ML20085M508

1988 Annual Radiological Environ Operating Rept

ML20085M508
Person / Time
Site:	Perry
Issue date:	12/31/1988
From:	CLEVELAND ELECTRIC ILLUMINATING CO.
To:
References
RTR-NUREG-1437 WM, NUDOCS 9111110074
Download: ML20085M508 (35)

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THE PERRY WUCLEAR POVER PLANT 1988 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT

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e TAPLE OF C0tGE!US DESCRIPTION PAGE Executive Summary ......................................... 1

1. Introduction ......................................... 2 II. Program Status ....................................... 2 III. Program Changes .. ................................... 3 IV. Sampling Methods and Procedures ...................... 4

1. Direct Radiation ................................ 4 2 Fish ............................................ 5

3. Sediment ........................................ 5

4. Air ............................................. 6

5. Vater ........................................... 6

6. Milk ............................................ 7

7. Vegetation ...................................... 7

8. Feed Silage /Tood Products ....................... 8

9. Soil ............................................ 8

10. Precipitation ................................... 9 V. Discussion and Results ... ........................... 9

1. Direct Radiation ................................ 9

2. Air ............................................. 13

3. Vater ........................................... 15 4 Milk ............................................ 16

5. Precipitatiei ................................... 18

6. Fish .................... ....................... 19

7. Sediment ........................................ 20 l

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e TABLE OF CONTENTS (Cont.)

DESCRIPTION PACL <

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8. l Soil ............................................ 23

9. Feed Silage / Toed Products ....................... 24

10. Vegetation ...................................... 26 VI. Effluent Releases .................................... 27 VII. Lover Limit of Detection ............................. 28 VIII. Land Use Census ...................................... 28 IX. Quality Assurance .................................... 29 X. Conclusion ........................................... 30 Table 1: List of Sample Locations ................... 32 I

Figure 1: Sample Locations Vithin Two Hiles .... 38 Tigure 2: Sample Locations Vithin Two-Eight Hiles ................................ 39 Tigure 3: Control Sample Locations ............. 40 Table 2: Missing Sample Collections ................. 41 i

Table 3: Summary of Results ......................... 44 Table 4: Nearest Garden by Sector and Disposition (D/0) Value .................... 62 Table 5: Nearest Resident by Sector and Disposition (X/0) Value .................... 63 Table 6: Hilk Animals by Sector and ,

Disposition (D/0) Value .................... 64 Table 7: Non-Dairy Animals by Sector and Disposition (D/0) Value .................... 66 Table 8: Agricultural Grovers Vithin Vicinity of PNPP ....................................... 70 Table 9: EPA Intercomparison Program 1988 ........... 74 l

l Table 10: Environmental TLD Results - 0.C.

Spiking Program 1988 ....................... 77 ,

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TABLE OF CONTENTS (Cont.)

DESCRIPTION PACE ,

Table 11: Fourth Quarter Comparison betveen TIHL and IT/RSL TLD results ..................... 78 Table 12: Direct Radiation - Thermoluminescent Dosimetry Results of Quarterly and Annual i Field Cycles 1988 ........................... 79 '

Table 13: Comparison of TLD Direct Radiation Results Summing Quarterly and Semiannual Results .... 80 i Table 14: Plant Gaseous Effluents taken from the 1988 Semiannual Radioactive Effluent Release Report ............................. 82 Table 15: Plant Liquid Effluents taken from the 1988 Semlannual Radioactive Effluent Release Report ...................................... 84 Table 16: Summary of Radionuclides Associated with i Light-Vater Reactors and the Activity  !

Reported, from the PNPP Radiologjcal Environmental Monitoring Program ............ 85 ,

Appendix A 1988 Radiological Environmental Monitoring ,

Program Data ................................ A t

EXECUTIVE

SUMMARY

This report is a summary of the PNrr Radiological Environmental Honitoring Program for 1988. The report includes a reviev of the results reported in 1988, as well as a comparison with preopetational results and 1987 results.

The report also includes results from the 1988 Land Use Survey, the EPA Cross-Check Intercomparison Program, and the TLD 1rradiation Program.

A total of 124$ environmental samples vert collected and analyred in 1988, in accordance with the PNTP Technical Specifications for Radiological Environmental Monitoring.

The presence of Co-60, Cs-137, and Sr-90, was detected in several samples, such as sediment, soil, milk, and vater. After further reviev, it was evncluded that the activity detected in these samples was not from the plant.

Therefore, the results of these analyses show no significant activity other than that from naturally occurring radionuclides and fission product deposition from veapons testing. These results were similar to those observed during the preoperational period.

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PERRY POVER PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 1988 ANNUAL REPORT I. INTR 9 DUCTION The Perry Pover Plant is a BVR plant vith a capacity to generate 1205 HVe. The main condenser circulating vater is cooled by a closed-loop natural draft cooling tower system. The plant is located on Lake Erie, on approximately 1100 acres about thirty-five (35) miles northeast of Cleveland, Ohio.

During 1988, Unit 1 produced 22,316,936 megavatt-hours of gross thermal energy and was operational (critical) for 6939.2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.

The primary objective of the PNPP Radiological Environmental Monitoring Program was to measure ambient direct radiation and radioactivity levels within a twenty-five mile radius around the Perry Power Plant. The objectives of this program vere conducted in accordance Sith the PNPP Technical Specification 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 compared to preoperational data to determine if any direct radiation or radioactivity was being contributed to the environment from the plant.

II. PROGRAM STATUS During 1988, the Perry Operational Radiological Environmental Monitoring Program consisted of seven air sampling locations, five water sampling locations, seven milk sampling locations (increasing to eight in June), thirty-five TLD (Thermoluminescent Dosimeter) locations, five precipitation sampling locations (increasing to six locations in January of 1988), two fish sampling loedtions, four sediment sampling locations, and eight soil sampling locations. The food product locations were divided into three sections with the following number of stations; produce-four sampling locations, feed / silage-seven sampling locations (increasing to eight locations in June), and vegetation (which includes grass and leaves)-five sampling locations.

The TLD locations, one through twenty-four, the four sediment and two fish sampling locations were placed into operation in 1981. In 1982, sample collection was started for air, water, milk, and food products / silage. The program was augmented in 1985 to include snov and soil. In 1988, the method for collecting precipitation was modified to include snov and rain. Print to 1988, only snov vas collected when available. Although precipitation and soil saeples are not required by the NRC Eranch Technical Position on Radiological Environmental Mnnitoring (Revision 1) or the PNPP

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Technical Specifications for Radiological Environmental Hnnitoring, the two media have been added to the program to expand the scope of environmental monitoring.

The location of each campling location within a twenty-five mile radius of the Perry Plant is shovn in Figures 1, 2, and 3. Figure 1 shows all sampling locations withir. a two 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 plant site and direction from the plant site. A description of each sample location and the media pathway found in that particular sample location are also found in Table 1.

In 1988, several samples from different environmental media vere not collected due to circumstances beyond the control of FNPP. Table 2 lists the samples, their location, the collection date, and a brief reason why each sample was not collected.

