ML20210B153

Annual Radiological Environ Operating Rept,Sequoyah Nuclear Plant,1986

ML20210B153
Person / Time
Site:	Sequoyah
Issue date:	12/31/1986
From:	Gridley R TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
NUDOCS 8705050245
Download: ML20210B153 (61)

Text

,

TENNESSEE VALLEY AUTiloltITY I

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT SEQUOYAH NUCLEAR PLANT 1986 It AI)l01.OGICAI, CONTit01.

Sp03U$0$$Eo$o$ob27 PDR R

r ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT SE0VOYAH NUCLEAR PLANT 1986 1

I i

TENNESSEE VALLEY AUTHORITY O! VISION OF NUCLEAR SERVICES RADIOLOGICAL CONTROL i

April 1986 i

I

CONTENTS Page til List of Tables.....

IV List of Figures Introduction............................

1 Atmospheric Honitoring.......................

11 Terrestrial Monitoring.......................

23 Reservoir Monitoring........................

41 55 Quality Control 55 Data Analysis 55 Conclusions 11

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

3 Table 2 - Atmospheric and Terrestrial Monitoring Station -

Sequoyah Nuclear Plant 4

Table 3 - Detection Capabilities for Environmental l

Sample Analysis.....................

5 l

Table 4 - Results Obtained in Interlaboratory Comparison l

Program.........................

7 Table 5 - Maximum Permissible Concentrations for Nonoccupational Exposure

.......................13 4

Table 6 - Radioactivity in Air Filter...............

14 Table 7 - Radioactivity in Rainwater

...............15 Table 8 - Radioactivity in Charcoal Filters............

16 l

Table 9 - Radioactivity in Atmospheric Molsture..........

17 Table 10 - Radioactivity in Milk..................

27 Table II - Radioactivity in Vegetation...............

28 i

Table 12 - Radioactivity in Soll..................

29 l

Table 13 - Radioactivity in Hell Water...............

30 l

Table 14 - Radioactivity in Public Water..............

31 l

Table 15 - Environmental Gamma Ridlation Levels 32 l

Table 16 - Radioactivity in Cabbage 33 Table 17 - Radioactivity in Corn..................

34 i

Table 18 - Radioactivity in Green Beans 35 Table 19 - Radioactivity in Potatoes................

36 l

Table 20 - Radioactivity in Tomatoes................

37 Table 21 - Radioactivi ty in Apples.................

38 Table 22 - Sampling Schedule - Reservoir Monitoring

........43 Table 23 - Radioactivity in Surface Water, Total..........

44 Table 24 - Radioactivity in White Crapple (Flesh)

.........45 I

Table 25 - Radioactivity in Channel Catfish (Flesh)

........46 Table 26 - Radioactivity in Smallmouth Buffalo (Flesh).......47 Table 27 - Radioactivity in Smallmouth Buffalo (Whole).......48 Table 28 - Radioactivity in Sediment................

49 Table 29 - Radioactivity in Shorellne Sediment...........

50 t

Table 30 - Radioactivity in Clam Flesh...............

51 111 t

List of Figures Figure 1 - Tennessee Valley Region.................

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

18 Figure 3 - Local Monitoring Stations - Sequoyah Nuclear Plant 19 Figure 4 - Sequoyah Nuclear Plant - Site Monitoring Stations.... 20 Figure 5 - TLD Stations - Sequoyah Nuclear Plant.......... 21 Figure 6 - Annual Average Gross Beta Activity in Air Filters -

Sequoyah Nuclear Plant 22 Figure 7 - Annual Average Gross Beta Activity in Orinking Water - Sequoyah Nuclear Plant 39 Figure 8 - Olrect Radiation Levels - Sequoyah Nuclear Plant 40 Figure 9 - Direct Radiation Levels - Sequoyah Nuclear Plant -

4-Quarter Moving Average 40 Figure 10 - Annual Average Gross Beta Activity in Surface Water -

Sequoyah Nuclear Plant 53 IV

i ANNUAL RADIOLOGICAL ENVIRONNENTAL OPERATING REPORT 1

SEQUOYAH NUCLEAR Pl, ANT i

1986 i

Introduction The Sequoyah Nuclear Plant (SQN), operated by the Tennassee 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) i 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 MNt and 1,171 i

MWe, Fuel was loaded in unit I on March 1, 1980, and the unit achieved i

I criticality on July 5, 1980.

Fuel was loaded in unit 2 in July 1981, and l

the unit achieved initial criticality on November 5, 1981.

The plant has been shut down since August 1985.

This report describes the environmental radiological monitoring conducted in 1986.

The preoperational environmental radiological monitoring program i

established a baseline of data on the distribution of natural and manmade i

radioactivity in the environment near the plant site.

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

In order to i

determine the potential increases in environmental radioactivity levels caused by the plant, comparisons were made between data for indicator i

stations (those near the plant) and control stations (those remote from l

the plant) In conjunction with comparisons with preoperational data.

