ML20085M490

1987 Annual Radiological Environ Operating Rept

ML20085M490
Person / Time
Site:	Perry
Issue date:	12/31/1987
From:	CLEVELAND ELECTRIC ILLUMINATING CO.
To:
References
RTR-NUREG-1437 WM, NUDOCS 9111110051
Download: ML20085M490 (28)

Text

r.

c d

THE PERRY NUCLEAR POVER PLAN 1 1987 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT l

9111110051 871231 FDR NUREG PDR i .1437 C L

-s e

- a.

'd TABLE OF CONTCNTS DESCRIPTION PAGE Executive Summary . . . . . . . . . . . . . . . . . . . 1 2

I. Introduction .....................

2

11. Program Status ....................

Program Changes . ................... 3 III.

Sampling Methods and Procedures . 4 IV. . . . . . . . . . . .

1. Direct Radiation . . . . . . . . . . . . . . . . . 5

2. Fish . . . . . . . . . . . . . . . . . . . . . . . 6

3. Fediment ............, . . . . . . . . 6 ,

4. Air ....................... 6 Unter ...................... 7

5. .

7

6. Hilk . . . . . . . . . . . . . . . . . . . . . . .

' 7, Vegetation . ................... 8

8. Feed Silage / Food Products . . . . . . . . . . . 8

. . . . . . . . . . . . 9

17. Soil . . . . . . . . . . .

10. 9 Srov . ................. .

' 9 V. Discussion and Results . . . . . . . . . . . . . .

-1. Direct Radiation . . . . . .. . . . . . . . . . . 10-Fish ... . .................... 11 2.

Sediment . . . . . . . . . . . . . . 12

3. ......

4. Air ....................... 14 5.- Vater ...................... 15

< . 6. tilk . . . . . . . . . . . . . . . . . . . . . . . 16

7. Vegetation . . . . . . . . . . . . . . . . . . . . 18

8. Feed Silage / Food Products . . . . . . . ..... 18

(-

l

- L - = _--- _ _

4 TABLE OF CONTENTS (Cont.)

DESCRIPTION PAGE 19

9. Soil.......................

20

10. Snov . ......................

. . . .. . . .. . . . . . 21 VI. Lower Limit of Detection .

21 VII. Land Use Census . . . . . . . . .. . . ... . . . ..

23 VIII. Quality Assurance . . . , .. . .. . .... . . . . .

24 IX. Conclusion ......................

List of Sample Locations . . . . . . . . . . 25 Table 1:

Figure 1: Sample Locations Vithin Two Miles . .. 30 Figure 2: Sample Locations Vithin Two-Eight Miles . ... . ... .. . . . . 31 32 g

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

Table 2: Missing Sample Collections . . . . . . . . . . 33 Summary of nesults . . . . . . . . . . . .. . 35 Table 3:

Table 4: Nearest Garden by Sector and 54 Disposition (D/0) Value . .. . . . . . . ..

Table 5: Nearest Resident by Sector and Disposition (X/0) Value . . ... . . . . . . 55-Table 6: Milk Animals by Sector and 56 Disposition (D/0)-Value . ... . . . . .. .

Table 7: Non-Dairy Animals by Sector and 57 Disposition (D/0) Value .... . . . . .. .

Table 8 . Agricultural Grovers Vithin Vicinity 60 of PNPP . ... . . .. . . . . . .. . ...

Table 9: EPA Intercomparison Program 1987 . . . . . . . 63 Table 10: Environmental TLD Results - 0.C. 66 Spiking Program 1987 . . . . . . ._. . . . . .

4 i

9-TABLE OF CONTENTS (Cont.)

DESCRIPTION PAGE-Appendix A . . . . . . . . . . . . . . . . . . . . . . - . A-1 Appendix B . . .. . . . . . . . . . . . . . . . . . . . B-1 i

<)

?

, ~'i-i

+~'b ,-

EXECUTIVE

SUMMARY

This report is a summary of the PNPP Radiological Environmental Monitoring Program for 1987. The report includes a review of tae results reporte." in 1987, as well as a comparison with preoperational results and 1986 results- The report also includes results from the 1987 Land Use Survey, the EPA Cross Check Intercomparison Program, and the TLD Irradiation Program.

A total of 1199 environmental samples vere collected and analyzed in 1987, in accordance with the PNPP Technical Specifications for y

Radiological Environmental Monitoring.

The presence of Co-60, Cs-137, and Sr-90, was detected in several samples, such as sediment, ellk, and vater, respectively. After further investigations that included the collection and analyses of additional sediment samples.-it was concluded that the activity detected in these sarples was not from the plant. This conclusion was supported by plant effluent reports, which showed no releases of these radionuclides.

Th3refore, the results of these analyses shov no significant

- activity other than'that from naturally occurring radionuclides and fission product deposition from global nuclear 'allout and vere similar to those observed during the preoperational period f 4

{

l l.

l I

L

!~

J

%&@ 9$;- 1 N 40 e,

IMAGE EVALUATION ////p k*/,f,pf t4 (p

\//o

//7 %<]h Y@h*

% ,[ %g TEST TARGET (MT-3)  %

p /($rj ff*

g7fx-

$ p &'  %

l ga m J l,0 E lt! NE  !

1 u ?l R?1 l.25

-- t.l -

1.4 M 1.6 4 150mm

• 4 6" >

W *'4 py

• kllV b,,,(,,,r= =

/ 4N

> t t

.:i i

%.Q> <

i 15 % :: .. _

. ..= a n zu;d 51_ _L -q IL L

x _ _

d l(g pg% 4>

S.D #e..2 V IMAGE EVALUATION gN\ [O[%[@ 'A*e,ig)<$* TEST TARGET (MT-3)

</ [J 4g

\ .

I k

+ <w I 1.0 P "* W j s. w, gnm t

l,l "

!!! l.8

] l l]_ _ .

1.25 1.4 il I.6 1i-4 150mm >

4 6" >

d, 4 4 p447,, - _ - .