III. PROGRAM CHANGES There vere several-changes to the program in 1988. These changes include the addition and deletion of sample locations as follovst January There vere a total of 5 changes to the precipitation sampling program. This included the deletion of 3 locations, location 1 (Haines road, north of Vest Chepel road) 3.4 miles ENE, location 44 (Patmly road) 1 mile $5E.

and location 48 (Antioch road) 1.1 miles ENE. These locations vere deleted because the method of precipitation sampling was changed from an active sampling method to a '

passive sampling method. These passive precipitation collectors vere susceptible to vandalism and could no longer be relied upon to supply valid data.

All locations were designed to ensure that samples were collected in the 3 highest D/0 sectors and at the same time ensuring that the collectors were secure. This is why 2 additional locations vere added to the precipitation i sampling program. These locations are, location 3

(Meteorological Toner) 1 mile SE and location 4 (Auxiliary i road gate on Parmly road) 0.7 mile S.

June One location (location 61) vas added for milk, feed, and l silage sampling. This location.(Keller residence, 58B8 Devey road) 7.4 miles SE, was added when the residence notified the Perry Plant that they had milk goats and vanted to participate in the program.

l August One produce sampling point.vas added and one deleted.

Location 38 (Seith farm, 2861 Antioch road) 1.1 miles E, was deleted because the Seith family moved and the nev l

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ovner did not keep the garden. A nev location 62 (Shreve farm 2431 Antioch road) 1.2 miles E, was added to replace -

the lost location at the Seith farm.

IV. SAMPLING HE1 HODS AND PROCEDURES To derive meacingful and useful data from the program, esspling I methods and procedure: have br un developed which provide samples representative of potential pa ivays to man for the area. The methods described herein vere used for sample collection in 1988. ,

Samples vere collected at indicator locations or control locations.

An indicator location is a location near the plant that has a high probability cf detecting plant effluents, whereas, a control locatlon is a location that is away from the plant and cannot be influenced by the plant effluents.

1. DIRECT RADIATION Environmental thermoluminescent dosimeters (TLDs) were used to [

measure the direct (ambient) radiation Icvels at thirty-five locations as described in Table 1. Environmental TLDs were located in two rings around the station as well as along the site boundary. The inner rinE measured direct radiation within a one-mile radius around the plant, whereas, the outer ring measured direct radiation at an approximate distance of four to five miles from tho station. 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 two locations approximately ter. miles in distance in the two least prevalent vind directions from the plant.

The area around the plant is divided into 16 radial sectors, each of which is 22 1/2 degrees. Environmental TLDs vere placed in each sector except those sectors which radiate from the site directly out over the lake without intersecting any unrestricted areas over land.

Each environmental TLD consists of several calcium sulfate chips with dysprosium impurities. Each location had one field environmental TLD, one emergency environmental TLD, and one annual environmental TLD. The field environmental TLD and the emergency environmental TLD vere collected quarterly, whereas, the annual environmental TLD var scheduled to be collected once a year, in 1988, due to special circumstances two semiannual TLDs vere used instead of one annual.

The first quarter TLDs for 1988 vere lost at the vendor's laboratory. A calcu)'ted dose for the first quarter was used instead of an actua' The first quarter TLD dose vas calculated by pulling the annual TLDs at the same time the second quarter TLDs vere collected. First quarter readings vere calculated by subtracting out the second quarter TLD g

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i readings from the pulled annual TLD readings. A set of ,

semiannual TLDs vere placed out in the field to capture the remaining 3rd and 4th quarters along with the normal emergency and quarterly TLDs. The sum of the two sets of semiannual TLD results vere used to compute an annual dose instead of the use of a single set of annual TLDs. This is shown in Table 13.

The field environmental TLD vas the primary environmental TLD used for measuring direct radiation exposure and the results are included in this report. However, because the emergency '

environmental TLDs vere 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 vere not included in thia report.

Transient TLDs vere used during transportation to correct for any direct radiation not received during the field cycle.

Special ecotrol TLDs 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 reco~rded on a TLD or a group of TLDs was attributed by the plant.

All environmental TLDs vere packaged at the site and vere shipped by commercial freight to the vendor laboratory for ,

analysis.

2. TISH Fish samples vere collected semiannually from two locations.

One in the immediate vicinity of the plant discharge was the indicator location and an offshore location near Mentor-On-The-Lake vas the control location.

A passive collection technique was used for fish collection.

An experimental gill net, with a mesh ranging from approximately 1.0 to 2.5 inches was used to maximize catches in the useful size range. The net was set in the evening and removed the following morning. A scientific collecting permit has been obtained from the Ohio Department of Natural Resources to permit sampling.

Available edible portions vere packed in dry ice and shipped to the vendor laboratory for analysis by gamma spectrometry.

3. SEDIMENT Sediment samples were collected semiannually from four locations. Two samples were collected at the same locations where fish snmples were collected. The other sediment sample locations vere offshore in the vicinities of fairport Harbor and Redbird.

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Samples vere collected with a Ponar Grab Sampler. The depth of sample collection is in the approximate range of 20 to 40 feet.

These samples were collected approximately 1-2 miles offshore.

The samples vere then transferred to a plastic container. A minimum of 1000 grams of sediment from each sample location was collected, frozen, and shipped to the vendor laboratory for analysis.

4. AIR nar samples vere collected veekly at seven locations. These air sampics consist of glass fiber filters and charcoal cartridges. The glass fiber filters were used to collect particulates and the charcoal cartridges vere used to collect iodine.

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

The air samples vere collected on a lov volume air sampler (Research Appliance Company Model No. 209088-2). The air samplers run continuously and sample approximately 10,000 cubic feet of air a veek. The total air volume was measured by a dry gas meter and the time vas registered by a time totalizer. The samples were packaged and shipped to t!.e vendor laboratory for analysis.

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

5. VATER Vater samples were collected monthly at three locations and veekly at two locations. The three monthly locations ares the control location at the Ashtabula Generating Station, a drinking vater f acility (Lake County Vater Plant) in Painesville, and the Perry Plant Service Vater Pumphouse forebay. The two veekly-locations are taken from the shoreline at the north end of Green Road and at the shoreline at the boat launch in Perry Park. These two locations are on opposite sides of the plant.

Samples are collected monthly at 3 locations using composite samplers. The Perry Plant Intake sample location and the Ashtabula sample location obtain vater samples via a Horizon Interval Sampler, which collects a small volume of water at short intervals, nominally a one-and-one-half minute sample every fifteen minutes. The other vater location at the Lake County Vater Plant in Painesville uses an interval timer to

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. . control a solenoid valve on a pressurized sampling line. This sampling unit collects a one minute sample of water from the rav vater sample line every hour.

At the remaining 2 locations, grab samples are collected veekly and.composited for a monthly sample. These grab samples are taken from the shoreline.

Each' sample was composited in a tive-gallon containei. Each 1 month, two one-gallon samples and one 125-milliliter sample vere removed from each of the five-gallon containers. The remaining sample volume in the five-grilon container was disposed of. The two one-gallon samples were 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-out on the container.

All samples were then packaged and shipped to the vendor laboratory for analysis.

6. MILK During 1988, the number of milk locations had-varied from two locations to as many as eight locations. The locations that contain goats generally proouced milk from early spring to late fall. The goats vere 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 location (Rettger's Farm) was a dairy farm.