Radiologlal Control (Office of Nuclear Power) and the Office of 1

)

Natural Resources and Economic Development carried out the sampling program outlined in tables 1 and 22. 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 radlochemical and Instrumental analyses were conducted in TVA's Western Area Radiological Laboratory (WARL) located at Muscle Shoals, Alabama. Alpha and beta analyses were performed on Beckman Low Beta II, and Tennelec LB l

5100 low background proportional counters. Gamma spectral analyses were performed with a Nuclear Data (ND) Model 6700 multichannel analyzer system utilizing germanium detectors.

Specific analysis for I-131 in charcoal filters is performed using Na!(TI) well detection systems l

attached to single channel analyzers.

TVA-fabricated beta-gamma i

coincidence counting systems are utilized for the determination of I-131

~

concentrations in milk.

Tritium determinations are made with Packard j

frl-Carb 3255 or 4000 series liquid scintillation counting systems.

)

I l

i

2 Data were entered into computer storage for processing specific to the analysis conducted.

The data obtained by germanium detectors were resolved by the appropriate analyzer software and the software program HYPERNET.

The detection capabilities for environmental sample analysis given as the noriinal lower Ilmits of detection (LLD) are listed in table 3.

All photopeaks found in germanium spectra were identified and quantified. Many of the isotopes identifled by germanium spectral analysis are natural occurring or naturally produced radioisotopes, such as Se-7, K-40,81-212, B1-214, Pb-212, Pb-214, Ra-226, etc. 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 identifled 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 Studles Program conducted by the Environmental Protection Agency (EPA)*Las Vegas.

This program provides periodic cross-checks on samples of the type and radionuclide composition normally analyzed in an environmental radiological monitoring program.

Routine sample handling and analysis procedures were employed in the evaluation of these samples.

The results received during calendar year 1986 are 1 o Ilmits based on one measurement were divided 3

shown in table 4.

The by the square root of 3 to correct for tripitcate determinations.

Tabla 1 ENVIB0 MENTAL BADIQACTIVITY SAWLING SCMDULE Air Charcoal Rain-Atmospheric Elwer Well Public Aquatic Life Station Location Filter Filter waterC Moisture Soil Vegetation Wilk Water Water Water and Sediment Chattanooga W

W M

A N

N Dayton W

W M

EW A

E N

i Daisy W

W N

A N

N l

Volunteer Ordinance W W

M A

N Works (Harrison)

Chester Frost Park W

W M

A E

l Cito N W

W M

BW A

N l

Bank Rec Park W

W M

BW A

N Skull Island W

W N

A N

5 Were Point W

W N

A N

Lakeside W

W N

A N

l Cleveland TN W

W N

A N

Dunlap. TE W

W M

A N

I Fam J M

BW Fam IEi N

SW Q

l Farm N*

M BW I

Fam Le N

Farm Hb N

EW Fem uN N

Fam Be M

Fam G E

l Chickamauga N

S 1

Reservoir

)

C. I. Dupont M

l C. F. Industries N

onsite Well (1)

Q Farm S (Control)

N BW Barm B (Control)

M BW Farm C (Control N

BW W - Weekly BW - Biweekly N - Monthly (overy 4 weeks)

Q - Quarterly 3 - Sealannually A - Annually c.

Dairy farm ceased operation in August 1986 b.

Dairy farm added to sampling program in September 1986.

w c.

Analyzed only if fallout activity is suspected.

4 Table 2 Atmospheric and Terrestrial Monitoring Station Locations Sequoyah Nuclear Plant Approximate Distance and Sample Station Olrection from Plant LM-2 SQ, Northeast 0.75 miles (1.2 kilometers)

N LM-3 SQ, Rec Park 1.5 miles (2.4 kilometers)

SSW LM-4 SQ, Skull Island 1.5 miles (2.4 kilometers)

NE LM-5 SQ, Ware Point 1.7 miles (2.7 kilometers)

NNE PM-2 SQ, Chester Frost Park, TN 3.75 miles (6.0 kilometers)

SW PM-3 SQ, Daisy, TN 5.5 miles (8.8 kilometers)

W PM-8 SQ, Harrison, TN 8.75 miles (14.1 kilometers)

SSW PM-9 SQ, Lakeside 2.7 miles (4.3 kilometers)

WSW RM-1 SQ, Chattanooga, TN (Control) 16.75 miles (27.0 kilometers)

SW RM-2 SQ, Dayton, TN (Control) 17.75 miles (28.6 kilometers)

NNE RM-3 SQ, Cleveland 11.3.nlles (18.1 kilometers)

ESE RM-4 SQ, Dunlap, TN 19.5 miles (31.2 kilometers)

WNW Farm J 1.25 miles (2.0 kilometers)

N Farm HW l.25 miles (2.0 kilometers)

NW Farm M*

3.5 miles (5.6 kilometers)

NNE Farm Le 3.5 miles (5.6 kilometers)

S Farm H*

4.3 miles (6.9 kilometers)

NE Farm EM 2.5 miles (4.0 kilometers)

N Farm Br 2.25 miles (3.6 kilometers)

SSW Farm G 1.5 miles (2.4 kilometers)

NNW Farm B (Control) 43.0 miles (69.2 kilometers)

NE Farm C (Control) 16.0 miles (25.7 kilometers)

NE Farm S (Control) 12.0 miles (19.3 kilometers)

NME a.