4'

,,3 A ggsNN z% a g;%7,gy,g/,,4 ( ~

<;gh;:ij3 i Oy  :

fs g h

m (_s

_j,

- - - - Am.. - _ _ _ . _ . _ _ _ _ _

~ -nu --2 --r,- .-s s sa s a m a a n --- u- m .r- s armaa,~+x -a - n, 6.- u shm en .h a s.a mnsmasan% ,g m - - - - - -

l 40 9

$+tt

' 4 [hQVa ga%ff IMAGE EVALUATION

/

e.

/ y,4@g,'(4',

//g// - TEST TARGET (MT-3)

'kg h ';h'

$+>pf'  %

il Il0 . lf a M l E j

~ nT L23

$ l,l U N i,

ll ._l.3_ _.

l.25 1.4 l 1.6 i ,

4 -

150mm >

4 6" >

,,rf. %f s'" a$//p yei ,y7/c.D:

o., j g

3 <>+4) f+e a e  :

~ 'NwL .

x .aum.;n$b 2- .

2%y

e. ,

ll;c .

V q

PERRY POVER PLAN 1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 1987 ANNJAL REPORT I. INTRODUCTION The Perry Power Plant is a twin unit BVR plant with a capacity to generate 1205 NVe per unit. The main condenser circulating water 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.

PNPF Unit 1 received approval for 5% power and achieved initial criticality on March 18, 1986 and June 6, 1986, respectively. The plant was approved for full power on November 13, 1986 and reached commercial operatior, on November 18, 1987.

During 1987, Unit 1 produced 7,918,314 segavatt-hours of gross

-thermal energy and was operational (critical) for 4,504.3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 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 were conducted in accordance with the PNPP Technical Specification Section 3.12 Radiological Monitoring Program.

Prior to initial criticality, '.ne program compiled several years of preoperational data to establish a baseline database. The operational data vere compared to preoperat.lonal data to determine if any direct radiation or radioactivity va" being contributed to the environment from the plant.

In addition to collecting environmental data, the preoperatsonal period provided the opportunity to evaluate ,irocedures, equipment y and techniques,.as well as to provide experience to personnel, t

'II. PROGRAM STATUS During 1987, the Perry Operational Radiological Environmental Monitoring Frogram consisted of seven air sampling locations, four water sampling locations, seven milk sampling locations, thirty-Ivuc TLD (Thermoluminscent Dosimeter) locations, seven snow sampling _

locations, two fish sampling locations, four sediment sampling locations, and eight soil sampling locations. The food product locations were divided into three sections with the following number p

4 of stations; produce-four sampling locations, silage / feed-six sampling locations, and vegetation (which includes grass and leaves)-five sampling locations.

i The TLD locations, one thr ough tventy-four, and the f out :ediment and two fish sampling locations veie placed into operation in 1981.

In 1982, sample collecticn was started for air, vater, milk, and food products / silage. The program vas augmented in 1985 to include snow and soil. Although snov and toil samples are not required by the NRC Branch Technical Position on Radiological Environmental Monitoring Revision 1 or the PHPP Technical Specifications for Radiological Environmental 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 radies of the Ferry Plant is shevn in Figures 1, 2, and 3. Figure I shows all sampling locations within a two mile tadius of the plent, Figure 2 shows all sample locntions approximately two miles to eight miles of the plant and Figure 3 shovs all control locations greater than ten miles from the plant.

Table 1 identifies each semple station by number, the distance from the plant site ard direction from the plant site. A description of each . sample location and the media pathvay found in that particular sample location are also lound in Tab?e 1.

In 1987, several samplas from differtnt eevironmental media vere not collected due to circumstances beyond the control of PNPP. Table 2 lists the samples, their location, the collection date, and a brief reason why each se aple vas not collected.

III. PROGRAM CHANCES There vere several changes to the program in 1987. These changes include the addition and deletion of sample locations as well as temporary changes.

The program lost two milk sampling locations and gained one location. The loss includes Location No. 30 (Manley residence, 2.3 miles, SSV), an indicator location and Location No. 33 (Creig's Farm, 10.2 miles, S) which was a control location.

Tim owner of the goat farm at the Manley residence was returning to a nev job and vould not be able to maintain the goats. A new control location (Lotetion 51, Rettger's Farm, 9.2 miles, S) began participating in the program in 1986. This location was placed in service in anticipation of losing Creig's Farm (Location No. 33) to the government's program to reduce milk production.

The new milk sampling location is Location No. 57 (Butler residence, 8.5 miles, e). This milk sampling location qualifies as a location with a high deposition rate (D/0) with respect to other locations.

l Several owners participating in the milk sampling program removed their goats from milking in November. They ate as follows:

Location 29: Valtes Residence 1.3 miles /ESE Location 31: Hofer Residence 1.4 miles /ESE Location 47: Zoldak Residence 6.5 miles /E Location 57: Butler Residence 8.5 miles /E This has been a normal husbandry practice in the past years and most participants return to the program in the spring.

The vater sampling program lost Location No. 37 (Ohio Vater Service Co. Green Rdr 4.1 miles ENE) at the end of August. It was learned from Ohio Vater personnel that the Green Rd Vater Treatment Facility vill be terminating all operations and taken completely out of service.

This loss eliminated a suitable vater sampling location east of the plant. An investigation to locate a new vater intake east of the plant tevealed that the nearest intake is at the Ashtabula Generating Station, 22 miles east. Because of its distance from the plant, this source vould be a poor choice for an indicator location.

To ensure adequate vater samples from the lake, in addition to the remaining vater sample locations, two vater sample locations (Location No. 59, 0.33 miles, NNE and Location 60, 0.66 miles. VSV) vere added to the program. These samples vill be taken directly from the shoreline on a veekly basis and composited for monthly analysis in 1988.

A TLD location (Location No. 58, 0.8 miles, ENE) vas added to the program in the fourth quarter. A review of current maps used for identifying sample locations shoved that TLD Location No. 8 was very close to the E/ENE sector line. This prompted the addition of TLD Location No. 58. The map situation is being updated with more current and accurate maps.

