ 39(

16o39-De03(

De03-0 ~ 05(

0 ~ 05-1/

1) 16 ~ 39 1/

1) 0'3 1/

1)

Oe05 0 HILES N

0 HILES N

4 HILES N

16g39(

16 ~ 39-Oj03(

0)03-Ot05(

0)05-1/

1) 16'9 1/

1) 0'3 1/

1) 0'5 a.

Nominal Lover Limit of Detection (LLD) as described in Table 2.

Hean and range based upon detectable measurements only.

Fraction of detectable measurements of specified locations is indicated in parentheses (F).

TABLE 18 NAME OF FACILITY BBOWUS EEBBY LOCATION OF FACILITY LIUESIOUE RADIOACTIVITY IN POUL'TRY PCI/KGH - 0 ~ 037 BQ/KGH (WET WEIGHT)

DOC~ET NO, BU-.ZS)."3-.8Ea 4L48484 REPORTING PERIOD 1928 TYPE AND TOTAL NUMBER OF ANALYSIS EEBEOBUEQ GAHHA INAI )

2 LOWER LIHIT OF DETECTIONa CLLQ1 ALL INDICATOR LOCATIONS LOC4IlQU UiIU UIGUESI 4UUUAL, UEAU HEAN (F) b NAHE HEAN (F) b BAUGE 015IAUCE 49D QCBECIIQU 84UGEb ANALYSIS PERFORMED -- ALL VALVES BELOW LLD CCNTROL LCCATIONS HEAN (F) b BAUGEb NUHBER OF NONROUTINE REPORTED UE4SUBEUEUIS-a.

Nominal Lower Limit of Detection (LLD) as described in Table 2.

di ated in arentheses (F).

b.

Mean and ranSe based upon detectable measurements only.

Fraction of detectable measurements of specified locations is indicated in parentheses (F.

33 Reservoir Monitorin Samples are collected from the Tennessee River as detailed in table 19.

Samples collected for radiological analysis include plankton from three of these cross sections and bottom fauna and sediment from four cross sections.

The locations of these cross sections are. shown on the accompanying map (figure 4) and conform to sediment ranges established and surveyed by the Data Services

Branch, TVA.

Water Water samples are collected automatically by sequential type sampling devices at three cross sections and composite samples analyzed monthly for gamma-emitting radionuclides.

Further composites are made quarterly for strontium and tritium analyses.

Sampling locations are shown in table 19.

Grab samples were also collected monthly from the vicinity of the plant discharge

.to the Tennessee River, and at a point on the Elk River.

Results are displayed in table 20.

Fish Radiological monitoring for fish is accomplished by analysis of composite samples of adult fish taken from each of three contiguous reser-voirsWilson, Wheeler, and Guntersville.

No permanent sampling stations have been established within each reservoir; this reflects the movement of fish species within reservoirs as determined by TVA data from the Browns Ferry Nuclear Plant preoperational monitoring program.

Two species, white crappie and smallmouth buffalo, are collected representing both commercial and game species.

Sufficient fish are collected in each reservoir to yield 250 to 300 grams oven-dry weight for analytical purposes.

All samples are collected semiannually and analyzed for gamma-emitting radionuclides.

The composite samples contain approximately the same quantity of flesh from each fish.

For each composite a subsample of material is drawn for counting.

Results are given in tables 01, 22, and 23.

Plankton As indicated in table 19, net plankton (all phytoplankton and zooplankton caught with a 100 p mesh net) is collected for radiological analyses at each of three stations by vertical tows with a 1/2-meter net.

At least 50 grams (wet weight) of material is necessary for analytical accuracy.

Samples are collected semiannually and analyzed for gross beta activity, and when quantities are sufficient, for gamma activity and Sr and Sr content.

During this reporting period, three samples did not'ontain sufficient material for gross beta analysis.

Results are shown in table 24.

34 Sediment Sediment samples are collected from Ponar dredge hauls made for bottom fauna.

Gamma radioactivity and Sr and Sr content are determined 89 90 semiannually in composite samples collected from each of four stations.

Locations of these stations are shown in table 19.

A third set of samples was taken in late 1977.

The results from the analyses of these samples are included herein.

Results are shown in table 25.

