ML20085M479

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1989 Annual Radiological Environ Operating Rept
ML20085M479
Person / Time
Site: Perry  FirstEnergy icon.png
Issue date: 12/31/1989
From:
CLEVELAND ELECTRIC ILLUMINATING CO.
To:
References
RTR-NUREG-1437 WM, NUDOCS 9111110039
Download: ML20085M479 (39)
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4 THE PERRY NUCLEAR POVER PLANT 1989 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT l

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e TABLE OF CONTENTS

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DESCRIPTION PAGE 1

Executive Summary........................................

2 I.

Introduction..........................................

2 II.

Program Status.........................................

3 III.

Program Changes.......................................

4 IV.

Sampling Methods and Procedures.......................

4 1.

Direct Radiation.................................

5 2.

Air..............................................

6 3.

Vater............................................

6 4.

Milk.............................................

7 5.

Fish.............................................

7 6.

Sediment.........................................

B 7.

Soil.............................................

8 8.

Precipitation....................................

9 9.

Food Products....................................

9 s

J 10.

Feed / Silage......................................

9

11. Vegetation.......................................

j 9

V.

Discussion and Results................................

10 1.

Direct Radiation.................................

13 2.

Air..............................................

15 3.

Vater............................................

17 4.

Milk.............................................

20 5.

Fish.............................................

21 f.

Sediment.........................................

23 7

Soil............................................

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1 TABLE OF CONTENTS (Cont.)

DESCRIPTION PAGE 26 B.

Precipitation....................................

28 9.

Food Products....................................

29 10.

Feed / Silage......................................

30

11. Vegetation.......................................

31 VI.

Effluent Releases.....................................

32 VII.

Lover Limit of Detection..............................

32 VIII.

Land Use Census.......................................

34 IX.

Quality Assurance.....................................

34 X.

Conclusion............................................

36 Table 1: List of Sample Locations....................

Figure 1:

Sample Locations Vithin Two Miles.....

42 Figute 2:

Sample Locasions Vithin Two-Eight 43 Miles.................................

44 Figure 3: Control Sample Locations..............

45 Table 2: Missing Sample Collections..................

46 Table-3:

Summary of Results..........................

Table 4: Direct Radiation - Thermoluminescent Dosimetry Results of Quarterly and Annual 70 Field Cycles 1989...........................

Table 5: Comparison of TLD Direct Radiation Results Comparing Quarterly Sums 71 and Annual Results..........................

Table 6:

Plant Gaseous Effluents taken from the 1989 Semiannual Radioactive Effluent 72 Release Report..............................

Table 7: Plant Liquid Effluents taken from the 1989 Semiannual Radioactive Effluent 74 Release Report..............................

11

TABLE OF CONTENTS (Cont.)

1 DESCRIPTION PAGE Table 8:

Summary of Radionuclides Associated with Light-Vater Reactors and the Activity Reported, from the PNPP Radiological 76 Environmental Monitoring Program............

Table 9: Nearest Carden by Sector and 77 Deposition (D/0) Value......................

Table 10: Nearest Resident by Sector and 78 Dispersion (X/0) Value......................

Table 11: Milk Animals by Sector and 79 Deposition (D/0) Value......................

Table 12: Froduce Grovers Vithin Vicinity of PNPP.....

80 Table 13: Recreational Areas and Public Drinking 81 Vater Facilities............................

82 Figure-4: Land Use Census Hap...................

83 Table 14: EPA Intercomparison Program 1989............

Table 15: Environmental TLD Results - Quality 86 Control Spiking Program 1989................

Appendix A 1989 Radiological Environmental A

Monitoring Program Data................

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EXECUTIVE

SUMMARY

is a summary of the PNTP Kadiological Environmental Monitering This report The report includes a review of the results of sampling Program for 1989.

performed in 1989, as well as a comparisca with preoperationel results and The report also includes r-sults f rom the 19891.and Use Survey, 1988 results.

the EPA Cross-Check Intercomparison Program, and the TLD Irradiation Prograr.

A total of 3261 environmer.tal samples were collected and analyred in 1989, in accordance with the PNPP Technical Specifications for rladiological Environmental Monitoring.

The presence of cs-137, and 57-90, vere detected in several samples, such asAfter further re sediment, soil, milk, fish, and sater.

that the activity detected in these samples was not from the plant.

The results of all the analyses per Lrr.ed in 1989 show no significant activity from naturally occurring radionuclides. These results were other than that It can be similar to those observed durir.g the preoperationai period.

concluded that the Perry Nuclear Tover Plant eperation did not have a measurable impact on the environmcnt duri:g 1939.

1 _ _ _ _ _ _

I PERP,Y POVER PLANT RADIOLOGICAL ENVIRONMENTAL HONITORING PROGRAM 1989 ANNUAL REPORT 1.

INTRODUCTION The Perry Power Plant is a BVR plant v!th a capacity to generate The main condenser circulating vater is cooled by a 1205 MVe, The plant is located on closed-loop natural draft cooling tower system.

Lake Erie, on approximately 1100 acres about thirty-five (35) miles northeast of Cleveland, Ohio.

During 1989, Unit 1 produced 16,245,873 eegavatt-hours of Fross thermal energy and was operational (critical) for 4997 hours0.0578 days <br />1.388 hours <br />0.00826 weeks <br />0.0019 months <br />.

In 1989, the first refueling outage for the Perry Power Plant occurred.

The generator came off line for the outage at 03:39 Peoruary 22 and was back on line 10:32 August 5.

The outage duration was approximately 164 days.

.The primary objective of the PNPP Radiological Environmental Honitoring' radiation and radioactivity levels Program is to measure ambient direct The within a tventy-five mile radius around the Perry Pover Plant.

objectives of this program are conducted in accordance with the PNPP Technical Specificction Section 3.12 Radiological Monitoring Program.

Prior to initial criticality on June 6, 1986, the program compiled several years of preoperational data to establish a baseline database.

The operational data is :ompared to preoperational data to determine if radiation or radioactivity has been contributed to the any direct enviranment from the plant.

11. PROGRAM STATUS During 1989, the Perry Operational Radiological Environmental Honitoring Program conristed of seven air sampling locations, five water sampling locations-(increased to six in September), six milk sampling locations (increased to seven in December), thirty-five TLD (Thermoluminescent Dosimeter) locations, six precipitation sampling locations, two fish sampling locations, four sediment sampling locations (increased to seven The food product locations in May), and eight soil sampling locations.

were divided into three sections with the following number of stations; ling locations, feed / silage-six sampling locations, and produce-four samP vegetation (wh!ch includes grass and leaves)-five sampling locations.

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and tvn fish-J' TLD locations one :through twenty-four, the four sediment

sampling locations were placed-into_ operation in 1981. In:1982, sample collection:vas' started for air, vater, milk, and food products / silage.

In 1988, the The program vas, augmented in 1985 to include st.ov and soil.

h snov and method for collecting-precipitation vas modified to. include bot Prior--to 1988, only.snov vas collected when available.-.51though rain.

precipitation and soil samples are not required by the NRC Branch Technical Position en Radiological Environmental Monitoring (Revision 1).

or the PNPP Technical Specifications-for Radiological Environmental t

Monitoring, the two media have been added to the program to expand the

. scope of environmental monitoring.-

The location of each sampling location within a twenty-five mile radius' of.the Perry Plant is shovu in Figures'1, 2, and 3.

Figure 1 shows all sampling locations within a.tvo mile radius of the plant. Figure 2 shovs-all sample-locations approximately two to eight. miles from the plant and Figure 3 shows all control locations greater-than nine miles from the plant.

Table 1 identifies each sample _ station by number, the-distance from the A description of each plant site and direction.from_the plant site.

sample location _and the media pathvay found in that particular sample location are also fcund.in Taole 1.

In'1989, several samples from different environmental media were not Table 2 lists collected:due to_circunstances beyond the control of PNPP.

l-the samples, their' location, the collection date,-and a brief reason why each sample vas not collected.

III. PROGP.AM CHANCES-

There vere several changes to the~ program in 1989. These changes include the addition and deletion of-sample locations as follows:

Three new sediment sampling points were added to the May-sampling program. These sampling points are:

location 63

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'(minor stream outlet to Lake Erie) 400 feet NNE, location 64 (NV drain inpoundment outlet to Lake Erie) t 450 feet NV, and location 65 (major stream outlet to

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Lake Erie) 950 feet V.

These locations were added-as a result of_a recommendatian from American Nuclear Insurers to monitor-sediment from on-site stream:3.

One produce location'(location 49) vas deleted while a new

, August Location 49 produce locatica (location 67) was added.

(4385 Lockwood Road) 0.8 of a mile NE, was= deleted because the-resident' reported that_he would no longer have a Location 67 (5674 N. Ridge Road-in Madison) garden.