IV. SAMPLING METHODS AND PROCEDURES To derive meaningful and usef ul data f rom the program, sampling methods and procedures have been developed which provide samples representative of potential pathways to man for the area. The methods described herein vere used for sample collection in 1987.

Samples vere collected at indicator locations and control locations.

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

4-l

\

l

1. DIRECT RADI/. TION Environmental thermoluminescent dosimeters (TLDs) were used to measure the direct (ambient) radiation levels at thirty-five locations as described in Table 1. Environmental TLDs vere located in two rings around the station as well as along the site boundary. The inner ring measured direct radiation within a one-mile radlos around the plant, whereas, the outer ring measured dirr

• radiation at an approximate distance of four to five miles from the 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 ten miles distant 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 were 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 er.vironmental TLD consists of several calcium sulf ate 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 vas collected once a year.

The field environmental TLD was the primary environmental TLD used for measuring direct radiation exposure and the results are included in this report.Since the emergency environmental TLDs were intended to be used only under emergency conditions and they may be removed from their locations at intermittent times during tne year, the results of the emergency environ-mental TLDs were not included in this report.

This report also includes the annual environmental TLD results.

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

Special control TLDs were 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 group of TLDs vos attributed by the plant.

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

2. FISH Fish samples vere collected semi-annually 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 was 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 to maximize catches in useful size ranges, was set in the ev(ning and removed the following morning. A scientific collecting permit has been obtained from the Ohio Department of Naturtl Resources to permit sampling.

Available edible species vere filleted at the time of

. collection. The edible portions were packed in dry ice and shipped to the vendor laboratory for analysis by gamma spectrometry.

3. SEDIMENT Sediment samples vere collected semi-annually from four locations. Ivo ssmples were collected at the same locations where fish samples where collected. The other sediment sample locations where of fshore in the vicinities of Fairport Harbor and Redbird.

Samples vere collected with a Petite Fonar Grab Sampler. The depth of sample collection ranges from 20 feet to 40 feet.

These samples were collected approximately 1-2 miles offshore.

The sampics vere then transferred to a plastic container.

Approximately 2 lbs. of sediment was collected and frozen from each sample location, and shipped to the vendor laboratory for analysis.

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

There were six air sample locations cperating within a four mile radius 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 were collected on a lov volt'me air sampler (Research Appliance Company Model No. 200 0?-2). The air samplers run continuously and sample generally 10,000 cubic feet of air a week. The total air volume was measured by a dry gas meter and the time was registered by a time totalizer. The 1

I' l

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

All air samplers were calibrated for total air flov and had maintenance checks every six months or after repair.

5. VATER Vater samples vere collected mon:hly at four locations, of which, one location was a control location (Ashtabula Generating Station). Two locat.cns (Peinesville and Green Rd.

in Madison) are drinking vater facilities. The othet facilities, (Perry Power Intake and the Ashtabula cortrol location) extract surface water from Lake Erie for industrial use.

In August, Ohio Vater Service closed the Green Rd. Vater Treatment Facility permanently. The program incorporated two new surface water sample locations into the Radiological Environmental Monitoring Program. These samples vill be collected from the shoreline on a weekly basis and composited for monthly analysis.

The Perry Plant Intake sample location and the Ashtabula sample location obtain water samples via a Horitor 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 two vater locations use an interval timer to control a solenoid valve on a pressurized sampling line.

Thic sampling unit collects a one minute sample of water from the rav vater sample line every hour.

Each sample was composited in a five-gallon container. Each month, at each location, two one-gallon samples and one 125-milliliter staple vere removed from the five-gallon container. The remaining sample volume in the five-gallon container was disposed of back into the lake. 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, and it does not plateout on the container.

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

6. MILK During 1967, the number of milk locations had varied from one location to as many as seven locations. The locations that contain goats generally produced milk from early spring to late fall. The goats were generally dried-out in the vinter. This has been a normal husbandry practice. Bovever, dairy cows have been producing milk on a year-round basis. The control l

location (Rettger'c Farm) was a dairy farm.

Milk samples vere collected monthly during the non-grazing season (October 15 thru April 15) and twice a month during the grazing season. Milk samples were normally collected f rom a batch tank at the dairy farm. The owners who supply goat milk samples were given two one-gallon containers and the filled '

- containers vere collected several days later, since goats require several days to produce two gallons. i All milk samples vere treated with eighty milliliters of  :

formalin to preserve the milk. In October, sodium bi-sulfite vas used to preserse milk. The sodium bi-sulfite does not interfere with the ion exchange process when attempting to extract iodine from milk. This chemical has been used in subsequent milk samples. The samples were then packaged and shipped to the vendor laboratory for analysis.

7. VEGETATION Samples of grass and leaves were collected monti.ly, when available, to supplement milk sampling. These samples vere colletttd at five locatinns. The control location (location 6) vis in the least prevalent vind direction.

At ecch grass sample location, grass was clipped from an area pproxima'.ely 24 square feet in area. However, due to the moisture content of the grass, the grass samples veight j from 1100 grams to 4400 giams. Samples were taken at the bi; hest D/0 secter, the highest D/0 sector with milk-producing animals, or both.

Leaves vere sampled at or very neaa the same locations as grass sar. pie s . Leaves vere taken f rom one particular specie (the Staghorn Sumac or Rhus typhina L.) that is abundant in the area. A minimum of 500 grt s was collected each month when available.

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

The food products were collected from locally grown gardens and roadside vendors near the plent. One location (Location 50) vas a control location located approximately 11 miles south of the plant. 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.

Feed / silage samples were collected f rom each milk sample location, and vere packrged and shipped to the vendor laboratory for analysis.

'4

9. Soll Soll samples vere taken quarterly at eight it. cations, of which one sample was a control sample lo ated eleven miles SSV at the Concord Service Center. The other soll sanples vete located in two rings around the-station. There vere three soil samples in the inner ring within a mile of the plant.- Another three soil samples were collected in an outer ring approximately five miles from the plant. The eighth soll sample was located near a community in the ENE sector. 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 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 r. oil-vas placed in a one-liter plastic container at each locotton. The samples vere then packaged and shipped to the vendor laboratory for sample analysis.