Bottom Fauna The flesh and shells of Asiatic clams collected semiannually from the cross sections at four stations (table 19) are analyzed for gamma-emitting radionuclides.

Levels of Sr and Sr are determined on the

shells, and on the flesh when sufficient amounts were available.

A 50-gram (wet weight) sample provides sufficient activity for counting.

A third set of samples was taken in late 1977.

The results from the analyses of these samples are included herein.

Results are given in tables 26 and 27.

Table 19 SAMPLING SCHEDULE RESERVOIR MONITORING Biolo ical sam les collected semiannuall River/river mile Zooplankton, chlorophyll, h to lankton Benthic fauna a

Sediment Fish Water samples (collected monthl Tennessee 277.98 Tennessee 285.2 Tennessee 288.78 Tennessee 291.76 Tennessee 293.5 Tennessee 293.70 (discharge area)

Tennessee 305.0 Tennessee 307.52 Elk 20.5 a.

Gill net and/or electroshocker wi11 be used for collection.

Samples of fish are collected from Guntersville,

Wheeler, and Wilson Reservoirs.

b.

Automatic sampler.

c.

Grab sample.

36 Figure 4

R ESERVOIR MONITORING NETMIQRK Elk River N

WHEELER DAM mile 274.90 mile 277.98 Rogersville 0

mile 282.6 rnite 29l.76 Athens

~mile 285.2 B.F. NUCLEAR PLANT ml Champion Paper Co.

0 Cour tland ile2887B mite 293.50 rnite 293.70 mite 305.0 Decatur rnite 307.52

~ - Automatic Sam ler Scale of Miles 0

NAHE OF FACILITY BROGANS EEBRY LOCATION OF FACILITY LI))ESIOHE TABLE 20 RADIOACTIVITY IN SURFACE WATER TOTAL PCI/L - 0.037 BQ/L 4LBB4(14 DOCKET

)ID'

RHm29m3nBE2- -----

REPORTING PERIOD IBIS TYPE ANO TOTAL NUHBER OF ANALYSIS EEREORHEQ GAHHA (NAI) 58 GAHHA (GELI) 2 81-214 NOT ESTAB P8-214 SR 89 SR 90 TRITIUH 20 20 20 NOT ESTA8 10 ~ 000 F 000 330 F 000 12 VALUES <LLO ANALYSIS PERFOR)(EO 12 VALUES <LLO ANALYSIS PERFORHEO 460'0(

5/

12) 398 F 00- 529e00 TRH 285 '

482q50(

2/

4) 436)00 529e00 LOWER LIMIT ALL OF INDICATOR LOCATIONS LOC4IIOU )(iIII MIGUESZ 45UVAL I)EAU DETECT IONa HEAN (F)b NAHE HEAN (F)b ILLOA RANGE OISZAHCE 480 OIRECIIOB BAHGE ANALYSIS PERPORMED ALL VALUES BELOW LLD CONTROL NUHBER OF LOCATIONS NONROVTINE HEAN (F)b REPORTED BAMGEb HE4SUREHEBZS 17 ~ 51(

1/

2) 17'1-17'1 12 '6(

1/

2) 12'6 12'6 8

VALUES <LLD

-8 VALVES <LLO 440 F 00(

2/

8) 394 F 00 486 F 00 a.

Nominal Lower Limit of Detection (LLD) as described in Table 2.

b.

Mean and range based upon detectable measurements only.

Praction of detectable measurements of specified locations is indicated in parentheses (p).

TABLE 21 RADIOACTIVITY IN WHITE CRAPPIE (FLESH)

PCI/GH - Os037 BQ/GH (DRY WEIGHT)

NAHE OF FACILITY BROWIIS EERRY LOCATION OF FAC ILI TY LI(IESIOUE DOCKET NO ~ 'Um29-3mBE2 4L484I)4 REPORTING PERIOD 192d TYPE AND TOTAL NUMBER OF ANALYSIS REREORHEO GAHHA (NAI) 3 GAMMA (GEL I )

3 CS-137 K 40 81-214 PB 21.4 LOWER LIMIT OF DETECTION ILLOI 0'20 NOT ESTAB 0'20 NOT FSTAB Oo12(

Oell-15o43(

14 ~ 89-Oe06(

De06-0 ~ 05(

0'4" 2/

2)

