ML20245E880

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Trojan Nuclear Plant Operational Environ Radiological Surveillance Program 1988 Annual Rept
ML20245E880
Person / Time
Site: Trojan File:Portland General Electric icon.png
Issue date: 12/31/1988
From:
PORTLAND GENERAL ELECTRIC CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
PGE-1006-88, NUDOCS 8905020173
Download: ML20245E880 (58)
v • d • e


Text

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9 4

Trojan Nuclear Plant u OPERATIONAL ENVIRONMENTAL RADIOLOGICAL SURVEILLANCE PROGRAM 1988 ANNUAL REPORT PORTLAND GENERAL ELECTRIC COMPANY- l I

i PGE 1006-88

PGE-1006-88.

):

TROJAN NUCLEAR PLANT OPERATIONAL ENVIRONMENTAL RADIOLOGICAL SURVEILLANCE PROGRAM January through December 1988 May 1989 Prepared by PORTLAND GENERAL ELECTRIC COMPANY With Analyses by TMA/EBERLINE ALBUQUERQUE,.NEW MEXICO l 1

TROJAN NUCLEAR PLANT I OPERATIONAL ENVIRONMENTAL RADIOLOGICAL SURVEILLANCE PROGRAM CONTENTS Section Title Page ABSTRACT . . . . . . . . . . . . . . . . . . . . . -

1.0 INTRODUCTION

. . . . . . . . . . . . . . . . . . . 1-1 2.0 SAMPLING AND PROGRAM PROCEDURES. . . . . . . . . . 2-1 1

2.1 SAMPLING LOCATIONS . . . . . . . . . . . . . . . . 2-1 2.2 SAMPLING PROCEDURES. . . . _ . . . . . . . . . . . . 2-1 2.2.1 Air Particulate and Radioiodine. . . . . . . . . 2 2.2.2 Ambient Radiation Measurements Using TLDs. . . . 2-2 2.2.3 Food Crops . . . . . . . . . . . . . . . . . . . 2-2 2.2.4 Milk . . . . . . . . . . . . . . . . . . . . . . 2-2 2.2.5 Well Water . . . . . . . . . . . . . . . . . . . 2-3 2.2.6 Drinking Water . . . . . . . . . . . . . . . . . 2-3 2.2.7 Shoreline Soil . . . . . . . . . . . . . . , . . 2-3 2.2.8 Aquatic Animal . . . . . . . . . . . . . . . . . 2-4 i 2.3 YEARLY AGRICULTURAL SURVEY WITHIN S-MILE RADIUS 1 0F TROJAN. . . . . . , . . . . . . . . . . . . . . 2-4 l I

) 3.0 ANALYTICAL PROCEDURES AND COUNTING METHODS . . . . 3-1 3.1 AWALYTICAL DETECTION LIMITS AND COUNT RATE ERRORS. 3-1 l

3.2 AIR PARTICULATE . . . . . . . . . . . . . . . . . 3-1 j 3.3 RADI0 IODINE. . . . . . . . . . . . . . . . . . . 3-2

.1 1

3.4 DRINKING AND WELL WATER. . . . . . . . . . . . . . 3-2 3.5 SHORELINE SOIL . . . . . . . . . . . . . . . . . . 3-2

)

3.6 FISH, INVERTEBRATES, AND FOOD CROPS. . . . . . . . 3-2 3.7 MILK . . . . . . . . . . . . . . . . . . . . . . . 3-3  !

3.8 AMB'IENT RADIATION MEASUREMENTS . . . . . . . . . . 3-3

)

3.9 QUALITY CONTROL. . . . . . . . . . . . . . . . . . 3-3 3.10 REFERENCES FOR ANALYTICAL PROCEDURES . . . . . . . 3-4

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TROJAN NUCLEAR PLANT OPERATIONAL ENVIRONMENTAL RADIOLOGICAL StTAVEILLANCE PROGRAM CONTENTS Section Title Page 4.0 RESULTS AND. DISCUSSION . .. . .. . . . . . . . . 4-1 4.1 SAMPLES FROM THE TERRESTRIAL ENVIRONMENT , .. . . 4-1 4.1.1 Air Particulate and Airborne I-131. . . .. . . 4-1

-4.1.2 Food Crops . . . . . .. . ... . .. . . .. . 4-1 4.1.3 Well Water . . . . . .. . . .. .. .. . . . . 4-2 4.1.4 Milk . . . . . . . . .. . ... . . . . .. . 4-2 4.1.5 Ambient Radiation Levels . . . . . . . . . .. . 4-2 4.2 SAMPLES FROM THE AQUATIC ENVIRONMENT . . . . .. . 4-3 4.2.1 DrinkinE Water Samples . . . .. . . . .. . . . 4-3' 4.2.2 Shoreline Soil . . . . .... .. . . ... . . 4-4 4.2.3 Fish . . . . . . . . . . . . .. .. . . . .. . 4-4 4.3

SUMMARY

OF RESULTS . . . . . .. . . . . . ... . 4-4 5.0 COMMENTS ON AND TERMS USED IN DATA TABLES. . . . . 5-1 l

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11

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TROJAN NUCLEAR PLANT OPERATIONAL ENVIRONMENTAL RADIOLOGICAL SURVEILLANCE PROGRAM TABLES Number Title 2-1 Sampling Locations and Frequency by Type 2-2 1988 Land Use Census 3-1 Program Analyses and Reported Detection Levels 3-2 1988 U. S. Environmental Protection Agency - Analysis Laboratory Intercomparison Program 3-3 1988 Quality Control Analyses Summary

, 4-1 Average Gross Beta Concentrations for Air Particulate 4-2 Radiological Environmental Monitoring Program Summary 5-1 Airborne Iodine-131 and Gross Beta in Air Particulate Filters (Weekly Collections) 5-2 Summary - Gross Beta in Air Samples 5-3 Gamma Emitters Concentrations in Air Particulate Filters 5-4 Radioactivity in Food Crops 5-5 Radioactivity in Well Water 5-6 Radioactivity in Milk 5-7 Ambient Gamma Radiation Levels for 1988 5-8 Radioactivity in Drinking Water 5-9 Radioactivity in Shoreline Soil 5-10 Radioactivity in Fish / Invertebrates FIGURES Number Title  ;

2-1 Sampling Locations 2-2 Sampling Locations (Detail) iii i

b l

ABSTRACT

'l This report presents the data obtained through the analyses of environ- i

)'

mental samples collected through the Portland General Electric Trojan Nuclear Plant Environmental Radiological Surveillance Program for the j period January 1, 1988 through December 31, 1988.

In several milk samples, levels of radioactivity observed during 1988 l were higher than years prior to 1986. This higher. level of radio-  !

l activity was due to biota uptake of fallout radioactivity dispersed over Oregon from the April 1986 accident at the Chernobyl Nuclear Power Station in the Ukraine, USSR. In no case did radioactivity attributed to l

the Trojan Nuclear Plant exceed the Reporting Levels of the Trojan  !

Radiological Technical Specifications.

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1.0 INTRODUCTION

The Trojan Nuclear Plant, a 1130 megawatt-electric pressurized water reactor, first achieved criticality on December 15, 1975. This report presents the analytical data from the Environmental Radiological surveillance Program with appropriate interpretation for 1988.

The analytical contractor during this period has been TMA/Eberline,-

Albuquerque, New Mexico. In comparing data obtained during this period with those from previous periods, care should be taken to ensure that differences in procedures between the several contractors are considered. This is particularly true for'" gross beta" measurements for which the use of different reference nuclides may produce appropriately significant differences in gross beta concentrations.

Information concerning the Environmental Radiological Surveillance Program prier to this period may be found'in earlier reports.

1 l

1-1

2.0 SAMPLING AND PROGRAM PROCEDURES 2.1 SAMPLING LOCATIONS Sixty-seven (67) sampling locations were used in the Environmental Radiological Surveillance Program in 1988, 66 on land, and 1 in the Columbia River. This is the same number of sampling locations in use at the end of 1987.

During 1988, there were no new sample locations added or any 1987 sample locations deleted. At the beginning of the fourth quarter, an air monitor and ambient radiation monitor location (II) was moved from a steep ridge to its previous location. In addition, two other ambient radiation monitor locations (56 and 62) were moved from river pilings to shore locations at the beginning of the first quarter. These monitors were moved due to personnel safety considerations. These new locations are in the same direction as the previous locations, plus their radial distances from the Plant were not significantly changed.

The sampling locations are shown in Figures 2-1 and 2-2. Tabin 2-1 includes a listing of the sites, their distance from Trojan, and the type and frequency of sample collection.

2.2 SAMPLING PROCEDURES 2.2.1 AIR PARTICULATE AND RADIOIODINE Air particulate and radiciodine sampling was performed weekly. The samples were gathered with a low-volume air sampling device which is designed to draw a constant flow rate regardless of the pressure drop across the filter. The sampling devices were set to maintain 1 cfm. The sample pump, metering devices, and timer were in a weatherproof housing.

The filter and cartridge were located in an inlet parallel to and about 1 meter above the ground. Glass fiber filters were used to collect particulate matter. Activated charcoal cartridges were used to collect I radioiodine.

2-1  ;

The glass fiber filter was removed from the air sampler and placed in a 2-inch plastic petri dish. The activated charcoal carteidge was removed at the same time. Air flow readings and other data required to compute the levels of radioactivity were recorded and submitted to the analysis laboratory along with the samples.

2.2.2 AMBIENT RADIATION MEASUREMENTS USING TLDs j l

Thermoluminescent dosimeters (TLDs) were placed for field exposure and collected on a quarterly frequency. The TLDs were placed about 1 meter above ground level in plastic bags. The time of collection, the exposure period, and any abnormal conditions such as moisture in the holders, 1

l damage done by animals, etc, were recorded when the TLDs were retrieved.

l Care was taken to minimize exposure to the TLDs between collection and t delivery to the laboratory. The TLDs were transported to the field in lead boxes to ensure low background levels. Control TLDs were carried with the field TLDs during collection and delivery.