Dairy farm ceased operation in August 1986.

b.

Added to sampling program in September 1986.

Table 3 P

DETECTtos CAPAsttIIIEs TCE EnglacePENTAL SArett AmALYSIS i

A.

Specific Analyses F

NcesmAL LOWER LIself 0F DETECitoes (t19)*

Fish.

Air vegetation Soll and Clam Flesh.

Foods, seest, Particulates Chercoat Fallout idater and Crain Sediment

Flankton, Clan Shells Poultry.

Milk pCI/m*

pCI/a' mCIImm' pC3/t pCI/s. Sry pCl/s, Dry pCl/q, Bry pCI/q, try pCI/Es,idet Q

Cross e 0.005 2

0.c5 0.35 0.1 0.7 Gross 8 0.01 0.05 2

0.20 0.70 0.1 07 25 D-3 330 3-131 0.01 0.5 Se-83 0.005 30 0.25 1.5 0.5 5.0 4

10 t

St-30 0.001 2

0.C5 0.15-0.3 1.0 8

2 r

• All LLS walmes for Isotopic separations are calculated by time method developed by Pasterneck and Steeley as described in 9045L-300.

Factors such as sample slae, decay tBee, che=Ical yleid, and counting efficiency mey very for a given sample; these worlations mey change the LLS welee for the given sample. The assymetlen Is meste that all samples are analysed i.Ithin ene week of tine s

collectlen dete. Conversion factors: 1 pCI = 3.7 m 10 Seg; I aCl - 3.7 m 10' Sat.

8

[

[

w l

_.~_m,-

.-.mm

,~,.---~1-.

e

.-..,-r-,

3,,

i Table 3 (Continued)

C(TECTIO4s CAPAS ttlTIES FCit EltylR0nPENTAL SAsett AssALY585 5.

Camma Analyses h0MimAL LC%TR LIMIT CF CETECTION (LLD) air Water Wegetation Soll and Ctam flesh Foods, (tomatoes Heat and particagates and mItk and grain sediment Fish and plankton Clae shells potatoes,etc.)

poultry pCl/m pCl/L pCl/g, dry pCi/q, dry pCI/g, dry pC3/q, dry pCI/q, dry pCI/Eg, wet pCl/Eg, wet M L6)*

Ge(Li)

Getti)

Ge(L.)

Celli)

Ge(Li)

Ce(Li)

Ce(Li)

Ce(LI)

Ce-1 M 0.C2 33 0.22 0.06 0.C6 0.35 0.c6 33 40 Cr-51 0.03 0.47 0.10 0.10 0.56 0.10 44 30 5-Ill 0.01 8

0.03 0.32 0.02 0.07 0.02 8

20 Ra-IC4 0.03 30 0.51 0.35 0.II 0.7%

0.II 40 90 Cs-13%

0.cl 5

0.33 0.05 0.07 0.48 0.08 26 40 Cs-137 0.01 5

0.06 0.c2 0.02 0.05 0.02 5

15 Ir-SS 0 Ct to 0.11 0.03 0.03 0.35 0.03 10 20 al>-SS 0.01 5

0.05 0.05 0.01 0.07 0.01 5

IS Co-53 0.ct 5

0.05 0.01 0.01 0.07 0.01 5

15 rw-55 0.Cl 5

0.05 0.01 0.01 0.05 0.01 5

15 In-45 0.Cl 3

0.st 0.c2 0.c2 0.17 0.02 3

20 Co-60 0.Cl 5

0.04 0.01 0.01 0.08 0.03 5

15 Fe-53 5

0.10 te-140 0.C2 25 0.3%

0.07 0.07 0.30 0.07 25 50 La-l%Q 0.01 7

0.05 0.02 0.02 0.10 0.02 7

15

• The Ce(LI) LLD walues are calculated by the method develcped try Fasteranck and Marley as described in HA5L-300. These LLD values are e=pected to vary depending on the actleities of the components in the sasples. These figures do not represent the LLD values achievable en g4wm samples. Water is co=nted in either a 0.5-L or 3.5-L narinell! beaker. Solid sa oles, such as soil, sediment, and cle= shells, are cow ted is a 0.5-4. MariseIII beaker as dry weight.