Os13 2/

2) 15i96 1/

2) 0,06 2/

2) 0.06 ALL INDICATOR LOCATIONS HEAN (F)

R4((GE ANALYSIS WI(.SON RESERVOIR TRH 259>>275 WHEELER RES TRH 275 349 WHEELER RES TRH 275"349 WHEELER RES TRH 275~349 0)13(

0) 13-15y96(

15(96" 0,06(

0)06-Os06(

0 ~ Ob 1/

1) 0 ~ 13 1/

1) 15,96 1/

1) 0,06 1/

1) 0'b LOC41108 ADIEU UIGUESI 4'(IU4L BE4hl NAHE HEAN (gT OLSIAHCE-4WD DIRECZIOII--

R4(IGE PERFORMED -- ALL VALUES BELOW LLD CONTROL NUHBER OF LCCATION]

NONROUTINE HEAN (F)

REPORTED RAWGEb -

IIEaSUREIIE((IS De21(

1/

1) 0 ~ 21 0@21 16'3(

1/

1)

Ibt53~

Ibe53 1

VA(.UES CLLD 0 ~ 05(

1/

1) 0'5 0'5 a.

Nominal Lover Limit of Detection (LLD) as described in Table 2.

b.

Mean and range based upon detectable measurements only.

Fraction of detectable measurements of specified Iocations is indicated in parentheses (F).

TABLE 22 RADIOACTIVITY IN SHALLHOUTH BUFFALO (FLESH)

PCI/GH - 0 ~ 037 BQ/GH (ORY WEIGHT)

NAHE OF FACILITY BROWSES EERRY DOCKET NO ~ RHm29m3mBE2--

LOCATION OF FACILITY LIIIESZOUE ALABAMA REPORTING PERIOD1124 TYPE ANO TOTAL NUMBER OF ANALYSIS 9EREQR)IEQ GAHHA (NAI) 3 GAHHA (GELI) 3 CS-137 K-40 81-214 PB 214 0'20 NOT ESTAB 0'20

.NOT ESTAB 0 F 07(

0 F 05" 12' 03(

lle 64-0'6(

0 ~ 06",

0'0(

0 F 07>>

2/

2) 0 F 08 2/

2) 12'L 1/

2) 0'6 2/

2) 0 ~ 12 LOWER LIMIT ALL OF INDICATOR LOCATIONS OE TEC T IONa MEAN (F) b CLLQL RANGE ANALYSIS WHEELER RES TRH 275 349 WHEELER RES TRH 275~349 WILSON RESERVOIR TRH 259 275 WHEELER RES TRH 275 349 Oy08(

0)08-L2y4L(

L2)4L Oy06(

0)06-OyL2(

0 ~ 12-1/

1)

OIOB 1/

1) 12'1 1/

1)

Oo06 1/

1) 0'2 LQCAZZON VIZ'IZGuESZ AN)(VAL L)EAN >

NAHE HEAN (F)

QISL'ANCE-ABQ QIRECEIQH RA((GE PERFORMED -- ALL VALUES BELOW LLD CONTROL NUHBER OF LOCATION)

NONROUT INE MEAN (F)

REPORTED RANGE b HEASOREHEUIS Oo 13(

1/

1)

Oe13 0 ~ 13 13 ~ 36(

1/

1) 13'6-13'6 VALUES <LLO 1

VALVES <LLO a.

Nominal Lower Limit of Detection (LLD) as described in Table 2.

b.

Mean and range based upon detectable measurements only.

Fraction of detectable measurements of specified locations is indicated in parentheses (F).

TABLE 23 RADIOACTIVITY IN SHALLHOUTH BUFFALO (WHOLE)

PCI/GH - Oe037 BQ/GH (DRY WEIGHT)

NAME OF FACILITY RRQUUS EERRY LOCATION OF FACILITY LIUESXOUE DLABAUA-------

DOCKET NOe RUtZQ=R=RE2 REPORTING PERIOD 19ZS NUHBER OF NONROUTINE REPORTED UEOSUREUEUIS CONTROL LOC ATIONbS HEAN (F)

RAUGEb---

LOWER LIMIT ALL OF INDICATOR LOCATIONS LOGAZIOU ){IIU UIGUESI AUU{JAL UEAU DETECTION HEAN (F) b NAHE r

HE AN

{ F )

