ML20116P210

Annual Radiological Environ Operating Rept for 1984

ML20116P210
Person / Time
Site:	Sequoyah
Issue date:	12/31/1984
From:	Mccloud D TENNESSEE VALLEY AUTHORITY
To:	Adensam E Office of Nuclear Reactor Regulation
References
NUDOCS 8505070554
Download: ML20116P210 (65)

Text

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i TENNRSSEE VALLEY AUTHORITY 1

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9 RADIOLOGICAL HEALTH STAFF v M' t5E 8505070554 841231 PDR ADOCK 05000327 R

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s ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT SEQUOYAH NUCLEAR PLANT 1984 TVA/NUC PR/RH

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CONTENTS Page

' List of Tables...........................

iii List-of Figures iv Int roduction 1

Atmospheric Monitoring.

11 Terrestrial Monitoring..

25 Reservoir Monitoring 45 Quality Control 59 Data Analysis ~

.59 Conclusions 59 I

i l

11

m List of Tables Page Table 1.- Environmental Radioactivity Sampling Schedule.

3

-Table 2 - Atmospheric and Terrestrial Monitoring Station Locations - Sequoyah Nuclear Plant.

4 Table 3 - Detection Capabilities for Environmental Sample Analysis S-Te.ble 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 Fallcut.

16 Table 9 - Radioactivity in Charcoal Filters.

17 Table 10 - Radioactivity in Atmospheric Moisture.

18 Table 11 - Radioactivity in-Milk..

29

~ Table 12. Radioactivity in Vegetation.

30 Table 13 - Radioactivity in Soil.................

31 Table 14 - Radioactivity in Well Water.

32 Table 15 - Radioactivity in Public Water Supply 33 Table 16 - Environmental Gamma Radiation Levels 34 Table 17 - Radioactivity in Cabbage 35 e

. Table 18 - Radioactivit7 in Corn.

36 6

Table 19 - Radioactivity in Green Beans 37 Table 20 - Radioactivity in Potatoes.

38 o

Table Radioactivity in Tomatoes.

39

' Table 22 - Radioactivity in Turnip Greens 40 Table 23 - Radioactivity in Poultry 41 Table 24 - Sampling Schedule - Reservoir Monitoring

. 47 Table 25:- Radioactivity in Surface Water, Total.........

48 Table 26 - Radioactivity in White Crappie (Flesh) 49 Table 27 - Radioactivity in Channel Catfish (Flesh) 50.

Table 28 - Radioactivity in Smallmouth Buffalo (Flesh)......

51 Table Radioactivity in Smallmouth Buffalo (Whole)......

52

~ Table 30 - Radioactivity in Sediment.

53 Table 31 - Radioactivity in Shoreline Sediment.

54 Table 32-- Radioactivity in Clam Flesh..............

55 Table 33 - Radioactivity in Clam Shell..............

56 e

111

List of Figures Page Figure 1 - Tennessee Valley Region.

10

' Figure 2 ~- Atmospheric and Terrestrial Monitoring Network 19 Figure 3

. Local Monitoring Stations - Sequoyah Nuclear Plant 20 Figure 4 - Sequoyah Nuclear Plant - Site Monitoring Stations.

'21 Figure 5 - TLD Locations - Sequoyah Nuclear Plant 22 Figure 6 - Annual. Average Gross Beta Activity in Air Filters, Sequoyah Nuclear Plant 23 Figure 7 - Annual Average Gross Beta Activity in Drinking Water, Sequoyah Nuclear Plant 42 Figure 8 - Direct Radiation Levels, Sequoyah Nuclear Plant.

43 Figure 9 - Direct Radiation Levels, Sequoyah Nuclear Plant, 4-Quarter Moving Average.

43 Figure 10 - Reservoir Monitoring Network - Sequcyah Nuclear Plant

........-57

. Figure 11 - Annual Average Gross Beta Activity in Surface Water, Sequoyah Nuclear Plant 15 8 iv

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT SEQUOYAH NUCLEAR PLANT 1984 Introduction The Sequoyah Nuclear Plant (SQN), operated by the Tennessee Valley Authority, is located on a site owned by TVA containing 525 acres of land in Hamilton County, Tennessee, bounded on the east by Chickamauga Reservoir (see figure 1).

The site is 12 miles (19.3 kilometers) northeast of Chattanooga, Tennessee, and 11 miles (17.7 kilometers) west-northwest of Cleveland, Tennessee. The plant consists of two pressurized water reactors; each unit is rated at 3,423 MWt and 1,171 MWe. Fuel was loaded in unit 1 on March 1, 1980, and the unit achieved criticality on July 5, 1980. Fuel was loaded in unit 2 in July-1981 and the unit achieved initial criticality on November 5, 1981. This report describes the environmental radiological monitoring conducted in 1984.

The preoperational environmental radiological 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 obse rved.

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

i Radiological Health (Office of Nuclear Power) and the Office of Natural Resources and Economic Development carried out the sampling program outlined in tables 1 and 24.

Sampling locations are shown in figures 2, 3, 4, 5, and 10.

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 Radio-logical Laboratory (WARL) located at Muscle Shoals, Alabama. Alpha and beta analyses were performed on Beckman Low Beta II, Beckman Wide Beta II, and Tennelec LB 5100 low background proportional counters.

Nuclear Data (ND) Model 6700 system, in conjunction with germanium detection systers were used to analyze the samples for specific gamma-emitting radionuclides. Specific analysis for iodine-131 in charcoal filters is performed using NaI(TI) well detection systems attached to single channel analyzers. TVA-fabricated beta gamma coincidence counting systems are utilized for the determination of 131 1 concen-trations in milk. Tritium determinations are made with Packard Tri-Carb 3255 or 4000 series liquid scintillation counting systems.

2 Data were entered in computer storage for processing specific to the analysis conducted. The data obtained by germanium detectors were resolved by the appropriate analyzer sof tware and the sof tware l

program HYPERMET.

I The detection capabilities for environmental sample analysis l

given as the nominal lower limits of detection (LLD) are listed in table 3.

All photopeaks found in germanium spectra were identified and quantified. Many of the isotopes identified by germanium spectral analysis are naturally occurring or naturally g2sRa, etc.

roduced radioisotopes, such as 7Be, 40K, zi2Bi, 214Bi, 212Pb, 214Pb, LLDs for additional radionuclides identified by germanium 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 WARL participates in the Environmental Radioactivity Laboratory Intercomparison Studies Program conducted by EPA-Las Vegas.

This program provides periodic cross-checks on samples of the type and radionuclide composition normally analyzed in an environmental radio-logical monitoring program. Routine sample handling and analysis procedures were employed in tb evaluation of these samples. The results received during calendar year 1984 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.

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I 3

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Table 1 BN Q N AL RAD,1 %.V AIS_Af9LJg4,8C M L{

Neevy Air Charroel Sele-Particle Atasepherte R6ver Wil Public Agustic Life statie. H etssa Et.tler.. rs tter, water telleul,. Mete,tur t So.8.1 Y?aalit1*a Milk wier Weyr Weter sad. mt Chettonoose W

W M

M A

N Dayton W

W H

M BW A

M Sale Creek V

W M

M A

Deley W

W M

M A

N Horthwoode W'

W M

M A

Volunteer Ordleence Works (Narrison)

W W

M M

A Berrison Bay V

V M

N A

Georgetown W

W M

M A

Chester Frost Park (formerly Namilton County Park)

W W

M M

A Work W

W M

M A

Site N W

W M

M BW A

Site SV W

W M

M DW A

Fere L Q

W M

F2re J Q

W Form IN Q

W hmM Q

W F;te Le M

W Fire Su M

W FIra 5m M

FIra EM M

Ftra Br M

F$rm C M

Chickamauga Reservoir M

g/3 l

E. 1. Dupont l

M Cleveland. TM y

C. F. laJustries M

f On 5!te Well (l)

F;rs Ma M

Finn S (Control)

M W

Fire B (Control)

M W

F:re C (Control)

M W

U = Weekly BW - Blweekly M = Monthly (every 4 weeks)

Q. Quarterly S = Sealannually A - Annually N

4 Table 2 ATMOSPHERIC AND TERRESTRIAL MONITORING STATION LOCATIONS SEQUOYAH NUCLEAR PLANT Approximate Distance Approximate Direction Sample Station From Plant From Plant Df-1 SQ, Southwest 0.75 Miles ( 1.2 kilometers)

SW l

L:(-2 SQ, Northeast 0.75 Miles ( 1.2 kilometers)

N l

PM-1 SQ, Northwoods 10.5 Miles (16.9 kilometers)

WSW l

l PM-2 SQ, Chester Frost Park, TN (formerly Namilton Co.~ Park) 3.75 Miles ( 6.0 kilometers)

W PM-3 SQ, Daisy, TN 5.5 Miles ( 8.8 kilometers)

W PM-4 SQ, Sale Creek, TN 10.5 Miles (16.9 kilometers)

N PM-5 SQ, Georgetown, TN 9.5 Miles (15.3 kilometers)

ENE l

PM-6 SQ,' Work, TN 4.5 Miles ( 7.2 kilometers)

NNE l

PM-7 SQ, Harrison Bay, TN 3.5 Miles ( 5.6 kilometers)

SE i-PM-8 SQ, Harrison, TN 8.75 Miles (14.1 kilometers)

SSW l

RM-1 SQ, Chattanooga, TN 16.75 Miles (27.0 kilometers)

SW l

(Control)

)

RM-2 SQ,-Dayton, TN (Control) 17.75 Miles (28.0 kilometers)

NNE I

Fara J 1.25 Miles ( 2.0 kilometers)

W Farm HW 1.25 Miles ( 2.0 kilometers)

NW Farm L 2.75 Miles ( 4.4 kilometers)

NNE Fara M 3.5 Miles ( 5.6 kilometers)

NNE Fara Ma 0.75 Miles ( 1.2 kilometers)

W

-Fara Le 3.0 Miles ( 5.6 kilometers)

S Farm SM 1.75 Miles ( 2.8 kilometers)

SE

{

Farm Su 3.25 Miles ( 5.2 kilometers)

SSE f

Fara EM 2.5 Miles ( 4.0 kilosaters)

N Farm Br 2.25 Miles ( 3.6 kilometers)

SSW Farm G 1.5 Miles ( 2.4 kilometers)

NNW j,

Farm B (Control) 43.0 Miles (69.2 kilometers)

NE f

Farm C (Control) 16.0 Miles (25.7 kilometers)

NE.

Farm S (Control) 12.0 Miles (19.3 kilometers)

NNE t

P l

Table 3 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS A.

Specific Analyse:

_ NOMINAL LOWER LIMIT OF DETECTV (LLD)*

Fish Air Vegegation Soil and Clam Flesh, Foods, Meat.

Particulates Charcoal Fallout Water and Criin Sediment

Plankton, Clam Shells

Poultry, Milk pC1/m3 pC1/m3 mC1/Km2 pC1/1 pC1/g. Dry pct /g. Dry pC1/g. Dry PCi/R. Dry pC1/Kgm. Wet pC1/1 Cross a 0.005 2.0 0.05 0.35 0.1 0.7 Cross B 0.01 0.05 2.3 0.20 0.70 0.1 0.7 25 3H 330 1311 0.01 0.05 895r 0.005 10 0.25 1.5 0.5 5.0 40 10 90Sr 0.001 2

0.05 0.3 0.1 1.0 8

2

• All LLD values for isoccpic separations are calculated by the method developed by Pasternack and Parley as described in HASL-300. Factors such as sample size, decay time, chemical vield, and counting efficiency may vary for a given sample; these vertations may change the LLD value for the given sample. The assumption la made that all samples are analyzed within one week of the collection date. Conversion factors:

2 7

1 pCi - 3.7 x 10 Bq; I rCi = x.7 x 10 Bq.

w l

l

.s Table 3 DETECTION CAPABILITIES FOR ENVIRoletsitfAL SAMPLE ANALYSIS B.

Camms Analyses NOMINAL IAWER LIMIT OF DgTETION (LLD)

Air Water Vegetation soil and

. Clan flesh Foods,(tomatoes - Meat and particulates and milk and grain sediment Fish and plankton Clan shells potatoes, etc.)

poultry e.

pCi/m3

_ pC1/1 pC1/a, dry pC1/a, dry pct /s. dry PC1/a. dry pC1/a. dry pct /Ka wet pC1/Ka. est NaI* Ge(L1)**

NaI Ge(L1)

Nel Ce(Li)

Nat Ce(L1)

NaI Ce(L1)

Na1 Ce(L1)

Mal.Ce(L1)

Mal Ce(L1) NaI Ce(L1) 161 166Ce 0.03 38 0.55 0.35 0.35 0.35 38-90 0.06 0.35 0.06 33 40 166Ce 0.02 33 0.22 0.06 0.10 0.56 0.60 0.10 60 44 200 90' 51 r 0.07 0.03 60 44 1.10 0.47 0.60.0.10 0.60 C

1311 0.01 0.01 15 8

0.35 0.09 0.20 0.02 0.20 0.02 0.07 0.20 0.02 15 8

50 20 103 106 u 0.04 40 0.65 0.45 0.45 0.45 40 150 R

to6 u 0.03 40 0.51 0.11 0.11 0.74 0.11 40 90 R

136Cs 0.01 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 137Cs 0.01 0.01 10 5

0.20 0.06 0.12 0.02 0.12 0.02 0.08 0.12 0.C2 10 5

40 15 95 r-Nb 0.01 10 0.20 0.12 0.12 0.12 10 40 2

95 r 0.01 10

. 0.11 0.03 0.03 0.15 0.03 10 20 2

95Nb' O.01 5

0.05 0.01 0.01-0.07 0.01 5'

15

'59 o 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 C

56Mn 0.02 0.01 10 5

0.20 0.05 0.15 0.01 0.15 0.01 0.08 0.15 0.01 10 5

40 15 65 p 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 2

~

Seco 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 koK 0.10 150 2.50 0.90 0.90 0.90 150 400 160 a-La 0.02 15 0.68 0.15 0.15 0.15 15 50 E

!=osa 0.02 25 0.34 0.07 0.07 0.30 0.07 25 -

50 theta 0.01 7

0.08 0.02 0.02 0.10 0.02 7

15

• The NaI(TI) LLD values are calculated by the method developed by Pasterna$ and Harley as described in NASL-300 and Nucl. Instr. Methods 91, 533-40 (1971). These LLD values are expected to vary depending on the activities of the components in the samples. These figures do not-represent the LLD values achievable on a given sample. Water is counted in a 3.5-1 Marinelli beaker. Vegetation, fish, soil, and sediment are counted in a 1-pint container as d y weight. The average dry weight is 120 grams fot ves(,tation and 400-500 grams for soil sediment and fish. Heat and poultry are counted in a 1-pint container as dry weight, then corrected to wet weight using an average moisture content of 70%. Average dry weight is 250 grams. Air particulates are counted in a poll 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 seconde. All calculations are performed by the least-squares computer program ALPHA-M. The assumption is mode that all samples are analyzed within one week of the collection date.