The average dry weight Is 600-500 grams. Air filters and very small volume i

sarples are counted In petti dishes centered on the detector endcap. The counting systes consists of a MD-6700 multichannel analyrer j

and gernmium detector heeleg an etficiency of 20 percent. The cowiting time is normally 4-85 hours. All spectral analyses are performed is made that all samples are analyzed within one week of the collection date.

esieg the sof twre program ettPERFIT. 2The assemoti n Conversion factoe: I pCI = 3.7 m to-84.

l l

l L

l TABLE 4 EE5utT5 Cef atwED 14 InfEaLASCRAt0Er C09A2150es FROGRkt A.

Air F ef ter (pC /F blter)

Gran Airks Gr; R gta jtrete& L Cesites 137 EFA walee I.A EPA walme i.A EPA value iba EPA walve IVA "d t

!?37 A-0.

f?34 h

ft35 h

f*3d A,s.

4/M 1521 14 47,9 51 1923 13*

1029 13 SIM 22 %

21 t6 9 68 22:1 23 22:3 20 2

2 8.

a 44. chemical Analpis of imater IpCi/D Ce m tia _

__.lir2"lis*_-E2_

_.itreii&91_

Tritiue I; tire-13I EPA walee 1.1 EFA walve i.A

[FA walee IdA EPA =alue IVA EPA walve IVA Cale f$37 E.L f?M1 Aan ftM1 as f* 3c1 A g.

I v71 Avg.

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2 l

2/to 5227 906 4643 2

9 10 9

2/%

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621 12 7%

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73 6

4/%*

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2 4/*6 9210 8

15 1 16 5/36 2

Ere6 38252624 2777 19 1 22 F/%

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8/?6 451 0 AS 1

9/25 8+1 IG 13/%

597321034 5333 IS/M' 51,9 40*

1019 16 43 3

IIIt$

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C.

Gamma-Spectral Analysis of Water (pCi/IJ

_ D rce_igo-Si Cchalt-10 Zi#c-65 Ruthenium-106 Cesiue-134 Cesium-137 EPA walve TVA EPA walse IVA EPA walue TWA EPA walve IVA EFA walue IVA

[PA value IVA Date f *3 '"5 AA f?3M Avg.

f* 3 ?1 A,2..

f* 3'J1 Av1t.

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2 2

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10/86*

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os I

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5treati M _

_ 5tretiwa r4 Indiee-131 Cesism.137 Potassium-40' 4

EPA walee fwa EFA walve IWA EPA walee IWA EPA walue TWA EPA walve IVA A

f* 3 9 Avg.

(+ 3c1 Arc.

1. 371 Arm (t 3m pyg.

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testk (pCi/L3 1

S t ret t ua-8 }

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f* 301 Arh j

L 42 io di 56 9 55 1540t 33 1533 1

i 13/35 43 9 63' 26t3 26 t

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1613 16 41210 42 31 9 34 16002 39 1677 1

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49210 48 39 9 43 15652135 1633 1

The le= results for Sr-90 were associates with a poor chemical yield due to chemical separation problems.

a.

j b.

Laboratory performance evaluation study.

c.

Selow tid.

The cause of the 16. gross beta results could not be clearly identified. However, problems appear to d.

esist with a large percentage of the other participatieg laboratories not being able to obtain agreement j

with the EPA method of calculating the known gross beta activity for LPES cross-checks.

e.

Valises rep @rted as og E/Eg-Ieoperature variatsoms case predece siner gain shif ts in the detection systees. The low abundance and low 4

f.

counting etisciency for the 1460 kev line used f or identification of K-40 combined with a minor gain shift will prodote resalts with a large bias.

Valses reported as og Elliter.

j g.

Results were investigated, but the source of the high result for Sr-89 could act be clearly identified.

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11 Atmospheric Monitorine The atmospheric monitoring network is divided into three subgroups; local monitors, perimeter monitors, and remote monitors.

Four local monitors are located within or near the plant boundary.

Four r

perimeter monitors are located at distances out to 10 miles and four remote monitors, which are used as control or baseline ste.tlons, are located between 11 and 20 miles from the site.

l Each monitoring station consists of an air sampling system and a l

collection tray and storage container to continuously collect rainwater.

The rainwater is analyzed only if *allout activity is sJspected.

Selected stations are equipped with a Geiger-Mueller (GM) tube with a recorder to continuously monitor and record gamma radiation levels.

Additionally, at two local and one remote monitors, moisture is collected from the atmosphere and analyzed for

'H.

The air particulate system uses a 1-7/8-inch (47m) diameter glass fiber particulate filter.

The charcoal filter used to sample i

alrborne radiolodine is a 2-1/4-inch (57m) diameter,1-inch (25.4m) thick filter filled with TEDA-tmpregnated charcoal. The particulate and j

charcoal filters are contained in a round cone-shaped filter holder Iocated on the outside of the monitoring station and protected from rain by a metal overhang.

Air is continuously drawn in through the particulite and charcoal filter by an air puep at a flow rate of approximately 2 CFM.

The total flow through the system is measured with a domestic type dry gas meter.