I i j 2.2.3 FOOD CROPS

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Representative samples of tuberous and foliar fruits and vegetables were collected during local harvesting. Samples of leafy vegetables were  ;

collected dut.ng each of the three summer months of June, July, and I

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August. Samples were sealed in plastic bags following collection, taking (

care not to include any soil or foreign materia!.. The sample site identification number, the date collected, the sample type, and the f amount obtained were recorded on the data collection forms.

l 2.2.4 MILK Milk samples (cow or goat) were collected monthly during January, February, and December with twice montM y collections during the other months. Milk was collected in polyethylene bottles (2 gallons for cow dairy and 1 gallon for goat dairy). Prior to shipment of samples to the l

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2-2 l

i analysis laboratory, an ion exchange resin was used to concentrate any iodine present to improve detection sensitivity. The whole milk (after iodine removal) and resins were labeled and collection data forms prepared specifying sample site, date collected, sample type, and volume obtained.

2.2.5 WELL WATER Well water was collected quarterly either from the tap that leads off the pump or directly from the well itself. At sites with faucets the line was purged for 1 minute prior to collection. Sixty milligrams were drawn from the 1-gallon sample for tritium analysis. The remainder of the sample was put in a 1-gallon polyethylene bottle and acidified with concentrated HC1. The bottles were securely sealed, labeled, and collection data forms prepared specifying site, date collected, volume, and sample type.

2.2.6 DRINKING WATER Honthly composite samples of municipal drinking water were collected for Rainier (Sample Location 2) and St. Helens (Sample Location 66) at their respective intake structures on the Columbia River. Rainier is downstream of the Trojan Nuclear Plant while St. Helens is upstream. At each location, a compositing sampler took a sample every 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and aliquots of this monthly composite were sent for analysis. From these aliquots, 60 milliliters are sent for tritium analysis and a 1-gallon polyethylene bottle is acidified with concentrated hcl and rent for the other analyses. The bottles were securely sealed, labeled, cud collection data forms prepared specifying site, date collected, volume, and sample type.

2.2.7 SHORELINE SOIL Shoreline soil samples of about 1 quart in volume were taken twice a year. The samples were taken from a 1 square foot area with the 2-3

vegetation and large rocks removed before cample collection. The soil sampling dept.h varied between 1 to 4 inches and the soil was passed through a No. 6 sieve before placement in the plastic collection bottles. The sample site identification number, date collected, and volume obtained were recorded on the collection data forms.

2.2.8 AOUATIC ANIMAL Aquatic animal sampling was performed semiannually. Both indigenous and anadromous species of fish and invertebrates such as crayfish were acquired by seining, netting, or trapping. The radioacti' ity analysis was performed on fish muscle or crayfish muscle samples. If needed for a particular sampling location, the fish nuscle sample may be a mixture of several panfish species. The sample site identification number, the date collected, the fish species, and the amount obtained were recorded on collection data forms.

2.3 YEARLY LAND USE CENSUS WITHIN 5-MILE RADIUS OF TROJAN The annual land use census within a 5-mile radius of Trojan Nuclear plant was performed during August 1988. Identified by this census were the locations of the nearest milk animal (cow and goat), meat animal, residence, and vegetable garden in each of the 16 meteorological sectors <

within this area. This census was completed by driving the roads within a 5-mile radius of Trojan. Table 2-2 presents the results of the yearly land use census. 1 2-4 l

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. TABLE 2-2 1988 LAND USE CENSUS p NEAREST LOCATION TO TROJAN WITHIN A FIVE-MILE RADIUS l

i Radiation Mileage for Nearest Location j Directional Meat i Sector Residence Carden Milk Cow Milk Goat Animal j N 0.6 0.6 None None None NNE 2.4 2.4 None None 2.7 l

~I NE 1.6 1.8 .None None .None L ENE 2.4 5.0 None None 5.0 E 1.3- 1.6 None None 1.4 ESE 0.8 1.8 None None 1.7  !

SE 2.5 2.5 None None 2.5 SSE 1.4 3.0 None None 3.0 S 1.2 1.4 None None 2.0 SSW 0.9 0.9 None 2.6 1.0 SW 1.5 1.8 None None 1.6 WSW 1.4 1.9 None None 1.9 l W 1.7 2.1 None None 1.7  !

! WNW 1.7 1.7 None None 1.7 l NW 1.2 1.2 None None 1,2 NNW 0.6 0.6 None Not.e 2.0 f

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3.0 ANALYTICAL PROCEDURES AND COUNTING METHODS Samples are analyzed for the various radioactive components by standard radiochemical methods. These methods are equal to, and in most cases, identical with, those of the U. S. Department of Energy [ Health and Safety Laboratory (HASL) Procedures Manual, HASL-300, see references, Section 3.10), or those of the U. S. Environmental Protection Agency (EPA).

Analyses of individual sample types, general methods, and routine ana-lytical sensitivities are discussed below. The analytical program and j

)

sensitivity requirements are given in Table 3-1.

3.1 ANALYTICAL DETECTION LIMITS AND COUNT RATE ERRORS l

l In environmental radiological analyses the dominant known uncertainty is usually the sample count rate. Error teems given in this report are based on this factor since all other analytical uncertainties are relatively small. Uncertainties are calculated by standard methods (HASL-300), and are reported at the 95-percent confidence level (2a).

The lower limit of detection (LLD) is defined as the smallest concentra-tion of radioactive material in a sample or the smallest amount of radia-tion to a dosimeter that will yield a net indication, above system

)

background, that will be detected with 95-percent probability with only 5-percent probability of falsely concluding that a blank observation represents a real signal. Analytical data for samples for which concen-trations are less than or equal to the LLD are preceded by the symbol "<".

3.2 AIR PARTICULATE i

Gross beta concentrations are measured with low background, window-type (0.85 mg/cm in thickness), proportional counting systems. The routine detection limit (LLD) is 0.002 pCi/m for gross beta measurements

assuming a collected air volume of 300 m / week.

)

1 3-1

I

l. L I

Camma iuotopic cualyses are performed with germanium detectors with a 3

  • routine detection limit of 0.05 pCi/m for the gamma emitters.

3.3 RADIOIODINE The charcoal cartridgas used are of the TEDA-impregnated type. The ,

icdine is extracted from the charcoal, chemically separated, and counted

~

as AgI using the low-background beta counters mentioned in Section 3.2 < 1 l which yield an LLD of 0.05 pCi/m .

3.4 DRINKING AND WELL WATER

(.

(

Gross beta analysis of water samples is performed by evaporation of a measured aliquot of the sample, digestic . planchetting of the processed sample and radiometric assay by the low-background beta counters men- .

tioned in Section 3.2, with an LLD of 0.5 pCi/1. Tritium analysis is performed on all water samples to the required LLD of 1000 pCi/1 by liquid scintillation counting. Gamma isotopic analysis is performed ,, ('

using germanium detectors with a routine LLD of 10 pCi/1 per gamma emitting radionuclides.

3.5 SHOPELINE SOIL 4

Samples are oven-dried and results reported based on dry weight. Gamma emitters are measured with germanium detectors with an LLD of 0.1 pCi/g per nuclide. NI .

3.6 FISH. INVERTEBRATES. AND FOOD CROPS Measured amounts of these types of camples are analyzed for gamma emitters by gamma spectrometry with counting times adjusted to provide LLDs at leset as sensitive as those required in Table 3-1 for the ,

appropriate sample type.

b 3-2 i'

l 3.7 MILK f The determination of Iodine-l'1 in fresh milk is based on anion exchange removal of the Iodine-131 followed by radiochemical purification and low background beta counting using the systems descr3 bed in Section 3.2.

The LLD is 0.5 pCi/l or better. Gamma emitters in milk are measured with j germar.ium detectors with an LLD of 10 pCi/l per t.aclide. The analysic

> for Strontium-89 and Strontium-90 is performed on ached samples using a strontium chemical yield and two-separation technique with an LLD of 1.0 pCi/1.

3.8 AMBIENT RADIATION MEASUREMENTS The responsibility for ambient radiation dose measurements resides with Portland General Electric Company (PC$). A total cf 57 field locations were monitored with the dosimeters analyzed quarterly. The field dosimeters used thermoluminescant radiation detection materials (CaF :Dy, 2

TLD-200 chips) with each dosimeter having more then two separate chips or measurement devices. For each field dosimeter, the chips were packed in a plastic foam and sealed in shielded containers. To minimize radiation energy dependence for the TLD-200 chips, the field dosimeters were shielded with a two-element filter of 10 mil tantalum and 2 mil lead as described in the report by Denham, et al (see Section 3.10).

Calibration of the field dosimeters was performed with a Cesium-137 source traceable to the U. S. National Bureau of Standards. Calibration dosimeters were p -pared for each readout of the field dosimeters.

3.9 OUALITY CONTROL Approximately 15 percent of the analyses performed by the analysis laboratory are for quality control purposes. The analysis laboratory participates in EPA, Nuclear Regulatory Commission, and other intercalibration programs. Reports of all quality control analyses 3-3

are presented monthly to PCE. Recults of EPA intercalibrations (for which "known" data are available) are given in Table 3-2. In those cases where discrepant values are obtained, the analysis laboratory performs an investigation to determine the cause and corrective action as required.

Table 3-3 summarizes the intralaboratory quality control results for the year 1987.

During 1981, 1982, and 1984, PGE participated in the Fifth, Sixth, and Seventh International Intercomparison of Environmental Dosimeters. The l results of these participation were presented in the 1982, 1983, and 1984 reports, respectively. By the successful PGE participation in these l

three intercomparison projects, the measurement method for the environ-mental ambient radiation levels has been shown to be appropriate and accurate.