2.9 miles E, was added as a result of being identified in-the 1989 Land Use Survey.

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a A nev/ drinking vater
intake-(location 68) was added to the

_ September

.vaterfsampling program. -Location 68 (Ohio-American Vater-Company - Ashtabula Plant) is~ located 19.5 miles ENE. It was added to eventually replace the'eurrent control location l8-(CE1 Ashtabula Generating _ Station) located i

  • 2 miles ENE. Several months of background data vill be collected before location 68 vill become the new control-

- The control point is being-location beginning in 1990.

changed-to.svitch from an industrial sampling location to a drinking vater _ sampling location.

.A new milk location was added. Location 69 (John Rhoades December Farm, Chester Township)_18.7 miles SSV, was added to become the new control location. This location is located' in the least predominant vind. direction as opposed to'the c.ontrol location used in.1989. (location 51, Rettger Farm, 9.6: miles 5) vhich vas' located in the second to least

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predominant.vind direction. Location 69 vill-be the

- control location ier 1990.

IV. SAMPLING METHODS' AND PROCEDURES To derive meaningful and useful data from the program, sampling methods and procedures have been developed which provide samples representative

.The methods A* scribed herein of= potential _pathvays to man for the area.

were usedifor sample collection in.1989.

t An Samples were. collected at indicator locations and control locations.

indicator location is a location near the plant that.has a high probability-of-detecting plant effluents, vhereas, a control location is a location that is away from the plant and the probability of influence by the plant effluents.is lov.

-1.

DIRECT RADIATION Environmental -thermoluminescent dosimaters (TLDs) were used _ to measure the direct and ambient radiation levels at thirty-five Environmental TLDs1 vere-loceted locations as described in Table 1.-

in two rings around the station as well as along the site boundary.

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The' inner; ring measured direct radiation within a one-mile radius-around the pinnt, whereas, the outer' ring measured direct radiation at an approxiaate distance of four to five miles from the station,

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The site boundary-ranges from 0.42 miles in the NE sector to 0.82 miles in'the SSE sector.

Control TLD's were placed in tvo locations approximately-ten kiles-in distance in the two least prevalent. wind directions from the I

plant.

-The area around the plant is divided into 16' radial sectors, each.of E

Environmental TLDs were placed in each vhich is 22 1/2 degrees.

those sectors which radiate from the site directly out l

sector except over1the lake without intersecting any unrestricted areas over land.

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Each environmental TLD consists of a calcium sulf ate vnfer with "t-dysprosium impurities. Each location had one field environmental TLD, one emergency environmental TLD, and one annual environmental The field environmental TLD and the emergency environmental

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TLD.

TLD vere collected quarterly, whereas. --the annual environmental TLD vas-scheduled to be collected once a year.

The field environmental TLD vas the primary environmental TLD used for measuring direct radiation exposure and the results are included Results from the annual environmental TLDs are also in this report.

However, because the emergency environmental TLDs were included.

intended to be used only under emergency. conditions and because they may-be removed from their locations at intermittent times during the year, the results of the emergency environmental TLDs were not included in this report. In'certain situations in which the field environmental TLD is lost and the emergency environmental TLD data for:that location exists, the' emergency environmental TLD data is substituted for the lost TLD data.

Transient TLDs vere used during transportation to correct for any direct radiation not received during the field cycle. Special control TLD's vere kept in a. lead-shielded container. These special control TLDs can be used in conjunction with the other control field environmental TLDs to determine if any abnormal exposure recorded on a TLD or a Eroup of TLDs was attributed by the plant.

4-All environmental TLDs vere packaged at the site and vere shipped by commercial freight to the vendor-laboratory for analysis.

2.

AIR.

These air Air samples were collected weekly at seven locations.

samples consist of glass fiber filters and charcoal cartridges. The glass fiber filters vere used to collect particulates and the charcoal cartridges were used to collect iodine.

There vere six air sample locations operating within a four mile radius of the plan The seventh location was a control location that vns located in the least-predominant vind direction at a distance greater than ten miles from the plant.

The air samples were collected on a lov volume air sampler. (Research 209088-2). The air samplers run Appliance Company Model No.

continuously and sample approxizately 10,600 cubic feet of air a The total air volume was measured by a dry gas meter and the veek.

time vas registered by a time totalizer. The samples were packaged and shipped to the vendor laboratory for analysis.

Ac Calibrations for total air flov and maintenance checks vere performed every six months or after repair.

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3. VATER

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Vater samples vere collected monthly at four locations and veekly at two locations. In 1989, the program started with three monthly locations, increasing to four at the end of September. The four monthly locations aret the control location at the Ashtabula Generating Station (28), a dtinking water f acility (Lake County Vater Plant (36)) in Painesville, the Perry Plant Service Vater Pumphouse forebay (34), and a drinking vater facility (Ohio-American Vater Company) in Ashtabula. The two veekly locations are taken from the shoreline at the north end of Green Road (59) and at the shoreline at the boat launch in Ferry Park (60). These two locations are on opposite sides of the plant.

Samples are collected monthly at four locations using composite samplers. The Ferry Plant Intake sample location, the Ashtabula Generating Station, and the drinking vater facility in Ashtabula obtal., vater samples via a Horizon Interval Sampler, which collects a small vclume of snter at short intervals, nominally a one-and-one-half ulncte sample every fif teen minutes. The other vater location at the Lake County Vater Plant in Painesville uses an interval timer to control a rolenoid valve on a pressurized sampling line. This sampling unit collects a one minute sample of vater f rom the rav vater sample line every hour.

At the remaining two locations, grab samples are collected veekly and composited for a monthly sample. These grab samples are taken I

from the shoreline.

Each sample was composited in a five-gallon container. Each month, two one-gallon camples and one 125-milliliter sample vere removed from each of the five-gallon containers. The remaining sample volume in the five-gallon container was disposed of. The two one-gallon samples vere treated with ten-milliliters of nitric acid to prevent plate-out on the sample container. The 125-milliliter sample was not treated with nitric acid, since it is analyzed only for tritium, which does not plate-cut on the container.

All sampics vere then packaged and shipped to the vendor laboratory for analysis.

4.

MILK During 1989, the number of milk locations had varied from one location to as many as six locations. The locations that contain goats generally produced milk from early spring to late fall. The goats were generally dried-out in the vinter as part of a normal husbandry practice. However, dairy cows produce milk on a year-round basis. The control Incation (51 Rettger's Farm) was a dairy farm and was the only location to produce milk year round. _

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Milk samples were collected monthly during the non-grnring senson (October 16Lthrough April 14) and twice a month during the grazing Milk samples vere normally collected from a batch tank at season.

the' dairy farm. 'The ovners.he supply milk samples were'given tva

,ere collected two one-gallon containers and the filleo

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to three days later.

All allk samples vere treated with forty grams of sodium bi-sulfite to preserve the allk. The samples were then packaged and: shipped to the vendor laboratory for analysis.

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FISH 4

Fish' samples were collected semi-annually from two locations. :The

' indicator location is in the immediate vicinity of the plant discharge and an offshore location ~near Mentor-On-The-Lake is the-control location.

An A passive; collection technique was used for fish collection.

experimental gill net, with a mesh ranging from approximately-1.0 to 2.5 inches vas used.to maximize catches in the useful size range.

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-The-net:vas setfin the evening and removed the followingl morning.

scientific collecting permit has-been obtained from the Ohio

-Department of. Natural Resources to permit sampling..

Available edible portions vere packed in ice and shipped to the

. b vendor _ laboratory'for analysis by gamma spectrometry.

6.

SEDIMENT Sediment samples vere collected semi-annually from seven locations.

Two-samples vere collected at the same locations where fish samples were collected. The other sediment 1 sample locations were offshore in the vicinities of Fairport Harbor and Redbird. Three new on-site-shoreline; sampling locations vere added in 1989. These vere;the minor and major stream. outlets 7to Lake Erie and the storm drain

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Limpoundment outfall-to--the' lake.

At-the four offshore sediment sample locations, sacples vere collected with a Ponar Grab Sampler. ~ The depth of sample collection -

vas approximately-20-to 40-feet. These samples were then transferred to plastic containers. At the:three.new shoreline sediment sampling points, samples vere collected by a scoop-just

-offshore in 1 to 1-1/2 feet of water.. A minimum of 1000 grams of-sediment from each sample location was collected, and shipped to the vendor laboratory for analysis.

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SOIL Soil samples vere taken quarterly at eight locations, of which one sample was a control sample Location 6, located eleven miles SSV at the Concord Service Center. The other soil samples were located in two rings around the plant. There vere three soil samples in the inner ring within a mile of the plant. Another four soil samples were collected in an outer ring approximately five miles from the plant. The eighth soil sample vas located near a community in the This sector is one of the three highest D/0 (Deposition ENE sector.

rate) sectors. The highest D/0 sector covers a small sparsely populated area and then eventually continues out over the lake.