[

l Each of the local and perimeter air monitoring stations is l

fitted with a GM tube that continuo'asly monitors the gama activity i

levels at the stations.

The disintegration rate of the atmospheric radioactivity is continuously recorded at each station.

The data from three local monitors (LM 2, LM 3, and LM 5) and from three perimeter i

monitors (PM-2, PM-3, and PM-9) are transmitted via radiotelemetry into i

the environmental data station.

This system is in the process of being I

removed.

i l

Table 5 presents the maximum permissible concentrations l

(MPC) specified in 10 CFR 20 for nonoccupational exposure, j

Air Filters l

i Air filters are collected weekly and analyzed for gross beta activity. Adequate time is allowed for decay of radon daughters between f

I collection and analysis.

This time period is typically 3 days.

The t

samples are composited monthly for analysis of specific gamma-emitting i

radlonuclides. Due to fallout from the Chernobyl nuclear reactor accident, one set of weekly air filters received a gamma scan for i

specific gamma-emitting radionuclides, increased levels of I-131, Ru-103, CS-137, and Cs-134 were identified in these samples.

The results of analyses are sumarized in table 6.

During this report period, 33 1

l samples were not collected because of equipment problems. An increased

12 incidence of pumps being off was eventually traced to the installation of smaller pulleys, which resulted in increased heat bulldup and automatic shutdown of the units. Appropriate size pulleys were installed, thus alleviating the problems.

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 1971-1986 are presented in figure 6.

Increased levels due to fallout from atmospheric nuclear weapons testing are evident, especially in 1971, 1977, 1978, and 1981.

Increased levels from the accident of the Chernobyl nuclear power station are also in evidence.

These fluctuations are consistent with data from radiological monitoring programs conducted by TVA at nonoperating nuclear power plant construction sites.

Rainwater Rainwater samples were collected monthly from each of the atmospheric monitoring stations.

The samples are analyzed only if radioactivity levels in other media indicated the presence of increased levels of fallout. During this report period, samples from one control station (as part of the Hatts Bar Nuclear Plant program) were analyzed monthly for gamma-emitting radionuclides and for strontium content.

In addition, samples collected during the Chernobyl accident fallout period vere analyzed for gamma-emitting nuclides.

I-131 was identified in four samples, with the highest value approximately 33 pCl/L.

The above data are reported in table 7.

Charcoal Filter Charcoal filters are collectea weekly and analyzed for radiolodine.

Each filter is counted in a single channel analyzer system. During the period of suspected fallout from the accident at the Chernobyl nuclear power station, a gamma spectral analysts was performed on each sample.

Samples collected following the accident at the Chernobyl nuclear power station exhibited increased levels of I-131.

The highest level reported was 0.17 pCl/m'.

In 1986, 33 samples were not collected because of the equipment problems noted above, one filter was destroyed during analysis, and one sample was lost during processing.

The data are summarized in table 8.

Atmospheric Holsture An atmospheric moisture collection device containing molecular sieve is located at two local monitors and at one remote monitor.

Samples are taken every other week, the moisture driven off the molecular sieve, collected in a cold trap, distilled, and counted for 'H content.

The results are shown in table 9.

During this reporting period, 5 samples were not collected because of equipment malfunction and 21 samples contained insufficient volume for analysts.

4 13 Table 5 4

MAXIMUM PERMISSIBLE CONCENTRATIONS FOR NONOCCUPATIONAL EXPOSURE a

3 MPC

{

In Water In Air pCi/l*

pCi/m3*

3' Alpha 30 Nonvolatile beta 3,000 100 Tritium 3,000,000 200,000 137Cs 20,000 500 103,106Ru 10,000 200

~

344Ce 10,000 200 88Zr 98Nb 60,000 1,000 j

140Ba.140La 20,000 1,000 j

1311 300

100, 652n 100,000 2,000

{

84Hn 100,000 1,000

~

60Co 30,000 300 4

j 88Sr 3,000 300 80Sr 300 30 l)

SICr 2,000,000 80,000 134Cs 9,000 400 j

t ssCo 90,000 2,000 89Fe 50,000 2,000 l

• 1 pCi a 3.7 x 102 Bq.

Source:

10 CFR, Part 20, Appendix B, Table II.

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RADI0 ACTIVITY IN ATROSPMERIC MOISTURE PCI/M(3) 3.037 93/*(3)

NAME OF FACIL*Tf,$ggy2I33..__..____....______________..........

DOCKET N0._10-32Z:323.......__...

LcCATIc4 Os FACILITv_ga ILI23. ______________.Ishhis5::._______.......

4EPORTIN3 PERIOD.I232__...____...

TYPE AND LodER LIMIT AL.

CONT 80L hu=6ER Or TOTAL huMSER OF IN3ICATOR LOCATIONS _Lyg!II;3 gII:_cI3bi31.833UAL_!E85...___

LOCATIONS NONROUTIh!