3.10 REFERENCES FOR ANALYTICAL PROCEDURES

1. American Public Health Association, American Water Works Association and Water Pollution Control Federation (1971): Standard Methods for the Examination of Water and Wastewater. Thirteenth edition, pp 583-632; 12th edition, pp 325-352. APRA, 1740 Broadway, New York, NY 10019.
2. Department of Health, Education and Welf are, Public Health Service:

Radiosesay Procedures for Environmental Samples. National Center for Radiological Health (1967), Sec. 1, pp 36-115.

3. Atomic Energy Commission: Regulatory Guide 4.3 (September 1973).
4. Health and Safety Laboratory, Atomic Enc'rgy Commission: HASL Procedures Manual (now known as EHL of the Department of Energy).

HASL, 376 Hudson Street, New York, NY 10014.

5. National Environmental Research Center, Environmental Protection Agency; Handbook of Radiochemical Analytical Methods. Program Element 1HA 325. Office of Research and Development, Las Vegas, NV 89114.
6. D. H. Denham, R. L. Kathren, and J. P. Corley, "A Ca2:Dy Thormoluminescent Dosimeter _for Environmental Monitoring". USAEC Report BNWL-SA-4191 (1972).

3-4

l l TABLE 3-1 PROCRAM ANALYSES AND REPORTED DETECTION LEVELS r

1 1

Program Analysis Reported Detection Limits (LLDl[a]

Air Particulate-gross beta 0.002 pCi/m3 Air Particulate-gamma scan 0.05 pCi/m 3 /nuclide Air Radioiodine 0.05 pCi/m 3 Food crops-gamma scan 0.02 pCi/g/nuclide (wet)

Milk-Iodine-131 0.5 pCi/ liter Milk-Strontium 89/90 1.0 pCi/ liter i

Milk-gamma scan 10 pCi/ liter /nuelide Water-gross beta 0.5 pCi/ liter Water-tritium 1000 pCi/ liter Water-gamma scan 10 pCi/ liter /nuclide Shoreline Soil-gamma scan 0.1 pCi/g/nuclide (dry)

Fish / Invertebrates-gamrr.a scan 0.1 pCi/g/nuclide (wet)

Direct Radiation 0.04 mR/ day

[a] Reported detection level or LLD is defined in Section 3.1.

^

i l

e

~

.(

7ABLE 3d Sheet'3 of 2 1988 U. S. ENVIRONMENTAL PR07U2T10N AGENCY (EPA!

ANALYSIS LABORATORY INTERCvMPARISON PROGRAM Eberline Sample Type Analysis FPA Vaius Value__. . Units i

Water. Pe-'226 4.8010.72 4.7010.26, pCi/1 i Water Ra-228 5.30t0.80 4,3511.40 .pci/1 I Water I-131 26.0i6.0 24.013.60 pci/1 Water Alpha .28.017.0 40.012.0 .pCi/1 ,

Water Beta 72.0 5.0 90.014.0 pC1/1 1 Water PS-226 4.80 0.72 4.5310.15 pCi/1 Water Ru-228 3.6010.54 4.6010.95 pCi/l Water UtNat.) 3.016.0 F.3310.58 pCi/1 i Water Sr-89 16.015.0 9.3310.58 pCi/1 q Water Sr-90 10.011.5 9.3310.58 pCi/1 J Water Co-60 16.015.0 18.711.53- pCi/1 ]

. Water Cs-134 16.015.0- 17.311.23 pC1/1  ;

Water Cs-137 24.014.0 22.011.7 pCi/l l Water Alpha 4 0015.00 3.33i0.60 pCi/l 'l Water Beta 8.0015.00 9.30i0.60 pCi/l I Water Tritium 33271362 3760137 pCi/l  !

Water Sr-89 30.0 t*i.0 29.310.6 pCi/l j Water Sr-90 15.011.5 13.011.0 pCi/1 j Water Co-60 69.0 5.0- 71.315.0 pCi/1 Water 2n-65 9' 7t9.4 93.014.4 pCi/l  !

Water Ru-106 1;'00.5 105t11 pCi/l ,

Water Co-134 64. 4.9 57.512.3 pCi/1 '

Water C3 -13 7 94.0;* 91.313.5 pCi/l l Water U(tJa t. ) 3.016.0 3.710.6 pCi/l Water Alpha 6.015.0 5.3io.6 pCi/1  ;

pCi/1 Water Beta 13.015.0 16.3io.6 Water Tritiur. 62021640 69401260 pCi/1 Water Ra-226 7.6011.14 7.2710.25. pCi/1 Water Ra-228 7.7011.16 8.7310.5 pCi/1 Water Alpha 15.015.0 12.710.6 pCi/1 i Water Ceta (.015.0 5.011.0 pci/1 Water Ra-226 10.911.51 9.9010.53 pCi/1 Water Ra-228 12.4011.86 14.8010.72 pCi/,1 Wate~c Alpha 46.0 11.0 53.312.9 >

pCi/l Water Ra-226 6.4010.96 6.3710.59 pCi/1 Water Ra-228 5.6010.84 6.50io.10 pCi/1 Water U(Nat.) 6.0016.00 6.3310.58 pCi/1 Water Beta 57.015.0 69.712.9 pCi/l Water Cr-89 5.0015.00 4.0010.00 pCi/1 Water Sr-90 5.0011.50 5.0010.00 pCi/l Water Co-60 50.015.0 48.314.5 pCi/1 Water Cs-134 7.0015.00 5.33io.58 pCi/l Water Cs-137 7.0015.00 7.0010.00 pC1/1 Water H-3 5565i557 5982170 pCi/1 Water Sr-89 20.01S.0 19.312.1 pCi/1

i TABLE 3-2 Sheet 2 of 2 i

Eberline i Sample Type Analysis EPA Value Value Units Water Sr-90 20.011.5 18.710.6 pCi/1 q Water Cr-51 302130 294118 pCi/l Water Co-60 15.015.0 15.715.0 pCi/1 )

Water 2n-65 101110 10418 pCi/l l Water Ru-106 195 20 193119 pC1/1 j Water Cs-134 20.015.0 16.7t0.6 pCi/l j Water Cs-137 25.0i5.0 25.710.6 pCi/1 Water Pu-239 10.2 1.0 0.53 0.06 pCi/1 Water U(Nat.) 6.016.0 7.0 0.0 pCi/1 Air Filter Alpha 20.0 5.0 20.3to.6 pCi/ sample Air Filter Beta 50.015.0 56.011.7 pCi/ sample Air Filter Sr-90 17.011.5 18.711.5 pCi/ sample f Air Filtee Cs-137 16.015.0 22.012.7 pCi/ sample Milk I-131 4.010.4 3.67io.58 pCi/l (

Milk I-131 94.019.0 90.016.9 pC1/1 Milk Cs-137 51.0il.7 54.011,7 pci/1 Milk K 1600180 1540126 mg/l Urine H -3 30251359 3913;',10 pC1/1 Data for EPA reported 1 sigma of the mean.

4 e

f f

TABLE 3-3 1988 QUALITY CONTROL ANALYSES

SUMMARY

1 The table below summarizes results of samples run for per oss quality ]

control purposes during the subject year. These listings are in addition to such measurements as detector backgrounds, check source values, radiometric-gravimetric comparisons, system calibrations, etc. Detailed listings of each measurement are maintained at the analysis laboratory. J and are available for inspection if required.

Blank Samples Nuclide Number of Number of Analyses Exceeding Analyzed Determinations the LLD for that Analysis -)

1 Gross Alpha 67 0 Gross Beta 38 0 1 H-3 93 0 U-234 68 0 U-238 178 0

) Th-230 13 0 Ra-226 59 0 Ra-228 4 0 Sr-90 39 0 i Pu-239 33 0 l Am-241 36 0  !

I-131 3 0 l

l 'l Spiked Samples l

i Nuclide Number of Within 2 Sigma Within 3 Sigma Analyzed Determs, of Known of Known Gross Alpha 67 67 -

Cross Beta 38 38 -

I H-3 99 99 -

) U-234 41 41 -

i U-238 149 149 -

k Th-230 6 6 -

Ra-226 77 77 -

'Ra-228 4 4 -

Sr-90 35 35 -

Pu-239 14 14 -

I Am-241 23 23 -

I-131 3 3 -

?

i f

t

4.0 RE.?ULTS AND DISCUSSION 4.1 SAMPLES FROM THE TERRESTRIAL ENVIRONMENT 4.1.1 AIR PARTICULATE AND AIRBORNE I-131 The gross beta air particulate data obtained during 1988 were comparable to the data obtained during the years of 1982, 1983, 1984, 1985, 1986 (except May 1986), 1987, and the preoperational period. Cross beta concentrations for air particulate for all sampling periods in 1988 i

remained generally at low levels.

Average concentrations with their average standard deviations for the years 1988 and before are presented in Table 4-1 for both onsite and offsite locations. In October 1980, the Peoples' Republic of China tested a nuclear device in the atmosphere. For this reason, the increased average concentrations in 1981 were due to increased fallout levels from the October 1980 Chinese test and not from operation of the Trojan Nuclear Plant. The larger average standard deviation for the 1986 data was due to the increased gross beta activity for May 1986 resulting from the Chernobyl incident.

Airborne I-131 concentration values for 1988 were below the detection

) limit of 0.05 pCi/m (at collection time) for all samples.

3 For 1988, the measurement of gamma emitting radionuclides in quarterly composites of air particulate filters for each monitoring location did not show detectable activity above the detection limit of 0.05 pCi/m . ,

r Data for these air monitoring samples are listed in Chapter 5, Tables 5-1, 5-2, and 5-3.

4.1.2 FOOD CROPS 1

Samples of food crops (garden produce) were collected and analyzed for gamma emitters. The sample collections of these garden produce were made 4-1 f f

i during the harvest months of June, July, and August 1988. Gamma emitting radionuclides were not detected in the food crop samples. The data are presented in Chapter 5 Table 5-4.

4.1.3 WELL WATER  ;

Well water samples were collected quarterly from three locations.