10. SNOV Snov samples were collected from seven locations when available. Snov samples were generally collected within a short time frame after a fresh snoviall when more than several inches have accumulated, i Snov samples vere collected from two of the three highest dispersion sectots near the site boundary and several other locations near the site boundary. A control sample is taken approximately eleven miles SSV of the plant.

A large rectangular scoop vas used to remove the snov. Only several inches from the surface of the snov vere removed and placed in a four-liter contairer. -A sufficient amount of snov vas removed and packed it.to the container until 1000 grams had been collected in the container. A spring scale is used to veigh each container. Once a sufficient amount of rnov has been collected, the area was measured and documented on the col'ection field f orm. When the snow melts, the liquid contents (1000 ml) were transferred to a one-liter container.

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

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 f sample medium in Appendix A.

_9 4

The 1987 results recorded in Table 3 are discussed belov for each sample medium and the results ate compated with the historical values to reflect any possible trends.

1. DIRECT RADIATION During 1987, there were 137 environmental TLDs placed in the field. A total of seven quarterly and seven annual environmental TLDs vere found to be missing at the time of exchange.

The annual average quarterly exposures for all TLDs in 1987 vas 19.92 2.6 mR/Std.0tr. This is equivalent to an annual dose of 79.6 mR per year. The annual average quarterly expcsure level in 1986 was 20.322.7 mR/Std.Qtr. or 81.2 mR per year. The average pre-operational quarterly exposure level was 18.913.38 mR/Std.Qtr. or 75.6 mR per year. The exposure levels reported in 1986 and 1987 agree vell with each other and vere consistent with pre-operational exposure levels for this area.

The quarterly exposure rates ranged from 12.7 mR/Std.0tr. to 27.8 mR/Std.0tr. and the location with the highest annual average vas Location No. 18, 5 miles 5 from the plant. The highest annual average was 27.03 mR/Std.0tr.

The annual average quarterly exposures for indicator and i control locations in 1987 vete 19.9 22.7 mR/Std.0tr. and 19.131.4 mR/STd.0tr., respectively. There is no significant difference in exposute levels between the indicator locations and the control locations.

Appendix B shows the results of all quarterly environmental T LDs , including the average for each quarter and the average for each location, as well as the annual environmental TLD results. The annual environmental TLD results by location are compared to the sum of each quarterly environmental TLD for each location.

A review of the data shows that there may be some seasonal variation between the average quarterly results for the 1st and 4th quarters, and the 2nd and 3rd quarter. The average quarterly exposure level by location shows some spatial variation at Location No.16. Location No.18, Location No. 21, and Location No. 36. The results were 24.620.7 mR/Std.0t r. ,

27.020.7 mR/Std.0tr., 23.1 1.3 mR/Std.0Tr. and 24.6 1.9 mR/Std.0tr., respectively. These exposure rates appear to be influenced by soil composition.

Comparison of the TLD values with the soil concentrations at Location No. 18 show a good correlation between high exposure rates and high naturally occurring radionuclides detected in the soil.

l

The majority of the annual environ senti l TLDs, which remain -in

'l the field for approximately one yeur show higher exposute levels than quarterly environmental TU ts, which are summed by each quarter-and remain in the field fir caly 13 weeks. The average of the annual TLDs for 1987 va a 88.7s12.8 na/Yr. This value is approximately 11% higher ti;an the annual average quarterly exposure for all locations ii 1987.

The results of the annual environe -

TLDs for 1986 vere not available due to poor packaging vi ,sulted in damage to the TLD valers from veather condition nis area, t

2. FISH r

A total of 18 samples of fish vete collected and analyzed by gamma spectrometry. This collection comprised of 7 species of fish. Only the naturally occurring nuclide " 4n was detected in each sample. Only one sample was detected with the nuclide ka-226. This radionuclide is also natutally occurring.

The major species collected each year, along with other species, have been Freshvater Drum, Valleye and Yellov Ferch.

These species are major recreational and commercial species.

The annual average concentration for K-40 for all locations was 3503s552 pci/Kg (vet). The annual average concentration for K-40 in 1986 vas 3562 503 pCi/Kg. These values are in good f agreement with each other.

The concentration for K 40 ranged from 2700 pCi/Kg to 4410 pC1/Kg. The location with the highest annual average concentration was Location No. 25 which was located 0.6 miles NNV from the plant. The concentration was reported as 3678 pCi/Kg.

The annual average K-40 concentrations for the indicator location and the control location vete 36783 605 pC1/Kg and 3328 429 pCi/Kr, respectively. These values compare very well with each other.

The indicator location, No. 25. has been identified as the sampling location with the highest mean value for K 40 every year except 1984. The control location was identified ss the location with the highest mean value in 1984.

All other nuclides analyzed by gamma spectrometry were reported as the lover limit of detection, with the exception of Ra-226, which was reported as 13312 3 pC1/Kg for the specie Valleye during the October-collection.

t

E

3. SEDIMENT There vere twelve sediment samples collected in 1987, of which four sediment samples vere collected on a special assignment.

The results from these special sediment samples were not included with the avetage values reported for the routine PNPP Radiological Environmental Honitoring Program. However, the ,

results from these special sediment samples are included in this report f or comparative analysis.

The majority of the results indicate the presence of naturally occurring radionuclides. The most predominant radionuclides were K-40, Ra-226 and Ra-228. These radionuclides have been detected in most sediment samples since 1981. Other naturally occurring radionuclides that have been detected.in sediment samples on s less f requent basis in 1987 vere Be-7 and Th-234.

The annual average concentrations for K 40, Ra-226 and Ra-228 for all locations in 1987 vere 15362e2055 pCi/Kg, 10212137 pC1/Kg, and 988293 pCi/Kg, respectively. These values compare reasonably well with those annual average concentrations for all locations in 1986 for K-40 Ra-226 and Ra-228 vhich vere 134992 4121 pC1/Kg, 8313274 pCi/Kg, and 7852250 pCi/Kg, respectively.