LLLOX RAUGE OISIAUGE AUO OIRECZIOU RAUGd'NAl YSIS PERFORMED

- ALL VALUES BELOW LLD TYPE AND TOTAL NUMBER OF ANALYSIS REREORUEO GAHHA (NAI) 3 GAHMA (GEL I) 3 CS-137 1/

1) 0'5 1/

1) 9e21 I,/

1) 0.06 1/

1)

Oo04 1/

1)

Oe03 1/

1)

Oe06 1/

1) 6'4 1/

1)

Oe05 1/

1)

Oo04 1/

1) 0,02 0.06(

0'6 6i44{

br44" 0'5(

0'5" 0 F 04(

0'4~

0'2(

0 F 02~

Og05 (

Oy05-

9) 21(

9)21-0,06(

0'6 Oe04(

OI04 Oj03(

0,0)<<

NOT ESTAB K-40 81-214 NOT ESTAB 0 020 0 04{

2/

2)

WHEELER RES 0'3-0'5 TRH 275-349 7i90{

2/

2)

WHEELER RES 6 60 9'1 TRH 275-349 0'20 DE 05{

2/

2)

WHEELER RES Oe05-0+06 TRH 275>>349 PB-214 NOT ESTAB Oe04(

1/

2)

WHEELER RES 0,04-0'4 TRH 275 349 Oi03(

2/

2)

WILSON RESERVOIR 0 F 02 0'3 TRH 259"275 a.

){oninal Lower Limit of Detection (LLD) as described in Table 2.

b.

Mean and range based upon detectable measurcaents only.

Fraction of detectable moasurencnts of specified locations is indicated in parentheses (p).

TABLE 24 NAHE OF FACILITY BBOUUS EEBBY LOCATION OF FACILITY LIUESIOHE RADIOACTIVITY IN PLANKTON PCI/GH - 0 ~ 037 BQ/GH (DRY MEIGHT)

DOCKET hO ~

BUmZQ=SmBE2 4LABAUD REPORTlhG PERIOD 1928 TYPE AND TOTAL NUMBER OF ANALYSIS PEBEQBUEO GROSS BETA 3

GAHHA-(GELI) 6 LOMER LIMIT OF DETECTION a LLLO1 0'00 ALL INDICATOR LOCATIONS HEAN (F)b RANGE 6'4(

2/

2)

F 16-8'2 4

VALUES <LLD ANALYSIS PERFORHED LOCAZEOU )flXU UIGUESI aUUUAL BEAU NAME 'EAN (F)b OISIAUCE AhlO QIBECIIOB BABOON'RH 291 ~ 76 8 ~ 52(

1/

1) 8)52 8'2 CONTROL LOCATIONS HEAN (F)b UGEb 5 46(

1/

1)

F 46 5e46 2

VALUES <LLD NUHBER OF NONROUTINE REPORTED UEaSUBEUEHIS a.

Nominal Lower Limit of Detection (LLD) as described in Table 2.

b.

Mean and range based upon detectable measurements only.

Fraction of detectable measurements of specified locations is indicated in parentheses (F).

TABLE 25 RADIOACTIVITY IN SEDIHENT PCI/GH - Oe037 BQ/GH (DRY WEIGHT)

NAHE OF FACILITY BRQHUS EERRY LOCATION OF FACILITY LLUESIQUE DOCKET hQ.

RUrlII=B=BE2 DLABAUA REPORTING PERIOD LRZB TYPE ANO TOTAL NVHBER OF ANALYSIS EEREQRUEQ GAHHA (GELI) 12 LOWER LIHIT OF DETECTION a LLLQL ALL I'IOICATOR LOCATIONS LQCaZLQU XXZU UiGUESZ aUUV4L UEAU HEAth (F)b NAHE HEAN (F)b RAUGE QISIAUCE AUQ QIRECIIQU RAUGE CGNTRQL NVHBER OF LCCATION)

NONRQVTINE HEAN (F)

REPORTED ROUGE-UEAS(IREUEUCS TRH 288'8 0.060 0.010 0.020 Oe010 NOT ESTAB Oe010 0'20 Oe100 NOT ESTAB NOT ESTAB NOT ESTAB NOT ESTAB 0'20 Oe060 NOT ESTAB CE-144 CO-60