Tritium and gamma emitting radionuclides levels were below the sensitivity j requirements of the program. The data are presented in Chapter 5 Table 5-5. j 4.1.4 MILK

(

l I l Milk samples were collected from four locations and were analyzed for f I-131, Sr-89, Sr-90, and and gamma emitters. No samples contained I-131 Le Sr-89 at detectable levels. Most samples contained Sr-90, which'is j l attributable to worldwide fallout due to atmospheric weapons tests.

i During the monthe March through June and in December, 17 of 79 milk

samples collected for the year showed detectable levels of radiocesiums.

Eleven of these samples exceeded 20 pCi/1, all Cs-137. The, lack of I-131 and Sr-89 radioactivity in the milk samples shows that the measured cesium radioactivity is attributable to fallout radioactivity due to the April 1986 Chernobyl incident in Russia, rather than operational activity of the Trojan Nuclear Plant. Re.ner to the 1986 report for discussion of this incident.

The milk scmple data are presented in Chapter 5, Table 5-6. ,

l 4.1.5 AMBIENT RADIATION LEVELS Ambient dose rates in mR / day for dosimeters at measurement locations in the environs around the Trojan Nuclear Plant are shown in Chapter 5, Table 5-7. Several of these measurement locations were established ,

before the Plant became operational. The mean and standard deviation 4-2 l

l

)

i i

for the quarterly dosimeters data has been calculated for the three geo-graphical groups of Oregon, Washington, and Trojan onsite locations, i

For 1988, the mean amb3ent dose rates were: 0.1210.02 mR/ day for the j

)

14 Trojan onsite locations, 0.1410.02 mR/ day for the 20 Oregon locations, j and 0.1210.02 mR/ day for the 23 Washington locations. These values do not differ significantly from the results of previous years.

Another manner for review of the ambient radiation measurements is to divide the results between three rings which are grouped as to radial ~

distance from Trojan: the close ring (24 locations) at distances from j 0.1 to 2.0 miles; the 5-mile ring (17 locations) at distances from 2.1 to 7.0 miles; the 10-mile ring (16 locations) at distances from 7.1 to 10.7 l miles. The 10-mile ring serves as the control locations for the ambient {

radiation measurements. Each ring has at least one measurement location 1 in each of the 16 directional sectors. The measurement mean and standard j deviations were calculated to be 0.1210.02 mR/ day for all locations, with I the close, 5-mile, and 10-mile rings being 0.12 0.02 mR/ day, 0.1310.02 mR/ day, and 0.1410.02 mR/ day, respectively. These data  ;

1 indicate that the operational activities of the Trojan Nuclear Plant- do ]

not affect the ambient radiation levels aro 7d the Plant.

The ambient gamma radiation data in Table 5-7 were also analyzed for dose rate differences in the four major compass directions from the Trojan

)

Nuclear Plant. No significant differences were found, in respect to both the compass directions or the similar data from 1987 and before. The values were: 0.13 0.02 mR/ day for the 16 north locations.

0.1110.01 mR/ day for the 9 east locations, 0.14 0.03 mR/ day for the 12 south locations, and 0.14 0.01 mR/ day for the 6 west locations.

4.2 SAMPLES FROM THE AQUATIC ENVIRONMENT i 4.2.1 DRINKING WATER SAMPLES l

I composited drinking water samples were collected from municipal water

)

supply locations on the Columbia River that are downstream (Sample 4-3

I I

Location 2) and upstream (Sample Location 66) of the Trojan site.

The samples were analyzed monthly for gross beta activity, tritium, and gamma emitters. The data are presented in Chapter 5, Table 5-8.

No radioactivity attributable to operation of the Trojan Nuclear Plant f was detected in any of the water samples. j 4.2.2 SHORELINE SOIL j Shoreline soil samples were collected from a location on the bank of the  ;

Columbia River near the Trojan site. Analyses were performed for gamma emitters. The data are presented in Chapter 5. Table 5-9. None of the 1 shoreline soil samples showed detectable levels of gamma emitters.

4 4.2.3 FISH Fish and crayfish were collected twice during the year and the fillets j i

and/or tails were analyzed for gamma emitters. None of the fish or j crayfish samples contained gamma emitting radionuclides larger than the  !

detectability level of 0.1 pCi/g. The dat's are presented in Chapter 5, l Table 5-10.

4.3

SUMMARY

OF RESULTS Table 4-2 presents a summary of the radioactivity analysis results for  ;

each medium or pathway sampled for the 1988 Radiological Environmental Monitoring Program around the Trojan Nuclear Plant. The format of Table 4-2 is that which is required by Trojan Technical l Specification 6.9.1.5.2.

A review of Table 4-2 shows that, except for milk, none of the radio-activity measurements were larger than the Reporting Levels defined by 4-4

Technical Specification 3.12.1. The milk samples that exceeded the Reporting Levels were determined to be caused by fallout radioactivity and not Trojan Nuclear Plant operations.

7 For the gross beta analyses of the air particulate samples, the value for the location with the highest annual mean was not significantly different from the the values for the control location or all locations.

For the milk samples, the only detectable radioactivity was due to the I atmospheric weapons testing and the Chernobyl nuclear accident fallout radionuclides, Sr-90, Cs-134, and Cs-137. Also, the dairy with the highest measured values of Sr-90, Cs-134, and Cs-137 was a goat dairy.  ;

Goats tend to concentrate radioact!.vity in the milk to a greater degree than do cows.

\

1 For the ambient radiation measurements, the mean value for the control l locations (10-mile ring) was not significantly different than the m On )

values for all locations or the close ring (see Section 4.1.5).

t I

For the radioactivity measurements in drinking water, the annual mean for {

the gross beta determination was higher (though not significantly) for l the upstream (Columbia River) or control location (St. Helens) than it 1

was for the downstream location (Rainier).

l i

As is shown by Table 4-2, except for milk, most of the radioactivity

> measurements performed for the 1988 Trojan Nuclear Plant Radiolog,ical Environmental Monitoring Program were at or below the level of detect-ability. There is no indication that the operations of the Trojan Nuclear Plant had a radiological impact on the environs around'the Plant.

F I

4-5 l

-1 TABLE 4-1 AVERACE GROSS BETA CONCENTRATIONS FOR AIR PARTICULATE

~~ ~

)

(Units: 10 , .pCi/m )

]

Trojan Oregon Washington ]

(onsite) (offsite) (offsite) -]

I J

Preop 212 212 312 1976 2 6- 318 214 1977 314 414 512 1978 2i2 211 2t1 j 1979 111 lil 1+1

, j 1980 3.+4 3+4 2+4 1981 1112 11 4 1111  ;

1982 215 217 216 l 1983 212 212 212 1984 212 212 212 1985 212 211 211 1986 317 316 3i7 1987 111 111 111 1988 111 111 It1 9

l l

I

1 a [ 55 )

c ) / 0 1 3 o f e 2 2 L ( g 50 /

r nn ( - 3 e l aa 4 4 1 b o eR 1 0 D D D D (

m r M 00 L L A A A L L 4 e t L L / / / L L c n 00 < < N N N < < 2 e o D C

- ]

1 a y n [ )

r a ) 2 1

)

a e f e 56 M ( g /0 1 u nn 2 2 n l aa 50 /

a a eR ( - 0 J u M 4 4 2 Y n 1 0 D D D D D D D (

L R n 00 L L L L L L 3 A  :

A L L L L L L L M d 00 < < < < < < < 5 M o t U i s S r e e h M P g A g i R n H

. G i n y O h d o d R t r t ni n i

r P i at aS o

p We c l a G

N e mee na cr t -

r D

_ I R oN ni oi k R ,

i aD P m n O t t i T 4 4

a s 5 R 2 I 3

c i

- N -

o D 97 3 4 O 0 L 13 - - - - - - - 6 M 5 E

L L t

] )

B A e r a 4 o

A T k

[ 6

- T N c t s) 3 1 E anf / 6 )

M o co( e 4 0 9 N D ii ng 6 7

- O dt an 3 0 /

R n

na ea ( - 4

_ I o I cMR 3 4 6 V o D D D D D D D

(

1 0

- g

_ N e l L 00 L L L L L L L 5 E r l L L L L L L L

_ O A 00 < < < < < < < 3 L

A C y n e e

. I t o d d G t ii i i e O n mt l l d u

L o i c) c c i

- O C L eD u u l n n

_ I tL c

- D a reL 2 / / u A i eD( 0 5 5 2 0 n

- R w 0 0 0 0 0 / 5 0 0 b of 0 0 m L o 0 0 0 0 1 1 0 1 1 u

l o r C es

- db ed t

nmse auym n Nl r B m a e ao n n u n l pl nf s 1 a a i a 1 9 0 P

s c c c yaAr 3 t 3 8 9 r Tt e o4 14 s s i s . 1 -

ofP r6 - 6 8 - r2 2 - 9 r9 r a T o G3 13 Y2 y7 T1 y1 I7 S7 S e

l c

u y

- N af s

- n h wo) t t e .

a t t n a )

j t aie l o P nm u e ) )

r sw rr r U e c T r( r i p ee e o u o -

t ) t t t

- d s r r ai i mea C g Wl Pd a l ul e ipM i di

/

li

- /

ki

/

d m rC oC l c l C

- ea i p op ep ip MS A( F( W( M(

a ]

c a )

o [

3 )

L ) 68 2 f e ) /1 12 l ( g 1 3 . /

o nn 2 60 22 ]

r aa / ( - 11 b t eR D 1 4 0 ( - D D [

D n M L ( 11 92 L L A L o L 3 . L L / L C - < 2 00 53 < < N <

]

n a a [

e ) )

M f ) ) 8 2

( e ) 1 4 1 12 l ng 1 2 / . /

a an 2 / 4 0 22 m!!ea r

R

/0 52

( -

5 19

( 4

(

87 1 1

- 1 1

(

92

- D L

D L

D L

D L

A 4 8 9 - .