3F ANALYSIS DETECTION

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REPORT' PERFORMED (LLD) 9AN38 JISTANCE AND DIoECTION P A *. G E

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TRITIUM NOT ESTAB 7.53E-01(

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1. NOMINAL LO=ER LIMIT OF DETECTIch (LLD) AS DESCRISE3 IN TABLE 3.

NOTE:

2. MEAN AND RANGE BASED UPCN DETECTABLE MEASUREMENTS 0 *.L Y. FRACTION OF DETECTABLE MEASUREMENTS AT SPECIFIED LOCATICNS IS INDICATED Ih PARENTHESES (F).

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18 Figure 2 ATMOSPHERIC AND TERRESTRIAL MONITORING NETWORK ATMOSPHERIC AND TERRESTRIAL SAMPLES COLLECTED AT EACH STATIOft O LOCAL MONITOR

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23 Terrestrial Monitoring Terrestrial monitoring is accomplished by collecting environmental media at locations within the general area of the plant for indicators and at locations remote from the plant for controls.

In addition to milk, samples include vegetation, soll, ground water, public water.and food crops.

Environmental gamma radiation levels are determined by strategic placement of thermoluminescent dosimeters (TLDs). Once each year, a land use survey is conducted to determine census and location of milk producing animals.

Land Use Survey The land use survey was conducted during the summer of 1986.

Milk animal census and locations were unchanged from the previous survey.

Projected doses to individuals in the area were not significantly different from those calculated for 1985.

Milk Milk samples were routinely collected from three indicator locations (one of which is a commercial dairy) and from three control locations.

Raw milk was analyzed semimonthly for I-131 and gamma-emitting radioisotopes and quarterly for Sr-89 and Sr-90 content.

During August the dairy farm from which milk samples were collected ceased operations.

In September a replacement dairy was added to the sampling program.

Table 10 summarizes the analytical results. During this reporting period, 13 samples were not available for collection and one sample spoiled before analysis.

As has been noted in previous reports, the levels of Sr-90 in milk samples from farms producing milk for private consumption only are up to six times the levels found in milk from commercial dairy farms.

Samples of feed and water supplied to the animals were analyzed in 1979 in an effort to determine the source of the strontium. Analysis of dried hay samples indicated levels of Sr-90 slightly higher than those encountered in routine vegetation sanples. Analysis of pond water Indicated no significant strontium activity.

This phenomenon was obs rvec during preoperational radiological monitoring near SQN and Bellefonte Nuclear Plant (BLN) 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

24-relationship between the levels of Sr-90 in milk and the quality of fertilization and land management.'

Vegetation Vegetation samples were collected monthly from 12 air monitoring stations (semimonthly at one control location) and from 11 farms and dairies (semimonthly from three control dalries). 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 for samples taken at farms and datries.

Samples were analyzed monthly for I-131 and gamma-emitting nuclides and quarterly for strontium content.

The results of laboratory analyses are summarized in table 11.

During this report period, one sample spoiled, two samples were destroyed during analysis, and on one occasion sufficient quantitles of sample were not obtained.

Soil Soll samples were collected annually near each air monitoring station to provide an indication of any long-term buildup of radioactivity in the environment. An auger or a " cookie cutter" type sampler was used to obtain samples of the top 2 inches (5 cm) of soll.

These samples were analyzed for gamma-emitting radionuclides and Sr-89 and Sr-90.

The results are given in table 12.

Groundwater A pump sampling device collected groundwater from a well down gradient from SQN. A quarterly composite sample from this well was analyzed for gross beta activity, gamma-emitting radionuclides, and

'H.

A quarterly grab sample was also taken from a farm near 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 SQN were sampled at five locations and analyzed monthly for gross beta and gamma-emitting radionuclides.

Tritium, Sr-89, and Sr-90 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.

In 1

'Hansen, H.G., Campbell, J.E., Fooks, J.H., Mitchell, H.C., and Eller, C.H., 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.

4

25 addition, the upstream drinking water supply and the upstream surface water station are sampled by automatic samplers. These two stations are considered controls for the downstream potable water supplies. The results are shown in table 14.

Figure 7 shows the trends in gross beta activity in drinking water from 1971 through 1986.

The annual averages reported in 1986 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 (Ca,F: Mn). TLDs were placed at 21 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 1 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 TLO.

The system meets or exceeds the performance specifications outlined in Regulatory Guide 4.13 for environmental application of TLDs.

The TLDs are exchanged every three months.

The quarterly gamma radiation levels determined from these TLDs are given in table 15, which indicates that average levels at onsite stations are approximately 2-4 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 environmental radiation levels, earth moving activities onsite, the mass of concrete employed in the construction of the plant, and other undetermined influences.

Figure 8 compares plots of the data from the onsite or site boundary stations with those from the offsite stations during the period 1976 through 1986.

To reduce the variations present in the data sets, a 4-quarter moving average was constructed for each set.