• • The Ce(L1) LLD values are calculated by the method developed by Pasternack and Harley an described in NASL-300. These LLD values are e fected to vary depending on the activities of the components in the samples. These figures do not represent the LLD values achievable on given.amples.

Water is counted in either a 0.5-L or 3.5-L Marinelli beaker. Solid samples, such as soil, sediment, and clam shells, are counted in a 0.5-L Marinelli beaker as dry seight. The average dry weight is 400-500 grams. Air filters and very small volume samples are counted in petri dishes centered on the detector endcap. The counting system consists of a ND-6620 multichannel analyser and germantiss detector having an ef ficiency of 20 percent. 1he counting time is normally 4-15 hours. All spectral analysis is performd usina the software promram HTFERMET. The assumption is made that all samples are analysed within one week of the collection date.

2 Conversion factor: 1 pCi - 3.7 x 10 Bq.

x 3

TABLE 4 RESULTS OBTAINED IN INTERLABORATORY COMPARISON PROGRAM A..

Air Filter- (pCi/ Filter)

Gross Alpha Gross Beta Strontium-90 Cesium-137 EPA value TVA EPA value TVA EPA value TVA EPA value-TVA Date (i30) h

( 30)

Am (i30)

AA (t33)

Avg.

11/83 19i9

<1"

'50 9 40*

1513-16 21 9 20 3/84 15 9 18 51i9 60 21 3 20 11 9 10 b

j 8/84 17i9 17 51i9' 60 18 3 N/A 15:9 15 B.

Tritum in Urine (pCi/1)

Date EPA value ( 3c)

TVA Avg.

2/84 2383 608 2466 11/84 2012 598 2047

a. Sample fouled in preparation. Procedure modified to prevent recurrence,

b. Lost in analysis.

t i

O as YABLE 4 (Continued)

RESULTS OSTAINEP TN INTERIABORATORY COMP /RISolt PROGRAM C.

Radiochemical' Analysis of Water (pCi/1)

Cross Alpha Gross Beta St ront ium-89 Strontium-90 Tritium lod ine-131 EPA Falue TVA EPA value TVA EPA value TVA EPA value TVA EPA value TVA EPA value TVA" A1 (130)

Am Date (230) h (t30) h (130) -

h (t30)

_h

'(130) 1/84 1019

'10 1229 15 3619 39 24t3 23 l

3/84 5t9

-6 2019 20 35082630 - 3580 620.8 6

4/84 -

4 619 6

2529 32 523 5

i 5/84 329 30812622 2770 6/84 7/84 6t9 6

1319 16 28171617 2607 34210' 36 8/84

'1619 12 34t9 41 19t3 18 9/84' 529 5'

28102617 2517 10/84 10/84*

14t9 11 64 2 )

60 1129 12 1213 13 11/84 729 8

2019 22 31822624 3400 36210 33 12/84 D.. Gamma-Spectral Analysis of Water ' (pci/1)

Chromium-51 Cobalt-60 Zine-65 kuthenium-106 Cecium-134 Cesium-137 EPA value TVA EPA value TVA EPA value TVA EPA value TVA EPA value TVA EPA value TVA Date (13c) h (230) h (130) h (t30) h (230) h.

(23s? _ h 2/84 4019

<44 1019 11 5019 50 6129 53 3129 29 1619 15 6/84 6619 72 3119 32 63t9 66 2919

<40 4719 44 3729 27 10/84 4029 43 2029 22 14719 151 4719 48

- 31t9 29 2429 26 229

<5

'.29 16 10/84*

14t9 17

c. Iaboratory performance evaluation study

r..

.+,.

l

. TABLE 4 (Continued)

RESULTS OBTAINED IN INTERIABORATORY COMPARISON PROGRAM E.

Foods (pC1/kg, Wet Weight) d Stront ium-89 Strontium-90 Todine-131 Cesium-137 Pot assium-40 EPA value TVA ETA value TVA EPA value TVA EPA value TVA EPA value TVA Date (130) h (t30) g (130)

Ag (130) -

Avg.

(230)

Avg.

'1/84 3429 40

2013, 19 20110 20 2019 21 27301236 2670 7/84 2529.

N! ','

2013 N/A*

39t10 40 2519 26 26052226 2624 F.

Milk (pC1/1)

S trontiin-89 Strontium-90 Iod ine-131 Cesium-137 Potassium-40 EPA value TVA EPA value. TVA EPA value TVA EPA value TVA EPA value TVA Date (130)

Avg (130)

Ayg.,

( 130)

Avg.

(130)

Avg.

(130)

Avg.

[

3/84 6t0.3 6

h 6/84 2519 24 1723 18 43110 39 3529 34 14961130.

1483 10/84 22 9 26 1613 15 42t10 40 3229 30 15172132 1563

d. Values reported as og K/kg.

e. Lost in sample preparation.

f. Values reported as og K/1.

dB t

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ytowvus D. f).

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11 Atmospheric Monitoring The atmospheric monitoring network is divided into three - subgroups. Two local air monitors are located within the plant boundary. Eight perimeter air monitors are located at distances out to 10.5 miles (16.9 kilometers) from the piant in the towns of Sale Creek, Daisy, Northwoods, Harrison,' and four other populated areas. The remote air monitors used as control or baseline stations are located at distances out to 17.75 miles (28.6 kilometers) from the plant in the towa of Dayton and the city of Chattanooga. See figures 2, 3,. 4, and 5. At each monitor, air is continuously pulled through a 'HollingsworthandVossLB5211g/ min). lass fiber particulate filter at a ~ 3 flow rate of 3-ft / min (0.085 m In series with, but downstream 4. -of the particulate filter, is.a charcoal filter used to collect iodine. Each monitor has a collection tray and storage container to collect i ' -rainwater on a continuous basis, and a horizontal platform covered with gummed acetate to catch and hold heavy particle fallout. Hoisture-is collected from the atmosphere at each local monitor and at one remote monitor.and analyzed'for tritium. ~ Each of the local and perimeter air monitors is fitted with 4 a GM tube-that continuously scans the particulate filter. The disinte-gration rate of the atmospheric radioactivity is continuously recorded at each station. The data from the two local monitors and the four< perimeter monitors located within approximately five miles of the l plant are radiotelemetered into the plant control room. 5 Table 5 presents the maximum permissible concentrations (MPC) specified in 10 CFR 20 for nonoccupational exposure. Air Filters Air filters are collected weekly and analyzt.1 for gross beta activity. Analyses are not performed until three days after sample . collection. The samples are composited monthly for analysis of specific gamma-emitting radionuclides, and. quarterly for 89Sr and 90Sr analysis. The results are presented in table 6. During this reporting period, .seven weekly air filters were not callected, five because of equipment l, malfunction, and two because of flood conditions. Three weekly air filters were off the filter holder and were unusable. One monthly i composite for gamma analysis was not obtainable because of reoccurring . pump problems at one station. 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 i. 1971-19'd4 are presented in figure 6. Increased levels due to fallout from. atmospheric nuclear weapons testing are evident, especially in '1971,-1977, 1978, and 1981. - These fluctuations are consistent with data from radiological monitoring programs conducted by TVA at non-operating nuclear power plant construction sitec. ~ q"r 4- ,,+weg w y-rv-s-ty

• --m--

-g-enig, 0 m.

12 Rainwater - Rainwater-is collected monthly and analyzed for gross beta activity, specific gamma-emitting isotopes, strontium, at.d tritium. I During this. reporting period, one sample was not available for any I analyses ~because of equipment failure, three samples were not available due to lack of rain, and one sample was inadvertently discarded before analysis. For the gross beta analysis, a maximum of 500 ml of the sample is boiled to dryness and counted. A gamma scan is performed on a 3.5-liter monthly sample. The strontium isotopes are separated chemically and counted in a low background system. The results are shown in table 7. Heavy Particle Fallout The' gunned 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. Charcoal Filter 1-Cha'rcoal filters are collected weekly and analyzed for radioiodine. During this' period, five samples were not obtained because of equipment malfunction and six samples were inadvertently-lost or destroyed during collection and were unusable. One sample was inadvertently destroyed during processing. Flood condi-tions prevented L collection of two samples. The filter is counted in a single channel analyzer system. The data are shown in table 9. Atmospheric Moisture An atmospheric-moisture collection device containing a molecular sieve is located at each local monitor and at one remote monitor. Samples are taken every other week, the moisture driven off the molecular sieve, collect'ed in a cold trap, distilled, and counted for tritium content. The results are shown in table 10. During this reporting period, eleven samples were not collected because of equipment malfunction. One sample collected was not usable because of insufficient-volume, one sampler could not be installed because of flood conditions, and on two occasions samplers'were not installed at any location. ) i O 1 c..-... -.,.-n,.

13 Table 5 + s MAXIMUM PERMISSIBLE CONCENTRATIONS FOR NONOCCUPATIONAL EXPOSURE MPC In Water In Air pCi/1* pCi/a?* Alpha 30 Nonvolatile beta 3,000 100 Tritium 3,000,000 200,000 337 Cs 20,000 500 3*3'306Ru 10,000 200 3Cc 10,000 200 '5Zr 'SNb 60,000 1,000 'Ba 3La 20,000 1,000 isa - 300' 100 y '5 Zn 100,000 2,000 5'Mn. 100,000 1,000 Co' 30,000 300 Sr 3,000 300 Sr 300 30 i; 53 Cr 2.000,000 80,000 3Cs 9.000 400 5'Co 90,000 2,000

• 1 pCi = 3.7 x 10-2 Hq.

e

TABLL $. RACI0 ACTIVITY IN AIR FILTER PCI/M(3) - 0.037 EC/P(3) Y NAME CF FACILITY.jiGJ0Zit........................................._LOCEET NV. 10-))[g]23.____....... . LOCATION OF FACILITY..digILIgg.. __.... __.e...IEbbt33EE........__.... R E F 0 8 T I N G P t 910 D 1213.._ __... _ _....... TYPE AND LOWER LIMIT SLL C 0 r.T E L L. T.*fE4 CF J LCCATIO45 NONRCOTINE TOTAL NUMsER CF INCICATCR LCCAgICNS (QC&I'lQb.g))d.g[QU21I.{L* WAL gi&d).. OF ANALYSIS '0ETECTI0h* MEAN (F) NAPE FEAN (F Mia 4 (Fh Rf8CRTED ..E18E08550 ..iLLdl.... ..... _ _ S 6 3 2 b_ _ _.. DISIASLt_AsG.Q1BECIlDh.....!!bstI... ...E3Ukit...'.... Ti!!bitt13IS.. GR3$5 BETA 0.C10 C.02( 6SC/ 511) SALE CREEK,.TN 0.02( 45/ 4b) 0.02( ?v/ 1C3) 614 C.01-0.05 10.3 MILES A 0.L1-- 0.0. 0.01-C.04 GA"MA (GELI) "4 ~ 155 K-40 NCT ESTA6 C.cet c2/ 1i9) DAI5y,.Th C.C2( 1/ 13) 0.J2( tc/ 26) C.0G-0.04 5.5 MILES w 0.C1-0.03 3.0a-C.34 FB-212 NOT ESTAS C.udt 31/ 129) LP2 NCRTMEAST 0.00( 2/ 13) 0.GJC 5/ :) C.CG-C.CC 0.75. MILES N C.CO-J.03 0.0c-C.CC BE-7 0.050 C.C7( S2/ 129) COLNTT PARK, TN 0.C7( s/ 13) 1.07( 19/ ;23 C.05-0.10. 3.75 yILES Sk O.C6-0.10 C.35-C.11 TL-206 NOT ESTAB C.CC( 28/ 129) NORTHWCOGS) TN 0.C0( Si 13) 0.JLC 3/ 2e) C'.00- _. 0.C0,, 19 5 MILES NSh -C.CO-0.J0 .0.00-C.uG .C.CC( 10/ 129) NOR1HWCODS) Th 0.C1C 1/ 13) 0.00( 2/ 23) ESTAB AC-228 NOT C.CO-0.01' 1C.$ MILES dSw 0.C1-C.01 0.00-C. 31 PA-234M NCT ESTAs C.21( 1/ 129) LF7 h0RTMEAST 0."21 t 1/ 13) 2e V=LLES <LL C '. 21 - 0.21 3.75 hILES N C.'21 - C.21 SR 89 0.005 . 4C VALUES <LLO 3 VALLES <LL 45 AN ALY SIS PERFORMED 40 WALuc5 <tLD a VALLE) < LLC $R 90 -0.001 48 ANALYSIS PERFORMED o. 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).