A garden trovel vas used to remove the soil from a twelve inch by twelve inch area approximately one inch deep. The soil was placed in a one-liter plastic container at each location. The samples were then packaged and shipped to the vendor laboratory for sample analysis.

8.

PRECIPITATION Precipitation samples are collected from six locations. Five sample locations are located at the site boundary in the highest The sixth location, (location 6) acting as the D/0 sectors.

control, is located 11 miles SSV at the Concord Service Center.

Samples ate collected monthly as a composite using 3 gallon passive collection containers. Containers are remo.ed when the sample container is full or nearly full. A nev container is then placed in the same location for the remainder of the sample period. All collected water is composited, strained to remove debris, and shipped to the laboratory for analysis.

Nitric acid, normally added to prevent plate-out, is not added to Since precipitation samples until the samples are ready to ship.

the amount of sample volume may vary from collection period to collection period, it is not known until the end of the collection period whether or not a sufficient volume exists to perform all the analyses required, one of which is Tritium. The addition of nite' acid to the composite sample prior to the removal of 125 m1 for tritium would adversely affect the Tritium analysis. Nitric acid is added to_the remaining sample once 125 m1 has been set aside for tritium analysis.

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FOOD PRODUCTS The food product samples vere collected once a year during the harvest season (late August or early September). The food products vere collected from three locally grown gardens and ruadside vendors near the plant. One location (Location 50) vas a control location located approximately 11 miles south of the plant. In 1989 and 1988, no food products vere available from the control location. In lieu of this, 1987 data for food products collected at Station 50 var used as control data. Every effort was made to collect broad-leaf vegetation (i.e., cabbage, lettuce, etc.) if possible.

However, if broad-leaf vegetation was not available, other food products vere collected for samples.

10.

FEED / SILAGE The feed silage and hay products were collected once a year during the harvest season (late August or early September). Feed / silage and hay were collected from each milk sample location. Samples were

- packaged and shipped to the vendor laboratory for analysis.

11.

VEGETATION Samples of grass and leaves vere collected monthly during the groving season, when uvailable to supplement milk sampling. These samples vere collected at five locations. The control location (Location 6) was in the least prevalent vind direction (11 mr es SSV).

At each grass sample location, grass was clipped from an area ranging from 15 to 210 square feet in area. Large sample areas vere often used to obtain the required sample size. Grass samples veighed approximately 1,000 grams dapending on the moisture content.

Samples were-taken at the highest D/0 sector, the highest D/0 sector with milk-producing animals, or both.

Leaves vere sampled at or very near the same locations as grass samples. Leaves vere taken from one particular species (the Staghorn Sumac or Rhus Typhina L.) that is abundant in the area. A minimum of 1,000 grams was collected each month when available.

V. DISCUSSION AND RESULTS A summary of the results for each sample medium is provided in the Radiological Environmental Monitoring Program Summary Table 3.

The average values recorded in Table 3 reflect the results for each sample medium in Appendix A.

The 1989 results recorded in Table 3 are discussed belov for each sample medium and the results are compared with the h;storical values to reflect any possible trends.

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1. -DIRECT RADIATION During 1989, there _ vere 140 environmental TLDs,-140 Emergency.TLDs, and 35 Annual TLDs. placed in the field.. A total of five quarterly, and.six emergency.TLDs were found to be missing at the timo of

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Three annual-TLDs vere found missing during the year but

-exchange.

Dne-vere replaced and the results were prorated to-365 days.

emergency TLD data point was substituted for a missing environmental TLD data point to give 'a total of 136 environmental TLD data points collected in 1989.

T The average quarterly exposure for the year for all TLDs and equivalent annual dose per year are as follows:

Average Quarterly Equivalent Annual Exposure Exposure 1989 14.7 1 4.5 LR 6td.0tr.

58.8 mR/ year 1988 14.2 t 4.4 PE,/S;d.0tr.

56.8 mR/ year 75.6 mR/ year Preoperational 18.9 e 6.B A/Std.0tr..

ine exposure levels reported in 1989 are slightly higher-than reported in 3988 but lover than the preoperational everage.

The 1989l snt' 1988 values are not significantly different and in close *.gies aent with each other.

.The preoperation 1-average was compiled by' using TLDs. f rom two cne of those vendors, IT/RSL used TLDs that when s

toticr: vendor; compared to che current vendor TIHL, showed 10 to 30% bias toward higher valves when compared to the current vendor TIHL.

The quarterly exposure rates for 1989 ranged from. i i h the 11.2 mR/Std.0tr. to 23.7 mR/Std.0tr. and the locat on w t highest annual average'vas location No. 18, 5 miles S from the P

Leestion 18 historically has-always been the highest plant.

TLD location. The highest average-dose for the year vas-again found to be lecation 18.

It-vas 22.25 mR/Std.0tr.

The annual average quarterly exposures for indicator and control locations in 1989 vere:

Control Indicator 13.4 2 2.2 mR/Std.0tr.

34.7 t 4.5 mR/Std.0tr.

There is no statistica. iifference.in exposure levels between the indicator and the control locations.

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-1989-1988-TLD comparison

-In comparing the average TLD quarterly exposure recorded by the Perry Plant's vendor TIML and the average TLD quarterly exposure recorded by the NRC field TLDs, both-values are in good agreement.

Average Quarterly Value for 1989 TIML NRC*

UNITS

.14.714.5 E 5:4.7 mR/Std. Otr.

  • Average annual quarterly value was calculated by averaging the 1st, 2nd and 3rd quarterly averages.

together. The 4th quarter was not-used because it was

- not available at the time of this report.

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Table 4 shows.the results of all quarterly environmental TLDs, including the average.for each cuarter and the average for each location. as well as the. annual-environmental TLD=results.

No seasonal variation-in the TLD data was seen in 1989. No seascnal variation vas seen in 1988. In 1987 seasonal-variation vas-seen, where slightly higher-readings'are seen in.

the colder months than the varmer months. -A seasonal pattern is.not unusual and can be seen-in TLD. data from other nuclear

= ~ I pover' plants.

The!same spatial variation vas seen in 1989-as was seen in 1988. - Four of - the five-highest. reading 'TLD locations in 1988

. vere the same in 1989 61though the order was slightly different.

1988 1989-Station Aver. mR/Std.0tr Station Aver mR/Std.0tr.

18 22.2522.19 18 c19.8833.50 16 18.35 1.54 16 16.90 4.91 21 17.3822.12 17 16.8042.96 17-

'16.83 1.69 21-16.3322.40

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16.77 1.32 36 16.1322.05 2

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Historically, these TLDs have usually been.the TLDs with the highest readings. These consistently high locations appear to be influenced by soil composition. For example, location 18 has sivays _ been the highest reading TLD since 1981..

I Lotation 18 also is a soil sample location.

In comparing the TLD values with-the soil concentration of naturally occurring radionuclides, there is a good correlation between the high exposure rates and the high concentrations-of naturally occurring radionuclides in the soll. Historically there has been no correlation between these highest reading TLD-locations and the most predominate inland vind direction over the years.

The sum of - the quarterly TLDs to the annual TLDs compared quite The annual TLDs were just slightly lover than the sum of vell.

the quarterly TLDs.

Annual:

Sum of all Quarters.

TLD Average TLD Average 58.72 4 mR 4

58.4 8.4 mR 2

The annual environmental TLD results by location are compared to the sum of each quarterly environmental TLD for each location as shown in Table 5.

B.

Comparison To Semiannual Radioactive Effluent Release Reports A dose comparison is compiled between actual release results from the Semiannual Radioactive Effluent Release Reports (SRERR) for the first and-second halves of 1989

.and the equivalent results from the 1989 Radiological

-Environmental Honitoring Program. For this comparison the

-air gamma exposure from plant gaseous effluents going to the predominant land based sector at the site boundary, (as reported in the Semiannual Radioactive Effluent-Release Reports (SRERR) for 1989), is compared to the actual readings from the TLD-in the corresponding location.

According to the first and second halves of the SRERRs for 1989, the land based sector predicted to receive the highest exposure for each quarter of 1989 and the corresponding TLD located there, are as follows:

Sector at' Site.

Corresponding Boundary from SRERR TLD Location Quarter 1 VSV sector 12 4.

Quarter 2 No data due to outage Quarter 3 S sector 42 Quarter 4 ESE sector 9

p 1

1 The predicted exposure according to the SRERRs is in erem while the TLD exposure is listed in mR.

For the purpose of this comperison, these units can be considered as equivalent to each other using the gamma quality factor of 1.

In comparing the expected exposures from the release data shown in the SRERRs to the four quarters of TLD results at the corresponding locations gives the following:

1st Otr.