Figure 9 presets a trend plot of the direct radiation levels as defined by the moving averages.

The data follow the same general trend as the raw data, but the curves are smoothed considerably.

Prior to 1976, measurements were made with less sensitive dostmeters, and consequently the levels reported in this phase of the preoperational monitoring program are 1-2 times the levels reported herein.

Those data are not included in this report.

[

26 Food Crops and Poultry Food crops raised in the vicinity of SQN were sampled annually as they became available during the growing season.

During this sampling period, samples of cabbage, corn, green beans, potatoes, tomatoes, and apples were collected and analyzed for gross beta and specific gamma-emitting radionuclides.

The results are given in tables 16 through 21.

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32 Table 15 ENVIRONMENTAL GAMMA RADIATION LEVELS Average External Radiation Levels at Various Distances from Sequoyah Nuclear Plant for Each Quarter - 1986 mR/ Quarter

• Average External Gamma Radiation Levels _*

Distance 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Miles (Feb-Apr 86)

(May-Jul 86)

(Aug-Oct 86)

(Nov 86-Jan 87) 1 0-1 23.1 1 2.2 21.2 1 3.4 21.7 1 3.4 21.4 1 1.8 1-2 18.0 1 3.5 16.7 1 4.5 19.3 1 3.7 17.8 1 2.4 2-4 16.6 1 4.2 15.1 1 3.5 16.6 1 4.4 17.3 1 2.4 4-6 16.7 1 3.1 15.4 1 3.2 17.0 1 3.8 16.9 1 2.4

>6 16.7 1 3.2 14.7 1 3.1 16.5 1 3.0 17.6 1 2.2

Average, 20.9 1 3.8 19.3 1 4.5 20.6 1 3.8 19.7 1 2.8 0-2 miles (onsite)

Average 16.7 1 3.2 15.1 1 3.2 16.8 1 3.6 17.2 1 2.2

>2 miles (offsite) a.

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

b.

Averages of the individual measurements in the set 31 standard deviation of the set.

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1. 3 (b

to e3 ee 4 4 4 e4 4 e* 2O .J 9 9 R / 8 1 ee 0 se # M 9 h 4 at fe' t to N 0 f 1 **e SJ 6es 49 0 A e e* 9 es O fn De 6) 9 M I J ES tal ses I se J 0 e o as 3 a= 3 iF es 4 e= e4 .* JW l ied e9 0

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e* U f4 N f%d 0 444 esa >+ 0= tad t wt 5 0 0 t 0 0 9 F p-O th & lo B we we e eo est .J B O ta bO Ie et ta u we as a >= 0 0 Lp 49 I Figure 7 Annual Average Gross Beta Activity Drinking Water (pCi/ liter) Sequoyah Nuclear Plant Indicator S Control Operational g Preoperational Phase Phase 8 4.5 -' Preoperational Average 3 111ilHL 71 72 73 74 75 76 77 78 79 80p 800 81 82 83 84 85 86 a ~ ai a Figura 8 23. Direct Rodiation L.v.l. 40 S.quoyoh fival.or Plant

4. b :t.

O Off. t. I 22. j i 20. 'g j i k \\ 18. j j y t p 1 S. g I l \\ A 14 lOp. cation Begin Plant iliiiIe lie il,,.Iie iI,,,!,,,[ i n, e i e i 1975.1977.1978.1979.1989.19C1.1982.1983.1984.1985.1986.1987. Figure 9 24 .g. On it. Dir ot Radiation Levela 0 04.st. Sequoyoh Nvel.or Plant

22..

4-Quarter having Averog. I 20. +b f ) Ne y a N 18. d '" ! \\cfago/F%p ~ == o I 14 IBegin Plant !0petion I i IIII*!IIII! 12. 1970. 1977. 1978. 1979. 1900. 1981. 1082. 1083. 1984. 1985. 1986. 1987. l 41 Reservoir Monitoring Samples are collected from the Tennessee River as detailed in table 22. Samples collected for radiological analysis include water and l 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. 1 Water Water samples were collected automatically by sequential type sampling devices at three cross sections and composite samples analyzed monthly for gross beta activity and gamma-emitting radionuclides. Further composites were made quarterly for strontium and tritium analyses. Results are displayed in table 23. Figure 11 presents a plot of the gross beta activity in surface water from 1971 through 1986. 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. Fish Radiological monitoring for fish was accomplished by analyses of composite samples of adult fish taken semlannually 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 preoperational monitoring program. Three species, white crapple, 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. Samples were analyzed for gamma-emitting radionuclides. Results are given in tables 24 through 27. Sediment Sediment samples were collected semlannually from four cross sections of the Tennessee River by dredge hauls made for bottom fauna. Samples were analyzed for gamma-emitting radionuclides. 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 28. Three samples were not collected because of personnel error. In addition to the sampling described above, shoreline sediment samples were collected semiannually at three recreation-use areas (two 42 downstream from the plant and one upstream) in the vicinity of SQN. Samples were taken in May and December. Samples were analyzed for gamma-emitting radionuclides, and results are given in table 29. Asiatic Clams Samples of Asiatic clams were collected semiannually with a Ponar dredge from three stations. Samples collected were analyzed only for gamma-emitting radionuclides. Results are given in tables 30 and 31. During this report period, two samples were not collected because of personnel error. ( i i l L 43 Table 22 SAMPLING SCHEDULE - RESERVOIR MONITORING Biological Samples Tennessee River Benthic Shoreline (Mile) Fauna Sediment Sediment Fish