Milk samples vere collected monthly during the non-grating season (October 16 through April 14) and twice a month during the grazing season. Hilk samples vere normally collected from a batch-tank at the dairy-farm. The ovners who supply goat allk samples were given two one-gallon containers and the filled containers vere collected two to three anys later, since goats require several days to produce two gallons.

All milk samples vere -treated with forty grams of sodium bi-sulfite to preserve the milk. The samples were then packaged and shipped to the_ vendor ~1aboratory for analysis.

7. VEGETATION Samples of grass and leaves were collected monthly during the growing season, when available to supplement milk sampling.

These samples were collected at five locations. The control location (Location 6):vas in the least prevalent vind

-direction.(11-miles SSV).

~At each grass sample location, grass was clipped from an area ranging.from-15 to 168 square feet in area. Large sample areas vere used because the drought ti.at occurred during the summer

severely limited the grovth of grass. Grass sartples veighed approximately 500 grams depending on the moisture content. Samples were taken at the highest D/0 sector, the highest D/0 sector with cilk-producing animals, or both.

Leaves vere sampled at or very near the same locations as grass sanples. Leaves vere taken from one particular species (the Staghorn Sumac or Rhus Typhina L.) that is abundant in the area. A minimum of 500 grams was collected each month when available.

8. FEED SILAGE /FGOD PRODUCTS The feed silage / food product samples vere collected once a year during the harvest season (Late August or early September).

The food products vere collected from locally grown gardens and roadside vendors near the plant. One location (Location 50) vas a cchtrol location located approximately 11 miles south of the plant. In 1988 due to the drought, no food products vere collected from the control location. In lieu of this, 1987 data for food products collected at statien 50 was used as control 6ata. 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.

Teed / silage samples were collected from each milk sample location, and vere packaged and shipped to the vendor laboratory for analysis.

9. SOIL Soil samples were treken quarterly at eight locations, of which one sample vas a :ontrol sample located eleven miles SSV at the Concord Service Center. The other sail samples vere located in two rings arovrd the plant. There vere three soil samples in the inner ring vithin 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 was located near a community in the EPL sectot. This sector is one of the three highest D/0 (Deposition rate) sectors. The highest D/0 sector covers a small sparsely populated area and then eventually cor.tinues out over the lake.

A garden trovel was 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 vore then packaged and shipped to the vendor laboratory for sample analysis.

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. 10. PRECIPITATION Precipitation saraples are collected f rom six locat Aons. Five sample locations are located at the site boundary in the highest D/0 sectors. The sixth location acting as the control, is located 11 miles SSV at the concord Service Center.

Samples are collected monthly as a composite using 3 gallon passive collection containers. Containers are checked veekly and removed when the sample container is full or nearly full.

A new container is than placed in the same location for the remainder of the sample period. All r.ollected vater is composited, strained to remove debric, and shipped to the laboratory for ant. lysis.

Nitric acid is not added in precipitation semples. Since the amount of sample volume may vary fron 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, of which includes Tritium.

The addition of r.itric acid to the sample prior to shipment vould advs sely affect the Tritium analysis.

V. DISCUSSION AND RESULTS A summary of the results for each sample nedium is provioei in the Radiological Environmentul Monitoring Program Summary Table 3. The

-average values recorded in Tabic 3 reflect the reruits for each sample medium in Appendix A.

The 1988 results recorded in Table 3 are discussed balov for each sample medium and the results are compared v!.th the historical values to reflect any posrible trends.

1. DIRECT RADIATION During 19P8, there vere 138 environmental ILDs plSced in the field.- A total of tselve quarterly, sevan first half

. semiannual and two second half seulannual environmental TLDs vere found to be missing at the time of exchange.

As discussed in Section IV (1), the first quarter TLDs for 1988 vere lost at the vendor's laboratory. A calculate.d dose was used for the first quarter in lieu of the aissing first quarter TLDs. The first quarter TLD dose was calculated by pullins the annual TLDs at the same time tho second quarter TLDs were collected, and subtracting the second quarter reading from the semiannual TLD reading te get the calculated first quarter TLD read >ng.

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The average quarterly expost re for the year f or all TLDs and equivalent annual dose per year are as follovs:

Average Quarterly Equivalcnt Annual Exposure Exposure 1988 14.2 t 4.4 d/Std.0tr. 56.8 mR/ year 1987 19.9 s 5.2 d/Std.0tr. 79.6 d/ year Preoperr.tional 18.9 2 6.8 d/Std.0tr. 75.6 d/ year The exposure levels reported in 1988 are lover than reported in 1987 and the preoperational average. The lover 1988 levels are coincident with a change of vendors in 1988.

The quarterly exposure rates for 1988 ranged from 8.7 d/Std.0tr. to 22.4 mR/Std.0tr. and the location vith the highest annual average was location No. 18, 5 miles S from the plant. The highest annual average vas 19.08 mR/std.0tr.

The annw l average quarterly exposures for indicator and contt , locations in 1988 vere:

Indicator Control 14.3 3 d mR/Std.0tr. 12.7 2 4.8 d/Std.0tr.

There is no significant difference in exposure levels between the i 9 cator and the con.' ol locations.

A. 8-1987 TLD Compar Yeomparisonshovedt at the 1988 TLD results were ignsistentlylowerth4rprevioushistoricalTLDresults.

.'); an ef f or t to expleiin this difference, the 1988 TLD ftsults vere comparec' to soil samples rerults and air

14mples results to de termine if these eatrices also o perience lover that previously reported results prior to 1988. The matrices shoved no significant variation as compared to the TLDs, TLDs irradiated under the quality control program shoved that the vendor TIHL TLD results vere within the 30%

neceptance criteria, but all of the results vere biased tobrds a lover valet than the actual delivered dose.

Thnt bias was 27% f or the second quarter TLD spiking renults and 12% for the third quarter TLD spiking results vhen compared to the actual delivered dose.

In 1987 under the quality control spiking program the previous vendor IT/RSL shoved a slight bias toward a higherthanactua[<value. The average for the first la -

quarter quality control spiking program vas 9.6% higher than the recorded delivered dose. The average for the third quarter was 2.4% lover than the delivered dose.

To further evaluate the dif ference between the TLD readings from the different vendors, double badging was performed for the fourth quarter of 1988. The results of the double badging are shovn in Table 11. The average dif ference between the current vendor, TIHL, and the previous vendor, IT/RSL, shoved that TIHL vas 66% lover on the average frem IT/RSL. The control TLD's which vere placed in a lead pig for the entire fourth quarter shoved TIHL to be 62% lover on the average than IT/RSL.

TIEL compares more f avorably to the NRC results than IT/RSL in looking at the average quarterly value over the year for 1987 and 1988.

Average Quarterly Value for 1987 IT/RSL NRC* UNITS 19.931.1 1579 2.5 mR/Std. Otr.

Average Quarterly Value for 1988 TIHL** NRC* UNITS I4773 0.9 T6T3:1.0 mR/sid. Otr.

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

• • Average annual quarterly value vas calculated by averaging the 2nd, 3rd and 4th quarterly averages together.

IT/RSL is 25% greater than the NRC's value while TIHL is 10% less than the NRC's value.