'S-137 NB-95 K 40 HN-54 81-214 81-212 PB-214 PB-212 RA-226 RA-223 TL-208 AC-228 PA-228 5/

0'3 9/

Oe80 9/

2e67 0'8(

0'4" 0'0(

Oe05-1 ~ 92(

Oe72-Oe 12.(

0 ~ 05-15 '3(

10 ~ 41-0'5(

0 ~ 05-Le49(

le04-le39(

0 ~ 94-1 ~ 57(

0 ~ 95-1 75(

le 06" 1 ~ 49(

1 ~ 04-0'8(

0 ~ 38-Oe59(

Oe33-le86(

Le26" 0'7(

0 ~ 05-3'6(

2 ~ 01-0 ~ 36(

0 ~ 36-9) 9)

9)

TRH 293 '

BFNP DISCHARGE TRM 277'8 9) 9)

9) 9)

9) 9)

9) 9)

9) 9)

9) 9)

9) 9)

TRH 277'8 TRH 288e78 4/

Oe18 9/

17e74 1/

Oe05 9/

le78 9/

2'3 9/

Le91 9/

2e19 9/

Le 78 1/

0'8 9/

Oe72 9/

2e48 3/

Oe08 3/

4'6 1/

0e36 TRH 293e7 BFNP DISCHARGE TRH 277'8 TRH 277'8 TRH 277'8 TRH 277'8 TRH 277'8 TRH 293 '

BFNP DISCHARGE TRM 277e98 TRH 288 '8 TRH 277'8 TRH 288 '8 TRH 277'8 1 '00 SR 89 SR 90 12 0'00 12 a.

Nominal b.

Mean and Lover rang Limit of Detection (LLD) as described in Table 2.

e based upon detectable measurements only.

Fraction of Oy36(

Dt28-OI33(

ot05-Zy46(

2'7 OgLB(

0>18-Le)53(

le,07-Ot05(

Ot05 lt68(

1 ~ 55-Ltel(

1 y07-Lq80(

Lt68-Lt97(

Lt84" L168(

Lt55" 0'8(

0(38-0'0(

Ojee-Zt07(

L(76 Ot08(

0)07" 4,2e(

4,2e<<

0'6(

Oj36" 2/

Oe43 3/

OeBO 3/

Ze67 1/

Oe18 3/

17'7 1/

Oe05 3/

le78 3/

2 ~ 53 3/

1 e'91 3/

2e19 3/

1'8 1/

0'8 3/

0'2 3/

2'8 2/

Oe08 1/

4e26 1/

0'6 detectable measurements 3) 3)

3) 3)

3) 3)

3) 3)

3) 3)

3) 3)

3) 3)

3) 3)

3) of 3

VAI.VES <LI.D 3

VALVES <LLD 0'3(

3/

3)

OelB Oe31

-3 VALVES <LLD 14e88(

3/

3) 10 F 88 17'5 3

VAI,VES <LLD 1 ~ 51(

3/

3) 1 ~ 27 1 ~ 72 1 ~ 34(

3/

3) 0 ~ 81 2 ~ 14 1 ~ 61(

2/

3) 1 ~ 57 1eb5 6'9(

3/

3) le34 16'0 1 ~ 51(

3/

3) 1'7 1 ~ 72 3

VALVES <LLO Oe57(

3/

3) 0'4 0'9 le80(

3/

3) 1 ~ 44 2'0 0 F 07(

1/

3) 0'7~

0 F 07 3

VALVES <LLD Oe71(

1/

3) 0 ~ 71" 0 ~ 71 specified locations is indicated in parentheses (P).