3rd Otr.

4th Otr.

Expected Exposure from the SRERRs 1.28E 2 3.85E 2 1.5$E-2 mrem /Otr.

Actual TLD Results 12.510.4 13,610.5 12.1:0.1 mR/Std Otr.

Therefore, the expected exposure from the SRERRs is far too small to be positively identified above the normal fluctuatio.) of the natural background sources of radiation in the environment and the error associate?

Ith the TLD measurements. The expected exposures from the SRERRs for each quarter in 1989 vas less than the lover limit of detection of 1 mrem for CaSO4 (Dy) environmental TLDs.

2-elR A total of 362 samples were collected in 1989 for each air particulate and air lodine medium. Air particulate filters vere analyzed for gross beta veekly and air fodine cartridges were analyzed by gamma spectr ometry weekly. The air particulate filters vere composited by location and analyzed quarterly by gamma spectrometry.

The 1989 annual average gross beta activity for all locations for air with respect to its previous year and preoperational value is as follovst ACTIVITY (pCi/Cu.a.)$2 Sigma YEAR 22.13 E-03118.88 E-03 1989 21.72 E-03t14.44 E-03 1988 17.44 E-03 13.74 E-03 Preop.

The gross beta concentration ranged from 6 pCi/Cu.m to 61 pCi/Cu.m for all locations. The location with the highest annual average concentration vas location lio. 5 approximately 0.6 of a mile 3V from the plant. This location had an annual concentration of 25.31 E-3221.58 E-3 pCi/Cu.m.

i The 1989 annual average gross beta ennientratinr. int etr for indicator locations and the c'nts.1 location ir as follovs:

RADIOPUCLIDE INDICATOR LOCATIONS CONTROL LOCATION Gross Beta 22.03 E-03:18.94 E-03 22.11 E-03:18.69 E-03 pCi/Ce m.

pC1/Cu.m.

There appears to be no statistical difference in gross beta concentrations between the indicator locations and the control location.

The radionuclide Be-7 vhich is naturally occurring was detected in all compo2ite air sam!'es. The 1989 annual average concentration for Be-7 in air with respect to its previous year and preoperational value is as follows:

YEAR ACTIVITY (pCi/Cu.m. )f2 Sigma 1989 60.7 E-03:29.3 E-03 1988 72.1 E-03232.4 E-03 Preop.

70.9 E-03:41.4 E-03 These cor.centrations are in agreement with each other and with previous historical concentrations.

l The Be.7 concentration ranged from 30 E-03 pC1/Cu.m. to 100 E-03 pCi/Cu.m. for all locations. The location with the highest annual average was location No. 5, approximately 0.6 of a mile SV frou the plant. The highest-annual average concentration was 72.5 E-3244.3 E-3 pC1/Cu.m.

The 1989 annual average concentration for Be-7 in air is as follovs:

RADIONUCLIDE INDICATOR LOCATIONS CONTROL LOCATION Be-7 60.0 E-03 30.1 E-03 65.0 E-03:25.8 E-03 pCi/Cu.m.

pCi/Cu.m.

There was no statistical difference between the annual average concentrations for the indicator locations and the control location.

The radionuclides Co-58, co-60, Cs-134 Cs-137 and 1-131 vere reported as the lover 1!!ait of detection.

A.

Unusual Air Saeple Readings During the year 1989, several one week collection periods for air samples indicated high gross beta readings that exceeded the 3 gma contsal limit established for each station. The weekly collection periods ending 1-4-89, 1-18-89, 11-1-89, and 12-20-89, all had elevated readings of which most if not all stations exceeded the 3 sigma control limit for gross beta.

Average Veck Reading for 1989 Yes.rly Au_tage Ending All Stations Range For All Sta'tions 1-04-89 45.4s13.1 39-58 22.1118.9 pC1/Cu.a.

22.12 8.9 pC1/Cu.m.

1 1-18-89 48.039.7 35 48 11-01-89 37.926.2 34 43 22.1118.9 pCi/Co.m.

$1.6 10.8 44-61 22.1218.9 pC1/Cu.m.

12-20-89 3

Each high reading was compared to the predominant vind directions for that veek. No direct correlations between high readings and vind directions from the plant could be

\\.

made.

A gamma spectroscopy was done on each air filter from the 7 stations for the 4 veeks identified. No isotopes except Be-7 vere identified. This spectroscopic reviev included

(

examinations for manmade and plant related isotopes.

Therefore it is reasonable to assume that the source of the high gross beta readings is from naturally occurring sources such as Be-7 rather than manmade sources.

BE-7 is a naturally occurring cosmogenically produced element. Of all the elements produced in the upper atmosphere only BF-7 is a gamma emitter produced in sufficient quantities with a long enough half life to be seen by gamma spectroscopy. It is most likely that the high gross beta readings vere cosmogenic radionuclides

+ hat as a result of properly aligned meteorological conditions deposited out. As the solar cycle comes to the largest peak since 1957-1958, more high gross beta readings can be expected in 1990.

3.

VATER A total of 62 vater staples vere collectes and analyzed for gross beta activity, and by gamma spectroscopy in 1989. During each quarter, strontium analyses vere performed on 20 vater samples. A total of 21 vater samples vere also composited and analyred for tritium.

..'. AD AM

The 1989 annual average grnst-beta netivity for all Incations in vater with respect to its previous year and pteoperational value is as follovs:

j l

ACTIVITY (pCi/L) 2 Sigma YEjR 2.9 1.3 1989 3.0$1.0 1988 5.26$6.78 Preop.

These values are in relative agreement with each other when the 2 Sigma error is considered.

The gross beta activity ranged from 1.8 pCi/L to 5.3 pCf/L for all locations and location No. 60 was identified as the location with the highest annual average grosa beta activity.

This activity was reported as 3.22 pCi/L.

The 1989 annual average gross beta activity in Vater is as follovs RADIONllCLIDE INDICATOR LOCATIONS C0!TTROL LOCATION Gross Beta 2.9$1.3 pCi/L 3.2tl.1 pCi/L There appears to be no significant deviation between indicator and control locations.

The radionuclide Sr-90 vas detected in 11 out of 20 vater samples analyzed for strontium-89 and strontium-90. In 1988, 5 out of 18 samples had detectable Sr-90 and in 1987, 2 out of 11 had detectable Sr-90.

All detected levels vere extremely The reason for the apparent increase in the number of lov.

samples shoving Sr-90 is that Kkb (Minimum Detectable Level) decreased for samples counted in 1989. prior to 1989 the HDL In 1989 the HDL varied from 0.3 to 1.0 pC1/L.

vas 1.0 pCi/L.

This greater sensitivity is the reason more samples appeared to have detectable Sr In looking at results where St-90 is found greater than 1.0 pcl/L shovs that in 1987 2 samples shoved 1.B and 1.9 pCi/L, in 1988 only 1 sample, 1.4 pCi/L, was No f ound, and in 1989, 2 samples 1.5 and 1.3 pCi/L vere seen.

positive activity was detected in samples analysed for s-

-ntium-89.

The radionuclide strontium-90 has been detected periodically in other water samples since 1983 vell before the plant vent critical in June of 1986. The activity ranged from 0.55 pC1/L to 1.9 pCi/L. It appears that this radionuclide originates fron nuclear weapons fallout.

._._. _ _.....,_ ~ - _ _ _ _ -

A gamma isotopic analysis was done on vater for Os-117, cs.114 Te-59, La-140, Mn-54. Hb.95. En-65, and tr-95. No positive activity was detected above the lovar limit of detection for l

any of these radionuclides.

It Tritium vac detected in 17 out of 21 samples taken in 1989.

vas not untti 1988 vhen the nev and current vendor TIML started Prior doing analyses that tritium was once again detectable.

to this the prevlons vendor from 1985-1987 had their LLD (Lover Limit of Detection) at the NRC's required LLD of 2000 pCf/L.

This LLD setting did not detect any tritium activity above this The current vendor's ability to detect lover levels setting.

of tritium greatly improved the LLD obtainable. The current i

vendor TIML had a MOL (Minimum betectable Level) that varied between 146-148 pCi/L for 1989. All preoperational data used vas obtained prior to 1985 from the first vendor whose LLD was lov enough to detect the presence of tritium.

The 1989 annual average concentration for H-3 for all locations in water with respect to its previous year and preoperational value is as ;ollovst l

ACTIVITY (pC1/L) 2 Sigma YEAR 248.71117 1989 284.8 351 1988 333.62341 Preop.

The.1989 annual average concentration for H-3 in vater for indicator locations and the control location is as follovst RADIONUCLIDE INDICATOR LOCATIONS CONTROL LOCATION 243.01 20 pCi/L 291.5s47 pCi/L 1

H-3 The indicator The range of values were from 173 to 373 pCi/L.

locations and the control location are in agreement with each other considering the 2 sigma errors. These values are well below the NRC lover limit of detection of 2000 pCf/L.