L L L L

_ - 11 27 00 53 < < < <

~

t s

e

.. h y g t i i H C

)

h d y y ad s E t nn ao rE rW i a n S i iN iN b o e S Wemet i aW aW mR S l D D u ) e) -

na c c - - l nl - Hl oN ne k k oa o oi i ar ni ni Cmri .rm t ti i m i m st m tt a sD R R - nn S n5 c i 1 - 1 eo6 - o 2 o D 3 . 3 .

7 G c 6 c0

- L 68 6 8 2( ( 9 6( 1 - - - -

. 4 m E ]

L r a )

B o l 4

A t s) 2 1 T anf 2 )

co( e ii ng

) /8 4

) 9 4 1 22 dt an 9 7 2 . /

na ea 7 / 20 42 I cMR / 7 ( - 21 o

6 0 19 38 ( - D D D D l L ( 2 ( 4 10 84 L L L L l 3 - 7 -

A 18 L L L L

- 27 00 42 < < < <

n t o e e ii e e d d mt d d i i

, i c) i i l l L eD l l c c t L c c u u reL u u n n eD( n

' *. w of

/

0 4

0 5 0

0 /

n /

1

/

1 L o 1 0 0 .

0 0 1 1 0 0 r

es db ed e nms e r auymNl ,

u s B m e ao n 4 7 o u n n n a

pl nf 3 3 p s a c i a a yaAr Tt e s 1 1 x s t c c c d of P s

- - e4 o i s s s 8 s - 2 r4 r4 4 - -

T o y8 C C Y2 G2 T2 T2 T2 T8 b

y s n e af o h

wo) t i t

a t r l r t t n a e i) b) aie i t oy et P nm d d a) S r t e r( r U e R

a Wre d rw o u ) gt e e d s t y n - v -

ni n mea na il i

l g I g ul e ed k/ e/ / / m

. i pM i/ ni d m ri hi bR ic oc sC e a mm rp h p ip

]

MS A( D( S( F( [

l

5.0 COMMENTS ON AND TERMS USED IN DATA TABLES Wet Weight A reporting unit used with organic tissue samples such as vegetation and aquatic animal samples in which the amount of sample is taken to be the weight as received I from the field with no moisture removed.

1 1

Dry Weight A reporting unit used for shoreline soil in which the amount of sample is taken to be the weight of the sample after removal of moisture by drying in an oven at about 110*C for about 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br />.

pCi/m A reporting unit used with air particulate and radio-l iodine data which refers to the radioactivity content expressed in picoeuries of the volums of air expressed in cubic meters passed through the filter and/or the charcoal trap. Note that the volumes are not corrected to standard conditions.

Camma Emitters Samples were analyzed by high resolution germanium gamma or spectrometry. The resulting spectrum is analyzed by a Gamma Isotopic computer prograa which scans about 50 to 2000 kev and lists the energy peaks of any nuclides present in concentrations exceeding the sensitivity limits set for that particular experiment.

Error Terms Figures following "i" are error terms based on counting uncertainties at the 2a (95-percent confidence) level. Values preceded by the "<" symbol were below the stated concentration at the 3a (99-percent confidence) level.

5-1

Sensitivity All analyses meet the sensitivity-requirements of the i program as given in Table 3-1. For the few samples that do not'(because'.of inadequate sample quantities, analytical' interference, etc), the. sensitivity actually obtained.in'the analysis is given.

1 Comment When all analyses of a particular type.during the period resulted in-concentrations below the sensitivity limits,.

a statement is made on the appropriate table'rather-than presenting a whole page of "<" data. If all but one or-

j. two data points are below the sensitivity limits, the previously mentioned convention is followed and the.

finite data are given as footnotes.

l 1

1 i

5-2 -f 1

1

- _ _ _ _ _ _ - _ _ . - _ _ __ _. .______---_-______________-_Y

TABLE 5-1 Sheet 1 of 7 AIRBORNE IODINE-131* AND CROSS BETA IN AIR PARTICULATE FILTERS (Weekly Collections)

Location IF* Location 1F*

Collection Volume Gross 8 Collection Volume Gross 8 Date (m3) (pci/m 3) Date (m3 ) (pci/m 3) 01/05/88 290 0.056 0.004 07/05/88 285 0.00710.003 01/12/88 285 0.057 0.004 07/12/88 285 0.012 0.003 01/19/88 285 0.007 0.003 07/19/88 280 0.006 0.003 01/26/88 285 0.01410.003 07/26/88 280 0.01510.003 02/02/88 285 0.025 0.003 08/02/88 245 0.00910.003 02/09/88 285 0.02010.003 08/09/88 285 0.00710.003 02/16/88 285 0.008 0.003 08/16/88 285 0.00910.003 02/23/88 285 0.00910.003 08/23/88 285 0.00810.003 03/01/88 285 0.02510.003 08/30/88 285 0.01610.003 03/08/88 285 0.007io.003 09/06/88 285 0.01810.003 03/15/88 285 0.008 0.003 09/13/88 285 0.00910.003 03/22/88 285 0.015 0.003 09/20/88 285 0.014 0.003 03/29/88 285 0.00410.003 09/27/88 280 0.01010.003 04/05/88 285 0.008 0.003 10/04/88 280 0.020io.003 04/12/88 285 0.015 0.003 10/11/88 285 0.021io.003 04/19/88 285 0.01710.003 10/18/88 290 0.013 0.003 04/26/88 280 0.006 0.003 10/25/88 285 0.008io.003 05/03/88 285 0.00910.003 11/01/88 285 0.01510.003 05/10/88 285 0.008 0.003 11/08/88 290 0.00610.003 l 05/17/88 295 0.009 0.003 11/15/88 275 0.00610.003 05/24/88 285 0.008t0.003 11/22/88 290 0.00710.003 05/31/88 285 0.008t0.003 11/29/88 185 0.004t0.003 06/07/88 285 0.00710.003 12/06/88 285 0.03110.004 06/14/88 285 0.007 0.003 12/13/88 290 0.01410.003 06/21/8e 285 0.007 0.003 12/20/88 285 0.023 0.003 06/28/88 285 0.00710.003 12/27/88 280 0.008io.003

  • Iodine cartridge concentrations are <0.05.

TABLE 5-1 Sheet 2 of 7 Location II* Location II*

Collection Volume Cross B Collection Volume Gross B 3

(m ) 3) _,Date 3 (m ) 3)

Date _ (pci/m (pcl/m i 01/05/88 285 0.06110.004 r 5/88 285 0.005 0.003 01/12/88 290 0.04910.004 07/12/88 285 0.01010.003 ,

01/19/88 285 0,009 0.003 07/19/88 285 0.00910.003  ;

01/26/88 285 0.015 0.003 07/26/88 285 0.012 0.003 '

02/02/88 285 0.02510.003 08/02/88 285 0.00810.003 j 02/09/88 285 0.02410.003 08/09/88 285 0.00710.003 4 02/16/88 285 0.007 0.003 08/16/88 285 0.010 0.003 02/23/88 285 0.00810.003 08/23/88 285 0.00910.003  ;

03/01/88 280 0.02510.003 08/30/88 285 0.01710.003 l l 03/08/88 285 0.006 0.003 09/06/88 285 0.01410.003 ]

03/15/88 285 0.01210.003 09/13/88 285 0.011io.003 j 03/22/88 285 0.01610.003 09/20/88 285 0.016io.003  !

03/29/88 280 0.00510.002 09/27/88 280 0.008io.003 1 04/05/88 285 0.00510.003 10/04/88 290 0.01710.003 j 04/12/88 285 0.01310.003 10/11/88 285 0.01710.003 l

04/19/88 285 0.01710.003 10/18/88 290 0.01610.003 04/26/88 290 0.007i0.003 10/25/88 285 0.0091s.003 j 05/03/88 285 0.00910.003 11/01/83 285 0.01310.003 05/10/88 285 0.01210.003 11/08/88 290 0.00710.003 05/17/88 290 0.01110.003 11/15/88 275 0.007io 003 05/24/88 285 0.009+0.003 11/22/88 290 0.005+0.003 i 05/31/88 285 0.00950.003 11/29/88 285 0.004[0.003 06/07/88 285 0.007 0.003 12/06/88 285 0.037 0.003 06/14/88 285 0.008 0.003 12/13/8? 290 0.01210.003 {

06/21/88 285 0.005 0.003 12/20/88 290 0.02710.003 06/28/88 285 0.008+0.603 12/27/88 285 0.011+0.003

)

  • Iodine cartridge concentrations are <0.05. i i

i i

j i

s i

_ - _ - - - - - - - - - i

TABLE 5-1 Sheet 3 of 7 Location 6B* Location 6B*

Collection Volume Cross B Collection Volume Gross 8 Date (m3 ) (pci/m 3) Date (m3 ) (pci/m 3) 01/05/88 285 0.04710.004 07/05/88 285 0.00610.003 01/12/88 290 0.04210.004 07/12/88 285 0.00910.003 01/19/88 285 0.00710.003 0//19/88 285 0.00810.003 01/26/88 285 0.01510.003 07/26/88 285 0.01710.003 02/02/88 285 0.017io.003 08/02/88 285 0.00710.003 02/09/88 285 0.01810.003 08/09/88 285 0.00710.003 02/16/88 285 0.00810.003 08/16/88 285 0.00710.003 02/23/88 285 0.00810.003 08/23/88 285 0.01110.003 03/01/88 280 0.023io.003 G8/30/88 285 0.015io.003 03/08/88 285 0.00510.003 09/06/88 285 0.015i,0.003 03/15/88 285 0.008 0.003 09/13/88 285 0.011 0.003 03/22/88 285 0.01910.003 09/20/88 285 0.01410.003 03/29/88 280 0.004io.003 09/27/88 280 0.007i0.003 04/05/88 285 0.006io.003 10/04/88 290 0.017 0.003 04/12/88 285 0.015 0.003 10/11/88 285 0,01510.003 04/19/88 285 0.02010.003 10/18/88 290 04/26/88 0.013ic.003 285 0.00610.003 20/25/80 285 0.008 0.003 05/03/88 285 0.00810.003 11/01/88 285 0.01710.003 05/10/88 285 0.00910.003 11/08/88 290 0.006t0.003 05/17/88 295 0.01310.003 11/15/88 275 05/24/88 0.00410.003 285 0.00810.003 11/22/88 270 05/31/88 0.00610.003 235 0.007 0.003 11/29/88 285 0.00610.003 06/07/88 285 0.00910.003 12/06/88 285 C.03110.004 06/14/88 285 0.00910.003 12/13/88 290 06/21/88 0.01110.003 285 0.00910.003 12/20/88 285 06/28/88 0.02010.003 285 0.00810.003 12/27/88 285 0.01310.003