The pre-operational average concentration for K-40 for all locations was 13317 3957 pCi/Kg. The operational average concentration for K-40 appears to agree well vith the pre-operational average concentration.

The' annual average concentrations for K 40 in indicator locations and the control location in 1987 vere 1463331854 pCi/Kg and 175502450 pC1/Kg, respectively. The pattern of activity being higher in the control location than the indicator location was also observed in 1986.

The annual average concentrations for Ra-226 in indicator locations and the control location vere 975;128 pCi/Kg and 1160210 pC1/Kg, respectively.

For Ra-228, the annual average concentrations in indicator locations and the control location vere 992$110 pCi/Kg and l 9773 5 pCi/Kg, respectively.

l Other radionuclides that have been detected in sediment samples vare Cs-137 and Co-60. These radionuclides are fission

! products and activation products, respectively. The radionuclide Cs-137 has been detected in most sediment samples since 1981.

- l

~ _ .-

.)

l

. i The annual average concentrations for Cs-137 for all locations in 1987 vas 355 289 pC1/Kg. This concentration is in good agreement with the annual average concentiation for Cs-137 for all locations in 1986 which vas 3213221 pCi/Vg. l The pre-operational average concentration for Cs-137 for all locations was 2431155 pCi/Kg. Again, the operational average ,

J concentrations appear to be in good agreem*nt with the pre-operational concentrations.

i The annual average concentration for Cs-137 has fluctuated videly. This fluctuation is illustrated in the annual average concentrations for all locations reported in 1982, which was 3653190 pCi/Kg, and in 1984, which was reported as J 79315 pCi/Kg. The year in which the lovest annual average concentration was reported only 2 samples out of eight vere detected for the radionuclide Cs-137.

The annual average concentration of Cs-137 in sediment samples in 1987 from indicator locations and the control location vere 177+78 pCi/Kg, and 799+7, tespectively. The radionuclide

~

Cs-137 seems to follov the same pattern observed with the naturally occurring radionuclide K 40 which showed the control location having a higher annual average concenttation than the indicator locations. This pattern was also observed in 1986.

The radionuclide Co-60 has been detected in some samples during 1981, 1985, and 1986, and again in 1987. The radionuclide Co-60 was detected in only one sample in 1987. The activity was 73 f 3 pCi/Kg. The radionuclide Co-60 vas not detected in sediment samples from 1982 thru 1984.

Several additional sediment samples vere taken several miles from.the most eastern sediment sampling location and the most vestern sediment sampling location 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 vaste 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 vest or east of PNPP.

The results of this special sample collection showed that the radionuclide Co-60, as vell as the tadionuclide Cs-137, was found in these samples. One sample east of the plant and one sample vest of the plant showed Co-60 activity slightly above the lover limit of detection which vas-50 pCi/Kg. The activities were 56 pC1/Kg and 58 pCi/Kg, respectively.

The radionuclide Cs-137 vas detected in all samples and ranged from 243 pCi/Kg to 581 pC1/Kg.

It was inferred fron these tesults that no large buildup of Co-60 exists around the plant. Again, the radionuclide Co-60 has been detected during the pre-operational period and continues to be detected infrequently in sediment during the operational period. The source of this Co-60 can not be readily determined.

The results f or Cs-134, Sr-89 and Sr-90 in sedir.cnt vere reported as the lover limit of detection.

ale A total of 364 samples vere col'lected in 1987 for each air particulate and mit iodine medium. Alt particulate filters and air tod'ne cartridges vete analyzed for gross beta and by gamma spectrometry weekly, respectively. The air particulate filters vere com;>osited by location and analyzed quat terly by gamma spec t r or.e t t y .

The annual average gross beta concentration found on particulate samples for all locations was 15.81 E-03 e4.94 E-03 pC1/Cu.M. This was a decrease of approxiantely 20% from previous annual average gross beta concentretions reported between 1982 and 1986. The annual average gross beta concentration reported in 1986 was approximately 44% higher than the values reported for this year. It is important to note that the annual average gross beta concentraticn reported for 1986 was influenced by the Chernobyl fallout that occurred from t:ay 5, 1986 thru June 11, 1986.

The pre-operational average gross beta concentration for all locations was 19.44 E-03 6.87 E-03 pC1/Ou.M.

The gross beta conu f iation ranged from 10 E-3 pCi/Cu.M. to 31 E-3 pCi/Cu M. for all locations. The location with the highest annual average concentration was Locr. tion No. 7 apptoximately 0.6 miles NE from the plant. The highest annual average concentration was 16.22 E-03 pCi/Cu.H.

The annual average gre s beta concentrations for all indicator locations and the control location in 1987 vere 15.86 E-03 4.98 E-03 pci/Cu.M. and 15.53 E-03 24.66 pCi/Cu.M.,

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

The radionuclide Be-7 was detected in all composite air samples. The annual average concentration for all locations

.vas 69.3 E-03 15.1 E-03 pci/Cu.M. The annual average ,

concentration for all locations in 1986 was 78.21 E-03 214.89 E-03 pC1/Cu.M. The pre-operational average concentration for Be-7 for all locations was 70.9 E-03 320.7 E-03 pCi/Cu.M.

These concentrations are in good agreement with each other and with previous historical concentrations.

l

- _ _ - _ _ - _ _ _ - _ _ - __ -_- ___ ___ __ __ )

.i The Be-7 concentration ranged from 40 E-03 pC1/Cu.M. to 100 .)

E-03 pC1/Cu.M. for all locations. The location with the highest annual average vas Location No. 7, approximately 0.6 miles NE from the plant. The highest annual average concentration was 72.5 E-3 pCi/Cu.M.

The annual average Be-7 concentration for 911 indicator locations and the conttol location in 1907 vere 69.2 E-03 214.4 ,

E-03 pC1/Cu.M and 70.0 E-03 318.7 E-03 pC1/Cu.M., respectively.

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

-The radionuclides Cs-134. Cs-137 and 1-131 vere reported as the lover limit of detection.