Table 12 shows the results of all quarterly environmental TLDs, including the average for each quarter and the average for each location, as well as the annual environmental TLD results. The sum of the semiennual environmental TLD results by location are compared to the sum of each quarterly environmental TLD for each location at shown in Table 13.

In 1987 the TLD data shoved some seasonal variation. Readings were slightly higher during the colder months (1st'and 4th quarters) than the varmer months (2nd and 3rd quarters).

In 1988 no such seasonal variation can be seen. The lovest quarterly reading vas the 1st quarter which was a calculated t

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and not an actual reading. The 1st quarter was calculated by subtracting the 2nd quarter TLDs f rom the semiannual TLDs.

(For a discussion on the lost TLDs refer to Section IV (1)).

The same spatial variation was seen in 1988 as was seen in 1987. The 5 highest reading TLD locations in 1987 vere the same in 1988 although the order of highest to lovest did change.

1987 1988 Station Aver, mR/Std.0tr Station Aver, aR/Std.Qtr.

18 27.0332.96 18 19.88t 3.50 36 24.63t7.33 16 16.9014.91 16 24.6032.99 17 16.80t2.96 21 23.08s5.05 21 16.33t2.40 17 22.25s4.20 36 16.13s2.05 These consistent.y high locations appear to be influenced by soil composition. Location 18 also is a soll sample-location.

In comparing the TLD values with the soll concentration of naturally occurring radionuclides, there is a good correlation between the high exposure rates and the high concentrations of naturally occurring radionuclides.

In comparing the second half semiannual environmental TLDs against the 3rd and 4th quarter TLDs, the majority of the semiannual TLDs shoved higher exposure levels than the 3rd and 4th quarter TLDs added together. This difference is probably due to the combination of two errors in adding the two quarterly results.

Second Half Semiannual Third and Fourth Quarter TLD Average Average TLD Sum 31.8t3.8 mR 29.5il.9 mR B. Comparison To Semiannual Radioactive Effluent Release Reports A dose comparison is compiled between actual release results from the Semiannual Radioactive Release Reports for the first and second halves of 1988 and the equivalent results from the 1988 Radiological Environmental Monitoring Program. For this comparison the total body 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 1988) is compared to the actual readings from the TLD in the corresponding location.

According to the first and second halves of the SRERRs for 1988, the land based sector to receive the highest exposure vas the NE sector at the site boundary. The field TLD that corresponds to this location is location number 7, also located in the NE section at the site boundary, The predicted exposure according to the SRERRs is in mrem while the TLD exposure is listed in mR. For the purpose of this comparison, these units can be considered as equivalent to each other using the gamma quality factor of 1. In cornparing the expected exposures f rom the release data shovn in twe SRERRs to the four quarters at TLD results at the sam 61ocatien gives the following:

1st Otr. 2nd Otr. 3rd Otr. 4th Ott.

Expected Exposure from the SRERRs 5.85E-4 1.77E-1 2.91E-2 2.23E-2 mrem /Qtr.

Actual TLD Results 14.71 0.9 14.72 1.0 16.3;1.1 14.111.2 mR/Std Otr.

Therefore, the expected exposure from the SREPas is far too small to be positively identified above the notmal fluctuation of the natural background sources of radiation in the environment and the error associated with the TLD measurements. The expected exposures from the SRERRs for each quarter in 1988 vas less than the lover limit of detection of 1 mrem for CaSO4 (Dy) environmental TLDs.

2. Q A total of 3 samples were collected it' 1988 for each air particulate and air iodine medium. Air particulate fi.lters vere analyzed for groes beta veekly and air iodine cartridges vere analyzed by gamma spectrometry veekly. The air particulate filters vero composited by location and analyzed quarterly by gamma spectrometry.

The 1988 annual average gross beta activity for all locations for air with respect to its previous year and preoperational value is as follovst YEAR ACTIVITY (pC1/Cu.m.)

198822 Sigma 21.72 E-03t14.44 E-03 19872 2 Sigma 15.81 E-0329.88 E-03 Preop. 2 Sigma 17.44 E-03 13.74 E-03

t This was an increase of apprnximately 37% from the previous 1987 annual average gross beta concentrations.

The gross beta concentration ranged from 7 pCi/Cu.m to 49 pCi/Cu.m for all locations. The location with the highest annual average concentration was location No. 3 approximately 1.0 miles SE from the plant. This location had an annual concentration of 22.87 E-3116.20 F-3 pC1/Cu.a.

The 1988 annual average gross beta concentration for air for indicator locations and the control location is as follovs RADIONUCLIDE INDICATOR LOCATIONS C0tfTROL LOCATION Gross Beta 21.67 E-03 14.51 E-03 21.98 E-03 14.14 E-03 pC1/Cu.m. pCi/Cu.a.

There appears to be no statistical difference in gross beta concentrations between the indicator locations and the control location. The reason for the apparent increase in levels in 1988 has not been determined.

The radionuclide Be-7 vhich is naturally occurring was detected in all composite air samples.

The 1088 annual average concentration for Be-7 in air with re v,.e c t to its previous year and preoperational value is as fcilovs YEAR ACTIVITY (pCi/Cu.m.)

19882 2 Sigma 72.1 E-03332.4 E-03 1987:2 Sigma 69.3 E-03230.2 E-03 Preop.;2 Sigma 70.9 E-03 41.4 E-03 These concentrations are in good agreement.vith each other and with previous historical concentrations.

The Be-7 concentration ranged from 40 E-03 pCi/Cu.m. to 100 E-03 pCi/Cu.m. for all locations. The location with the highest annual average vas location No. 35, approximately 0.6 miles E'from the. plant. The highest annual average concentration was 82.5 E-3219.1 E-3 pC1/Cu.m.

The 1988 annual average concentretion for Be'-7 in air is as follows:

RADIONUCLIDE INDICATOR LOCATIONS CONTROL LOCATION Be-7 73.3 E-03233.2 E-03 65.0 E-03 15.82 E-03 pC1/Cu.m. pCi/Cu.m.

There vas no statir,tical difference between the annus1 average concentrations for the indicator locations and the control location.

The radionnelides co-58, co-60, Cs-134, Cs-137 and 1-131 vere reported as the lover limit of detection.

3. VATER A total of 54 vater samples vere collected and analyzed for Fross beta activity, and by gamma spectrometry in 1988. During each quarter, strontium analyses vere performed on IB vater samples. A total of 18 vater samples vere also composited and analyzed for tritium.

The 1988 annual average gross beta activity for all locations in vater with respect to its previous year and preoperational value is as follovs:

YEAR ACTIVITY (pCi/L) 19882 2 Sigma 3.0$1.8 19872 2 Sigma 6.7 t 5.2 Preop. 2 Sigma 5.26 6.78 These values relatively agree with each other when the large 2 Sigma error is considered.

The gross beta activity ranged from 1.00 pCi/L to 6.10 pCi/L for all locations and location No. 60 vas identified as the location with the highest annual average gross beta activity.

This activity was reported as 3.80 pCi/L.

The 1988 annual average gross beta activity in water is as follovs:

RADIONUCLIDE INDICATOR LOCATIONS CONTROL LOCATION Gross Beta 3.1 1.8 pCi/L 2.8tl.6 pCi/L There appears to be no significant deviation between indicator and control locations.