  • Iodine cartridge concentrations are <n.05.

t TABLE 5-1 Sheet 4 of 7 Location 11B* Loc ation 11B*

Collection Volume Cross S Collection Volume Gross 8 l Date ' fmE ') (pci/m 3) Date (m3 ) (pci/m 3) 01/05/88 285 0.045 0.004 07/05/88 285 0.006io.003 l 01/12/88 290 0.045+0.004 07/12/88 285 0.010+0.003 J 01/19/88 285 0.007 0.003 07/19/88 285 'O.03210.003 01/26/88 285 0.01410.003 07/26/88 285 0.01410.003 -. j 02/02/88 285 0.026io.003 08/02/88 285 0.010 0.003

, 02/09/88 285 0.01910.003 08/09/88 -285 0.00910.003 1

02/16/88 285 0.009to.003 08/16/88 285. 0.00710.003- j 02/23/88- 285 0.01010.003 08/23/88 285 0.00910.003 03/01/80. 280 0.02410.003 08/30/88 285 'O.018io.003 03/08/88 285 0.004 0.003 09/06/88 285 0.01710.003 03/15/88 285 0.00810.003 09/13/88 285 0.011 0.003 03/22/88 285 0.01710.003 09/20/88 285 0.015io.003-l 03/29/88 280 0.005+0.003 09/27/88 280 0.007+0.003 04/05/88 235 0.00510.003 10/04/88 285 0.015io.003 04/12/88 285 0.01310.003 10/11/88 285 0.017io.003 04/19/88 285 0.016io.003 10/18/88 285 0.014 0.003 04/26/88 285 0.01110.003 10/25/88 285 0.00810.003 05/03/88 285 0.007 0.003 11/01/88 285 0.01510.003 05/10/88 285 0.007 0.003 11/08/88 290 0.00610.003 05/17/88 285 0.00810.003 11/15/88 285 0.004io.003 05/24/88 285 0.00710.003 11/22/88 280 0.00610.0v3 05/31/88 285 0.008io.003 11/29/88 285- 0.00510.003 06/07/88 285 0.006 0.003 12/06/88 285 0.03210.004 06/14/88 235 0.007 0.003 12/13/88 290 0.013io.003 1 06/21/88 285 0.007io.003 12/20/88 285 0.022io.003 l 06/28/88 285 0.00910.003 12/27/88 285 0.01110.003 l

  • Iodine cartridge concentrations are <0.05.

1 l

1 l

l i i

j u

l

)

TABLE 5-1 Sheet 5 of 7 Location 14* Location 14*

Collection Volume Gross B Collection Volume Gross 8 Date ,_ (m3 ) (pci/m 3) Date (m3 ) .(pci/m 3)

]

1 01/05/88 285 0.04710.004 07/05/88 285 0.00710.003 01/12/88 290 0.04610.004 07/12/88 285 0.01110;003 01/19/88 285 0.00910.003 07/19/88 285 0.013io.003 01/26/88 285 0.016t0.003 07/26/88 285 0.013 0.003 02/02/88 285 0.02210.003 08/02/88 285 0.00910.003 02/09/88 285 0.02110.003 08/09/88 285 0.005 0.003 j 02/16/88 285 0.008 0.003 08/16/88 285 0.00910.003 l 02/23/88 285 0.008 0.003 08/23/88 ~285 0.01010.003 J 03/01/88 280 0.02410.003 08/30/88 285 0.01710.003 03/08/88 285 0.008 10.003 09/06/88 285 0.013 0.003 03/15/88 285 0.01010.003- 09/13/88 285 0.01210.003 03/22/88 285 0.01610.003 09/20/88 285 0.01410.003 03/29/88 280 0.00410.003 09/27/88 280 0.00710.003-04/05/88 285 0.006 0.003 10/04/88 290 0.02110,003 1 04/12/88 285 0.01310.003 10/11/88 285 0.01910.003 l 04/19/88 285 0.016 0.003 10/18/88 285 0.01610.003 l 04/26/88 290 0.006t0.003 10/25/88 -285 0.00610.003  ;

05/03/88 285 0.00710.003 11/01/88 285 0.01510.003.

05/10/88 285 0.00810.003 11/08/88 290 0.006 0.003 05/17/88 285 0.011 0.003 11/15/88 285 0.00710.003 05/24/88 285 0.008 0.003 11/22/88 280 0.00810.003 l 05/31/88 285 0.007 0.003 11/29/88 285 0.00710.003 06/07/88 285 0.00710.003 12/06/88 285 0.035l0.004 06/14/88 285 0.00810.003 12/13/88 290 0.01410.003 06/21/88 285 0.00710.003 12/20/88 285 0.02210.003 06/28/88 785 0.009t0.003 12/27/88 285 0.01210.003

  • Iodine cartridge concentrations are <0.05.

l l

i i

l TABLE 5-1 Sheet.6 of 7 i i

i Location 2* -Location 2*

Collection Volume Gross S Collection Volume Cross 8.

Date (m3 ) (oci/m 3) Date (m3 )' (pci/m 3) j 01/05/88- 285 0.043+0.004 07/05/88 285 0.006+0.003 01/12/88 290 0.038+0.004 07/12/88 285 0.009+0.003 1 01/19/88 285 0.00910.003 '07/19/88 285 0.009io.003 i 01/26/88 285 0.01210.003 07/26/88 285 0.01210.003 I l 02/02/88 285 0.020to.003- 08/02/88 285 0.00910.003 .

l 02/09/88 285 0.028t0.003 08/09/88 285 0.007io.003 ,

l 02/16/88 285 0.008 0.003 08/16/88 285 0.008 0.003 -l 02/23/88 285 0,008t0.003' 08/23/88 285 0.00910.003 03/01/88 280 0.020t0.003 08/30/88 285 0.016t0.003 ,

l 03/08/88 285 0.005 0.003 09/06/88- 285 'O.01310.003 03/15/88 285 0.00910.003 09/13/88 285 0.01210.003 03/22/88 285 0.01610.003 09/20/88 285 0.01310.003 03/29/88 280 0.005t0.003 09/27/88 280 0.00810.003  ;

04/05/88 285 0.00610.003 10/04/88 430 0.01610.003 j 04/12/88 285 0.01010.003 10/11/88 285 0.02010.003 04/19/88 285 0.015 0.003 10/18/88 290 0.01710.003 04/26/88 290 0.01110.003 10/25/88 285 0.01010.003 j 05/03/88 285 0.006t0.003 11/01/88 285 0.01910.003-05/10/88 285 0.007 0.003 11/08/88 290 0.00510.003 05/17/88 290 0.01010.003 11/15/88 285 0.00610.003 285 'l 05/24/88 0.007 0.003- 11/22/88 280 0.007 0.003 05/31/88 285 0.005io.003 11/29/88 285 0.00810.003' 06/07/88 285 0.00510.003 12/06/88 285 0.03310.004 l 06/14/88 285 0.007 0.003 12/13/88 290 0.01310.003 l 06/21/88 285 0.00710.003 12/20/88 175 0.024 0.005 06/28/88 285 0.006 0.003 12/27/88 285 0.008 0.003 ,

i

  • Iodine eartridge concentrations are <0.05.

1 l

j j

i 4

l i

l l

TABLE 5-1 Sheet 7 of 7 Location 19* Location 19*

Collection Volume Gross B Collection Volume Gross B Date (m3 ) (pci/m 3) Date (m3 ) (pci/m 3) 01/05/88 280 0.057io.004 07/05/88 285 0.007 0.003 01/12/88 285 0.05510.004 07/12/88 283 0.004 0.002 01/19/88 285 0.00810.003 07/19/88 285 0 011to.003 01/26/88 285 0.01510.003 07/26/88 285 0.013t0.003 02/02/88 285 0.02410.003 08/02/88 285 0.009 0.003 02/09/88 285 0.020t0.003 08/09/88 285 0.00810.003 02/16/88 285 0.00710.003 08/16/88 285 0.01110.003 02/23/88 285 0.01010.003 08/23/88 285 0.008t0.003 03/01/88 285 0.03030.004 08/30/88 285 0.017 0.003 03/08/88 285 0.00?i0.003 09/06/88 285 0.01810.003 03/15/88 285 0.011 0.003 09/13/88 285 0.010 0.003 03/22/88 285 0.018 0.003 09/20/88 285 0.01510.003 03/29/88 280 0.00510.003 09/27/88 285 0.00610.003 04/05/88 285 0.006 0.003 10/04/88 285 0.02110.003 04/12/88 285 0.01310.003 10/11/88 285 0.02410.003 04/19/88 285 0.01810.003 10/18/88 285 0.015 0.003 04/26/88 285 0.00510.003 10/25/88 290 0.00910.003 05/03/88 285 0.00610.003 11/01/88 285 0.01310.003 05/10/88 285 0.008 0.003 11/08/88 285 0.007 0.003 05/17/88 285 0.011 0.003 11/15/88 285 0.006io.003 05/24/88 285 0.00910.003 11/22/88 290 0.005 0.003 05/31/88 285 0.00710.003' 11/29/88 285 0.00610.003 06/07/88 285 0.00610.003 12/06/88 285 06/14/88 0.02810.004 285 0.00810.003 12/13/88 285 0.01610.003 06/21/88 285 0.00810.003 12/20/88 285 06/28/88 0.02510.003 285 0.00910.003 12/27/88 285 0.013 0.003