TABLE 7 RA3!3 ACTIVITY IQ R AIN 4TER 'CI/L - 3 037 80/L NAML 3F FACI.ITY_1[12Q1AH LGCATION ur F ACILI f f MAML(lEN _______________liMML11[E DOCKrf NO._11-121tig8 _____d' REPORTING PERIOD _11gi_ TYPE AN3 LOWo* LIMIT ALL CONTROL' NUMBER OF TOTAL NJ4BER CF .- INDICAT3R LOCAgI34S. (QqiTLQ1_WITH 41gHggT_i332i(_g[A1 L3CATIO1)S N34 ROUTINE 3F AN ALYSIS DEsICTION

1. EAN ([3 NAME-

.MEAN (F# MEAN f r REPORTED b __PE9FORMiQ __ik(21____. RA11E__ _ _ 211[11EE_i12.QLi[ Ell 21 R Ag}{b ggggg_ g{gggggg{g{g__ JR3SS 8 ETA 4.300 3.72( 43/ 126) SALE CREE 4, TN 4.52( 4/ 13) 4.P7f 17/ 25) '151 2 34-9.59 10.5 MILES N 3.36-5.91 2.48-9.54 '149MA'(GELI) 151 (-40 NOT LSTAB 17 16( 11/ 126) LM2 43RTHEAST 41.92( 1/ 12) 19.34( 3/ 253 2 23-41 92 0 75 91LES N 41.92-41.92 8.65-25.97 91-214 NOT LSTAB 5.73t 63/ 126) SALE CREEK, TN S.99( 5/ 13) 1.75( 12/ 25) 0.33-17.96 10.5 91LES N 0 26-16.30 0 38-11.10 83-214 NOT LSTAB 4.42( 32/ 126) HARRISDN, TN 12.52( 1/ 11) 4.5C( 6/ 25) 0.1?- 13.5' 8.75 MILES SSW 12 52-12 52 2 15-12.30

1. 3-212 FOT LSTAB 1.58(

29/ 126) C304TY '4RK, TN 2.90( 4/ 13) 1.15( 8/ 25) 0.30-7.70 3.75 MILES SW 0.76-7.70 0 26-3.14 3E-7 NOT LSTAB 49.06( 35/ 126) 1ARRISON BAY, TN 59.92( 1/ 13) 47.97( 12/ 25) 21 13-79.20 3.5 MILES SE 59.92-59.92 25.35-69.02 i SR 89 10.000 125 #4 LUES CLLD 25 VALUES CLLD 151 ANALYSIS PERF3RdE3 S4 90 d.300 125 d4 LUES CL.) 25 VALJES <LLD 151 nNALYSIS PERF3R9E3 IRITIUM 33u.000 345.22( 1/ 126) COUNTY PARK, TN 345.22( 1/ 13) 25 VALUES CLLD 151 346 22-345 22 3 75 91LES SW 346.22-346.22 l G c. Nominal Lower Limit of Detection (LLD) as described in table 3. b. Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (F).

TABLE 8 RACI0 ACTIVITY Ih HEAVY PARTICLE FALLOUT MCI /sM(2) - 370C0000.00 EQ/KM(21 NAME OF FACILITY.3EGWGI&g.....,,,............................... DOCKET NO. 30-32Zs328............ $l LOCATICu 0F FACILITv..MiBILIGM..................IEbbE33EE............. REFORTING PERICO.1304................. CONTROL NUMBER OF TYPE AND LOWER LIMIT ALL LQGAIIQh MIIn.b1Gus3I.8hhW4L. BEAM... LOCATIONS NChRCUTINE l TOTAL NUMBER OF INCICATCR LCCgTICNS ....... B & W G E.g DI3IAbGE.AbG.QIREGIIGN..... RANGE.[.... MEAN (F NAME MEAN (F MEAN (F) REPORTED i OF ANALYSIS DETECTIch* .. 8ANGE......... HEA3WhitENI3.. ..EEEEQBEED . 1LL:1.... GROSS SETA 0.C50 C.16( 13C/ 130) LF2 NORTMEAST 0.31( 13/ 13) 0.16( 25/ 26) 156 C.C5-1.54 0.75 MILES N 0.Cd-1.54 0.05-0.52 Nominal Lower Limit of Detection (LLD) as described in Table 3. Traction of detectable measurements at specified locations is indicated in parentheses (F). a. b. Mean and range based upon detectable measurements only.

TA3LE 9 4ADI3ACT!WITY IN CHARCIAL FILTE S: 20!/9(3) - 0.037 80/9(31-NAML OF F AC I. I TY_1[],MRY A H DOCKET NO._gg-rig Mt LOCATION of FACILIIf _$i![([QR_.. _____...... 1[H[11[E ~ REP 00fING *ER103_1111. TYPE AMD LOWL9 L IMIT ALL 00NTR3L NJ4BER OF 3F ANALYSIS DE s EC T ION, 4EAN ({l Mk4E MEAN i LOCATIO1S' NON40UTINE TOTAL NU18ER OF INDICATOR LOORTIO4S (Qgil[q3,g!TH H{gif{SY ANgyil MEAN MEAN({r 4EPORTED __EL!LEEE1El __ik.2L _____.liMEE---- -- 211Li1EE_112_2L1EE11E1 liEEE_

• IRE' ELiME1E511_

133INE-131 u.010 0 02( 13F/ 509) WJR4, TN 0 02( 8/ 51) 0.018 29/ 102) 610 0.31 - 3.33 4.5 MILES NNE 0.01-0.03 0.01-0.03 O 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).

7-T ABLE 10 RADI0 ACTIVITY IN ATMOSPHERIC MOISTURE 0.037 BQ/P(3) PCI/M(3) hAME CF FACILITY.!ECWGIAU............__.....__.................. JCCKei NO. 1Q-32IA323............ ,, LOCATION OF FACILITY._gegILIQ!i........ __.......I16b133:1............. kEP04 TING P!RICD.12gy,,,,,...,,,,,,,,, TYPE AND LodER LIMIT ALL CONTFOL NU*9ER OF TOTAL NUMBEA CF INDICATCR LOC 4TIONS LQCAI;Gh.WIIU.g1GdE31_&hhgAL.dgab LOCATIONg NCh40uTIhE OF ANALYSIS DETECTION

• MEAfd (FT NAPE MfAN ( F T..
• f 4 '. (F)

RfPCRTED ..estegasta . 1LLa1.... ......_sasst.h...... aislaust.abc.alsacIIou..... tat.;tA... ...E a n t..._ _... - nasuste 3Is.. h TRITIUM NOT ESTAS 1.8J( 35/ 43) LM2 NCRTHEAST 2.47C 17, 21) 0.tet 12/ 16) 59 C.C3-14.34 0.75 MIL!S N 0.19-14.34 0.12-2.72 i a. Nominal Lower Limit of Detection (LLD) as described in Table 3. b. Mean and range based upon detectable measurements only. Traction of detectable measurasents at specified locations is indicated in parentheses (F).

l 19 i Figure 2 ATMOSPHERIC AND TERRESTRIAL MONITORING NETWORK ATMOSPHERIC AND TERRESTRIAL SAMPLES COLLECTED AT EACH STATION O LOCAL MONITOR @ PERIMETER MONITOR $ REMOTE MONITOR DAYTON N R M-250 SALE CREEK 450 PM SSQ 630 SOODY e ORGETOWN O PM 360 WORK OA6YJ LM*250 LMISO PM-730 l p g.,$ g PM 250 EVELAND OM MOUNT N SPM-8SQ RMt CHICKAMAUSA DAM l J go giggs F CHAT TAN 00GA IS MILES l LOOKOUT l MOUNTAIN N l 20 MILES l L

20 FIGURE 3 S UO N CLEA Pd l\\ ^h x )/ i A [ A q P A f g 0 1 2 f O Air' Monitor Score of M.ies 0 TLD Station Milk Sampling Station O O

w.t O e WSw-o gg,,, www. e f (.pe N N. N w.8 ? r 9 l o e ,Q e ,,N C' / V l' N ,8 ,rf( p J c% ~" a e,> .a 4 x't.. E x ssw-i / / \\ \\ e_ ( OO I \\ N i D A -j w-s f / W N. (Q G q / C-j .-7 Q] ./~%. gy>;- a g__~dk -y/ . to u ~ m. ^" .p __ _ ig, _, m SEQUOYAH NUCLEAR PLANT SITE MONITORING STATIONS S

Figure 5 8 7'.' ,g Ai - > - y.,',/ in 1'. -. *g: ~.... % 3. .. e 6 . x,,.y..% ~- A... >..., 1/ - ~ .s r.> /* L x.s h,g. l'.a. ~ '.. _., ', 1- .. - +.. 8 . 4

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Figure 6 I I I I I I I I I l l l l l l l l g AffiUAL AVERAGE ss BETA ACTIVITY .30 E AIR -ILTERS i 3 a UDYAH I!UCLEAR PUWT s i "3 u u u .25 5 "c &O I .0 ~ I f Preoperational Phase Operational Phase l .15 l I .10 .05 U 1 1971 1973 19 4 197.2 197 197 1978 1979 1 198 198 1 1 P O

a. Data not collected in 1974.

g.._.,...y.. s_.. E p l.- I d 5 0a e 1' ? k k 4 I B. -8 5 $^ T i I - i t a, k '4 l-i.-i ' t 4-7 I. i i-p f l 1 i pi 1. 1 l-4. I I s {- x l 5 4 I i. k 1-t s -m h' *, 4 4 e a. p 1-: h i.'n.^ s e g g-('b. i ~ i i. 1' rr ,n'- j 9 si - .]1. O. /. --. 4 [ I. b o p. C........

25 Terrestrial Monitoring Terrestrial monitoring is accomplished by collecting environ-mental media at locations within the general area of the plant for indicators and at locations remote to.the plant for controls. In addition.to milk, samples include vegetation, soil, ground water, public' water, food crops, and poultry. Environmental gamma radiation levels are determined by strategic placement of thermoluminescent dosimeters. Once each year, a land use survey is conducted to determine census and location of milk producing animals. Land Use Survey The routine land use survey was conducted in the summer of 1984'. Results of the survey identified one farm which should be ' included in the sampling program. The farm is. located east of the plant at a distance of 1.7 miles. This location, with only one milk ' producing animal, will be added to the sampling program as a monthly vegetation sampling site. .It was' concluded from an evaluation of the survey results that the small changes in land use have not increased the. projected doses to individuals in the area and that appropriate sampling was conducted. Milk Milk samples were routinely collected from four indicator locations (two of which are commerical daries), and from three control locations. Raw milk was analyzed weekly for iodine-131 and monthly - for gamma-emitting radioisotopes and strantium content. Table 11 summarizes the analytical results. During this reporting period, 18 samples were not available for collection, resulting in.18 iodine, 11 . gamma, and 6 strontium analyses not done. Three other locations added to the sampling program as a. result of the 198312nd use survey intermittently provided goat milk samples. At one of these locations, the owner removed the goats from the area (with milk samples unavailable, vegetation samples were collected monthly). This location was subsequently removed from the sampling program with a Special Report submitted to the Nuclear Regulatory Commission on December 10, 1984. Analytical data of milk ' samples that were collected are included in table 11. I' During a routine comparison between SQN technical specifications and the SQN Offsite Dose Calculation Manual (ODCM), a discrepancy was revealed between analytical frequency requirements and actual ODCM analytical frequency-for milk samples. The technical specifications specified that each milk sample routinely receives a gamma scan for isotopic identification. The ODCM specified the gamma scan on milk samples to be performed at least once per 31 days. The ODCM was corrected. TVA immediately began to perform a gamma scan on each milk - sample collected for SQN in accordance with the technical specification - requirement. TyyMpeg*-9++ mea < w'->4- -N T -'I----m'

• "W-"-7

'T 4-"P'-"

26 As has been noted in previous reports, the levels of 90Sr in i milk samples from farms producing ~ milk for privata consumption only are up to six times the levels found in milk from commercial dairy ~ farms. Samples of feed and water supplied to the animals were analyzed in 1979 in an' effort to determine the source of the strontium. Analysis .of dried hay samples indicated levels of SO Sr_slightly higher than those encountered in routine vegetation samples. Analysis of pond water indicated no significant strontium activity. This phenomenon was observed during preoperational radiological monitoring near Sequoyah and Bellefonte Nuclear Plants at farms where only one or two cows were being milked for private consumption of the milk. It is postulated that the feeding practices of these small farmers' differ from those of the larger dairy farmers to the extent that fallout from atmospheric _ nuclear weapons testing may be more concentrated in these instances. Similarly, Hansen, et al., reported an inverse relationship between the levels of 90Sr in milk and the . quality of fertilization and land management." Vegetation ' Vegetation samples were collected quarterly from four farms from which milk samples were collected and analyzed for gamma-emitting radionuclides and strontium. Monthly vegetation sas;. ling was conducted -at six additional locations and at three control faa:s. The monthly samples were analyzed for gamma-emitting radionuclides with quarterly analyses for strontium. Approximately 1-2 kg of grass was broken or cut at ground level and returned for analysis. Efforts were made to sample vegetation that was representative of the pasturage where animals graze. Table 12 gives the results obtained.from the laboratory . analyses. Soil Soil samples were collected annually near each monitoring - station to provide an indication of any long-term buildup of radioacti-vity in the environment. Two additional samples were taken at one of the control stations in conjunction with the Watts Bar Nuclear Plant radiological monitoring program. An auger, or " cookie cutter" type sampler was used to obtain samples of the top tw inches (5 cm) of soil. These samples were analyzed for gross beta activity,. gamma-emitting radionuclides, 89Sr'and Sr. The results are given in table l 90 13. i Groundwater i An automatic sequential-type sampling device collected groundwater from a well downgradient from Sequoyah Nuclear Plant. A composite sample from this well was analyzed for gross beta activity i