NAME OF FACILITY RROUUS EERRY LOCATION OF FAC ILI TY LEUESIOUE TABLE 26 RADIOACTIVITY IN CLAM FLESH PCI/GH - 0 037 BQ/GH (DRY NEIGHT)

DOCKET NO ~

RU~ZR"3"BE2 ALABAUA REPORTING PERIOD 1928 LOWER LIMIT OF DETECT ION I.LLO1 TYPE Af)0 TOTAL NUMBER OF ANALYSIS 4EREORUEO GAHHA (GELI) 12'S-137 Oe080 0'70 NOT ESTAB NB 95 K 40 81-214 NOT ESTAB P 8-214 NOT ESTAB PB-212 NOT ESTAB TL-208 NOT ESTAB AC-228 NOT ESTAB 0 ~ 41(

Oel8-6 ~ 61(

6e61 7e08(

4e73-0 ~ 90(

0'5" Oe88(

0 ~ 55-Oe74(

Oe59" 0.26(

Oel2" 1 ~ 09(

0 ~ 56-8/

9)

Oe92 1/

9)

F 61 9/

9) 9e69 9/

9) le34 9/

9) 1 ~ 23 9/

9) le 10 8/

9) 0 ~ 31 5/

9) le 61 ALL INDICATOR LOCATIONS MEAN (F) b BAUGE TRH 277e'98 TRH 288'8 TRH 288e78 TRH 277'8 TRH 277'8 TRH 277'8 TRH 2SB ~ 78 TRH 293i7 BFNP DISCHARGE Oy54(

0028 6,61(

6)61-Bq08(

6,88-0>97(

0)67-0>92(

Oe58 0 F 80(

Oe59-0)29(

Oy27 l)61(

1 eh)"

3/

3) 0'2 1/

3) bebl 3/

3) 9'9 3/

3) 1 ~ 34 3/

3) 1 ~ 23 3/

3) 1 e10 3/

3)

Oe31, 1/

3) lebl LOCAZZOU UXZU UZGUESZ AUUUAL UEAU NAHE HEAN (F)b OISXAUCE AUO OIBECILGU RAUGE 0'9(

1/

3)

Oe59-Oe59 3

VALUES <LLD F 04(

be52-0 ~ 90(

0 ~ 47-1 ~ 02(

0 ~ 65-Oe89(

0 ~ 44-Oe50(

0'0~

2'9(

2 ~ 29-3/

3) 13'3 3/

3) 1e64 2/

3) 1 ~ 39 3/

1 ~ 67 1/

3) 0'0 1/

3) 2'9 CONTROL NUMBER OF LOCATIONS NONROUTINE HEAN (F)

REPORTED BAUGEb UEASUREUEUZS a.

Nominal Lower Limit of Detection (LLD) as described in Table 2.

b.

Mean and range based upon detectable measurements only.

Eraction of detectable measurements of specified locations is indicated in parentheses (E) ~

TABLE 27 RADIOACTI)tITY IN CLAM SHELL PCI/GM - 0'37 BQ/GH (DRY WEIGHT)

DOCKET NOe RI)ml9=3mBE2 NAME OF FACILITY BROW(IS EERRY REPORTING PERIOD 192h LOCATION OF FACILITY-LIIIESXOUE 4LABAI)4

R P

CO-60 CS-137 K-40 81-214 81-212 PB-214 PB-212 RA-226 TL-208 AC-228 SR 89 SR 90 12 12 TYPE ANO TOTAL NUMBER OF ANALYSIS PEREORIIEO GAHHA (GELI) 12 LOWER LIMIT OF OCTECT ION CLLO1 Oo010 0 F 020 NOT ESTAB 0.020 0.100 NOT ESTAB NOT CSTAB NOT ESTAB Oe020 O.oeo 5.000 1.000 0'4(

0 ~ 01-Oe04(

0'3 0'3(

Oi 30-0'0(

Ool3" 0'5(

0 ~ 18-0'2(

Ool3" 0'3(

Oo13-Oo30(

0'3 Doll(

Os05" 0'0(

OiIO-9 VAL ANALYSIS 4 F87(

3e64 9)

Oe07 9/

9)

Oe05 9/

9)

Oe80 9/

9) 0'5 7/

9)

Oeb9 9/

9)

Oebe 9/

9)

O.ee 9/

9) 0'5 9/

9)

Oe22 9/

9) 1,08 UES (LLO PERFORMED 9/

9) 5eb0 TRM 293 '

BFNP DISCHARGE TRM 293I7 BFNP DISCHARGE TRM 277>98 TRM 293 '

BFNP DISCHARGE TRM 293 '

BFNP DISCHARGE TRM 293 '

BFNP DISCHARGE TRM 293 '

BFNP DISCHARGE TRM 293 '