4

5. VATER A total of 44 vater samples vere collected and analyzed for gross beta activity, tritium, and strontium, and by gamma spectrometry in 1987. During each quarter, strontium analyses were performed on water samples, with the exception of samples collected in the third quartet of 1987. These samples vere inadvertently omitted from strontium analysis. A total of 15 vater sa.$ples were composited in 1987 and analyzed for tritium.

The annual averaFa gross heta activity for vater for all locations in 1987 vas 6.732.6 pCi/L. The annual average gross beta activity in 1986 was 6.923.5 pC1/L. The pre-operational aserage gross beta activity for all locations was 5.2633.39 pC1/L. The values are in good agreement with each other. There appears to be some variation in gross beta activity reported between the current vendor laboratory and the old vendor laboratory. An investigation of this variation indicated that one of the vendor laboratories had a much shorter count time when compared to the other vendor laboratory. It is plausible that this factor may have contributed to the vide variation in gross beta results for vater, The gross beta activity ranged from 4.33 pCi/L to 16 pC1/L for all locations and Location No'. 34 was identified at the location with the highest annual average gross beta activity.

This activity was reported as 7.14 pCl/L.

The annual average gross beta activities for vater for indicator locations and the control location in 1987 vere 6.632.5 pC1/L and 6.9 2.8 pCi/L, respectively. There appears to be no significant deviation between indicator and control locations.

l l l l

4 The radionuclide Sr-90 vas detected in two out of eleven vater samples analyzed for strontium-89 and strontium-90. This activity was detected in sample Location 828 and Lotetion $36 during November's collection. The results were 1.820.5 pCi/L an 1.920.5 pCi/L, respectively. The lover limit of detection for strontium-90 was 1.0 pCi/L. No positive activity was detected in samples analyzed for strontium-89.

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

Vater samples analyzed for gamma isotopic shoved no positive activity above the lover limit of detection, with the exception of K-40, which was detected in only eight out of ;he forty-four samples collected and analyzed in 1987. The K-40 activity ranged from 50 pCi/L to 195 pCi/L. This radionuclide is naturally occurring in the environment.

All vater samples analyzed for tritium were reported as the lover limit of detection.

6. MILK During 1987, a total of 97 milk samples were collected and

' analyzed for iodine by chemical separation, gross beta activity and by gamma spectrometry. A total of 23 samples from the 97 samples were analyzed for strontium.

The most predominant radionuclide detected by gamma spectrometry was K-40. This radionuclide is naturally occurring and was detected in all milk Ja?ples.

The annual average concentration of K-40 in milk for all locations in 1987 was 16771271 pCi/L. The pre-operational average concentration was 15372273 pCi/L. This concentration is in good agreement with the annual average concentration reported in 1986, which was 16492268 pCi/L, but slightly higher than the pre-operational average concentration.

A comparison of the pre-operational average concentrations for cov milk and goat milk, snovs that goat milk contains higher K-40 concentrations than cov milk. The pre-operational average concentrations vere 1655 234 pCi/L and 13202197 pCi/L, respectively. Goats appear to have a higher bioaccumulation rate than covr. This probably accounts for the difference in K-40 concentrations as well as for any other radionuclide that may take residence in these animals.

.4 "

1The K 40 concentration ranged from 712 pci/L to 2140 pCi/L for all locations. The location vit' the highest annual average-concentration was Location No. 31 which is located 1.4 miles ESE f rom the plant. The highest annual average concentration was reported as 1904 pCi/L.

-The annual average concentrations of K 40 for indicator and the control location in 1987 vere 1731t269 pCi/L and 14554130 pC1/L, respectively. The concentration at the control location was approximately 16% lover than the indicator locations. This smaller concentration detected in the control location can be attributed to lov concentration of K 40 for cov

- milk. The indicator locations include several goat milk samples and one cov milk sample, llistorically, the annual average K-40 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.

Several milk samples analyzed for strontium-89 and strontium-90 detected positive activity above the lover limit of detection.

This activity ranged from 7.6 pC1/L to 1.0 pC1/L'for strontium-90. The radionuclide was detected in 15 out of 23 milk samples in 1987, s

The strontium-90 activity ranged from 0.47 pCi/L to 3.5 pCi/L prior to 1987. Milk samples have been analyzed for radiostrontium since 1983. Again, it appears that the strontium levels detected in milk originate from the nuclear weapon fallout.

The radionuclide strontium-89 was detected in only two milk -

samples and the activity ranged f rom 12.9 pCi/L to the detection level of 5.0 pCi/L. It is important to note that the milk. sample that-reported the activity of 12.9 pC1/L-had c two sigma value'of 28.6 pC1/L vhich makes this level of activity questionable. The other sample was reported as 5.11 1.2 pCi/L

-- which was just above the detection level of 5.0 pCi/L_for strontium-89. This radionuclide was detected in only one location (Location No. 52) on 08/10/87 and 08/24/87, respectively.

Further investigation by PNPP shoved that this activity was not released from the plant. It's origin may be from vorld-vide fallout and possibly cross conttilnation at the vendor laboratory. The-latter assumption is discussed in the Quality Assurance section of this report.

• Hilk samples analyzed for iodine vere reported as the lover limit of detection. The vendor laboratory had difficulty an extracting iodine from several milk samples in 1987. These results were reported as 99.99 in Appendix A. The value 99.99 I

is a default value used tn indicate missing data. The probable cause of this difficulty in extracting lodine nay arise from- '

the replacement of formalin with sodium bisulfite as a preservative for milk samples. .The difficulty in extreeting

' iodine during column ex ange occurred at the same time the replacement was made at PNPP.

7. VEGETATION Vegetation samples included grass end leaves. These samples were collected in conjunction with the food product (produce) samples and supplement the collection of milk samples. A total of 67 samples vere collected and analyzed by gamma spectrometry in 1987.

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

Another naturally occurring radionuellde that was detected in a fev leaf samples was Ra-226. This radionuclide was not detected in any grass samples.