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

.-.-__-_.,__m.,- ,_r,. - -,, -- - -. - - - -. - - -. 2

27 and gamma-emitting radionuclides monthly, and composited quarterly for determination.of tritium. A grab sample was also taken from a farm near the plant, and a control well across the river from the plant. The results of the analysis of well water are shown in table 14. During this reporting period, one sample for gross beta activity and gamma-emitting radionuclide analysis was not collected due to personnel error. Public Water i Potable water supplies taken from the Tennessee River in the vicinity of Sequoyah Nuclear Plant were sampled and analyzed monthly for gross beta and gamma-emitting radionuclides. Tritium, 89Sr, and 90Sr concentrations were determined in quarterly composite samples. The first potable water supply downstream from the plant is equipped with an automatic sampler with composite samples analyzed monthly. The results are shown in table 15. During this reporting period, one sample was not collected because of equipment malfunction, and one sample was inadvertently destroyed during analysis. Figure 7 shows the trends in gross beta activity in drinking water from 1971 through 1984. The annual averages reported in 1984 are consistent with the patterns established in the preoperational phase of the monitoring program and are slightly lower than levels reported in surface water samples (figure 11). Environmental Gamma Radiation Levels Bulb-type Victoreen manganese-activated calcium fluoride (Ca2F: Mn) thermoluminescent dosimeters (TLDs) were placed at 16 stations around the plant near the site boundary, at the perimeter and remote air monitors, and at 22 additional stations approximately 5 miles ~from the site to determine the gamma exposure rates at these locations. The dosimeters, located within energy compensating shields to correct for energy dependence, are placed approximately one meter above the ground, with three TLDs at each station. They are annealed and read with a Victoreen model 2810 TLD reader. The values are corrected for gamma response, self-irradiation, and fading, with individual gamma response calibrations and self-irradiation factors determined for each TLD. The TLDs are exchanged every three months. .The quarterly gamma radiation levels determined from these TLDs are given in table 16, which indicates that average levels at onsite stations are approximately 2-5 mR/ quarter higher than levels at offsite stations. This is consistent with levels reported at TVA's nonoperating nuclear power plant construction sites where the average radiation levels onsite are generally 2-6 mR/ quarter higher than levels offsite. The causes of these differences have not been completely isolated; however, it is postulated that the differences are probably attributable to combinations of influences, such as natural variations in environ-mental radiation levels, earth moving activities onsite, the mass of 4 concrete employed in the construction of the plant, and other undetermined influences. f 1-i 9

n. i &;.s 4 2 i R: - s. .j .Qocs h t 3 D.. E . w . :.; >:~- .. = c ^ W. J b. e. t 4.8 - = Cd ..) c.,. T 1 . i. i,. %. f -s g. .J N 7 g, 3 y - ,, s ^: l 28 /,.,- A, '. y.. .5 Figure 8 compares plots of the data from the onsite or site e ~. boundary stations with those from the offsite stations over the period N.,lJ - b from 1976 through 1984. To reduce the variations pre. ent in the data .,f g $ j's sets, a four-quarter moving average was constructed for 'ach set. . g. Figure 9 presents a trend plot of the direct radiation levels as

!W

'? defined by the mving averages. The data follow the same general trend as the raw dr.ta, but the curves are moothed considerably. + M[f} " h .4i _;g

f[],c[C' Prior to 1976, measurements were made with less sensitive dosimeters, and consequently the levels reported in this phase of the A~

t preoperational monitoring program are 1-2 times the levels reported p[T(A.' E N herein. Those data are not included in this report. ... _.. m Food Crops and Poultry ..M.c h.c .- + Food crops and poultry raised in the vicinity of SQN were f fy.. sampled annually as they became available during the growing season. 5l#g' During this sampling period, samples of cabbage, corn, green beans, ' h.afi potatoes, tomatoes, and turnip greens were collected and analyzed for (? "A s gross beta and specific gamma-emitting radionuclides. Poultry samples W7 were collected and analyzed for grossebeta activity and gamma-emitting K Q} radionuclides. The results are given in tables 17 through 23. F:3 ': ' ~ v; - stj.; -p J 'w r ..c s I ..g.7. .. ; \\,. e f -7 '

pi

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! i 2.5

1 -i a TABLE 11 RADICACTIVITY IN MILK PCI/L - 0.037 EQ/L NAME CF FACILITY.s!2WGI&U.....................__.....__......... OCCKET NO..}Q-]2Zg]2d............ LOCATICN OF FACILITY..didILIQs.........__....__.IEbbf33E!............. REPORTING PERICD_1236................. TYPE ANC L0aER LIMIT .9 L L i CONTRCL NLP6ER 05 TOTAL NUM8Ea CF IN6ICATOR LOC {TICNS LQC&IIQs.dlld_blid!!I.dhdWaL.EllW... LCCATIONS NCNRCUTINE ..e seaseta ..tLLca..__ ...s a b s t.6_..... oIszasceshc.oIsscIzos.....aanse.f (g)b sgego7sg OF ANALVSIS DETECTION" MEAN (Fr NAPE MEAN (F MEAN ...aasse_____.__. ecasustecsIs__ ICOINE-131 0.500 2 VALUES <LLO 151 VALLES < LLC 373 u. LYSIS PERFORPED GAMMA (GELI) 149 CS-117 5.000 7.29C 7/ 85) SUTTON FARP 9.97( 2/ 4) 64 VALLES (LLC 5.22-12.48 3.25 MILES 7.46-12.48 K-4C NCT E S T A S / Ave.foFe&r43 ( 25/ 85) SLTTON FARP 2025.e1C 4/ 4) 1228.69( 43/ 64) 481.55-2737.83 3.25 MILES 1435.27-2737.83 782.09-1513.56 81-214 NCT EST48 7.22( 54/ 65) SUTTON FARP 10.44C 4/ 43 46.56( 45/ E4) C.78-34.21 3.25 MILES 3.20-25.22 1.62-186.32 P8-214 NCT ESTA8 7.93( 26/ 25) SLTTON FARP 15.42( 1/ 4) 54.11C 38/ es) 1.40-16.51 3.25 MILES 15.42-15.42 0.33-149.55 PS-212 NOT ESTA6 3.02( 24/ 85) (CVELL FAar 3.19( 7/ 22) 1.91( 17/ d4) C.77-5.9e 2.73 MILES NNE 1.C5-5.21 0.65-5.43 TL-20S NOT ESTAs 1.81( 16/ 25) H hALKER FARM 2.13( 3/ 21) 1.23( 8/ 64) 0.28-3.28 1.25 MILES NW 0.44-3.74 0.33-2.78 AC-22d NCT ESTAS 4.83( 8/ 85) JCNES PARM o.14( 2/ 14) 4.99( 5/ 64) 1.27-10.47 1.25 MILES w 1.21-1C.47 2.09-10.40 SR 69 10.CJO 55 VALUES < LLC 36 VALLES < LLC 91 JNALYSIS PERFORNED SR 9C 2.C00 7.91C 54/ 55) JCNES FARM 13.67( 11/ 11) 2.55( 26/ 36) 91 2.1C-22.90 1.25 MILES W 7.48-22.90 2.01-3.47 + U a. Nominal lower Limit of Detection (LLD) as described in Table 3. b. Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (F).

TABLE 12 RACICACTIVITY IN VEGET ATIch PCI/G - C.037 BC/G (CRY hEIGFT) DCCKET NO. 1Q-]2Zg]21............ REPCRTING PERICD.1116................. hAME CF FACILITT.jggyGI&b.................................c p F AC I L I T Y..b a tILIC W..................Ilbh13 NLMBER OF CONTROL NChaCL1INE LOCA11CN LCCATION$ ?EAN (Fh MEAN (F)b REPCRTED (QGgIIQb.Mlld.tIGd!$I.jhbylk,gg&d... ALL NAPE ,,,g g g g g,b........ utd3WEttibII.. TYPE AN3 LOWER LIMIT OF INCICATCA LCCATICNS DI31 a n G E.a bs.QIs t GII Q t..... E a h G1.b,,,, TOTAL NLMSER DETECTIch" PEAN (Ffd OF ANALYSIS . 218E03519 . 16L21.... .......sa>G 0.23( 2/ 13) 0.08( 3/ 39) 0.C7-C.40 0.07-C.11 ,AMMA (GELI) 133 C.15C 26/ 94) SUTTON FARP CS-137 C.C6-0.41 3.25 MILES 29.dC( 4/ 4) 19.87C 39/ 39) 0.C60 17.23C 94/ 94) LCVELL FARP 20.91-40.33 2.9e-42.35 C.28( 3/ 4) 0.18( 15/ 29) 2.75 MILES NNE NCT ESTAE 1.27-51.29 0.20-0.40 0.10-C.37 K-4C C.18C 41/ 94) H hALKER FARM 39 VALUES < LLC 1.23 MILES NW BI-214 C.11-0.46 PALONE FAR C.44( f/ 13) 0.100 C.39( 3/ 94) EDGAR 0.44-0.44 SI-212 C.35. 0.44 2.5 MILES h 0.16( 10/ 13) 0.12( 27/ Ji) NOT ESTA6 C.C2-0.33 0.02-C.33 C.13( 60/ 94) SRADY FARM NCT ESTAS C.C8( 12/ 13) 0.07C 2a/ 39) PB-214 C.01-0.33 2.2$ MILES S$m C.06( 77/ 96) GCINS FARM 0.CO-0.17 0.01-C.35 C.CO-0.19 1.5 MILES hNW 11.61C 13/ 13) 7.5BC 39/ 39) NCT ESTAtt 1.30-29.14 ECGAR PALQhE PAR PB-212 2.50-18.46 BE-7 C.97-22.45 2.5 MILES h C.C4( 5/ 13) 0.04( It/ 39) 8.91C 93/ 94) NCY ESTAB C.C2-0 09 C.00-C.11 C.C3C 51/ 94) SMITM FARF NCY ESTAs 0.19C 7/ 131 0.1o( 12/ 39) TL-2JE C.CC-0.09 1.75 MILES 3E 0.01-C.34 C.14C 34/ 94) GCINS FARM C.C1-C.35 AC-2 2 3 C.CC-0.35 1.5 MILES hNd 4.41( 1/ 4) 6.18( 1/ 39) NCT ESTAd 4.41-4.41 6.18-6.18 . 41( 1/ 94) MALONE FARP 3.5 MILES NNE 0.37C 1/ 4) 0.27( 3/ 12) NOT ESTAB 0.20-C.22 PA-234M 4.41-4.41 C.33t 7/ 40) 88ADY FARM 0.37-C.37 0.d5( 4/ 4) 0.09( 11/ 12) 2.25 MILES SSd 0 250 SR a9 C.30-0.37 0.05-C.13 52 C.28( 39/ 40) GOINS FARP 0.25-1.34 0.050 1.5 MILES ANd SR 9C C.Co-1.34 32 h (F). specified locations is indicated in parent eses d in Table 3. Traction of detectable measurements at Nominal lower Limit of Detection (LLD) as describe- ^ NwA w>m dbtectable measurerents only.~~ a.

- m. ' TABLE 13 RADIDACTIVITY Ih SCIL a PCI/G - C.037 BC/G (ORY bEIGPT) AAME CF FACILITT.35GWGlab....................................... OCCLET No..jQ-jjZg]23............ s LOCATICN OF FACILITT. 2152LIGN..................Ithh:33!1............. REPORTING PERICC.123i................. TYPE AND LCwER LIMIT ALL C0hTE0L NUMBER OF TOTAL Nu15ER CF INCICATCR LCCATIONS LQG3IIQg.gIIg.blGggjI.lbbMIL. BESS LCCATIONg NChECUTINE ..tiEf03riQ ..ILLGl.... ....... B a h E E.b...... DI3I Ah G E. AbG.DIR EGIIQu.....H A h21.f..I.. OF ANALYSIS CETECTI0ga PEAN (F) % APE MEAN (F MEth (F) REPCR1EC .. 3AbGE......... 3:33W81tihI3.. GROSS SETA 0.7CC 29.93t 1C/ 10) GECRGETCdN, Th 5e.5c( 1/ 1) 19.24( 4/ 4) 14 19.83-So.56 9.C MILES ENE $6.56-56.56 11.32-37.14 GAMMA (GELI) 14 CS-137 0.C20 C.42( 10/ 10) WCRK, TN 0.99( 1/ 1) C.45( 4/ 4) C.C6-0.99 4.5 MILES NNE 0.59-0.99 0.2E-C.72 K *C 0.250 d.COC 1C/ 10) GECRGETOWh, Th 15.47C 1/ 1) 3.99f 4/ 4) 2.2e-13.47-9.C MIL'ES ENE 18.47-18.47 2.53-E.01 01-214 0.050 C.82( 10/ 10) LM1 50LTMhEST 1.C9( 1/ 13 C.73( 4/ 4) l C.37-1.C9 0.75 MILES SW 1.C9-1.09 0.66-C.d1 58-212 0.100 1.01C 10/ 10) GECRGET0dh, Th 1.36( 1/ 1) G.75( 4/ 4) C.42-1.36 9.C MILES ENE 1 36-1.36 C.63-1.03 1 PS-214 0.C50 C.92( 1C/ 10) LM1 $0LTMhEST 1.20( 1/

1) '

O.73-C.91 l 0.e0( 4/ 4) l C.44-1.20 0.75 MILES SW 1.20-1.20 PS-212 NCT ESTad C.91( 1C/ 10) GECRGETodN, Th 1.31( . 1/ 1) 0.cS( 4/ 4) C.37-1.31 9.C MILES ENE 1.31-1.31 0.53-C.93 RA-22s 0.C50 C.82( 1C/ 10) LM1 50LTMhEST 1.C9( 1/ 1) 0.73( 4/ 4) 0.37-1.09 0.75 MILES Sk 1.C9-1.09 0.6o-0.91 RA-223 NCT ESTAB C.27( 1/ 10) DAISY, TN 0.27( 1/ 1) 4 VALLES < LLC C.27-0.27 5.5 MILES w. 0.27-0.27 RA-224 NCT ESTAB 1.C9( 8/ 10) LM1 SOUTMWEST 1.42( 1/ 1) C.S4C 2/ 4) C.92-1.42 0.75 MILES SW 1.42-1.42 0.65-1.02 TL-205 0.C20 C.32( 1C/ ' 10) GECRGETOWN, TN 0.4s( 1/ 13 0.22( 4/ 4) C.12-G.48 9.C MILtS ENE 0.48-C.48 C.18-C.31 AC-229 C. coo C.9e( 1C/ 10) GECRGE70wk, Th 1.41t 1/ 1) C.68( 4/ 4) C.43-1.41 9.C MILES ENE 1.41-1.41 0.54-0.98 PA-234= NCT ESTAB 2.43( 4/ 10) dCRK, TN 2.79( 1/ 1) 2.0GC 1/ 4) 2.19-2.79 4.5 MILES NNE 2.79-2.79 2.00-2.CC SR 89 1.500 3.28C 7/ 10) SALE CREEK, Th 5.73C 1/ 1) 4.63C 2/ 4) 14 2.13-5.73 1C.5 MILES N 5.73-5.73 4.20-5.07 SR sc 0.300 1C VALUES <LLO 4 VALLES <LLO 14 ANALYSIS PERFORMED U a. heinal Iower Limit of Detection (LLD) as described in Table 3. b. Mesa and range tamed upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (F).