The radionuclide Sr-90 was detected in five out of eighteen water samples analyzed for strontium-89 and strontium-90. This activity was detected at sample Locations $34 and $36. At Location 834 the February and August collections shoved 1.00 .40 pC1/L and 1.002 .60 pCi/L respectively. These activities are right at the lover limit of detection for

strontium-90 at 1.0 pCi/L. At Location #36, the June and-August collections gave positive activities of 0.62 5 pCi/L and l

- 15 l

0.8 3 .4 pCi/L respectively even though the lover limit of detection was established to be 1.0 pC1/8.. No positive activity was detected in samples analyzed for strontium-89.

The radionuclide strontium-90 has been detected petiodically in other vater samples since 1983. The activity ranged from 0.55 pC2/L to 1.9 pC1/L. It appears that this radionuclide originates from nuclear weapons fallout.

A gamma isotopic analysis is done on water for Cs-137, Cs-134, Fe-59, La-140. Mn-54, Nb-95, 2n-65, and Zr-95. No positive activity was cetected above the lever limit of detection for any of these radionuclides.

Tritium vas detected in 10 out of 18 samples taken in 1988. In 1987, all samples shoved tritium to be at a lover limit of detection at 2000 pci/L. This value is equivalent to the NRC lover limit of detection for vater. In 1988, a new vendor was procured to analyze samples. The new vendor's ability to detect lover levels of tritium greatly improved the LLD obtainable.

The 1988 annual average concentration for all locations as well as for indicator locations and the control location for tritium in water is as follovs:

1988 ANNUAL AVERAGE INDICATOR CONTROL RADIONUCLIDE VALUE t 2 SIGMA LOCAT10NS LOCATION Tritium 284.82351 2942422 2632133 pCi/L pCi/L pCi/L The indicator locations and the control location are in good agreement witn each other. These values are vell belov the NRC lover limit of detection of 2000 pCi/L. Historforlly, preoperational data from 1982 to 1984 shoved a range from 190 pCi/L to 7!'O pCi/L. The previous vendor laboratory used from 1985 to 1987 reported one preoperational sample in 1985 to have a positive value at 2200 pCi/L. It is sttspected that this value was an abnormality.

4. MILK During 1988, a total of 119 milk samples vere collected and analyzed for radioiodine by chemical separation and by gamma spectrometry. A total of 22 samples from the 119 samples vere analyzed for strontium.

The most predominate radionuclide detected by gamma spectrometry was K-40. This radionuclide is naturally occurring and was detected in all milk samples.

i

L The 1988 annual average concentration for K-40 for all locations in vater with respect to the previous year and preoperational value is as follows:

YEAR ACTIVITY (pCi/L) 1988t2 Sigma 15412678 198722 Sigma 16772549 Preop.22 Sigma 15372546 The 1988 average value is in good agreement with the preoperational average value.

A comparison of the preoperational average concentrations for cov milk and goat milk, shovs that goat milk contains higher K-40 concentrations than cov milk. The preoperational average concentrations for goats and cows milk were 1655 i 468 pCi/L and 1320 - 394 pCi/L, respectively. Goats appeat to have a higher bioaccumulation rate than cows. This probably accounts for the difference in K-40 concentrations as well as for any other radionuclide that may take residence in these animals.

In 1988,the K-40 concentration ranged from 480 pCi/L to 2120 pCi/L for all locations. The location with the highest annual average concentration was location No. 61 which is located 7.4 miles SE from the plant. This average was reported as 1779 259 pCi/L.

l The 1988 annual average concentration-for K-40 in milk for indicator locations and the control location is as follows:

RADIONUCLIDE INDICATOR LOCATIONS CONTROL LOCATION ,

K 40 1576 712 pCi/L 13552 235 pC1/L The concentration at the control location was approximately 16%

lover than the indicator locations. In-1987 the concentration at the control location was again approximately 16% lover than the indicator locations. In 1986 the control was approximately 22% lover than the indicators.

This smaller concentration detected 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 one cov milk sample. Historically, the annual average concentration for goat milk has always been much higher than cov milk.

The radionuclides Ba-140, La-140 Cs-134, and Cs-137 vere all reported as the lover limit of detection.

i

- - . , .- , , ~n

- . . _ _ . - _ - . =

The 1988 annual average concentration for Sr-90 in milk with respect to the previous year and preopera *,nal value is as follows:

YEAR ACTIVITY (pCi/L) 198822 Sigma 3.2421.94 19872 2 Sigma 3.19t4.22 The annual average concentration for Sr-90 in milk for indicator locations and the control location is as follows:

RADIONUCLIDE INDICATOR LOCATIONS CONTROL LOCATION Sr-90 3.322.1 pCi/L 2.9t0.4 pC1/L '

The location with the highest annual average concentration was location No. 30, which is located 2.3 miles SSW from the plant.

This concentration was 4.6 pCi/L.

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

Preoperational data has shown the activity to ranBe from 0.47 pCi/L to 3.5 pC1/L. It appears the strontium-90 levels detected in milk originate from nuclear weapons fallout.

The radionuclide strontium-89 vas not dotected above the lover limit of detection.

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

5. PRECIPITATION A total of 61 precipitation samples vere collected in 1988.

There samples vere collected monthly as a composite using 3 gallon passive collection containers. Each sample was +

analyzed for gross beta activity, tritium and by gamma spectrometry.

The annual average gross beta activity for all location for precipitation with respect to previous years is as follows:

YEAR VALUE 2 SIGMA 1988 9.51tl6.94 pCi/L 1987 7.36i5.74 pC1/L 1986 8.7425.52 pC1/L 1985 10.01214.42 pCi/L r

Precipitation sampling, which until 1988 existed only as snov s sampling, started in 1985. In 1988 rain vatar was added. The

', historical results from 1965 to 1967 appear to be in agreement with the 1988 results.

The gross beta activity ranged from 1.4 pC1/L to 46.6 pC1/L for all locations and the location with the highest annual gross beta activity vas identified as location No. 3. This location is approximately 1.0 miles SE of the plant and the activity was reported as 11.872 17.46 pct /L.

The 1988 annual average concentration for gross beta in precipitation for indicator locations and the control Incation is as follows:

PADIONUCLIDE INDICATOR LOCATIONS CONTROL LOCATION Gross Beta 9.06 14.23 pCi/L 11.79227.58 pC1/L There is no significant difference bet'.ren the indicator locations and the control location considering the large range of error associated vich this analysis.

The results from samples analyzed for gamma isotopics were reported as the lover limit of detection int Ba-140, co-58, Co-60, Cs-134, Cs-137, Fe-59, La-140, Hn-54, Zn-65, and Zr-95.

No positive activity was detected in these samples by these analyses.

The results for samples analyzed for tritium shoved a total of 27 out of 61 samples analyzed giving readings above the lo-er limit of detection. The average tritium activity for all locations in 1988 vas 202.3 129.2 pC1/L. This result had a large range from 97 pC1/L to 324 pCi/L for all locations. The location with the highest annual tritium activity was also the control location. It is station No. 6, loc:..ed 11.0 miles SSV of the plant. It's activity was 236.6t71.5 pCi/L. Tritium vas rot detected in 1987 because the LLD for the laboratory performing the analysis in 1987 was 2000 pCi/L. Since the control location had the highest reading, tritium measured is most likely not associated vith the plant.