  • Iodine cartridge concentrations are <0.05.

l TABLE 5-2

SUMMARY

- GROSS BETA IN AIR SAMPLES DCi/m Average Maximum Minimum Trojan Onsite Stations IF 0.013io.011 0.057 0.004 II 0.01310.011 0.061 0.004 Oregon Stations 2 0.01210.008 0.043 0.005 6B 0.01210.008 0.047 0.004 19 0.01410.011 0.057 0.004 Washington Stations 11B 0.013 0.009 0.045 0.004 14 0.013 0.009 0.043 0.004 l

l

TABLE 5-3 GAMMA EMITTERS CONCENTRATIONS IN AIR PARTICULATE FILTERS (Quarterly Composites)

Collection (pCi/m3 /nuclide)

Date IF II 6B 11B lot Quarter <0.05 <0.05 <0.05 <0.05 2nd Quarter <0.05 <0.05 <0.05 <0.05 3rd Quarter <0.05 <0.05 <0.05 <0.05 4th Quarter <0.05 <0.05 <0.05 <0.05 Collection (DCi/m3/nue11de)

Date 14 2 19 1st Quarter <0.05 <0.05 <0.05 2nd Quarter <0.05 <0.05 <0.05 3rd Quarter <0.05 <0.05 <0.05 4th Quarter <0.05 <0.05 <0.05 l

I l

)

i TABLE 5-4 j

RADIOACTIVITY IN FOOD CROPS ]

[pci/g/nuclide (wet)]

1 Location II l 1

Sample Collection Gamma Type Date I-131 Emitters Lettuce [al 06/15/88 <0.02 <0.02 Swiss Chard 07/13/88 <0.02 <0.02 Carrots 07/13/88 <0.02 <0.02 Swiss Chard 08/03/88 <0.02 <0.02 Carrots 08/03/88 <0.02 <0.02 Blackberries 08/23/88 <0.02 <0.02 Apples 08/31/88 <0.02 <0.02

[a] Split with State of Oregon.

i i

1 i,

i l

1 l

e

TABLE 5-5 RADIOACTIVITY IN WELL WATER 9

pCi/1 Collection Location IG Location 3 Location 6B Gamma Gamma Gamma Date Tritium Emitters Tritium Emitters Tritium Emitters 03/09/88 <1000 <10 <1000 <10 <1000 <10 06/08/88 <1000 <10 <1000 <10 <1000 <10 l

l 09/12/88 <1000 <10 <1000 <10 <1000 <10 12/16/88 <1000 <10 <1000 <10 <1000 <10 l

l U

TABLE 5-6 Sheet 1 of 4 R.*_DI0 ACTIVITY IN MILK (Monthly Collections) pC1/1 Collection Location 17A Data I-131 Sr-89 Sr-90 Nuclides y Emitters 01/11/88 (d) (d) (d) (d) 02/08/88 (d) (d) (d) (d) 03/07/88 (d) (d) (d) (d) 03/21/88 (d) (d) (d) (d) 04/04/88 <0.5 <2 6.611.7 Cs-134 913

  • 04/19/88 <0.5 <1 1.5t0.9 <10 05/02/88 <0.5 <1 5.111.3 <10 05/16/88 <0.5 <1 4.7tl.1 <10 06/06/88 <0.5 <1 5.811.3 <10 06/20/88 <0.5 <1 2.810.9 <10 07/11/88 <0.5 <1 4.411.1 <10 07/25/88 <0.5 <1 4.8to.9 <10 08/08/88 <0.5 <1 1.210.7 <10 08/22/88 <0.5 <2(#} 2.210.8 <10 09/12/88 <0.5 <1 3.611.1 <10 09/26/88 <0.5 <1 <1 <10 10/10/88 <0.5 <2 3.2tl.0 <10 10/24/88 <0.5 <1 2.4 1.0 <10 11/07/88 <0.5 <1 2.310.9 <10 11/21/88 <0.5 <1 2.411.0 <10 12/12/88 (d) (d) (d) (d)

(a) All other gamma emmiters <10.

(b) Due to low sample volume. 4 (c) Due to low chemical recovery.

(d) No milk sample available; goats were dry.

TABLE 5-6 Sheet 2 of 4 pCi/1 Collection ,,,

Location 19 Date I-131 Sr-89 Sr-90 Nuclides Y Emitters 01/11/88 <0.5 <1 <1 <10 02/08/88 <0.5 <1 <1 <10 03/07-88 <0.5 <1 <1 <10 03/71/88 <0.5 <1 1.210.8 <10 04/04/88 <0.5 <1 <1 <10 04/18/88 <0.5 <1 4.410.8 <10 05/02/88 <0,5 <1 1.010.8 <10 05/16/88 <0.5 <1 <1 <10 06/06/88 <0.5 <1 0.810.7 <10 06/20/88 <0.5 <1 1.5 0.8 <10 07/11/88 <0,5 <1 8.6il.4 Cs-137 2314 "

07/25/88 <0.5 <1 4.211.1 <10 08/08/88 <0.5 <1 0.710.7 <10 08/22/88 <0.5 <1 <1 <10 09/12/88 <0.5 <1 1.9 1.0 <10 09/26/88 <0.5 <1 3.5 0.9 <10 10/10/88 <0.5 <1 <1 <10 10/24/88 <0.5 <1 2.110.5 <10 11/07/88 <0.5 <1 0.910.8 <10 11/21/88 <0.5 <1 0.910.7 <10 12/12/88 <0.5 <1 <1 <10 l l

(a) All other sama emiters <10.

_- - - - - - - - - - -- - i

TABLE 5<-6 Sheet 3 of 4 pCi/1 i Collection Location 63 Date I-131 Sr-89 Sr-90 Nuclides Y Emitte N 01/11/88 <0.5 <1 2.4 1.2 <10 02/08/88 <0.5 <1 3.411.1 Cs-137 11 2(* I 03/07/88 <0.5 <1 5.7il.1 <10  !

03/21/88 <0.5 <1 <1 Cs-137 22i3(*}

04/04/88 <0.5 <1 6.711.3 Cs-134 812 Cs-137 25 +4 ( * } ,

04/18/88 <0.5 <2 1311 Cs-134 10 2 l

Cs-137 3814 j 05/02/88 <0.5 <1 4.2tl.0 Cs-134 1413 Cs-137 4314  !

05/16/88 <0.5 <1 6.311.2 Cs-137 3014(*

06/06/88 <0.5 <1 3.7il.1 Cs-137 3614(*} i I

06/20/88 <0.5 <1 5.9 1.2 Cs-137 4013(a) J 07/11/88 <0.5 <1 1.410.7 <10 07/25/88 <0.5 <2 2.1 1.0 Cs-137 49112

  • 08/08/88 <0.5 <1 7.011.2 Cs-137 1113(*

08/22/88 <0.5 <1 1212 Cs-137 2114(*

09/12/88 <0.5 <2 8.711.6 Cs-137 1013(*}

09/26/88 <0.5 <1 4.3tl.3 <10 '

10/10/88 <0.8( <1 1.911.0 <10 10/24/88 <0.5 <1 3.9II.0 Cs-137 713(*

11/07/88 <0.5 <1 4.3tl.1 Cs-134 20i5 Cs-137 40 5(*}

11/21/88 <0.5 <1 4.1tl.1 <10 12/12/88 <0.5 <1 5.411.2 Cs-134 '

18t3 Cs-137 47t4(*}

(a) All other gamma emmiters <10.

(b) Due to low sample volume.

(c) Due to low chemical recovery.

TABLE 5-6 Sheet 4 of 4 pCi/1 Collection Location 68(8)

Date I-lil Sr-89 Sr-90 Nuclides Y Emitters 01/11/88 <0.5 41 1.210.9 <10 02/08/88 <0.5 <1 <1- <10 03/07/88 <0.5 <1 0.710.7 <10 03/21/88 <0.5 <1 3.311.2 <10 04/04/88 <0.5 <1 1.110.9 <10 04/18/83 <0.5 <1 4.810.9 <10 05/02/8C <0.5 <1 1.210.6 <10 05/16/88 <0.5 <1 1.311.0 <10 06/06/88 <0.5 <1 2.Stl.0 <10 06/20/88 <0.5 <1 1.811.0 <10 C7/11/88 <0.5 <1 3.511.1 <10 07/25/88 <3.5 <1 3.111.1 <10 08/08/88 <0.5 <1 1.6 0.8 <10 08/22/88 <0.5 <1 1.911.0 <10 09/12/88 <0.5 <1 1.7 1.0 <10 09/26/88 <0.5 <2 <1 <10 10/10/88 <0.5 <2 <1 <10 10/24/88 <0.5 <1 <1 <10 11/07/88 <0.5 <1 0.910.9 <10 11/21/88 <0.5 <1 <1 <10 12/12/88 <0.5 <1 1.010.9 <10 (a) Split sample with State of Oregon.

(b) Due to low chemical recovery.