T A BL E 14 RACIDACTIVITT IN WELL bATER PCI/L - 0.C37 SC/L hAME CF FACILITV.jggyGIAU....................................... DOCKET NO. 30-]2Zg]23............ d L0CATICN OF FACILITY. ;AEIL19h..................I!bb2311E............ REF0RTING PERICD.I236.................- TYPE AND lower LIMIT ALL CONTROL NLP8ER OF TOTAL NUMBER CF INDICATCR LCCATIONS LQCAIIQb.WIId.tIGdE31.Sht!UAL.2E45... LOCATIONg NChECUTINE GI31&h;t.AhC.QIEEGIIQb.... 88b38.f......MEAN.8 ANGE.b) NArt PEAN (F (F EPCRTED OF ANALTSIS OkTECTIOh* MEAN (*j E!alWBitf3II.. j . 218EQ85tQ ..iLLC1.... .......EANG1....... G;055 3 ETA 2.300 3.35( 7/ 26) MAYS FARM 3.est 4/ 13) -3.77( 12/ 12) 38 2.41-d.10 0.75 *ILES w 2.42-3.10 2.92-4.5C g GA%MA (GELI) 3! K-4C NCT ESTAS 14.65( 5/ 26) MAV5 FakM 16.24( 3/ 13) 13.66( 3/ 12) C.7d-24.17 0 75 PILES a 3.97-24.17 8.42-20.13 BI-214 NCT ESTAB 27.30( 22/ 26) Mays FARM 41.25( 12/ 13) 47.89C 11/ 12) I 3.41-1C9.87 0.75 MILES w 3.41- -109.87 3.73-75.62 l P3-214 NCT ESTAB 29.56( 2C/ 26) MAYS FARM 46.83( 10/ 13) 44.75( 11/ 12) C.6C-.114.CC 0.75 MILES w 7.20-114.00 0.06-75.19 PS-212 NCT ESTAs 1.06( 2/ 26) MATS FAR*. 1.C3C 4/ 13) 1.27C 4/ 12) C.28-2.71 0.75 FILES m 0.28-1.73 C.53-1.91 TL-208 NOT ESTAS 1.29( 2/ 26) S&h WELL so 1.37( 3/ 13). 2.11( 3/ 12) C.42-2.36 Ch5ITE NNE C.24-2.36 1.79-2.68 AC-22S NCT ESTAB 3.49( 2# 26) MAVS FARM 3.49( 2/ 13) 6.61( 2/ 12) 2.e4-4.34 0.75 MILES w 2.d4-4.34 4.91-8.32 I TRITIJM 330.C00 2 VALu!5 (LLC 4 VALLES < LLC ) 12 AhALYSIS PERFORMED l a Nominal Lower Limit of Detection (LLD) as described in Table 3. Fraction of detectable measurements at specified locations is indicated in parentheses (F). l a. b. Mean and range based upon detectable measurements only. l l ~

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34 Table 16 ENVIRONMENTA. GAMMA RADIATION LEVELS-Average External Gamma Radiation Levels at Various Distances from Sequoyah Nuclear Plant ' for Each Quarter - 1984 mR/ Quarter" b Distance Average External Gamma Radiation Levels Miles 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter I (Feb-Apr 84) (May-Jul 84) (Aug-Oct 84) (Nov 84-Jan 85) 0-1 18.011.7 20.3tl.9 23.4 2.1 22.7 3.0 1-2 15.6i2.9 16.8t3.6 18.2 6.0 18.613.9 2-4 15.212.2 16.5i3.2 16.014.6 17.912.8 4-6 15.2 2.0 16.7 2.4 16.9i4.0 18.0 2.5 >6 15.3il.7 16.6tl.9 16.413.9 17.9i2.3

Average, 0-2 miles (Onsite) 17.li2.5 18.913.1 21.Si4.6 21.li3.9

Average,

>2 miles (Offsite) 15.3i2.0 16.6t2.4 16.6i3.9 17.9i2.3 C aDate normalized to one quarter (2190 hours) bAll averages reported ila (68% confidence level)

TABLE 17 RADICACTIVITY 13 CAB 84GE PCI/KG - 0.037 60/KG (hET hEIGPT) lhAME CF FACILITY.3gGWQIad....................................... 00C K ET N 0. 3 Q::3 22432 a............ LOCATION OF FACILITY..MacILIGh..................IEbhE33EL............. REPORTING PERICO 1236..............;.. TYPE AND LOWER LIMIT ALL CONTROL NUMBER OF TOTAL NUM8ER OF INDICATCR LOCATIONS LGCaIIGb.WIIU.tIGUg3I.shggaL.glaN LCCATIONS NCNRCUTIht NAPE MEAN (FE.. MEAN (F)D REPORTED (Fyb 0"> ANALYSIS DETECTION

• MEAN

..etacoasta ..n t : 1.... .......aanst....... D I3 I a u c t.a b c.n z a g s II o u..... a a s s t.6.... ...sanst......... maajungethII.. GROS $ SETA 25.C00 3C0C.55( 1/ 1) H '.ALKER FARM 3C00.5SC 1/ 1) 2701.36( 1/ 1) 2 3C0C.55-3C00.55 1.15 MILES NW 3C00.55-3000.55 2701.3e-2701.16 G AWA (GELI) l 2 CS-137 5.C00 1 VALUES <LLD 5.16( 1/ 1) 5.16-5.16 K-4C NCT ESTAS 1500.E3C 1/ 1) H WALKER FARM 1500.E3C 1/ 1) 1378.81( 1/ 1) 150C.83-1500.83 1.25 MILES NW 1500.E3-1500.S3 1378.51-1373.81 6I-214 NOT ESTAB 1 VALUES <LLO 3.38( 1/ 1) 3.38-3.3E PS-214 NCT ESTAS 4.98( 1/ 1) H WALKER FARM 4.98( 1/ 1) 1 VALLES < LLC 4.98-4.98 1.25 MILES NW 4.98-4.98 U 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). t.

TCSLE 18 RADICACTIVITT In CCRh PCI/KG - C.037 BC/KG (WET WEIGMT) NAME OF FACILITT.31GWGlag........................................ 00CKEY NO. 1Q-32Z4323............. w* LOCATION OF FACILITT..g4BILIGN..................IEbbs3311............. REPORTING PERICD.1236................. . TYPE AND LOWER LIMIT ALL-CONTROL NUMBER OF OF ANALTSIS DETECTI0ha MEAN (F) NAPE MEAN (Ph LOCATIONg NChRCUTINE TOTAL NUMBER CF INCICATCR LCCATICNS LQC4IIQb.WIIg.gIGug1I.ibMW8L. Blab ~.. MEAN (F) REPCRTED ..egseossen ..ittcl...........aamst.t..... DIsIanct.ano.olstcIlos.....sauss.6.... ...sasst.6........ esasuagtenI3.. GROS $ SETA 25.CCO 4407.33( 1/ 1) M hALKER FARM 4467.33( 1/ 1) 3910.00( 1/ 1) 2 4467.33-4467.33 1.25 MILES NW 4467.33-4467.33 3910.00- 3910.00 GAMMA (GELI) 2 K-4C NOT ESTAS 2237.29C 1/ 1) H WALKEP FARM 2237.29( 1/ 1) 1918.43( 1/ 1) 2237.29-2237.29 1.25 MILES Nd 2237.29-2237.29 1918.43-1918.43 SI-214 NOT ESTAE 4.C1C 1/ 1) M hALKER FARM 4.C1( 1/ 13 1.60( 1/ 1) 4.01-4.C1 1.25 MILES NW 4.C1-4.01 1.60-- 1.6C FS-214 NCT ESTAS 1.84( 1/ 1) H hALKER FARM 1.84( 1/ 1) 1.94( 1/ 1) 1.84-1.84 1.25 MILES NW 1.84-1.34 1.94-1.94 Nominal lower Limit of Petection (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). . _ - _ _ -._ _. -. _. ~

TABLE 19 RacI0 ACTIVITY.IN GREEN EEA'5 J PCI/KG - 0.037 SQ/KG (WET HEIGHT) AAME CF FACILITY.31GUQIst....................................... DCCKET No. 10-]2Z4323............ LOCATICN OF FACILITY..useILIQu..................IghbE33EE............. REPORTING PERICO.1236................. 4? TYPE AND L0miR LIMIT .ALL CONTROL NUMBER OF NChRCUTINE TOTAL NbMBER CF INCICATCR LCCATIONS LQGaIIQb.'sIId.bIGUESI.abbWaL.BlaN... LCCATIOg)5' REPORTED 8' MEAN (FM NAME MEAN (FI MEAN (F C7 ANALYSIS DEftCTION ..Itstoseto . 1LLQ1.... .......sANGE....... QIslamGE abt QIstGIIQu.....BabGil.... ...sassik........ etasustetaIs.. GR055 BETA 25.000 4426.58( 1/ 1) H WALKER FARM 4420.88( 1/ 1) 4451.97( 1/ 1) 2 4426.88-4426.6d 1.25 MILES NW 4426.88-4420.88 4451.97-4451.97 G A::M A (GELI) { 2 K-4C NCT ESTAS 1753.93( 1/ 1) N WALKER FARM 1753.93( 1/ 1) 2019.96( 1/ 1) 1753.93-1753.93 1.25 MILES NW 1753.93-1753.93 2019.96-2019.96 SI-214 NOT ESTAB 1.86( 1/ 1) H hALKER FARM 1.86( 1/ 1) 5.09( 1/ 13 1.86-1.66 1.25 MILES Nd 1.40-1.86 5.09-5.09 PS-214 NCY ESTAS 3.19( 1/ 1) H hALKER FARM 3.19( 1/ 13 1.88( 1/ 1) 3.19-3.19 1.25 MILES NW 3.19-J.19 1.38-1.88 e. 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).

t TABLE 20 RADI0 ACTIVITY IN POTAT0E5 PCI/KG - C.037 SC/KG (WET WEIGHT) NAME CF FACILITY.312uQIad....................................... D 0 C K E T. N O. 10 -3 2 Zd 2 3............ Lo C AT ICN O F F ACI LIT T..tfiBILIoN................. 11bb113 E1............. REF0RTING PERICD.1286................. TYPE AND LOWER LIMIT ALL CONTECL NUPSER.0F Lgg3IIgh.gIId.b1GsE11.lbtUaL.EE4s)... LCCATIONg NChRCUTINE TOTAL NUMSER CF INCICATOR LCCATICNS (Fgb NA*c MEAh (F MEAN (F) REPCRTED OF A%ALYSIS DETECTIcha PEAN ..e sensato . 1LL61.... .......sahst....... oIslasse.anc.mIsscIIos.....samst.6.... ...aabst.6........ asasustegnI1.. GROS 5 SETA 25.C00 3e4C.C7( 1/ 1) H hALKER FARM 3640.C7( 1/ 13 7290.13( 1/ 1) 2 364C.07-3640.07 1.25 MILES NW 3440.C7-3640.07 7290.13-729C.13 GAMMA (GELI) 2 K-40 NOT ESTA8 3494.79( 1/ 1) H WALKER FARM 3494.79( 1/ 1) 3391.75C 1/ 1) 3494.79-3494.79 1.25 MILES NW 3494.79-3494.79 3391.75-3391.75 SI-214 NOT ESTAB 11.50( .1/ 1) H hALKER FARM 11.50(

• /

1) s.15( 1/ 1) 11.50-11.50 1.25 MILES NW 11.50-11.50 8.15-8.15 PB-214 NCT ESTAB 1.04( 1/ 1) H hALKEk FARM 1.C4( 1/ 13 9.03( 1/ 1) 1.04-1.04 1.25 MILES NW 1.C4-1.04 9.03-9.03 Nominal lower Limit of Detecticn (LLD) as described in Table 3. t b. Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (F). s.

TABLE al RACI0 ACTIVITY 10 TCMATCES PCI/KG - 0.037 BQ/KG (hET hEIGFT) NAME CF. FACILITY jggyCIAg....................................... OCCKET NO..jQ-22Za]23............ LOCATION OF FACILITY..gggILIgg..................Ighb!33Es............. REPOSTING PERICO.I$36................. TYPE AND LOWER LIMIT ALL CONTROL NUMBER OF TOTAL NUMBER CF INDICATOR LCCATICNS LQGAIIQb.WIIM.tIGut3I.8hhWAL.514M '.. OD ANALYSIS DETECTIch* MEAN (F)b NAME MEAN (Fjb LCCATION{ NCNROUTINE MEAN (F) REPORTED ..etseeseta .. n L a 1...........asust.t..... nIIIasst.anc.oIsicIIos.....eamst.6... ...aanGr 6........ stasustersIs.. SROSS SETA 25.C00 1524.57( 1/ 1) H hALKER FARM 1524.57( 1/ 12 4348.54( 1/ 1) 2 1524.57-1524.57 1.25 MILES NW 1524.57-1524.57 4345.84-4348.34 L GAMMA (GELI) 2 K-oC NCT ESTA8 2365.41C 1/ 1) H b4LKER FARM 2365.41( 1/ 1) 2120.08C 1/ 1) 2365.41-2365.41 1.25 MILES NW 2365.41-23e5.41 2120.08-2120.0E P8-212 NOT ESTAB C.33C 1/ 1) H hALKER FARM 0.33( 1/' 1) 1 VALLES < LLC C.33-0.33 1.25 MILES Nw C.33-C.33 1 i a. Nominal Lower Limit of Detection (LLD) as described in Table 3. b. Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (F). a