Historically, preoperational data from 1982 to 1984 shoved a The previous vendor range from 190 pCi/L to 780 pci/L.

laboratory used from 1985 to 1987.eported one preoperational It is sample in 1985 to have a positive value at 2200 pC1/L.

suspected that this value was an abnormality and was not.

counted in the preopetational average.

4.

MILK During 1989, a total of 98 allk samples were collected and analyzed for radioiodine by chemienl separation and by gamma A total of 18 samples from the 98 samples were spectrcmetry.

analyzed for strontium.

17 -

ew1 w

w ea+m,*<w-

. 4wer i

+simy--a emy m+,.y<wa,,.---s

,sw,%g m y y.y9p ygw g

y g-y w w ws-m-,wp.r--,egry-9mm.rspy mg ag g

.yy ig g

yyIg

--%m 9e eyy 4 9 2 9

g g-yp-4'7-m y 3.u p m 3-9 g-

I l

j The most predominate tedionucilde detected by gamma This radionuclide is naturally 4

spectrometry was K 40.

occurring and is not associated with the prodt. tion of nuclear K-40 vas detected in all milk samples.

pover.

The 1989 annual average concentration for K 40 for all locations in milk with respect to the previous year and preoperational value is as follovs:

ACTIVITY (pci/L)t2 Sirea f

YEAR 1508496 1989 15411678 1988 1537t546 Preop.

I The 1969 average value is in good agreement with the preoperational and previous year average values.

1 A comparison of the preoperational average concentration for i

cov ellk and goat milk, shows that goat milk contains higher K 40 concentrations than cov milk. The preoperational average concentration for goat stik was 1655t468 pel/L. The preoperationni average concentrations for cov milk vas 1320 t 394 pC1/L. Goats appear to have a higher bioaccumulation This probably accounts for the difference in rate than covs.

i K 40 concentrations as well as for any other radionuclide that may;take residence in these animals.

In 1989,the K-40 concentratinn ranged from 810 pCi/L to 2140 pC1/L for all locations. The location with the highest

~ i annual average concentration was location No. 29 vhich is located 1.4 miles ESE from the plant. The average was reported as 1770 392 pC1/L.

2 The 1989 annual average concentration for K-40 in allk for indicator loe.ations and the control location is as follovst

[

RADIONUCLIDE INDICATOR LOCATIONS CONTROL LOCATION 1

i K-40 1555 493 pC1/L 1310:268 pCi/L The concentration at the control location was 16% lover than the indicator locations. In 1988 and in 1987 the concentration

- i of the control was again 16% lover-than.the indientor.

This smaller concentration detuted -in the control location can be attributed to a lover concentration of K-40 in cov milk.

The indicator locations include several goat milk samples and Historically, the annual average-l one cov allk sample.:

concentration for goat milk has always been much higher than cov milk.

t 18 -

% fe gik we w

w-4 s-rw ar+ 4 ew wi W-Vrulnv'm'

-we e'w-*W-ir t-ep&w'tw--et-ar y^ge-'s deer ' 4 f' p-wg%ag*yMy-

  • y+ - ' -

p

=-

m'+-$

9-5-W-t't--Le-fr-rs*

tpgw:ys-wa-3gV T"-------pg e y sw-

- = _.

i

)

i I

The radionuclides 1-131. Ba-140, t.e-ids,05-134. and ca.137 vere all reported as the lover limit of ds *ction for the year.

The 1989 annual average concentration f or St-90 in milk with respect to the previous year and preoperational value is as follows:

ACTIVITY (pC1/L) 2 Sigga YEAR 2.7811.78 1989 3.24 l.94 t

1988 1.8022.12 Freop.

The annual average concentration for St-90 in silk for indicator locations and the control location is as follovs RADIONUCLIDE INDICATOR LOCATIONS CONTROL LOCATION Sr-90 2.821.0 pCi/L 2.712.1 pC1/L There appears to be good agreement between indicator and control locations. The location with the highest annual average concentration was location No. 52, which is located 4.5 miles SSV from the plant. This concentration was 3.6 pCi/L.

Historically strontium-90 has been detected every year since 1983 when the program first started to sampit for it.

Preoperational data has shown the activity to range f rom 0.47 pC1/L to 3.5 pC1/L. If there was any correlation with vind from the plant and deposition of Sr-90, the milk location #29 (1.3 miles ENE) vould be predicted to show the highest levels of Sr-90.

In fact, location $29 had the lovest levels found.

Lov level trace amounts of Sr-90 are found pretty much equally throughout the area and appears to come from a more universal source. Iteference mater 2als have indicated that the presence of Sr-90 is related to the type of pasture fertilization employed, the particular kind of feed grain used and soil charatteristiri. The radionuclide strontium-B9 vas not detected above the lover limit of detection. The lack of any detectable St-89 vould also tend to indicate that the source of St-90 ss not the Perry Plant.

Hilk samples analyzed for iodine-131 vere reported as the lover limit of detection.,

.-____--___.________m-I e

b.

T1SH A total of 28 ser.ples of fish vere collected and analyred by This collection vas comprised of 9 species gamma spectroscopy.

of fish. Cs-137 vas detected in 5 out of 28 samples. The naturally occurring nuclide K-40 was detected in every sample.

A list of species collected and analysed are as follovst VLitt j

Perch Yellov Perch, Valleye, White Bass, Smallmouth Bass, Catfish, Carp, Red Horse White Sucker, and freshvater Drum.

i The major rectestional and commercial species are Perch, Valleye, and White Bass.

The 1989 annual average K-40 concentration for all locations for fish with respect to the previous year and preoperational value is as follows:

ACTIVITY {pC1/Kg(vet)],2 Sigma YEAR 3213:1184 1989 3105:1379 1988 3722:2465 Preop.

The 1989 value is in agreement with the 1988 value and shove a decrease in concentration when compred to the preoperational value.

i b

The concentration for K-40 ranged from 2060 pCi/Kg to The location with the highest annual average 4271 pC1/Kg.

concentration was the control location No. 32 which was located 15.8 alles VSV from the plant. The concentration was reported r.s 3318 2 629 pCf/Kg.

The 1989 annual average K 40 cor. centration for fish for the r

indicator locatfor, and the control location is as follows:

RAD 10NUCL1,_DE INDICATOR LOCATION CONTROL LOCATION K-40 3171t1349 pCi/Kg 33182629 pC1/Kg These values are in agreesent with each other.

Cs-137 has barn seen periodically in fish samples since In 1988 Cs-137 was preoperational fish sampling began in 1981.

The 1989 reported at tne Lover Limit of Detection (LLD).

annual average Cs-137 concentration found for the 5 out of 28 samples of fish with respect to the preoperetional value is as follovs:

ACTIVITY [pCi/Kg(vet)]-

-TEAR 1989:2 Sigma 37.0e11.6 Preop 2 Sigma 30.9:46.6 l

l '

L I

All 5 fish samples found with Cs.337 vere f rom Inration 25 which is the indientor location, but thia is mainly accounted for by the fact that 70% of all sampled fish come from this in large bodies of water it is very difficult to location. _

know whether a fish caught at a given location had lived there for any extended period. Thus the presence or absena.e of a radionuclide in specific fish at one location does not permit any definite conclusion concerning the presence of the radionuclide in vater at that location. The Cs-137 found in The fact the fish is typical compared to preoperational data.

that no Cs-134 was found with the Cs-137 vould also tend to indicate the source was not the Ferry Plant. Therefore it is reasonable to assume that the source of the Cs-137 is from some source, other than the Perry Plant.

All other radionuclides (which included Co-58, Co-60, Cs-134, Fe-59, Mn-54, and 2n-65) vere analyzed by gamma spectroscopy and reported as the Inver limit of detection (LLD).

6.

KEDIMERT There vere 14 sedicent samples colletterl in 1989. The ecst predominant radionuclide was K-40.

This radionuelida has beer.

detected in all samples since sampling began back in 1981.

The 1989 annual Lverrge K 40 concentration for all ' locations f

for sediment with respect to the previoue year and preoperational value ic as follovs:

ACTIVITT (pCl/L)

YEAR 998115586 1989:2 Sigma 1409034237 198822 Sigma 1331727914 Preop.22 Sigma The 1989 annual average K-40 concentration for sediment for indicator locations and the control locations is as follovst RADIONUCLICE INDICATOR LOCATION 3 CONTROL LOCATION K 40 9682tS842 pCi/Kg 11775s382 pC1/Kg The indicator locations and control location are in relative In agreer ent with each other considering the associated error.

1987 and 1986 the control location was higher than the indicator locations.