• Water Samples 472.8 X

473.2 Automatic Sampler

• 477.0 X

478.0 X 480.8 X X 483.4 X X Automatic Sampler

• 485.0 (Control)

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• • +e-+**+

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52.

R ESER VOIR MONITORING NETWORK SEQUOYAH NUCLE AR PL ANT DAYTON (MILE 503.8,OAYTON)

I MILE 497 MILE 496.S SODDY (LITTLE SODOY CREEK MILE 0.5' SOD 0Y-DAISY)

DAISY SE000YAH MILE 495 NUCLEAR PLANT MILE 483 4 MILE 4808 MILE 478 v

CHICKAMAUGA MILE 477 DAM (MILE 470 5, E. I. DUPONT)

(MILE 473.0, C. F. INDUSTRIES) j l

MILE 4 73.2 l

MILE 4 72.8 1

l (MILE 46S.3, CHATTANOOGA)

@ SHORELINE SEDIMENT e. AUTOMATIC WATER SAMPLER (MILE). DRINKING WATER SOURCE CHATTAN000A l

0 5

H H

MILES f

l f

Figure 11 j

Annual Average Gross Beta Activity l

l Surface Water (pCi/ liter)

Sequoyah Nuclear Plant E Indicator C Control 6--

Preoperational Operational Phase Preoperational Average Phase 5

?

i llHIH IIIR 71 72 73 74 75 76 77 78 79 80p 800 81 82 83 84 85 86 l

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

Data Analysis The results from each sample are compared with the concentrations from the corresponding control stations and/or appropriate preoperational and background data to determine influences from the plant. During this report period, no activity was identified which exceeded the reporting levels outilned in Technical Specification 3.12.1.

Dose estimates were made from concentrations of radioactivity found in samples of environmental media such as air, milk, drinking water, and fish.

Doses estimated for persons at the indicator locations were similar to those determined for persons at control locations.

Greater than 95 percent of those doses were contributed by the naturally occurring radionuclide K-40, and by Sr-90, and Cs-137 which are long-lived radioisotopes found in fallout from nuclear weapons testing.

Increased levels of I-131 were reported in samples of air, milk, and rainwater following the Chernobyl nuclear power station accident.

In addition, Ru-103, Cs-137, and Cs-134 were identified in air particulate filters.

CONCLUSIONS From the above analysis of the data and from the trend plots presented earlier, it is concluded that there were no significant increase in the exposure to members of the general public attributable to the operation of SQN.

Indications of the presence of small quantitles of fission and activation products have been seen in samples of 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 Technical Specifications.

No increases of radioactivity have been seen in water samples.

These media will be monitored closely for Indications of increases.

The radioactivity reported herein may be the result of fallout, fluctuations in the existing environment, releases from other facilities, or releases from SQN. Any activity which may be present as a result of plant operations does not present a significant contribution to the exposure of members of the public.

..A TENNESSEE VALLEY AUTHORITY CH ATTANOOGA. TENNESSEE 37401 SN 1578 Lookout Place APR 301987 10 CFR 50.71(a)

U.S. Nuclear Regulatory Conunission ATTN:

Document Control Desk Washington, D.C.

20555 Centlemen:

In the Matter of

)

Docket Nos. 50-327 Tennessee Valley Authority

)

50-328 SEQUOYAH NUCLEAR PLANT (SQN) UNITS 1 AND 2 - ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT - OPERATING LICENSES DPR-77 AND DPR-79 In accordance with SQN technical specifications, 6.9.1.6 and 6.9.1.7, for units 1 and 2, enclosed is the Annual Radiological Environmental Operating Report for 1986. This report contains no conunitments.

If you have any questions, plesso telephone M. R. Harding at (615) 870-6422.

Very truly yours, TENNESSEE VALLEY AUTHORITY

/)

1

.M.

Ph64

. Celdley, Director Nuclear Safety and Licensing Enclosure cc (Enclosure):

Mr. C. C. Zech, Assistant Director for Inspection Programs office of Special Projects Division of TVA Projects U.S. Nuclear Regulatory Comission Region II 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Sequoyah Resident Inspector Sequoyah Nuclear Plant 2600 Igou Ferry Road 4

Soddy Daisy. Tennessee 37379

\\

An Equ.il Opportumty Employer

.