TABLE 22 RADI0 ACTIVITY IN JURNIP GREENS FCI/KG - C.037 BC/KG (WE1 WEIGHT) NAME OF FACILITY jgEyGI43..................,.................... DOCKET N0. 19-22Z432s............ g LOCATICN OF F A C I LIT Y..b a dz kIS B..................I84413388............. REFORTING PERICD;1336................. TYPE AND LOWER LIMIT ALL ~ CONTROL. NUMBER OF TOTAL NUMSER OF INCICATCR LCCA,TIONS LQC!IIQh.g))g.gIGUg&I.3buyjL 014M,... LCCATIONg NCNRCUTINE OF AhALYSIS DETECTIOh* MEAN (F F NAME MEAN (FP MEAN (F) REPCRTED _.esscosse: . 4LLot...........samst.6..... ozsIsuct.ans nzancIIon.....sansa.6.... ...s a s s e.6........ erasustersI3.. GROSS SETA 25.000 4725.03( 1/ 1) H hALKER FARM 4725.C3( 1/ 1) 7395.17( 1/ 1) 2 4725.C3-4725.03 1.25 MILES NW 4725.C3-4725.03 7395.17-7395.17 GAIMA (GELI) 2 E-40 NCT ESTAB 1973.76C 1/ 1) H hALKER FARM 1973.76( 1/ 1) 2979.16( 1/ 1) 1973.76-1973.76 1.25 MILES NW 1973.76-1973.76 2979.16-2979.16 31-214 NOT ESTAB -1 VALUES <LLO 12.71( 1/ 1) 12.71-12.71 $8-214 NCT !$7A8 1 VALUES < LLC 5.11( 1/ 1) 5.11-5.11 P8-212 NOT ESTAS 6.C3( 1/ 1) H hALKER FARM 6.C3C II 1) 9.94( 1/ 1) 6.C3-6.C3 1.25 MILES NW 6.C3-6.03 9.94-9.94 BE-7 NCT ESTA8 85.31C 1/ 1) M hALKER FARM d5.31( 1/ 1) 146.42( 1/ 1) a5.31-85.31 1.25 MILES NW 85.31-85.31 146.42-146.42 AC-228 NOT ESTAS 5.33( 1/ 1) H hALKER FAR9 5.33( 1/ 1) 1 VALUES < LLC 5.33-5.33 1.25 MILES NW 5.33-5.33 l i 4 s. Nominal Lower Limit of Detection (LLD) as described in Table 3. b. Me.n and enge based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (F). l i,

TA8LE 23 RADI0fCTIVITY I:3 P0ULTAT PCI/KG - 0.037 50/KG (WET h!IGPT) NAME CF FACILITT.31GuoIaU...................................... DCCKET NO..$Q-22Z4328............ LOCATION OF F A C I L I T Y..g a 51LIC 3..................IE b b i3 3 C E............. REPORTING PERICC.}]$6................. TYPE AND LOWER LIMIT ALL CONTROL NUMBER CF TOTAL NUMBER CF INDICATCR LCCATICNS LQGaIIGb.WIId.CIGul3I.abbuaL.5Eab... LOCATION $ NCNRCUTINE OF AhALYSIS DETECTIONa PEAN (F)b NAPE PEAN (Ph MEAN (F)b REPCETED ..restossna . 166oI...........sans.6...... DIslance abc.alsscIlos.....sanst.6.... ...s a u s t.6........ m ssurse:sII.. GROS $ SETA 25.000 3991.96l 1/ 1) H hALKER FARM 3991.96C 1/ 1) 4727.33( 1/ 1) 2 3991.96-3991.96 1.25 MILES NW .3991 96-3991.96 4727.3E-4727.38 G *.= A (GELI) 2 K-4C NOT ESTA8 1889.26C 1/ 1) n hALKER FARM 1889.26( 1/ 1) 1934.35( 1/ 1) 1889.26-1E89.26 1.25 MILES NW 1889.26-1859.26 1934.55-1934.35 SI-214 NOT ESTAS 2.04( 1/ 1) H hALKER FARM 8.C4( 1/ 1) 1 VALUES < LLC E.04-8.04 1.25 MILES NW 8.C4-8.04 P5-214 NOT ESTAB 9.21( 1/ 1) n hALKER FARM 9.21( 1/ 1) 1 VALUES < LLC 9.21-9.21 1.25 MILES NW 9.21-9.21 TL-20$ NCT ESTA8 C.91( 1/ 1) M hALKER FARM 0.91C 1/ 1) 1 VALLES < LLC C.91-0.91 1.25 MILE $ Na 0.91-0.91 O e. 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).

a .n .u., g 2"^'S"Evm S Q O AH C R PLANT ) Preoperational Phase Operational Phase ,,u 1 i 1,, 1m es 1ee. P O

n' f c ^s= h *\\ Figure R 24 : Direct 4diation Levels .Sequoyen Nuclear Plant I n j i 3 + l-Onsa te A -j is ! i. Ir ' i / 3 a I' li / i i' A ?- p-4 il /\\! kf fsita'! I 4' i i I.' 18 \\ ;j s, ,i 'ki / \\/ / i s i g k \\.*.

1. i s-4

\\ !

[\\ ! I 43

'b i! / i g. g \\l 'b' i. gegin Plant '] i i 19 t! t d 'I *I 'I ! Ope otion } l i f I I I f f 8 12 1976 19n ig73 ig73 iggt 1981 19g2 1983 1994 ~ - ~ "Mul -,,,. .) Figure 9 24 : Direct Radiot4cn Levels Sequcyoh Nuclear Plant 1-Cuo**ec Moving Ave *o98 I 22 I I I k 10 i 2 c I s g \\ A f, 16 .a i i; !/ gi \\'%,'." g /,%' ye g, j ey Of fsite i Vi 19 ! Begin Plate i ! Operation I l I I2 ' 1976 1977 t9?B 1979 198E 398' 3882 I003 II1 i

45. y Rnervoi r. Moni Loring Samples are collected from the Tennessee River as detailed in table 24. Samples collected for radiological analysis include water and Asiatic. clams from three of these cross sections, sediment from four cross sections, and fish from three contiguous reservoirs. The locations-of these cross sections are shown on the accompanying map-(figure 10) and conform to sediment ranges established and surveyed by TVA. Water Water samples were collected automatically by sequential type sampling devices at three cross sections and composite samples analyzed monthly for gross alpha and beta activity and gamma-emitting radionuclides. - Further composites were made quarterly for strontium and tritium analyses. Results are displayed in table 25. Figure 11 presencs a plot of'the gross beta activity in surface water from 1971 through 1984. Indicator stations are those located downstream from the plant and_ controls are located upstream. The levels reported are ' consistent with gross beta levels measured in surface water samples -taken from the Tennessee River in preoperational monitoring programs

conducted by TVA at other sites. During this reporting period, one monthly sample was not collected because of equipment problems.

Fish Radiological monitoring for fish was accomplished by analyses of composite samples of adult fish taken semiannually from each of -three contiguous reservoirs--Watts Bar, Chickamauga, and Nickajack. 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 preopera-tional monitoring program. Three species, white crappie, channel catfish, and smallmouth buffalo, are collected representing both commercial and game species. Sufficient fish are collected in each reservoir to yield 250 or 300 grams oven-dry weight for analytical purposes. All samples are analyzed for gross alpha and gross beta activity, for gamma-emitting radionuclides, and for strontium content. Results are given in tables 26 through 29. Sediment Sediment samples were collected semiannually from dredge hauls made for bottom fauna. Gamma, gross alpha, and gross beta 89 activity and Sr and 90Sr content were determined in samples collected from points in four cross sections..Each sample was a composite obtained by combining equal volumes of sediment from each of three dredge hauls at a point in the cross section. Results are given'in table 30. One sample was not taken because of flood conditions. l

rr-46 In addition to the sampling described above, shoreline sediment samples.were collected at three recreatinn-use areas (two . downstream from the plant and one upstream) in the. vicinity of SQN. . Samples were taken in May.and November and analyzed for,coss alpha,' gross beta, gamma-emitting radionuclides, 89Sr, and Sr. Results are 99 given in. table 31., Asiatic Clams Samples of. Asiatic clams were collected semiannually with a Ponar dredge from three stations and analyzed for gross alga, gross beta, and. gamma-emitting radionuclides. In addition, the Sr and '00Sr content was determined in the shells. Results are given in tables 32 and 33.

47' Table 24 SAMPLING SCHEDULE - RESERVIOR MONITORING Biological Samples Tennessee River Benthic. Shoreline (Mile) Fauna Sediment' Sediment-Fish" Water Samples 472.8-X b 473.2 Automatic Sampler 477.5 X 478.3 X 480.8 X X 483.4 X X Automatic Sampler - 485.2~(Control) X 496.5 (Control) X X b 497.0 (Control) Automatic Sampler " Fish samples are taken from Watts Bar, Chickamauga, and Nickajack Reservoirs, bComposite sample analyzed monthly. 4 F ~ i

4 .t. TABLE 25 44DI3 ACTIVITY IN - SU FCCE-CATER TOTAL- _ PCI/L - 0.0 37 80/L ~ - NAMc 0F F ACILITY_1[11gf AH . DOCKET-NO. 50-327tigg_ LOCATION u F AC ILI f f HAML(Tay__________ _lL33L'1LE < REDO # TING SERIOC_1gg4 CONTROL NUMBER OF TYPE AMD L0dt4 LIMIT ALL-L3 CATI 3 S~ 43NROUTINE. TOTAL NJ18ER OF INDICATOR LO;(TIONS (qEifiq3 WLIE_gliggST'4112i(_M[A1_f._- MEAN tr{T 32 ANALYSIS DETICTIONP MEAN (*r MAME 9EAN (b ) F ^ REPORTED b-PERFORMi2 __ik(21 4ANGE _ _ - gygggggL_i3g_gy gg77g3__. g3ygL R&gii G40SS ALPHA 4.000 26 d 4 LUES C LL3 - 12 VALJES CLLD_ 5[ A gg1(4[ylg_ 38 tNALYSIS PERF344E3 843SS HETA 2.300 2.98( 23/ 26) TRM 493.4 3.35( 9/.13) 3.14( 9/ 12) 38 2.54-4.55 -2.30-4.55 2.59 ' .3.64 GanMA (GELI) 3B 4-40 NOT LST AB. 10.39( 1/ 26) TRM 493.4 10.39( 1/ 13) 12 VALUES CLLD~ 10 39-13.39 10 39-10.39 bl-214 NOT L3 TAB 6.29( 14/ 26) TIM 473.2 10.55( 6/'.13) 2.75( 6/ 123 0.51-35.55 1.56-35.56 0.44-5.50 P3-214 NOT LSTAB 5.91( 9/ 26) TRM 473.2 8.69( 4/ 13) 12 VALUES CLLO 0.43-27 36 3 43-27.36 P 3 -212 NOT LSTAS 1 93( 13/ 26) TRM 483.4 1.86( 6/ 13) 1.10 ( - 3/. 123 0.24-3.78 0.55-3.21 0.77-' 1.28 SR 89 lu.000 8 #ALUES CLLD 4 VALUES.CLLD 12 %NALYSIS pgpr3R*E3 $4 90 4.000

• d4 LUES CL.3 2.22(

1/ 4) 2.22-2.22 4 12 364.33( 2/ 43 360.15( 1/ 4) T41TIuF 33u.000 359.12( 4/ 8) TRM 473.2 12 335 14-392.52 336.14-342.52 360.15 360.15-1 i a. Nominal Lower Limit of Detection (LLD) as described in table 3. b. Mean and range based upon detectable measurements oniv. Fraction of detectable measurements at specified locations is indicated in parentheses (F). I ? i I

TABLE 26 REDI0 ACTIVITY Ih EHITE CRAPPIE (FLESH) PCI/G - C.037 BC/G (CAY hEIGPT) NAME CF FACILITY.!!GW91&b....................................... DCCKET N0. 1G-]ZZgj23............ LOCATION OF FACILITY..gg31LIGs..................I1bbE1125............. REPORTING PERICO.1236................. TYPE AND LOWER LIMIT ALL CONTROL NUPSER OF LCCATIONS NChROUTINE TOTAL NUMBER CF INCICATCR LOCATIONS LQG3IIQb.gIIg.gIGyg3I.jhby&L gg4W.1.. OF ANALYSIS DETECTIcha MEAN ( F )b NAPE MEAN (F) MEAN (F) b REPORTED ..egneaseso . 1LL;I...........sanse.t..... aI:IamG.abG.cIs4GIIon.....aanst i... ...aanst.6........ esaswagttats.. GROSS ALPMA C.100 C.1et 3/ 4) CPICEAPAUGA RES 0.17( 1/ 2) 0.22( 1/ 2) e C.11-0.21 TRP 471-53C 0.17-C.17 0.22-C.22 CROSS BETA 3.100 3C.23( 4/ 4) hICKAJACK RES 32.25C 2/ 2) 26.92( 2/ 23 6 18.89-40.62 TAP 425-471 23.ES-40.62 15 66-37.97 GAMMA (GELI) 6 CS-137 0.C20 C.C7( 4/ 4) NICKAJACK RES 0.C7C 2/ 23 0.12( 2/ 2) C.04-0.08 TRP.425-471 0.C7-0.05 0.10-C.13 K-40 NCT ESTAS 13.4EC 4/ 4) NICKAJACK RES 16.59( 2/ 2) 13.0E( 2/' 2) 11.83-17.c0 TRP 425-471 15.58-17.60 9.37-16.29 tI-214 0.C20 C.31( 2/ 4) CPICKAPAUGA RES 0.34( 1/ 2) 0.24( 1/ 2) C.23-0.34 TRP 471-53C 0.34-0.34 0.24-C.24 P8-214 NCT ESTA8 C.24( 2/ 4) CHICKAMAUGA RES 0.33( 1/ 2) 0.21( 1/ 2) C.14-0.33 TRP 471-53C 0.33-0.33 0.21-C.21 54 49 0.500 4 VALUES <LLD 2 VALLES < LLC 6 ANALYSIS PER80RMED SR 90 0.100 C.13( 1/ 4) 'NICKAJACK RES 0.13( 1/ 2) 2 VALLES (LLD 6 C.13-0.13 TAP 425-471 0.13-0.13 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). a.