The annual average aciivities for K 40 and Be-7 for all locations in 1987 vere 558811743 oci/Kg and 20471 1802 pCi/Kg, respectively. The range of values for these radionuclides vere f rom 12,800 pCi/Kg to 1746 pC1/Kg for K 40 and 10,900 pCling to 240 pCi/Kg for Be-7.

- The ai nual average activity f or K 40 f or all locations it. 1986 was 51J4 1816 pCi/Kg. This annual average value compares very well with the annual average value for 1987. The annual average activity for be-7 for all locations in 1986 vas 292312126 pCi/Kg. This value appears tr be higher than the value reported for 1987, but it is within the range of activity detected in 1987.

The annual average activities for the indicator locations and the control location in 1987 fot K 40 were 560621829 pC1/Kg and 552111367 pC1/Kg, respectively.

The annual average activities for the indicator locations and the control location in 1987 f or Be-7 vere 1978t 879 1 pCi/Kg and

-22911 1472 pC1/Kg, respectively.

There was no positive activity above the detection limit for the nuclides Cs-134, Cs-137, I-131 and 4 All results were ,

reported as the lover limit of detection.

8. FEED AND SILAGE / FOOD 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 when collecting produce. Also, feed, hay, and silage-samples were collected from six milk sampling locations. These samples were collected

-1C-d

,,-wn , n -w-o v-e v ~m w- n- w,v2weem -nem m m e-' u-,es~-me- rwwe rswe ~ w* e

2 annually. Each sample vas analyzed by gamma spectrometry.

The most predominant radionuclide found in each produce sample vas the naturally occurring tadionoclide R-40. The average K-40 concentration foi all locations was 19352734 pC1/Kg. The activity ranged from 848 pCi/Kg to 3130 pCi/Eg. The average concentrations for all indicator locations and the control location vere 1460 367 pCi/Vg and 2727 455 pC1/Kg, respectively.

Comparison of the 1987 K-40 average concentration foi all locations to 1986 K 40 average concentration for all locations in produce, shovs that the 1987 K-40 concenttations were approximately a factor of 1.7 lover. The range of K-40 activity in produce reported in 1987 indicates that the average concentration can vary videly from year to year.

The major radionuclide detected in feed, hay and silage vss the na!9 tally occurring radionuclide K-40. This nuclide was detected in all samples. The average concentration for all locat'ons in 1987 was 1118126259 pCi/Kg. The average concentrations for all indicator locations and the control location vere 1181636546 pCi/Eg and 76852 2125 pCi/Kg, respectively.

These results ate in good agreement with those K-40 average concentrations for feed and silage reported in 1986 at PflPP .

Other naturally occurring radionuclides detected with cositive activity were Be-7 and Ra-226. These radionuclides vete detected in only a fev samples and have been detected in samples collected in 1986.

The radionuclide Cs-134, Cs-137 and 1-131 vere reported as the lover limit of detection.

9. SOIL A total of 30 soil samples were collected and analyzed for strontium and by gamma spectrometry in 1987. The major radionuclides detected in these saaples were naturally occurring, with the exception of the radionuclide Cs-137. This radionuclide is a fission product. The naturally occurring radionuclides detected vere K-40, Be-7, Ra-226 and Ra-228.

The annual average concentration of the naturally occurring radionuclides in 1986 and 1987 for all locations were as follows:

RADIONUCLIDE .1987 VALUE 31 SIGMA ,1086 VALUE 11 SIGMA K-40 1242013134 pel/Kg 12327e3086 pCi/Eg-Be-7 467 195 pCl/Kg 0291133 pCl/Kg -

Ra-226 740 249 pCi/Kg 7722 294 pCi/Kg Ra-228- 751;333 pCi/Kg 841s321 pCi/Kg 5

These values appear-to be in good agreement with each other, vith the exception of Be-7. The concentration of Be-7 in 1987 tends to be slightly lover than the concentration reported in 1986. The radionuclide is a naturally occurring radionuclide that originates from the atmosphere and deposits onto the soil.

The annual average concentration of the naturally occurring radionuclides in 1987 for indicator locations and control locatinns vere as follovst

'RADIONUCLIDE INDICATOR CONTROL K-40 12107:3067 pC1/Kg 1523332182 pCi/Kg Be-7 464 2 203 pci/Kg 4852 115 pci/Kg Ra-226 -719:254 pCi/Kg 927t 32 pci/Kg Ra-228 706:313 pCi/Kg 11624196 pCi/Kg The control values show slightly higher annual average concentrations than the indicator values for K-40, Ra-226 and Ra-228. It-has l'een observed that the results from samples taken at various locations differ significantly. This difference can be attributed to soil composition at the various locations. The radionuclide Be-7-vas not influenced by soil composition as greatly as those radionuclides that originate in the ground.

The radionuclide Cs-137 was detected in most samples in 1987.

The annual average concentration for all locations was 4633279 pCi/Eg. The annual average concentration in 1986~ for all locations was 569 551 pCI/Fg. These values are in agreement with each other. ,

The annual average concentrations for Cs-137 for indicator locations and the control location vere 408 254 pC1/Kg and 841285 pCi/Kg, respectively. Again, the higher concentration observed in the controi vas due to soil composition. This difference was also observed in 1986.

The results from Cs-134, Sr-89 and Sr-90 analyses were reported as the lover limit of detection.

10. ~SNOV-A total of 21 snow samples vere collected in 1987. These samples vere collected immediately after snowfall or within se sral days of snowfall. Each sample vas analyzed for gross

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

beta aciivity, tritium and by gamma spectiometry.

The average gross beta activity for all locations in 1987 was 7.373 2.87 pCi/L. The average gross beta activity for all locations in 1986 and 1985 vere 8.74 32.76 pCi/L and 10.01 7.21 pCi/L, respectively. The historical results appear to be in agreement with the results for gross beta activity reported for 1987.

The gross beta activity ranged tiom 4.3 pCi/L to 16.35 pC1/L for all locations and the location with the highest annual average gross beta activity was identified as Location No. 35.

This location is approximately 0.6 miles E of the plsnt and the activity was reported as 10.37 pCi/L.