Other radionuclides that have been detected in sediment samples were Cs-137 and Sr-90. These radionuclides are fission The radionuclides Cs-137 and Sr-90 have been products.

detected in most sediment samples since 1961, five years prior to the operation of Perry Unit 1. -

Ir, 1989, Cs-137 vas detected in 6 out of 14 sediment samples.

f The annual average concentration for Cs-137 for all locations in sediment vith respect to the previous year end i

preoperational value is as follovs YEAR ACTIVITY (pC1/L)t2 Sigma 1989 149t222 308:353 1988 243s310 Preop.

The 1989, 1988 and preoperational values are all close to each other. The large 2 sigma error indicates how much the actual numbers fluctuate. The range for 1989 vas from 34 to 304 i

pC1/Kr(vet). _Of the 7 locations sampled, 3 locations gave positive readings above LLD.

The annual average concentration for Cs-137'during preoperational monitoring fluctuated videly since the collection of sediment began back fn 1981. The annual average concentrations for all locations were reported as high as-365 2-380 pCi/Kg in 1982 to a lov of 79 i 30 pCi/Kg in 1984.

l

.In the year in which the lovest annual average concentration vas. reported, two samples out of eight samples showed any

-detectable Cs-137.

Cs-134 vas not detected in any of the sediment samples

~

collected. If the Cs-137 sporadically being found in the environment was from the plant, it vould be expected that Cs-134 vould also be found. Since it is not. it is likely that the Cs-137 has been in the environment for-some time, especially since preep data indicates-its presence long before the plant vent operational. The source of Cs-137 is unknown, but again it appears that it is not associated with the Perry Plant.

Vith the~ vender. (TIML) performing the strontium analysis,. in

~

1988 the lover limit of detection for St-90 was dramatically improved.- Prior to 1988, Sr-90 has been reported as below the lover limit of detection, which usually was 500 pCi/L.

In 1988, with much improved sensitivity, positive readings were obtained. =All preoperational data had indicated that no detectable levels of St-90 existed except for the full sample collection-in 1984.--Here all stations-sampled shoved positive-readings ranging from 350 to 1800 pCf/Kg.

In 1989 3 out of 13 samples gave' positive readings above the LLD for Sr-90. The 1989 annual. average concentration for Sr-90

~for all locations for sediment with respect to the previous year and preeperational value is as follows:

A.-e.,.,,--,

.m,.

_w.f',

,,,.. M.~

m..Mm.'m.w,-,.,v..',-e,d.,.,_m[-,

,.,,._,-.-w.

-.,m,,..,

M., - w w., #

y

I YEAR AC11VITY lp_Ci/Kg(vet)h2 Sigma 1989 12.3:2.4 26.4 22.0 1

-1958 Because the 1989 annual average is so lov compared to the previously recognized LLD at 500 pC1/Kg, it is hard to easign any significant meaning to this nember. Prior to 1988 all values of Sr-90 in sediment vere teported at the LLD of 500pCf/Kg.

There was no detectable St-89 found. If the St-90 vas from the plant, one vould expect to find Sr-89 also. Since it is not, the source of Sr-90 is not knovn. The Sr-90 found any be from bomb test fallout.

7.

SOIL A total of 24 soll samples vere collected and analyzed for strontium and by gamma spectroscopy in 1989. Two naturally occurring radionuclides were detected in these samples. These vere K-40 and Ra-226. Two radionuclides vere detected that are fission products. They were Cs-137 and Sr-90.

The 1989 annual average concentration of the naturally occurring radionuclides K-40 and Ra-226 for all locations in soil vith respect to the previous year and preoperational data are as follovs:

ACTIVITY [pCl/Kg(dry)J3 _ Sigma 2

YEAR K-40 1989 1206116197 1988 11298s7865 1239126174 Preop.

Ra-226 1989 208621225 1134 1797 2

1988 Preop.

7582596..

l' '

ACTIVITY lpCi/Eg(dry)]t2 Sigma YEAR PANCE 9106 to 22220 K 40 1130 to 3719 Ra-226 The average K-40 values are in good agreement with each other.

There appearm that there is a slight incresse in Ra-226, but with the 2 sigma error, it is hard to give these numbers too much significance.

The annual average concentration of the naturally occurring radionuclides K 40 and Ra-226 in 1989 for indicator locations and the control location vere as follows:

RADIONUCLIDE INDICATOR LOCATIONS CONTROL LOCATION K 40 1186226527 pCi/Kg 1345641520 pC1/Kg 202B2 260 pC1/Kg 24912509 pCi/Kg 1

Ra-226 The control values show slightly higher annual 6 verage concentrations than the indicator values for K 40 and Ra-226 but still because of the associated statistical error, they are It has been observed that the results in relative agreement.

from samples taken at various locations differ significantly.

The range for K-40 varied from 9106 to 22220 pCi/Kg and the This range for Ra-266 varied from 1130 to 3719 pC1/Kg.

difference can be attributed to soil composition and land use at the various locations.

The radionuclide Cs-137 vas detected in 22 out of 24 samples.

The annual average concentration fer Cs-137 for all locations in soil vith respect to the previous year and preoperational value is as follows:

ACTIVITY [pC1/Kg(dry))

YEAR 380 544 2

1989 2 Sigma 396 671 t

198B22 Sigma 867t1855 Preop.g2 Sigma

Tht large 2 sfrsa error given en indication of the 1erge range of values. The 1969 values tanged from 32 to 901 pCi/Kg. The Data has proeperational v61uee ranged from 109 to 3940 pCi/Es.

thovn a sitadv decrease of Cs-137 in the environment over the Thf3 decrease is probably due to the leaching of Cs-137

years, from the soil by rainfall. This decreasing trend voald also tend to indicate that most of the deposition occurred many years ago and that Cs-137 is not being deposited on an ongoi"g besis. It is suspected that this initial deposition could have cone from nuclear bomb test is11out. Again as discussed in other secthons, if Cs-137 was coming from a recent pover plant Cs-134 discharge, it vould most likely be seen with Cs-134.

has not been detected in the soil or eraironment and therefore

~

ic another indicetion that the Cs-137 f.ound in the environment is not frbs the terry Plant.

1he 1989 annuti average concentration for Cs-137 for indicator and control locations are as follovs RADIONUCLIDE INDICATOR LOCATIONS CONTROL LOCATION l

Cs-137 363.8s533.2 pC1/Kg 482.7s691.7 pCi/Kg The 2 sigma values make these numbers questionable as to how For Cs-137, the usable they are for comparison purposes.

control has been larger than the ind':stor locations since The ability of the control location to collect higher 1986.

(

concentrations of Cs-137 is most likely related to a difference in soil chemical properties. Properties like chemical couposition and ion exchange capacity along with moisture content and pH can vary from area to a:ea, thus making different ateas more susceptable to fallout accumulation.

The radionuclide Sr-90 vas detected in 18 out of 24 samples The annual average concentration for Sr-90 for all taken.

locations in soil with respect to the previous year is as follovs ACTIVITY [pCi/Kg(dry)}s2 Sigma YEAR 41.6t$8.1 1989 63.22121.5 1988 The lover limit of detection (LLD) has dramatically improved with the change to the current vendor T1HL back in 1988.

Prior to 1988, St-90 has been reported as belov the LLD vhich was 500 pCi/Kg. Therefore, no usable preoperational data exists.

The 1989 annual average concentration for Sr-90 for indicator locations and the control locations are as follows: <

1

~ ~ - _ -

r RADIOtJUCLIDE 3NDICATOR L9CATIO!jS C0!iTROL LOCATION Sr-90 38.5s53.2 pCi/Kg 95.2216.0 pCi/Kg For the control location only one value vas found above the Minimum Detectable Level (MDL). As with Cs-137 the range vas It ranged from 9.5 to 96.8 pCi/Kg. In 1938, as in large.

As 1989, the control was larger than the indicator locations.

explained above with Cs-137. this is probably due to soil chemical composition. No Sr-89 was detected in the soil or any media of the environment. This along with the control being the source of larger than the indicator tends to show that Sr-90 is not the Perry Plant.

The results from co-58, Co-60, Cs-134 and St-89 analyses were reported as the lover limit of detection.

P.

PRECIPITATION A total of 67 precipitation samples vere collected in 1989.

These samples vere collected monthly as a composite using 3 Fallon passive collection containers. Each sample was analyzed for gross beta activity 3 tritium and by gamma spectroscopy.-

The annual average gross teta activity for all locations for precipitation with respect to previous years is as follovs

(

YEAR VALUE 2 SICMA 1989 9.50s23.20 pCi/L 1988 9.51s16,94 pCi/L 1987 7.3635.74 pCi/L 1986 8.74s5.52 pCi/L 1985 10.01214.42 pCi/L Preefpitation sampling, vbich until 1988 existed only as snov sampling, started in 1985. In 1988 rain water was added. The historical results from 1985 to 1988 appear to be in agreement with the 1989 results.