5 2-title 21 RADICAC'2VITY I3 CHAh!EL CATFISH CFLESH) T .rC.fG - C.037 SC/G (CRY HEIGHT)- hAME CF FACILITY.31GUGI&g....................................... DCCKEY N0. 3Q-32ZA328............ LOCATICN OF FACILITV..t4BILIGh..................I!&b13311............. REPORTING PERICO.1156................. TYPE AND. LOWER LIMIT ALL CONTROL-NLMBER OF ' TOTAL NbM8ER CF INCICATCR LCCATIONS (QC)((Qg.gjlg.gligg$1.jhggjk 5gjg.1~. LCCATION{

NChRCUTINE OF ANALYSIS DETECTIcha PEAN (F)D

-NAPE PEAN.(F) MEAN.(F) REPORTED . 218f08510 .. i'. '. G l.... .......B4bGt.h QIslabG C. A bC.DIR E GIZ ON.....i ANGE.b..... .. 8 A b G E.b........ 5143ytitESIS.. GROSS ALPHA 0.100 C.1aC 2/ 4) h1CKAJACK RES 0.21( 1/ 2) C.16( 1/. 2) 6 C.14-0.21 TRP 425-471 0.21-0.21 0.16-C.16 CROSS BETA 0.100-21.99( 4/ 4) NICKAJACK RES 25.70C 2/ 23. 21.11( 2/ 2) 6 II.74-34.e7 TRP 425-471-16.73-34.67 11.$3-3C.38-GAMMA (GELI) t CS-137 0.020 C.C6C 4/ 4) CPICKAPAuGa RES 0.C6C 2/ 2) 0.04( 2/ 12 ) C.C5-0.C5 TAP 471-53C 0.C5-0.03 C.04-C.04 p-40 NCT ESTA6 13.71( 4/ 4) NICKAJACK RES 15.43( 2/ 2) 10.52( 2/ 2) 11.78-17.71 TRP 425-471 12.55. 17.91 7.75-13.28-51-214 0.C20 C.Co( 3/ 4) CFICKAPAuGA RES C.CdC 1/ 2) -C.03( 2/ 2) C.03-0.C6 TRF 471-53C 0.C3-0.05 0.02-C.04 PS-214 NCY ESTAB C.C4( .3/ 4) CHICKAPAUGA RES 0.C5C 1/ 23-0.04( 2/ 2) C.C4-3.C5 TRP 471-53C 0.C5-0.05 0.02-C.06 TL-20E NCT ESTAS C.COC 1/ 4) NICKAJACK RES 0.C0( 1/ 2) 2 VALLES < LLC C.CC-0.C0 TRP 425-47? 0.CC-0.03 AC-22s NOT ESTAS 4 VALUES < LLC 0.01C 1/. 2) 0.01-C.01 - SR 89 0.530

• VALUES < LLC 2 WALUES < LLC I

4 ANALYSIS PEPFORMED 50 90 0.100 4 VALUES <LLD 2 VALUES < LLC 6 ANALYSIS PERFORPED i rominal hver Limit of Detection (LLD) as described in Table 3. b. Mean and range based upon detectab? measurements only. Fraction of detectable reasurements at specified locations is indicated in parentheses (F). a. a

TCBLE 28 RADI0 ACTIVITY IN SPALLMOUTH BLFFALC (FLESH) PCI/G - C.037 BC/G (CPY hEIGPT) NAME CF FACILITY.31GbOIAb....................................... DOCKET NO. 1Q-32Za]23............ LOCATICN OF FACILITT..ba51LIGN..................IEbbE35tt............. REPORTING PERICO.j![i................. TYPE ANO L0 DER LIMIT ALL CO NT F OL NUP854 0F NCNRCUTIh! TOTAL NUMSER CF INCICATOR LOCATIONS LQCAIIQb.M))U.tIGug1I.ibbg3L.gg43 1.. LCCATIONg 0F ANALYSIS DETECTIONa MEAN (F NAPE MEAN (F) NEAN (F) REPCRTEC b ..esicaissa ..sL6:1...........ansse....... oI3rance.anc.oz Eczzcu.....sasas.t... ...sasse......... aga3ussessII.. GROSS ALPHA 0.100 C.2CC 2/ 4) CHICKAPAUGA RES 0.22( 1/ 2) 0.17 C 1/ 2) 6 C.15-C.22 TRP 471-53C 0.22-C.22 0.17-0.17 GROS $ SETA 0.100 19.50( 4/ 4) NICKAJACK kES 20.63( 2/ 2) 28.01( 2/ 23 e 13.06-23.67 TRP 425-471 20.46-20.81 23.75-3C.26 GAMMS (GELI) 6 C5-137 0.C20 C.Cet 4/ 4) CNICKAPAUGA RES G.C6C 2/ 2) 0.1E( 2/ 23 C.04-0.C7 TRP 471-53C 0.C6-0.07 0.05-G.3C K-4C NCT ESTAS 12.22( 4/ 4) NICKAJACK PES 13.26( 2/ 2) 12.67( 2/ 2) 9.21-17.32 TRP 425-471 9.21-17.32 12.20-13.15 BI-214 0.020 C.07C 3/ 43 NICKAJACK RES 0.C9( 1/ 2) 0.06( 1/ 2) C.C3-0.C9 TRP 425-471 0.C9-0.09 C.06-0.06 i FS-214 NLT ESTAS C.06( 3/ 4) CHICKAPAUGA RES 0.C7( Z/ 2) 0.05( 1/ 2) C.04-0.G9 TRP 471-53C C.C4-0.09 0.C5-0.05 PS-212 NCT ESTA8 C.CCC 1/ 4) CPICKAPAUGA RES 0.C0( 1/ 2) C.01( 2/ 2) C.00-0.CC TRP 471-53C 0.00-0.00 0.00-C.01 SR dS 0.500 4 VALUES < LLC 2 VALLES < LLC e ANALYSIS PERFORMED SR 9C 0.1CO 4 %ALUES <LLO 2 VALLf5 (LLC 6 ANALYSIS PERFORPED M Nominal lower Limit of Detection (LLD) as described in Table 3. Fraction of detectable measurements at specified locations is indicated in parentheses (F). a. b. Mean and range based upon detectable measurements only.

t . TABLE 29 RADI0 ACTIVITY IN SPALLn0UTH SUFFALO (WMOLE) PCI/C - C.037 8C/G (CRY hEIGPT) hAME CF FACILITY.jiGWGIAg....................................... OCCKET NO. 1G-22ZA328............ LoCATIcN OF FACILITY..uanILIGk................. 1166133E1............. REPORTING PERICO.2236................. TY;E AND LOWER LIMIT ALL CONTRCL

• cPBER OF LCCATIONS NCARCLlINE TOTAL NUMBER CF INCICATCR LCC(TICNS LGGAIIGh.WIID.b1Gu!3I.ibbWAL.514N.I..

NAPE MEAN (F) MEAN (F)b REPORTED OF An* LYSIS DETECTIcha . MEAN (FT ..E&EE9EEEQ ..iLLGl.... ....... BANG:.b...... QI3IAhGE.AhC.218:GIIQW.....EAbGE..... ...EAbGE......... E!d3WBitEhI3.. Gross ALPHA 0.100 C.17( 1/ 4) NICK 4 JACK RES C.17( 1/ 2) 2 VALUES < LLC 6 C.17-0.17 TRP 425-471 0.17-C.17 GROSS BETA 0.100 16.83C A/ 4) CPICKAPAUGA RES 17.14( 2/ 2) 17.45( 2/ 2) 6 12.33-20.19 TAP 471-53C 16.e3-17.65 12.25-17.6e GAMMA (GELI) 6 CS-137 0.020 C.05( 1/ 4) CPICKAPAUGA RES 0.C5( 1/ 2) 0.05( 2/ 2) C.G5-0.C5 TRP 471-53C 0.C5-0.05 0.03-C.C8 K-*C NOT ESTAS 7.57( .4/ 4) CPICKAPAUGA Rf5 7.E4( 2/ 2) 3.05( 2/ 2) 6.44-5.15 TRP 471-53C 7.72-7.96 7.95-3.15 BI-214 0.020 C.04( 3/ 4) CPICKArauGA RES C.CSC 1/ 2) 3.04( 1/. 2) C.C3-0.C5 TRP 471-53C 0.C5-0.05 0.C4-C.04 PS-214-NCT ESTA8 C.06( 3/ 4) CNICKAPAUGA RES C.C6C 1/ 2) 0.03( 2/ 2) 0.03-0.C8 TRP 471-53C 0.C6-0.06 0.02-C.03 PE-212 NCT ESTAs C.C0( 2/ 4) NICKAJACK RES 0.C0( 1/ 2) 0.01( 1/ 2) C.CC-0.CC TRP 425-471 0.CO-0.00 C.01-C.01 SR 89 0.500 C.67C 2/ 4) NICKAJACK RES 0.73( 1/ 2) 2 VALUES < LLC c C.61-0.73 TRP 425-471 C.73-0.73 52 9C 0.100 C.18( 1/ 4) NICKAJACK RES 0.13( 1/ 2) 0.16( 1/ 2) 6 C.18-0.18 TRP 425-471 0.1d-C.18 0.16-C.16 a 4 i 4 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.

T ASLE 30 RCOIDACTIVITY Ik SECICEhT PCI/G - 0.037 SC/G (ORY WEIGHT) NAME CF FACILITY.jggyCI&c....................................... OCCKET NO. 3C-32Z4325............ LOCATICN OF FACILITY..d481LI25................. 11bbE1311............. REPORTING PERICD.I256.................. TTp! AN3 LCwER LIMIT ALL CONTRCL NUPBER OF LCCATICNS NCNRCLTINE Total NUMSER CF INCICATOR LCC(TICNS LQG 4IIQh.'dlld.tIEBE3I.ibbW4L.!E A N.1.. (Fj NAPE PEAN (F) MEAN (F)b REPCRTE0 a 07 ANALYSIS CETECTION . PEAN ..t!!! Cit:0 ..iLLGl.... ...... 3&hGE....... DI3I&MG E. AbC.QIEECII Qh.....E!3Ei..... ...B&hGE......... DE63WEttihII.. GROSS ALPna 0.350 2.22( t/ e) TRP 4ec.82 2.65( 2/ 2) 3.42( 1/ 1) 7 1.12-3.50 1.79-3.50 3.42-3.42 GROSS SETA 0.703 37.98( 61 6) TRP 4bC.92 40.95( 2/ 2) 40.95( 1/' 1) 7 32.53-42.76 39.13-42.75 40.95-4C.95 GA"%A (GELI) 7 CO c3 0.C10 C.29( 4/ o) TRP 46C.82 0.37C 2/ 2) 1 VALLES < LLC C.17-0.41 0.33-0.41 CS-137 0.C20 1.51( 6/ o) TRP 472.dC 2.23( 2/ 2) 1.45( 1/ 1) 0.10-2.62 1.63-2.e3 1.45-1.45 K-*C NCT ESTA8 14.53t 6/ e) TRP 483.4 15.59C 2/ 2) 14.73( 1/ 1) 13.28-10.62 14.56-16.62 14.73-14.73 6I-214 0.C20 1.6C( 6/ e) TRP 4SC.52 1.E0( 2/ 2) 1.89( 1/ 1) 1.14-2.39 1.21-2.39 1.59-1 89 BI-212 0.100 1.63( 3/ 6) TRP 43C.32 1.74( 2/ 2) 1 vaLLES < LLC 1.56-1.89 1.59-1.59 P5-214 NOT ESTAB 1.75( 6/ o) TRP 4*C.52 2.C0( 2/ 2) 1.75C 1/ 13 1.21-2.47 1.34-2.67 1.75-1.75 PS-21I NOT ESTAB 1.46L 6/ o) TRP 48C.32 1.45( 2/ 23 1.55( 1/ 1) 1.21-1.94 1.36-1.94 -1.55-1 55 RA-226 NCT ESTA8 1.17( 2/ e) TRP 48C.82 1.21C 1/ 2) 1 VALLES < LLC 1.14-1.21 1.21-1.21 RA-22 NCT ESTAB 1.66( 1/ 6) TRP 4dC.S2 1.46( 1/ 2) 1 VALLES < LLC 1.66-1.66 1.66-1.66 TL-I:s 0.C20 C.49C 6/ el TRP 4ec.S2 0.53( 2/ 2) 0.39( 1/ 1) C.39-0.60 0.46-0.43 0.39-0.39 AC-;23 0.Ce0 1.41( 6/ 6) TRP 483.4 1.50( 2/ 2) 1.49( 1/ 1) 1.24-1.51 1.48-1.51 1.49-1.49 SR 59 1.500 d VALUES <LLO 1 VALUES < LLC 7 ANALYSIS PERFORMED SR ic 0.300 6 VALUES <LLO 1 VALLES < LLC i 7 ANALYS!$ PERFORMED U Nominal Lower Limit of Detection (LLD) as described in Table 3. s.h Mean and range based upon detectable measurements only. Traction of detectable measurements at specified locations is indicated in parentheses (F).