6. FISH A total of 22 samples of fish vere collected and annlyzed by ganna spectrometry. This collection was comprised of B species p

of fish. Only the naturally occurring nuclide K 40 vas detected in each sample. The major species collected each year, along vith other species, have been Freshvater Drum, Valleye and Yellow Perch. These species are major recreational and commercial species.

- 19

The 1988 annual average K-40 concentration for all locetions for fish vith respect to the previous year and preoperational value is as follovs:

YEAR ACTIVITY (pCi/L) 19882 2 Sigma 310511379 198722 Sigma 350321104 Preop.22 Sigma 372212465 The 1988 value is in agreement with the 1987 value and shows a decrease in concentration when compared to the preoperational value The concentration for K-40 ranged from 1940 pCi/Kg to 4840 pCi/Kg. The location with the highest annual average concentration was location No. 25 which was located 0.6 miles NNV from the plant. The cottentration was reported as 3286 2 1639 pCi/Kg.

The 1988 annual average K-40 concentration for fish for indicator locations and the control location is as follows:

RADIONUCLIDE INDICATOR LOCATIONS CONTROL LOCATION K 40 3286 1639 pCi/Kg 2954s1101 pCi/Kg These values are in agreement with each other.

Location No. 25 has been identified as the sampling location vith the highest mean value for K-40 every year except 1984.

The control location was identified as the location with the highest mean value in 1984.

All other radionuclides (which included Co-58, Co-60, Cs-134 Cs-137, Fe-59, Mn-54, and Zn-65) were analyzed by gamma spectrometry and reported as the lover limit of detection.

x

7. SEDIMENT There vere eight sediment samples collected in 1988. The most predominant radionuclide was K-40. This radionuclide has been detected in all samples since 1991.

The 1988 annual average K 40 concentration for ell locations for sediment with respect to the previous year and preoperational value is as follows:

YEAR ACTIVITY (pCi/L) 198822 Sigma 14090 4237 198722 Sigma IL362t4110 Preop. 2 Sigma 13317 7914

- ?O -

l

• L The 1988 value enmpares reasonably well with the 1987 and preoperational values.

The 1988 annual average K-40 concentration for sediment for indicator locations and the control locations is as follows:

RADIONUCLIDE INDICATOR LOCATIONS CONTROL LOCATION K-40 141203 4971 pCi/Kg 1400011414 pC1/Kg The indicator locations and control location are in close agreement with each other. In 1987 and 1986 the control locaxion vas higher '.han the indicator locations.

Other radionuclides that have been detected in sediment samples vere Cs-137 and Co-60. These radionuclidet are fission products and activation products, respectively. The radionuclide Cs-137 has been detected in most sediment samples since 1981. The radionuclide Co-60 has been detected periodically since 1981.

In 1988, Cs-137 vas detected in 8 out of B sediment samples.

The annual averr.ge concentration for Cs-137 for all locations in cediment with respect to the previous year and preoperational value is as follovs:

YEAR ACTIVITY (pCi/tl a

19883 2 Sigma 3081353 19873 2 Sigma 3551578 Preop.22 Sigma 2431310 The 1988, 1987 and preoperational values all appear to be in agreement with each other.

The annual tverage concentration for Cs-137 during preoperational monitoring fluctuated videly since the collection of sediment began back in 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 30 pCi/Kg in 1984.

In the year in which the lovest annual average concentration was reported, only two samples out of eight samples shoved any detectable Cs-137.

The 1988 annual average concentratisn of Cs-137 for sediment for indicator locations and the control location is as follows:

RADIONUCLIDE INDICATOR LOCATIONS CONTROL LOCATION Cs-137 278 354 pCi/Kg 3971404 pCi/Kg The indicator locations and control location are in general agreement with each other considering the large 2 sigma errors associated with each. Vith the naturally occurring K-40 and

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

i vith Cs-137 there is a pattern seen since 1986, where the

~ control 11ocation has a higher annual average than-the indicator '

locations. -In 1988, K-40 shovs an exception to this pattern.

For Cs-137, this pattern is seen in 1988, 1987, and 1986.

Co-60 was detected in 1 out of 8 samples taken in 1988. The sample taken in May of 1988 shoved a positive reading of 59 2 24 pCi/Kg.- This location was location 25, 0.6 miles NNV of_the plant; A sample taken in August at the same location shoved no detectable levels.above the lover limit of detection.

The~radionuclide Co-60 has been detected in some samples during 1981, 1985, 1986, and again'in 1987. The radionuclide Co-60 +

vas detected in only one sample in 1987. That_ activity was- ,

73 $_6 pCi/Kg. The radionuclide Co-60 was not detected in sediment samples from 1982 through 1984.

The detection of Co-60 by our current vendor laboratory agrees with our conclusion that this.radionuclide exists in the i

- environment. The detection of Co-60 has also been reported

. infrequently by two other previous vendor laboratories. In i 1987, in order to better understand the possible origin of Co-60, reveral additional sediment samples were taken several miles east from=the most eastern sediment sampling location and vest from the~most vestern sediment sampling locat.on identified in the PNPP Radiological Environmental Monitoring Program. ~These special locations vere offshore from Geneva and the east side of the city of Cleveland near the vaste1 treatment facility discharge.

'The purpose of these additional samples was to determine if any migratory pattern exists where the radionuclide Co-60 may have been discharged from another source west or east of PNPP.

The results of this-special sample collection shoved that the-radionuclide co-60, as well as the radionuclide Cs-137, vere found in these samples.- The radionuclide Cs-137 was1 detected in all samples. More detailed results of the_1987 special sample collection can be found in the 1987 annual report.

It was inferred-from these results that no significant buildup of Co-60 exists around the' plant. -Again,-the-radionuclide Co-60 has been detected during the preoperational period and continues to be detected periodically in sediment

-during the operational period. The source-of this Co-60 can not be readily determined.

With a new vendor performing the analysis in 1988 the-lover limit.o1 detection for-Sr-90 has dramatically improved. Prior to'1988, Sr-90 h:s been reported ~as below the lover limit of detection, which was 500 pCi/L. -In 1988, positive readings were'obtained. The 1988 annual average concentration for all

locations for St-90 in sediment along with the concentration for the indicator locations and the control location is as follovst 1988 VALUE INDICATOR CONTROL RADIONUCLIDE 2 SIGMA LOCATIONS LOCATION Sr-90 26.4222.0 28,5124 20.425.7 pCi/Kg pCi/Kg pCi/Kg The location with the highest annual average concentration was location No. 27 vhich is located 7.9 miles VSV of the plant.

This concentration was 30.4 2 39.7 pCi/L. Because these numbers are so lov compared to the previously recognized lover limit of detection, and their 2 sigma values so high, it is hard to assign any significant meaning to these numbers.

The results for Cs-134 and Sr-89 in sediment vere reported as the lover limit of detection.