The grosa beta activity ranged f rom 1.4 pCi/L to 77.8 pCi/L for all locations and the location vitb the highest annual gross This location beta activity was identified as location No. 3.

is approximately 1.0 miles SE of the plant and the activity was 14.74 44.94 pCi/L.

reported as 2

The 1989 annual average concentration for gross beta in precipitation for indicator locations and the control location is as follows: --

m ___

i f

RADIONUCLIDE INDICATOR LOCATIONS CONTROL LOCATION Gross Beta 9.85s25.21 pC1/L 7.93s9.74 pCi/L There is no significant difference between the indicator locations and the control location considering the range of ettor associated with this analysis.

The results from samples analyzed for gasma footopics were i

reported as the loser limit of detection for Ba-140 Co-58, Co-60, Cs-134. Cs-137, Fe-59, La-140, Mn-54, In-65, and Ir-95.

No positive activity was detected in the precipitation samples for these elements.

The results for samples analyzed for tritius showed a total of

-31 out of 67 samples analyzed giving readings above the lover limit of detection.

The 1989 annual average concentrati9n for tritium fc-all locations in precipitation with respect to its previous year is as follovs:

YEAR ACTIVITY (pCi/L) i 1989 163.9382.3 1988 202.32129.2 l

The results ranged from 104 246 pCi/L for all locations.

The annual average concentration for H-3 in precipitation for indicator and the control location is as follovst RADIONUCLIDE INDICATOR LOCATIONS CONTROL LOCATION H-3 103.5286.8 166260.3

.The indicator locations and the control location are in good agreement vith each other.

The location with the highest annuti tritium activity is sample location $3, located 1.0 mile SE. It's average activity sas

.179.33111.2 pCi/L. Again here as with other saeple media, there is no definite correlation between the station with the highest' reading and the most predosinant vind directions for-1989. This along with the indicator and control locations being in good agreenient tends to indicate that the environmental tritium is not associated with the plant.

A.

. Unusual Freefpitation Readings In the month of March, higher than usual gross beta precipitation readings vere seasured. They were as follovs:-

. P

?

' A k., +

e----

. ~.~

.-m...

...w.m.-

-w..

y-,..w-,,

.--.!,.,,m..,,.<m.--.~,.-

,,,..- - y

,,--..,,.e,

..,r,tvw-ry-c.-,*w-,,ww,,-.r--,-e

-s LOCATION DISTANCE READING P-3 1.0 SE 77.8:5.0 P-4 0.7 5 43.0 2.5 P-6 (control) 11.0 SSV 17.4 1.0 2

P-7 0.6 NE 12.As0.9 P-12 0.6 VSV 40.8s2.0 P-35 0.6 E 14.4s0.4 The average gross beta reading for 1989 was 9.85 25.21.

In reference to this, all locations including the control ate high. A gamma isotopic analysis was performed for each location. No activity above the LLO was seen. A reanalysis was perferied for the 4 highest locations for gross beta and-gamma 2sotopic. The gross beta tesults again reconfirmed the original gross beta readings, but again nothing was detected above the LLD vhen comma isotopic analysis was performed.

What might possibly have been seen here is a vash out effect of naturally occurring cosmostnically produced elements. The recently large increase in solar flare activity would account for this. Such an occurrence vould give high gross beta readings but not be detectable when performing a gamma spectroscopy. (See discussion on thir phenomenon in the section on air sampling.)

9.

POOD PRODUCTS A total of 6 different types of produce, including fruit, were collected from several grovers around the plant. An attempt was made to collect broad leaf vegetation such sa' cabbage and lettuce when collecting produce. These snsples were cc11ected

^

annually. Each sample was analyzed by gamma spectroscopy.

The most predominant radionuclide found in each produce sasiple s

was the naturally occurring radionuclide K-40.

The 1989 annual average concentration for K-40 for all locations in produce with respect to the previous year and preoperational value is as follovst YEAR ACTIVITY {pCl/Kg(dry)]f2 Cigma 1989 214211002 1988 1614 913 t

Preop.

2296s2160 The activity. ranged from 1440 20$(Eg to 3129 pCi/Ks. The average 1989 concentration-for all lod'entor' locations and the 4;

control location.or K-40 ir produc6 >> as follovss __ -

e RADIONUCLIDE INDICATOR LOCATIONS CN. 4TEDI,1,0CA.TI.ON

  • 2727 910 pCi/Kg K-40 2142$1002 pCi/Kg t
  • In 1988 there vas no produce available at the ctatrol location. The value used as th< control is the 1987 value. Saeples from conttol location 50 vere inadvertently omitted in 1989.

Comparison of the 1999 K-40 average concentration for all locations to 1988 K 40 average :oncentration for all locations in produce, shovs that the 1989 K-40 concentrations are highet than the 1988 value but in agreement with the preoperatiot.a1 value.

The nuclides 1-131 Cs-134, Cs-137, Co-60, Co-50, and Be-7 vere reported as the lover limit of dttection.

10.

FEED AND SILAGE Teed hay and silage samples were collecte/. from each sampling location. These samples vete collected annually. Each sample was analyzed by gamma spectroscopy. The major radionuclide detected in feed, hay and silage van the naturally occurring radionuclide K-40.

This nuclide was detected in all samples.

I The 1989 annual average concentration for K-40 for all locations in feed, hay and silaga vith respect to the previous year and the preoperational valde is as follevs ACTIVITY [pCi/Kg(vet)]s2 Sigme YEAR 1989 8003t 111 7

1988 955Ft9569 771!qb5'/0 Preop.

The activity ranged from 3630 pCi/Kg to 14380 pCi/Kg. The 1989 average annual concentration for all indicator locations and the control location for haf, feed, and silage is as follovs:

RADIONUCLIDE INDICATOR LDCATIONS CONTROL LOCA.ON K-40 845727314 pCi/rg

$73125024 pCi/Kg These results can be said to be in reasonably good agreement with those K-40 average contentrations for feed and silage reported in 1988, considering the 2 sigma values.

Another naturally occurring radionuclide which is not associated with the production of nuclear power was detected.

5 out of the 6 hay samples takea' shoved Be-7 levels above the LLD for Be-7.,-

4 The 1980 anno =1 average ecncentratinn for Be-7 for all locations in feed and silage with respect to the previous year and preoperational value is es follows:

ACTIVITY [pCi/Xg(vet)}s2 Sigma YEAR i=

984 1044 2

1989 676i1425 1988 021s1062 Preop.

The activity for Be-7 ranged from $$5 to 1670 pCi/Kg. The average 1989 concentration for all indicator locations and the cont 201 location for Ee-7 in hay is as follovs RADIONUCLIDE INDICATOR LOCATIONS CONTROL LOCATION Be-7 8132818 pCi/Kg 1670 pCi/Kg It is interesting to note that only hay and not feed or silage had positive Be-7 readings. This may be due to the fact that

. feed and silage is sheltered and not subject to the same atmospheric deposition that hay is.

The increased Be-7 activity in 1999 over 1988 can be attributtd to the increased solar fle.re activity which creates Be-7 in the upper These elevated Be-7 levels in hay ccrrelate with atmosphere.

the elevated Be-7 activity seen on air samplers and in f

precipitation.

The radionuclides Cs-134, Cs-137, co-60, co-58, and I-131 vere reported as the lover limit of detection.

11. VEGETATION Vegetation samples included grass and leaves. These samples vere collected in conjunction with the food product (produce)

A total samples and supplement the collection of milk saeples.

of 53 samples vere collected and analyzed by gamma spectroscopy in 1989.

The two naturally occurring radionuclides that were detected in vegetation samples were K-40 and Be-7.

The 1989 annual average K-40 and Be-7 concentrations for all locations for grass and leaves with respect to the previous year and preoperational values are as follovst

. m

=-

t

' e l

I 7EAtt ACTIVITY {pci/Er(vet))e2 S g K-40' l

1989 5262:2797 1988 5932:2660 l

4273s3949 i

Preop.

a Be 7 1989 1937:4946 1988 2337t 332 4

2306f1688 Preop.

RANCE 2540 to 9120 i

K 40 454 to 1Y000 Be-7 The large range for Be-7 suggests that deposition is based on localized conditions. The location with the highest Be-7 deposition was the control location, 96, located 11~eiles SSV.

The collection of grass and leaves started at the end of 1985 3

so little preoperational data exists.

The 1989 annual average coc entration for K-40 and Be-7 for g

indicator locations and the control location is as follovst

?