The average gross beta activities for indicator locations and the control location in 1987 vere 7.35 '.97 pCi/L and 7.4632.23 pci/L respectively. There appears to be no significant diftetence between the indicator locations and the control location.

The results from samples analyzed for tritium and for gamma isotopics were reported as the lever limit of detection. No positive activity was detected in these samples by these analyses, r VI. LOVER LIMIT OF DETECT 1nN There vere four samples that failed to meet the NRC Lover Limit of Detection Requirement. The sample media, analyses, date, location, reported value and NRC limit ate reported as in11ovs:

ANALYSES DATE LOCATION REPORTED VALUE NRC VALUE MEDIA AIR IODINE 870819 4 0.18 0.07 MILK IODINE 871012 31 1.1 1.0 MILK GAMMA 870727 29 18.0 15.0 MILK GAMMA 870727 57 19.0 15.0 The increase in the lover limit of detection for air iodine was due to a loss of power in the air sampler. The increase in the other samples was due to poor chemical yleids and counting methods.

VII. LAND USE CENSUS The 1987 Land Use Survey was conducted from June 8th to July 1st.

The purpose of this survey was to determine the use of land within the 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.

L I.

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

The garden identifi2d with the most conservative (highest) D/0 value (Deposition rate) as a function of distance with respect to other sectors was 3119 Parmly Rd. This garden vas also identified as the nearest garden with the highest deposition value in 1985 and 1986.

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

The residence at 3140 Center Rd. vas identified as having the most conservative X/0 value (Dispersion rate) as a function of distance vith respect to the other sectors.

This is a different resident when compared to the 1986 PNPP Land Use Survey. The 1987 PNFP Annual land Use Report uses the disper sion rates, X/0. as a function of distance, whereas previous reperts used the dispersion rate as a function of sector only. The previous annual land use reports selected the neatest resident based on the sector with the most conservative dispersion rate. The 1987 annual 3and use report uses the dispersion rate as a function of sector and distance. This method provides a more accurate assessment of dose to a particular receptor point from any potential gaseous releases.

The dispersion and deposition rates were selected from the PNPP Offsite Dose Calculation Manual (ODCH).

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

The location at 3291 Parmly Rd. for milk-producing animals was identified as having the most conservative deposition rate as a function of distance with respect to other sectors. This location was also Identified in the 1986 and 1985 surveys.

The other milk-producing animals identified in the survey by sector and distance are shown in Table 6.

Non-dairy animals, such as heifers, beef cattle or beef covs, 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 pathway is the a ir-grass-animal-man. Table 7 shows these animals by direction, location, deposition value, and number / type of animal.

The agricultural grovers are depicted in Table 8. They are listed by name, address, city, sector / distance, deposition value, and type of grover. No ranking of these grovers 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 s

y

. . l

- scattered over the Lake County area. _The deposition'value assigned to these locations only represents the point at which 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 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.

VIII. QUALITY ASSURANCE The Quality Assurance Program includes the results of the CPA Cross-Check Intercomparison Program and the Environmental TLD Quality Control Spiking Program depicted in Table 9 and Table 10, respectively.

The vendor laboratory increased the number of EPe samples _ analyzed in 1987, with respect to those samples analyzed in 1986, by 55%. A total-of 20 EPA samples fell outside the EPA Control Limit. This represents 25.3% of the total EPA samples. The EPA samples falling outside this control limit indicates that the vendor laboratory did not have control ever the process for these particular EPA samples.

The remaining EPA samples vere within the EPA Control Limit.

The vendor laboratory reported 21.6% of the EPA samples outside the EPA Control' Limi t in 1986.

A c1cser review of those EPA samples that were not in a state of control indicated that ' out of 8 EPA samples requiring strontium-90 analysis vere not withis. the EPA Control Limit and one sample vas not reported to the EPA. These samples constituted 15% of the total number of samples that fell outside the EPA Control Limit.

The remaining analyses that did not fall within the EPA Conttol Limit vere: . Gamma Spectrometry (35%), Radium (20%), Tritium and Iodine (10%), and Cross Alpha and Potassium extraction (15%). A total of four samples were not reported or no data was provided.

The vendor laboratory's poor performance with strontium analysis for EPA samples may be reflected in those field samples (i.e. milk, water, and soil) collected, analyzed, and reported in 1987.

A review of'the spiked environmental TLDs in 1987 shows that the sum of the average performance value and the-standard deviation for each spiking period did not exceed the performance criteria of 0.3. The '

environmental TLDs are performing satisfactorily.

~

L i

l .

IX. CONCLUSION A reviev of the environmental TLDs employed rallation in the field exposutes shoved to the no public.

significant increases in direct Several environmental TLDs displayed consistently higher exposureThis pattern was obse levels than other environmental TLDs.

be influenced by soil composition.

Several environmental samples, such as milk, vat (r and sediment, shoved positive activities above minimum detection levels on several These radionuclides vere Cs-137, Sr-90, and Co-60, occasions.

respectively. These radionuclides are not normallyItdetected or are was concluded detected on an infrequent basis in t.sese samples. rather from that these activities vere not of plant origin, but nuclear fallout.

It is important to nnte that some samples such as milk, sediment and soil tend to have appreciable amounts of radioactivity Hilk samples are above shoving a detection levels on a frequent basis. and soil consistent pattern of detecting 51-90, vhereas, sedimentThese radionuclides show a consistent pattern of detecting C.s-137.

are fission products that have been detected in the preoperational period of the PNFP Radiological Environmental Monitoring Program and most likely originate f rom the f allout of nuclear weapon testing.

Finally, all environmental samples, of one type of sample media or another, have detected naturally occurring radionuclides such asThe concentratio Be-7, K-40, Ra-226 and Ra-228. in appear to be in good agreement with other concentrations The consistency among naturally reported 1986 and in previous years. the occurring radionuclides over the years tend to indicate that vendor laboratory has performed, in general, satisfactorily.

the Perry Nuclear Power Plant Therefore, it can be concluded that did not have a radiological impact on the environment during 1987, 1

l

.I i

E i .

1 t

k

'h - ----- _