8. SOIL A total of 32 soll samples vere collected and analyzed for strontium and by gamma spectrometry in 1988. Two naturally occurring radionuclides were detected in these samples. These vere K-40 and Ra-226. Tvo radionuclides were detected that are fission products. They were Cs-137 and Sr-90.

The 1988 annual average concentration of the naturally occurring radionuclides K-40 and Ra-226 for all locations in soil with respect to the previous year are as follows:

RADIONUCLIDE 1988 VALUE t 2 SIGMA 1987 VALUE t 2 SIGMA K-40 11298 7865 pCi/Kg 12420t6268 pCi/Kg Ra-226 1134;1797 pCi/Kg 7401498 These values appear to be in good agreement with each other, considering the large 2 sigma error. 7 The annual average concentration of tie naturally occurring radionuclides K-40 and Ra-226 in 1988 for indicator locations and the control location vere as follovs:

RADIONUCLIDE INDICATOR LOCATIONS C0hTROL LOCATION K-40 1124528184 pCi/Kg 1167025963 pCi/Kg Ra-226 107511700 pCi/Kg 154322513 pC1/Kg The control values show slightly higher annual average concentrations than the indicator values for K-40 and Ra-226, it has been observed that the results from samples taken at various locations differ significantly. The range for K 40 i

i

varied from 5960 to 24200 pCi/Kg and the range for Ra-266 varied from 315 to 3570 pCi/Kg. This difference can be attributed ta soil composition at the various locations.

The radionuclides Cs-137 and Sr-90 vere detected in most of the samples collected in 1988. The annual average concentration for all locations in soil with respect to the previous year is as follows:

RADIONUCLIDW 1988 VALUE 2 SIGHA 1987 VALUE 2 SIGMA Cs-137 3962 671 pCi/Kg 463 558 pCi/Kg Sr-90 63.2t121.5 pCi/Kg LLD The 1980 annual average concentration for Cs-137 and Sr-90 for indicator locations and the control location are as follows:

RADIONUCLIDE INDICATOR LOCATIONS CONTROL LOCATION Cs-137 375 699 pCi/Kg 529t 427 pCi/Kg Sr-90 54.6 108.1 pCi/Kg 162.4 t 105.8 pCi/Kg In the ..Ases of Cs-137 and Sr-90, both of these have very large 2 sigma values. Also in both cases the control is larger than the indicators. For Cs-137 the control was larger than the indicator in 1987 and 1986 also. It can be inferred that whatever the relatively small amount of activity of these tvo radionuclides, the source is not the Perry plant. Nuclear weapons test fallout is the best possible explanation for the source of Cs-137 and Sr-90. The ability of the control location to collect higher concentrations of Sr-90 and Cs-137 is most likely related to a difference in soil chemical properties. Properties like chemical composition and ion exchange capacity along with moisture content and pH-can vary

' from area to area, thus making different areas more susceptible to fallout accumulation. Again here, as in the case of Sr-90 analysis in sediment, the lower limit of detection has dramatically improved with the change to a new vendor. Prior to 1988, Sr-90 has been reported as below the lower limit of detection which was 500 pCi/L.

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

9. FOOD PRODUCTS / TEED AND SILAGE A total of 6 different types of produce, including fruit, vere j collected from several grovers around the plant. An attempt vas made to collect broad leaf vegetation such as cabbage and lettuce when collecting produce. Also, feed, hay, and silage samples were collected from each milk sampling location. These samples vere collected annually. Each sample was analyzed by 6

gamma spectrometry.

i

- 24 i

4 The most predeminant radionuclide found in each produce sample was the naturally occurring radionuclide K-40. The 1988 ar.nual average concentration for K-40 for all locations in produce with respect to the previous year and preoperational value is as follovs:

YEAR ACTIVITY (pCi/L) 1988t2 Sigma 1614 913 1987 2 Sigma 193511468 Preop. 2 Sigma 2296s2160 The activity ranged from 650 pCi/Kg to 2190 pCi/Kg. The average 1988 concentration for all indicator locations and the control location for K-40 in produce is as follows:

RADIONUCLIDE INDICATOR LOCATIONS CONTROL LOCATION K-40 1614 913 pCi/Kg *27273910 pCi/Kg

• ' In 1988 because of the long summer drought, there was no produce available at the control location. The value used as the control is the 1987 value.

Comp 3rison of the 1988 K-40 average concentration for all loca; ions to 1987 K-40 average concentration for all locations in produce, shows that the 1988 K-40 concentrations were much lover. It is suspected that the drought may be the cause for the Lover K-40 concentrations.

The nuclides I-131, Cs-134, Cs-137 Co-60, co-58, and Be-7 vere reported as the lover limit of detection.

The major radionuclide detected in feed, hay and silage was the naturally occurring radionuclide K-40. This nuclide was detected in all samples.

The 1988 annual average concentration for K-40 for all locations in feed, hay and silage with respect to the previous-year and the preoperational value is as follows:

YEAR ACTIVITY (pCi/L) 1988 2 Sigma 9558$9569 1987 2 Sigma 11181 12518 Preop. 2 Sigma 771518590

l l

The activity ranged from 2790 pCi/Kg to I?150 pCi/Kg. The 1968 average annual concentration for al.1 indicator locations and the control location for hay, feed, and silage is as follows:

RADIONUCLIDE INDICATOR LOCATIONS CONTROL LOCATION K-40 97C3 967 pCi/Kg 8435il2374 pC1/Kg These results can be said to be in reasonably good agreement with those K-40 average concentrations for feed and silage reported in 1987, even though the 2 sigma values are very large.

Another naturally occurring radionuclide was detected with positive activity, only at the control location. The radionuclide Be-7 vas detected in 2 samples at control location 51, 9.2 miles south of the plant. Be-7 has been detected in only a few samples since 1982.

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

10. VEGETATION Vegetation samples included grass and leaves. These samples were collected in conjunction with the food product (produce) samples and supplement the collection of milk samples. A total of 62 samples vere collected and analyzed by gamma spectrometry in 1988.

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

The 1988 annual average K-40 and Be-7 concentrations for all locations for grass and leaves with respect to the previous year is as follows:

RADIONUCLIDE 1988 VALUE 2 SIGMA 1987 VALUE 2 SIGMA K-40 5932 2660 pCi/Kg 558813486 pCi/Kg Be-7 2337 4332 pCi/Kg 2047t3604 pCi/Kg RANCE K-40 2770 to 9310 pCi/Kg Be-7 230 to 8160 pCi/Kg

The 1988 annual average concentration for K-40 and BE-7 for indicator locations and the control location is as follovsi-RADIONUCLIDE INDICATOR LOCATIONS CONTROL LOCATIONS K-40 6097t 2541 pCi/Kg 5308t2829 pC1/Kg Be-7 22862 405 pCi/Kg 2520:4207 pCi/Kg The annual averages are slightly higher in 1988 than in 1987, 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 errot.

The collection of grass and leaves started at the end of 1985 so no preoperational data exists.

There was no positive activity above the d2tection limit for the nuclides Cs-134. Cs-137, I-131, 0o-58, and co-60. All results were reported as the lover limit of detection.