RADIONUCLIDE - INDICATOR LOCATIONS CONTROL LOCATIONS K-40 548332699 pCi/Kg 4417:2618 pct /Kg Be-7 1621 2743 pC1/Kg 311629324 pC1/Kg

.The annual. averages are slightly lover in 1989 than in 1988, but still in agreement with each other. The K-40 indicator sampling locations were slightly higher than the control, but-both are still-in' agreement considering the associated error, t

The Be-7 control location vas much higher than the indicetor l

location primarily due to one large reading. This was a reading of 17000 pC1/Kg on April 27, 1989. The control location (location 6) is located 11 miles SSV of the plant. It appears that varying localized conditions can lead to large Be-7 deposition.

There was no positive activity above the-detection limit for the nuclides Cs-134. Cs-137, 1-131, Co-58, and Co-60. All results vere reported as the lover limit of detection.

VI.

EFFLUENT RELEASES, Caseous effluents, particularly noble gases, decreased in 1989 over 1988 due to the outage which ran approximately 5-1/2 months and improved plant operations.,

7 v+

y

-r-t+=ev,1 v -w v***+w--rw e=m-v ww-=i=**-'ve*www*ww

'n-w

=

=we r-'-ev+

ww-"

w

---*mw--y,-a

-=-

9 Plant effluents int gaseous and 11guld relenkam in 19R9 vere i

compared to gaseous and liquid released in 1988 and are depicted in Table 6 and 1abit 7 respectively. The gaseous effluents were divided into particulate /lodines and noble gases. The liquid effluents shov only particulates. The sum of the activity (cr each category is presented with each tabic.

A summary of the radionuclides and the activity reported in the radiological environmental monitoring program from 1986 to 1989, that are identified with light-vater reactors, are displayed in Table 8.

A review of Table B shows no appreciable increase in activity for the sample matrices identified v'th light-vater reactors.

Alonuclide A review of preoperational data shows that the range t-activity prior to plant operation is statistically cons >:.ent with the range of activities report &? between 1986 and 1989, which are the first four years of operatton since criticality.

V11.

LOVER LIMIT Or DETECTION There was one environmental sample that exceeded the NRC Lover Limit of Detection Requirament. The samule media, analyses, date, location, reported value and NRC lteit are reported as follows:

REPORTED NRC I

MEDIA ANALYSES DATE LOCATION LLD VALUE LLD VALUE Precipitation Cama Spec March 3

FE-59 47.5 30 co-58 15.1 15 Zn-65 76.8 30 Nb-95 28.8 15 Cs-134 18.0 15 Ba-140 65.5 60 La-140 19.3 lb The elevated LLD for this one sample was due to a small sample sise.

r VIII.

LAND USE CENSUS The 1989 Land Use Survey ves conducted from July 20 to August 8, 1989. The survey was conducted in accordance with 10 CTR 50 Appendix 1 and the PHPP Yachnical Specifications, Section 12.

There are sixteen meteorological sectors which have their origin at the centerline of the Unit 1 and Unit 2 reactor buildings. The nearest residence, milk animal and garden vere identified in each of This information is used in the assessment of these sectors.

In addition, all potential radiological doses to the public.

produce grovers, re'reational areas, and public drinking water facilities within a five mile radius around the plant vere identified. -

4 The survey var conducted by visual inspection while traveling over all major roads within a five mile radius of PNPP, referring to previous years' reports, and talking with local residents.

The garden identified vith the highest D/0 value (Deposition rate) as a function of distance with respect to other sectors was 3121 Center Road. This is the same garden identified in 1988.

The other gardens identified in the survey by sector and distance are shovn in Table 9.

The residence at 3121 Center Road was identified as having the potential to produce the highest dore (most restrictive) X/0 value (Dispersion rate) as a function of distance with respect to the This is the same resident that was identified in the other sectors.

The dispersion and deposition rates were 1988 PilPP Land use Survey.

selected f rom the PNFP Of f-Site Dose Calculation Manual (ODCM).

Table 10 shovs the other nearest residences depicted by sector and distance.

The location at 3291 Parmly Road vas identified as the allk-producing animal location having the highest deposition rate as a function of distance with terpect to other sectors. Tnis location was also identified in the 1968, 1987, 1986 and 1985 surveys. This particular location is not participating in the Radiological The ovners have j

Environmental Monitoring Program's milk sampling.

declined when asked on several occarions.

The nther milk-producing anim ls identified in the survey by sector

(

and distance are shown it.Tsble 11.

The produce grovers are depicted in Table 12 They are listed by name, address, and sector / distance.

Some of these locations are nurseries vhich also sell produce and/or fruit.

Recreational areas and public drinking vater facilities are listed in Tab'le 13. They are listed by name, address, and sector / distance.

All locations identified in this land use section of this report and fa.'tified as in Tables 9 through 13 are shovn and listed on the m,"

Figure 4.

In summary, the Land Use Census shows that the vi 2ns.y vi' ain the 8 Km radius of the plant is considered to be a rurs; spar,ely populated area vith agricultural nurseries occupying,.arge fraction of the area. l

~

I IX.

OUALITY ASSURANCE The Quality Assurance program includes the results of the EPA Cross-Chech Intercomparison Program and the Environmental TLD Quality Control Spiking Program depicted in Table 14 and Table 15, respectively.

The vendor laboratory analyzed 73 EPA samples in 1989. A total of 4 EPA samples fell outside the EPA Control limit. This represents 5.5% of the total EPA samples. This is slightly higher than the 4.2? performed in 1988.

The four samp'es that vere out of the control limits vere as follovs:

RESULT CONTROL SAMPLE DATE TYPE COLLECTED ANALYSl$

2 SICMA_

LlHITS Vater January Pu-239 5821.1 3.5-4.9 Vater April Ra-228 2.6s1.0 2.7-4.5 Milk April Sr-89 26.0310.0 30.3 47.7 Milk April Sr-90 45.724.2 49.8-60.2 the A review of the spiked environmental TLD's in 1989 shows that sum of the average performance value and the standard deviation for each spiking period did not exceed the maximum acceptance criteria Based on this acceptance criteria, the environmental TLDs I

of 0.3.

are performing satisfactorily.

Table 15 gives a comparison of the spiked TLD results for 1989.

Spiked TLDs vere sent out during the first knd fourth quarters.

In comparing the 1989 spiked TLD quality control results of actual delivered dose to the values read, the results appear to be in For the first quarter 198'/ spiked TLDs, generally good agreenent.

the average reported value was 8% higher than the delivered dose.

The first quarter results shoved a much larger range of 7.9 mR and a The fourth greater fluctuation than the fourth quarter data.

The quarter TLD spike data shoved a definite bias to the lov side.

average was 6.5% lover than the actuel delivered dose. The range was 2.7 mR and the fluctuation of the numbers was such lover than the first quarter data. The averages vere much closer in 1989 to In 1988 the the delivered dose than those reported than in 1988.

first set of spiked TLDs vere 27% lover and the second set was 12%

The vendor lab's performance (TlHL) has improved in 1989.

lover.

X.

CONCLUSION A reviev of the environmental TLDs empicyed in the field shoved no increases in direct radiation exposur9s to the public.

significant Several environmental TLD locations displayed consistently higher exposure levels than other environmental TLDs. This pattern was observed to be influenced by soil composition. '

Environsente) air samplers indicated no appreciable chanFe in air I

activity levels. Several air sampling veeks indicated higher than usual readings which vere directly attributable to naturally produced radionuclides caused by the recently heavy solar flere activity.

Several environmental samples, such as milk, soil, water and sediment, shoved tra..:e amounts of positive activity above minimum detection levels for Sr-90.

Sr-90 was infrequently seen in water It and sediment, and frequently seen in milk and soil over 1989.

was shovn and concluded that these activities sere not of Perry Plant origin, but most likely originating from old nuclear bomb test In the case of milk, Sr-90 levels are also related to fallout.

pasttire fertilization and the kind of feed grain used.

Some environmental samples such as soil, sediment, and fish shoved trace amounts of positive activity above minimum detection levels Cs-137 vas infrequently seen in sediment and fish, and for Cs-137.

frequently seen in soil over 1989. Ilere as with the St-90, it was shovn and concluded that these activities vere not of Perry Plant origin, but most likely originating from old nuclear bomb test iallout.

to note that levels of manmade and naturally It is important occurring radionuclides have remained relatively constant ever since preoperational radiological environmental monitoring began back in 1981.

Finally, all er.vironmental samples, of one type of sample media or another, have detected naturally occurring radionuclides such as Be-7, K-40, and Ra-226. The concentrations reported in 1989 appear to be in agreement with concentrations reported in 1988 and in The consistency among unturally occurring previous years.

radionuclides over the years tend to indicate that the vendor labotatory has performed satisfactorily.

Therefore, it can be concluded that the operation of the Perry Nuclear Power Plant did not have any measurable impact on the environment during 1989. ^

_

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