TABLE 3I RACIDACTIVITT IN SHORE LIhE SEDIMEhT PCI/G - 0.037 SC/G (CRT WEIGPT) NAME CF FACILITT.!!GWGI&b....................................... DCCKET NO. 3C-32Z4]23............ LOCATICN OF FACILITT. 36EILIGN..................I135133EE............. REPORTING PERICD.If36................. TYPE AND LOWER LIMIT ALL TOTAL NU48ER CF CONTROL NUPBER OF INCICATOR LCCA{ICNS LOG 4!IQd.WIId.tIGUf3I.dhby4L.gtig LCCATICNg NCNRCUTINE OF ANAlf5Z5 CETECTION" PEAN (F) QIIIANCE. Ant.DIREGIIQW.....EANGE.gf".. .. 8AhGE.{........ NAPE MEAN ( MEAN ( } -REPORTED ..tE8 E28512 . 1LLUl.... .......EABG1....... Gros: ALPHA NOT ESTAS 2.61( 4/ 4) GCLD PCINT 3.48C 2/ 23 2.96( 2/ 2) HEA3WBittBIs.. e 1.25-3.55 TRP 478 3.41-3.55 2.83-3.1C CROSS BETA 0.700 14.34C 4/ 41 GCLD PCINT 16.C3C 2/ 2) 22.85( 2/ 2) e c.50-25.75 Tap 478 6.30-25.75 21.64-24.0d GAM;A (GELI) 6 Co-60 0.C10 C.C4( 1/ 4) GCLD PCINT 0.C4( 1/ 23 2 VALLES < LLC C.C4-0.C4 TRP 472 0.C4-0.04 'CS-137 0.C23 C.07( 3/ 4) GCLD PCINT G.C7( 1/ 2) 0.15( 2/ 2) C.03-0.10 TRP 478 0.C7-0.07 0.02-C.29 K-4C NCT ESTAB 4.23C 4/ 4) GCLD PCINT 6.20( 2/ 2) 6.97( 2/ 23 2.29-7.53 TRP 478 4.87-7.53 6.69- -7.25 BI-214 0.C20 C.29(- 4/ 43 GCLD PCINT 1.C1( 2/ 2) 0.98( 2/ 2) C.65-1.07 TRP 478 0.95-1.07 0.S6-1.10 BI-212 0.100 1.06( 4/ 4) GCLO PCINT 1.46C 2/ 2) 1.34( 2/ 2) C.55-1.54 TEP 478 1.39-1.54 1.24-1.43 P8-214 NCT ESTAS C.97( 4/ 4) GCLD PCINT 1.C8C 2/ 2) 1.0S( 2/ 2) C.73-1.17 TRP 478 1.CO-1.17 0.97-1.19 F8-212 0.C20 C.93( 4/ 4) GCLD PCINT 1.30( 2/ 2) 1.20( 2/ 2) C.45-1.33 Tap 472 1.28-1.33 1.08-1.32 RA-226 NCT ESTAS C.89( 4/ 4) GCLD PCINT 1.C1( 2/ 2) 0.98( 2/ 2) C.e5-1.07 TRP 478 0.95-1.07 0.86-1.1C RA-223 NCT ESTAB 4 VALUES <LLO 0.39( 1/ 2) RA-224 NCT ESTAe 1.09( 3/ 4) GCLD PCINT 1.38C 2/ 2) 1.31( 2/ 2) 0.39-C.39 C.51-1.52 TRP 478 1.24-1.52 1.13-1.48 BE-7 0.C20 C.18( 1/ 4) HARRISCN FLATS 0.18( 1/ 2) 2 VALLES < LLC C.18-0.18 TRP 477 0.18-0.18 "-208 0.020 C.32( 4/ 4) GCLD PCINT 0.44( 2/ 2) 0.40( 2/ 2) C.16-0.47 TRP 478 0.42-0.47 0.36-C.44 4.-228 0.C60 C.95( 4/ 4) GCLD PCINT 1.30( 2/ 2) 1.23( 2/ 2) C.47-1.34 TRP 478 1.25-1.34 1.13-1.33 PA-234M NCT ESTAS 2.65C 2/ 4) HARRISCh FLATS 2.90( 1/ 2) 2.08( 1/ 2) 2.41-2.9C TRP 477 2.90-2.90 2.08-2.Cf SR 89 1.500 4 VALufs <LLD 6 ANALT$IS PERFORMED 2 VALLES < LLC SR 9C 0.300 4 VALUES < LLC 2 VALUES (LLC 6 ANALYSIS PERFORMED Nominal Lower Limit of Detection (LLD) as described in Table 3. a. b. Mean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (F)

TCBLE 32 RADICACTIVITY IN CLAP FLESH PCI/G - 0.037'aQ/G (DRY WEIGHT) hA1E CF FACILITV.32GQQ1&B..........__.............__.__......... DOCKET NC. 12-22Zg343.__......... LOCATION OF FACILITY. 0151LIQs........... ......Ithh:1111............. RtPORTING'P5aICD 1336 __...........__. TYPE AND LOWER LIMIT ALL CONTFct NLwSER OF NCNR00 TINE TOTAL NUMBER 'CF IkCICATOR LCCATICN$ LQGEIIQh.gIIg.tIGug31.!bbygL gia).l0 LOCATIO?.g a PEAN (F)b N4PE MEAN (F) MEAN (F) RfPORTED $P ANALYSIS DETECTIch ..etseaseta ..ILLct.... .....__sanss_t.___. a ls I n uc t.a s c.cl a t cII as.. __. s a a s c.6_... ...a a s s a.b.....__.

asusse: sis..

CROSS ALPHA 0.100 C.47( 4/ 4) TRP 42C.82 0.70( 2/ i)

3. 2 ', (

2/ 2) 6 C.13-1.15 0.20-1.15 0.1o-C.42 GO 55 BETA 0.100 d.7CC 4/ 4) TRP 48C.32 12.C2( 4/ 2) 5.16( ?/ 2) 6 3.34-15.69' b.30-15.09 2.26- $.05 GO 2A (GELI) 6 CC-6G 0.Os0 C.21( 1/ 4) TRP 480.32 0.21( 1/ 4) 2 v&LLEE < LLC C.21-0.21 0.21-0.it CS-137 0.060 C.30( 1/ 4) TRP 46C.82 0.33( 1/ 2) 2 VALLts < LLC 0.3C-0.30 0.30-0.33 K-40 NOT ESTAS 3.4Ct 2/ 4) TRP 48C.82 5.C7C 1/ 2) 5.09( 1/ 2) 1.73-5.C7 5.C7-5.07 3.09-3.09 BI-214 NOT ESTA8 1.66( 3/ 4) TRP 48C.82 2.56( 1/ 2) 0.55( 2/ 2) C.30-2.56 2.56-2.5o C.25-C.s5 PB-214 NOT ESTAB 1.33( 4/ 4) TRP =eC.32 1.47( 2/ 2) 0.80( e/ i) C.18-2.64 0.31-2.o4 0.37-1.24 P8-212 NCT ESTAS C.25( 2/ 4) TRP 48C.82 0.25( 2/ 2) G.13( 1/ 2) C.11-0.39 0.11-0.3v 0.13-C.13 TL-238 NCT ESTA8 C.1e( 1/ 4) TRP 48C.82 0.1e( 1/ 2) 0.04( 2/ 4) C.16-0.16 0.16-0.1o 0.04-C.05 AC-228 NCT ESTAb C.23( 1/ 4) TRP 483.4 0.23( 1/ 2) 2 VALLES < LLC C.23-0.25 0.23-G.~ 2 3 0 c. Nominal lower Limit of Detection (LLD) as described in Table 3. b. Mann and range based upon detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parencheses (F).

TABLE 33[ RADI fCTIVITY I3 CLA7 3MELL PCI/G - 0.037 sc/G (DAY WEIGnT) hAME CF FACILITY.jgGyGlad......................................g GCCKET h0..$Q-22ZAJ23............ w LOCATICN OF FACILITY..gggILIGb................. 15hbE3315............. REFQRTING PERICO.liji................ TYPE AND LOWER LIMIT ALL CCNTact NLP8ER OF TOTAL NUNSER OF INCICATOR LCCATIONS (QG8IIQb.g))d.bIgggjl.gb3Mjk.gggg.. LCCATION5 NCh*CUTINE CF CNALYSIS DETECTI0ha PEAN (F NAME MtAN (F PEAh (F) b zgpggggg Ei.g LIIIANGE.AbG.QIEtGIIQL.....ia$ht.g __tEREQ8510 . 1LLGl_... ...... 84N .__tahGE...__.... 5183W!!tibI1_. GROSS ALPHA 0.700 4 VALUES < LLC 0.11( 2/ 2) 6 0.7o-C. 35 GROSS BETA 0.700 3.93( 4/ 4) TRP 48C.82 4.31( 2/ 2) 5.44( '?/ 2) 6 3.51-4.79 3.84-4.79 5.22-5.co GA00A (GELI) 6 C0-60 0.010 C.02( 2/ 4) TRP 48C.d2 0.C2( 2/ 2) 0.02( 2/ 2) C.C2-0.02 0.C2-0.02 0.01-C.J2 C5-137 0.C20 C.02( 1/ 4) Tar 460.82 0.C2C 1/ 2) C.02( 1/ 2) C.02-0.C2 0.C2-0.02 0.02-0.]2 K-40 NCT ESTAs 0.17C 3/ 4) TRP 43C.d2 0 20( 2/ 2) 0.22( 2/ 2) C.10-0.22 0.19-0.42 0.22-c.23 M0-54 0.C10 C.02( 2/ 4) TRP 48C.82 0.C2C 2/ 2) 2 VALUES < LLC C.01-0.C2 0.C1-0.02 SI-214 ' 0.C50 C.12 ( 4/

• )

TRM 4SC.82 0.17( 2/ 2) 0.22(. 2/ 2) C.06-0.21 0.13-0.21 0.18-C.27 BI-212 0.100 C.18( 1/ 4) TRP 48C.82 0.18( 1/ 2). 0.23( 2/ 2) C.18-0.18 0.13-0.18 0.22-C.25 Pa-214 0.C50 C.13( 4/ 4) Tar 48C.82 0.19C 2/ 2) 0.26( 2/ 2) C.05-0.21 0.16-0.21 0.19-C.32 78-212 N0f !$TAS C.07( 4/ 4) TRP 450.82 0.11C 2/ 2) 0.16( 2/ 2) C.01-0.11 0.11-0.11 0.16-0.16 RA-226 0.C50 C.12( 4/ 4) TRP 48C.82 0.17( 2/ 2) 0.22( 2/ 2) 0.06-0.21 0.13-0.21 0.18-C.27 TL-203 0.C20 C.04( 2/ 4) Ter 48C.82 0.C4( 2/ 2) 0.06C 2/ 2) C.04-0.C4 0.C4-0.04 0.05-G.07 AC-228 0.C60 C.21C 4/ 4) TRP 48C.82 0.21C 2/ 2) 0.32( 2/ 2) C.20-0.22 0.20-C.22 0.27-C.37 SR 49 5.C00 5.89( 1/ 4) TRP 483.4 5.!9C 1/ 2) 15.34( 1/ 2) 6 5.89-5.89 5.89-5.89 15.34-15.34 SR 7C 1.C00 1.36( 4/ 4) TRP 48C.82 1.64C 2/ 2) 1.20( 12 / 2) e 1.08-1.81 1.47-1.81 1.14-1.25 e. 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 precified locations is indicated in parentheses (F). //.

m i-a 58 r I l 1 l t I I I _a 1 t l i u 5 l ~ t: m >MMhh m tr.1 g < s ti l -== r m<ms. 1 >go = $a ~ 58mi j g i 3 w i-j, i E' d I l l. e i 1 ) B -........_i %e a M h? ~$ 4 \\ 9 R l l E f .::=::q m ; 4, g g l l I m N ~ _M e m o I/ lod =i: M m

Figure 10 R ES ER VOIR MONITORING NETWORK 57 SEQUOYAH NUCLE AR PL ANT DAYTON (MILE 503.8 DAYTON) b MILE 497 MILE 496.5 SODDY (LITTLE SODDY CREEK MILE O.5, SOODY-DAISY) DAISY f SEQUOYAH MILE 485 NUCLEAR PLANT l MIL E 48 3 4 MILE 480B r MILE 478 y CHICKAMAUGA MILE 477 DAM (MILE 470.5, E.1. DUPONT) NtLE 4 73.2 l ( MILE 4 7 2.8 i I (MILE 465 3, CHATTANOOGA) h SHORELINE SEDIME NT

• _ AUTOM ATIC WATER SAMPLE R (MILE). DRINKING WATER SOURCE l

O 5 P--e H MILES m.. -n

r E 59 [ Quality Control i [ A quality control program has been established with the ] { Tennessee Department of Public Health Radiological Laboratory and the = p Eastern Environmental Radiation Facility, Environmental Protection [ Agency, Montgomery, Alabama. Samples of air, water, milk, fish, and E soil collected around nuclear plants are forwarded to these laboratories { for analysis, and results are exchanged for comparison. = I- { Data Analysts 5 Data measured at the control stations for each medium were ( ,j averaged for each sampling period. In order to describe the distri-bution 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 the basis for comparing control and indicator data. If the indicator data fall ? within the 3-sigma limits defined for control data, we conclude that ( 3 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. i \\ = i A Conclusions = [ A vast majority of the indicator station data was found to be within 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 radio-nuclides in samples for indicator stations. Many of these values may p be discounted because the error reported by the analysis program was greater than the calculated concentration. The remaining isolated, p elevated concentrations may be the result of fallout, fluctuations in 5 r 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. L I J Dose estimates were made from concentrations of radioactivity i found in samples of environmental media such as air, milk, drinking i water, and fish. Doses estimated for persons at the indicator locations 4 3 were essentially identical to those determined for persons at control locations. Greater than 95 percent of those doses were contributed by [ the naturally occurring radionuclide potassium-40, and by strontium-90 a i and cesium-137 which are long-lived radioisotopes found in fallout from nuclear weapons testing conducted over the last several years. 25 4

60 From the above analysis of the data and from the trend plots presented earlier, it is concluded that there we c no significant increases in the exposure to members of the general public attributable to the operation of SQN. Indications of the presence of amall quantities of fission products have been seen in sampled media such as vegetation, Asiatic clams, and sediment. The levels measured were extremely low, for example near the nominal lower limits of detection, and were well below the reporting levels required by the NRC. No increases of radioactivity have been seen in water samples. These media will be monitored closely for indications of increases. i I O

E ~ '7 s TENNESSEE VALLEY AUTHORITY CHATTANOOGA. TENNESSEE 37401 400 Chestnut Street Tower II April 29, 1985 Director of Nuclear Reactor Regulation Attention: Ms. E. Adensam, Chief Licensing Branch No. 4 Division of Licensing U.S. Nuclear Regulatory C'ommission. Washington, DC 20555

Dear Ms. Adensam:

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - SEQUOYAH NUCLEAR PLANT UNITS 1 AND 2 - DOCKET NOS. 50-327 AND 50-328 - OPERATING LICENSES DPR-77 AND DPR-79 In accordance with the Sequoyah Nuclear Plant technical specifications, 6.9.1.6 and 6.9.1 7, for units 1 and 2 enclosed are ten copies of the Annual Radiological Environmental Operating Report for 1984. If you have any questions, please get in touch with Jerry Wills at FTS 858-2683 Very truly yours, TENNESSEE VALLEY AUTHORITY D. E. McCloud Nuclear Engineer Sworn to. d subscribe bergre me this 9.IIdayof ~ A< l 1985. llth / Notary Public p "O g My Commission Expires / - Enclosure (10) oc: U.S. Nuclear Regulatory Commission L Region II Attn: Dr. J. Nelson Grace, Regional Administrator 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 i 1 6' l 3\\t* An Equal Opportunity Employer }

1 1 I ERRATA SHEET FOR ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT SEQUOYAH NUCLEAR PLANT 1984 1. Page 29, table 11, Milk, the K-40 mean reported as "164.43" should be "1340.90." i ... - - - -}}