VI. EFFLUENT RELEASES Plant effluents for gaseous and liquid releases in 1988 vere compared to gaseous and liquid released in 1987 and are depicted in Table 14 and Table 15, respectively. The gaseous effluents were divided into particulate /lodines and noble gases. The liquid effluents show only particulates. The sum of the activity for each category is presented with each table.

A summary of the radionuclides and the activity reported !n the PNPP radiological environmental monitoring program from 1986 to 1988, that are identified with light-vater reactors, are displayed in Table 16.

A review of Table 16 shows no appreciable increase in activity for the sample matrices identified with light-vater reactors, with the exception of the radionuclide Sr-90 in milk.

This particular sample media has shown a slight increase in Sr-90 activity from 1986. A review of preoperational data shows that the range of Sr-90 activity prior to plat.t operation is consistent with the range of activities reported between 1986 and 1988 vhich are the first'three years of operation since criticality.

"h'

VII. LOVER LIMIT OF DETECTION There vere-three environmental samples that exceeded the NRC Lover Limit of Detection Requirement. The sample media, analyses,-date, locetion, reported value and NRC limit are reported as follovst HEDIA ANALYSES DATE LOCATION REPORTED VALUR NRC VALUE MILK IODINE B30520 30 1.3 1.0 HILK 10D1NE 880520 47 1.4 1.0 MILX 10DINr 880520 51 1.3 1.0 The increase in the lover limit of detection for radioic41ne in milk was due to the relocation of the vendor's laboratory and subsequent delays in the counting.

VIII. LAN9 USE CENSUS The 1988 Land Use Survey was conducted from June 3rd to June 14th.

The purpose of this survey was to determine the use of land within tha vicinity of the plant and to identify any changes from previous surveys. The survey focuses primarily on the nearest resident, the nearest garden and the location of milk producing animals within an 8 Km distance of the plant.

This survey also identified the non-dairy (Beef) animals and the agricultural grovers within an 8 Km distance of the plant. These two pathvays can be significant routes in assessing dose to the public from the food chain.

The garden identified with the highest D/0 value (Deposition rate) as a function of distance with respect to other sectors was 3121 Center Road. Last year the garden at 3119 Parmly Road had the

-highest D/0 value.

The other gardens identified in the survey by sector and distance are shovn in Table 4.

The residence at 3121 Center Road was identified as having the potential to produce the highest dose (most restrictive) X/O value (Dispersion rate) as a function of distance with respect to the other sectors.

This is a different resident when compared to the 1987 PNPP Land Use survey. The dispersion and deposition rates were selected from the PNPP Off-Site Dose Calculation Manual (ODCH).

Table 5 shows the other nearest residences depicted by sector and distance.

The location at 3291 Parmly Road for milk-producing animals was identified as having the highest deposition rate as a function of distance with respect to other sectors. This location was also identified in the 1987, 1986 and 1985 surveys. This particular location is not participating in the Radiological Environmental Monitoring Program's' milk sampling._ The owners have declined when askeduon several occasions.

The other' milk-producing animals identified in the curvey by sector-and distance:are shovn in Table 6.

Non-dairy animals, such as-heifers, beef cattle or beef cows, are  ;

animals-that consume pasture grass as.their main staple diet and

-these animals may eventually be consumed by man. Therefore, the major food chain pathvey is the air-grass-animal-man pathway.

Table 7.shows these animals by direction, location, deposition

-value,.and number / type of animal.

-The. agricultural growers are depicted in Table 8. They are listed by name,--address, city, sector / distance, deposition,value, and type of grover. No ranking of these growers by deposition-value was made in the survey because some agricultural grovers have very large property. In some cases, this property extends over many acres which crosses into other sectors. Also, the owners have property scattered over the Lake County area. The deposition value assigned '

to these locations only represents the point at where the property was identified.during the survey.

The majority of these locations were nurseries, with some nurseries also selling' produce and/or fruit.

In summary,.the Land Use Census shows that the vicinity within the 8 Km radius of the plant-is considered to be a rural sparsely populated area with agricultural nurseries occupying a large fraction of the area.

IX. QUALITY ASSURANCE i

The Quality Assurance program includes the results of the EPA Cross-Check Intercomparison Program and the EnvironmentalL7LD Quality' Control Spiking Progrem depicted in Table'9 and Table 10, respectively.

The vendor laboratory analyzed 72 EPA samples in 1988. A total of

-3 EPA samples fell outside the EPA Control limit. This represents 4.2% of the total EPA' samples. This is a significant improvement over 1987.~ In 1987 a different vendor reported a total of 20 EPA samples fell outside the EPA control limits which represented 25.3%

of the' samples'being out of the EPA control limits. The improvement seen is.a direct result of the change in vendors.

The three samples that vere out of the control limits vere as follows:

SAMPLE' DATE RESULT CONTROL TYPE COLLECTED ANALYSIS 1 SIGMA LIMITS Food . January K 1010.7i79.3 1123.5-1336.5 Vater April I-131 9.011.0 6.2-8.8 Vater April Co-60 63.3i0.65 41.3-58.7 A. review of the spiked environmental TLD's in 1988 shows that the sum of the average performance value and the standard deviation for each spiking period did riot exceed the maximum acceptance criteris of 0.3. Based on this acceptance criteria, the environmental TLDs are performing satisfactorily. In comparing the 1988 spiked TLD results'to the actual delivered dose there can be seen a bias towards lower values. That bias was 27% lover than the actual delivered dose for the second quarter TLD spiking results and 12%

for the third quarter TLD spiking results. This bias toward lover values ~vas not seen in the 1987 TLD quality contro) spiking program with the previous laboratory vendor. A bias towards lover values is also seen in the 1988 field TLDs when compared to 1987, 1986 and preoperational values. It was in 1988 that PNPP changed vendors from IT/RSL to TIHL. This bias can be directly attributed to the new vendor TIML, but the exact reason is unknovn. It is important to note that TIHL field TLD results are in better agreement with the NRC's field TLD results than the previous vendor IT/RSL.

X. CONCLUSION A review of the environmental TLDs employed in the field shoved no increases in direct radiation exposures to the public. Several environmental TLDs displayed consistently higher exposure levels than other environmental TLDs. This pattern was observed to be influenced by soil composition.

Several environmental samples, such as milk, soil, water and sediment, shoved positive activities above minimum detection levels on several occasions. These radionuclides were Cs-137, Sr-90 and Co-60, respectively. These radionuclides are not normally detected or are detected on an infrequent basis in these samples. It was concluded that these activities were not of plant origin, but rather from nuclear fallout.

It is important to note that some samples such as milk, sediment and soil tend to have appreciable amounts of radioactivity above detection levels on a frequent basis. Hilk samples are shoving a consistent pattern of detecting Sr-90, whereas, sediment and soll shov'a consistent pattern of detecting Cs-137. These radionuclides are fission products that have been detected in the preoperational period of the PNPP Radiological Environmental Honitoring Program and most likely originate from the fallout of nuclear weapon testing.

o Finally, all environmental 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 1988 appear to be.in good agreement with concentrations reported in 1987 and in previous years. _The consistency among naturally occurring radionuclides over the years tend to indicate that the vendor laboratory has performed, in general, satisfactorily.

Therefore, it can be concluded that the Perry Nuclear Power Plant did not have an impact on.the environment during 1988.

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