BFNP DISCHARGE TRH 293e7 BFNP DISCHARGE TRM 293 '

BFNP DISCHARGE TRM 277'8 o,oe(

0<05 0)04(

0(04-0'0(

0)44-Oi51(

0 (31" 0)42(

0)23 Oy53(

0(32-0 ~ 52(

Oe30" og51(

0) 31-0)18(

01 12 Oe72(

0<36-5e23(

5e03" 2/

3)

Oe07 3/

3)

Or05 3/

3)

Oe80 3)

O.e5 3/

3) 0'9 3/

3)

Oebb 3/

3)

Ogbb 3/

3) 0 i65 3/

3)

Oe22 3/

3) 1 ~ 08 3/

3) 5g60 ALL INDICATOR LOCATIONS LOC411OII )(rZII IIZraESZ 4I(NIIAL IIEAII HEAN (F)b NAHE MEAN (()b RAUGE

OLSZAIICE 480 O1RECElOH B4IIGE 3

VALUES (LLO 2/

3) 0'3 3/

3) le47 3/

3)

Oo79 3/

3)

Oo73 3/

3) 0'6 3/

3)

Oebl 3/

3) 0'9 3/

3)

Oe21 3/

3) 0 F 84 LUES <LLO 0'3(

0'2 Oe84(

0'3 0 ~ 61(

Oo46 Oe46(

0 '0>>

0'4(

Oe47 0'3(

0 F 40" 0'1(

0.4e-Oe17(

0)12 0 ~ 64(

0'6" 3

VA 4 F81(

3/

3) 4'6" 5'7 CONTROL NUMBER OF LCCAT ID'ONROIJTINE MEAN (F)

REPORTED RAIIGEb BE4SUREBEIIZS a.

Nominal Lover Limit of Detection (LLD) as described in Table 2.

s rements of s ecified locations is indicated in parentheses (F).

b.

Mean and range based upon detectable measurements only.

Fraction of detectable measurements of spec e

ocat ons s

ualit Control A quality control program has been established with the Alabama Department of Public Health Environmental Health Administration Laboratory and the Eastern Environmental Radiation Facility, Environmental Protection

Agency, Montgomery, Alabama.

Samples of air, water, milk, and vegetation collected around the Browns Ferry Nuclear Plant are forwarded to these laboratories for analysis, and results are exchanged for comparison.

Data Anal sis Data measured at the control stations for each medium were aver-aged for each sampling period.

In order to describe the distribution of control station data, a mean, standard deviation, and 3-sigma value were calculated.

We can expect, with 99 percent confidence, that background concentrations would be distributed within these limits.

This provides us the basis for comparing control and indicator data.

If the indicator data fall within the limits defined for control data, we can say, with 99 per-cent confidence, that 'the indicator data were not significantly affected by the nuclear plant. If the data do not fall within the limits, we will perform further analyses to determine if the difference is attributable to the nuclear plant.

Conclusions A vast ma)ority of the indicator station data were found to be within the distribution defined by the control station data.

The ALPHA-M least squares computer program identified concentrations slightly exceeding the limits of the control station data for a small number of radionuclides in samples from indicator stations.

Many of these values may be discounted because the error reported by the ALPHA-M program was greater than the cal-culated concentration.'he remaining isolated elevated concentrations may be the result of fallout, 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.

Increased levels of radioactivity were observed in milk, rain-water, air particulates, heavy particle fallout, vegetation, and in atmos-pheric radioiodine in, March and April following the atmospheric nuclear weapons testing conducted by the Republic of China.

This increase was seen in control stations as'ell as indicator stations, and was widely reported in the eastern portion of the United States.

Levels of I in milk as high as 53.9 pCi/1 were observed.

The primary radioisoto~es identified in the atmospheric media were Zr, Nb, I,

Ba, La, "Bi, and Ru.

In addition, slight increases in the concentrations of Cs and Sr were absorbed in sediment samples taken from the Tennessee River near Chattanooga, Tennessee, and in the vicinity of Browns Ferry Nuclear Plant in late 1977 after an earlier atmospheric nuclear weapons test.

46 It is concluded from the above analysis of the data that there were no significant increases in environmental radioactivity attributable to the operation of Browns Perry Nuclear Plant.

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