)

1 1

TABLE 5-7 Sheet 1 of 2 AMBIENT GAMMA RADIATION LEVELS FOR 1988 mR/ Day (Mean Daily Exposure 12a Error) ]

'j First Quarter Second Quarter Third Quarter Fourth Quarter-Site 02/10/88-05/04/88 05/04/88-08/10/88 08/10/88-11/09/88 11/09/88-02/08/89 .q

\

1A 0.1110.03 0.1019 02 0.1010.02 0.0910.03 1B 0.1110.03 0.10 0.02. 0.1110.02 0.1010.03 1C 0.12 0.04 0.11io.03 0.13 0.02 0.12t0.04 1E 0.1110.03 0.09t0.02 0.1010.02 0.0910.03 IF 0.14 0.04 0.11 0.03 0.13io.02. 0.1210.04 ]

IH 0.1710.05 0.1710.04 0.16io.03 0.1610.06 f II 0.1210.04 0.11 0.03 0.1310.05 AJ 0.11io.03 0.09tp.02 0.1110.02 0.1010.04 2 0.1610.05 0.1519 04 0.16io.03 0.15 0.06 ,

3 0.13_+0.04 0.14_+0.03 0.16_+0.03 0 .14_+0 . 05 ,

4C 0.1510.05 0.12 0.03 0.1410.02 0.12+0.04 6B 0.1310.04 0.1119 03 0.1210.02 0.1110.04 11A 0.2110.03 0.1010.02 0.1210.02 0.1010.03 20 0.11 0.03 0.10 0.02- 0.11 p.02 0.11 0.04 21 O.10 0.03 0.08 0.02 0.10 0.02 0.10 0.03-23 0 .11_+0 . 03 0.08_+0.02 0.11_+0.02 0.11_+0.04 ,

33 0.12 0.03 0.0919 02 0.1310.02 0.11 0.04 ]

i 24 0.17io.05 0.15 0.04 0.1719 03 0.1610.06 j 25 0 .14_+0. 0 4 0.11_+0.03 0.14_+0. 02 0.12_&O.04 )

26 0.16 0.05 0.15 0.04 0.17 0.03 0.16 0.06 27 0.1810.06 0.17 p.04 0.18 0.03 0.17 0.06 28 0.14 0.05 0.16 0.04 0.1810.03 , 0.16 0.06 29 0.1710.06 0.16 0.04 0.1810.04 0.1710.06

'30 0.1710.05 0.15ip.04 0.1710.05 0.1619 06 l

31 0.15 0.05 0.16 0.04 0.14io.05 32 0.14 p.04 0.1110.03 0.13 p.03 0.12 0.02

'33 0.15t0.05 0.14i0.04 0.1610.04 0.1410.03

~

c Dosimeter vandalized during monitoring period.

I

TABLE 5-7 Sheet 2 of 2 First Quarter Second Quarter Third Quarter Fourth Quarter Site 02/10/88-05/04/88 05/04/88-08/10/88 08/10/88-11/09/88 11/09/88-02/08/89 34 0.15 0.05 0.14 0.04 0.15 0.04 0.13 0.03 35 0.13 0.04 0.12 0.03 0.13 0.04 0.12 0.02 36 0.13 0.04 0.1310.03 0.14 0.04 0.12 0.02 37 0.1410.04 0.1310.03 0.16 0.04 0.13 0.03 38 0.14 0.04 0.11 0.02 0.12io.03 0.12 0.02 39 0.16t0.05 0.1510.04 0.17 0.05 0.1510.03 40 0.12 0.03 0.11io.03 0.14 0.04 0.12 0.02 41 0.14 0.03 0.12 p.03 0.14 0.04 0.13 p.02 42 0.12 0.03 0.11 0.03 0.13 0.04 0.12 0.02 43 0.13io.03 0.12 0.03 0.14 0.04 0.13 0.03 44 0.14 0.04 0.14 0.04 0.15 0.04 0.14 0.03 45 0.14 0.03 0.13 0.03 0.14 0.04 0.13 0.02 46 0.12 0.03 0.11 0.03 0.12 0.03 0.12!0.02 47 0.13io.03 0.11 0.03 0.13 0.04 0.12 0.02 48 0.12io.03 0.11 0.03 0.12 0.03 0.11io.02 49 0.1010.02 0.10t0.02 0.11iO.03 0.10 0.02 50 0.11 0.03 0.10 0.02 0.12io.03 0.10 0.02 51 0.12 0.03 0.12 0.03 0.13io.03 0.12 0.02 52 0.11 0.03 0.11 0.03

  • 0.11 0.02 53 0.1210.03 0.10 0.02 0.12 0.03 0.11 0.02 54 0.16 0.04 0.15 0.04 0.18 0.05 0.15 0.03 l 55 0.11 0.03 0.1010.02 0.1210.03 0.10to.02 56 0.14 0.04 0.12 0.03 0.1410.04 0.13 0.03 57 0.13 0.03 0.1310.03 0.15 0.04 0.12 0.02 58 0.15 0.04 0.13 0.03 0.15 0.04 0.14 0.03 59 0.1110.03 0.1010.02 0.12 0.03 0.10 0.02 60 0.11 0.03 0.10 0.02 0.12 0.03 0.10 0.02 61 0.15 0.04 0.13 0.03 0.15 0.04 0.14 0.03 62 0.13 0.03
  • 0.16 0.05 0.15 0.03 64 0.13 0.04 0.1010.02 0.12 0.03 0.11io.02
  • Dosimeter vandalized during monitoring period.

_ - - i

l1 li s

r l

y ae mt 0 0 0 10 01 0 0 01 0 0 0 0 p mt 1 1 1 1 1 1 1 1 1 p ai < < < < < < < < < < < <

u Gm

- S r

e E

t m a u 0 0 0 0 0 0 0 0 0 0 0 0

- W 1 i 0 0 0 0 0 0 0 0 0 0 0 0

_ / t 0 0 0 0 0 0 01 0 0 0 0 0

_ l i i 1 1 1 1 1 1 1 1 1 1 1 a C r < < < < < < < < < < < <

p p T i

_ c i

n a u t 2 1 3 1 0 1 0 9 8 3 9 2 M e B 1 1 1 1 1 1 1 0 1 1 0 2 1 1 1 1 1 1 1 1 1 1 1 y

's s 1 0 6 0 6 5 8 2 3 2 9 7 n s .

e o 5 7 6 5 3 5 6 3 8 2 3 3 l r 1 e G H

t 8 8 8 8 8 8 8 8 8 8 8 9 S s 8 8 8 8 8 8 8 8 8 8 8 8 e / / / / / / / / / / / /

- t 1 7 4 2 6 5 1 1 3 7 5 4 a 0 0 0 0 0 0 0 0 0 0 0 0 6 D / / / / / / / / / / / /

R 6 2 3 4 5 6 7 8 9 0 1 2 1 E n 0 0 0 0 0 0 0 0 1 1 1 0 T n o - - - - - - - - - - - -

A o i 8 8 8 8 8 8 8 8 8 8 8 8 W i t 8 8 8 8 8 8 8 8 8 8 8 8 t c / / / /7 / / / / / / / /

G a e 5 1 4 2 6 5 1 1 3 7 5 N c l 0 0 0 0 0 0 0 0 0 0 0 0 I o l

/ / / / / / / / / / 7/ /

K L o 1 2 3 4 5 6 8 9 0 1 2 N C 0 0 0 0 0 0 0 0 0 1 1 1 8 I

- R 5 D E N L I B

A Y T T s I r V a e I t T y m mt 0 1 1 0 0 10 0 0 0 0 0 0 0 10 1 1 1 1 1 1 C

A l

p ai Gm < < < < < < < < < < < <1 1 O p E I u D S A

R r m e u 0 0 0 0 0 0 0 0 0 0 0 0 t 1 i 0 0 0 0 0 0 0 0 0 0 0 0 a / t 0 01 0 101 0 01 0 10 01 01 0 10 W i i 1 l

C p T r < < < < < < < < < <1 <1 < 1 a

p i

c a i t 1 0 1 0 0 1 9 0 9 0 9 5 n e u B 1 1 1 1 1 1 0 1 1 1 0 2 M 1 1 1 1 1 1 1 7 1 11 010 1 s 6 9 4 7 4 6 9 9 r s . .

e o 4 2 2 2 2 3 3 2 8 6 3 2 i r n G i

a R

s 8 8 8 8 8 8 8 8 8 8 8 9 -

e 8 8 0 8 8 8 8 8 8 8 8 8 2 t

/ / 7 / /4 / / / / / / / /

1 2 6 5 1 1 3 7 5 4 a 0 0 0 0 0 0 0 0 0 0 0 0 n D / / / / / / / / / / / /

o 2 3 4 5 6 7 8 9 0 1 2 1 i n 0- 0 -0 0- 0 -0 0 0 1 1 1 0 t o - - - - - - - -

a i 8 8 8 8 8 8 8 8 8 8 8 8 c t 8 8 8 8 8 8 8 8 8 8 8 8 o c / / / / / 4/ / / / / / /

L e 5 1 7 2 6 5 1 1 3 7 5 l

l 0

/

0 0 0 0 0 0 0 0 0 0 0

/ / / / 4/ / / / / 7 / /

o 1 2 3 5 6 8 9 0 1 2 C 0 0 0 0 0 0 0 0 0 1 1 1 l1l

TABLE 5-9 RADIOACTIVITY IN SHORELINE SOIL (Semiannual Collections) pCi/ 5/nuclide (dry)

Location CR3 Collection Gamma Date Emitters 03/09/88 <0.1 09/12/88 <0.1 p

4 y

8 l

5 l

l i

l l<

TABLE 5-10 l,

RADI0 ACTIVITY IN FISH / INVERTEBRATES (Semiannual Collections) pCi/g/nuclide (wet)

Collection Location Date Species- Gamma Emitters 1A 03/15/88 Carp (1), Bridgelip sucker (2) <0.A 09/09/88 Bridgelip sucker (2), Carp (2),- <0.1 Black Crappie (2)

L ID 03/11/88 Carp (3), Largamouth Bass (1) <0.1 l

l 09/09/88 Carp (4), Smallmouth Bass (2),

White Crappie (2) <0.1 CR3 04/04/88 Steelhead (1)I*I <0.1 06/16/88 Crayfish Tails <0.1 09/07/88 Chinook Salmon * <0.1 09/30/88 Crayfish Tails <0.1

[a] Split sample with State of Oregon. l l

l

[ ,- { PortlandGeneralElectricCompany David W. Cockfield Vice President, Nuclear .

April 28, 1989 Trojart Nuclear Plant Dockoi. 50-344 License NPF-1 U.S. Nuclear Regulatory Coralssion ATTN: Document Control Desk Washington DC 20555

Dear Sir:

Radiological Environmental Monitoring Report Enclosed is one copy of the Portland Conoral Electric Company's 1988 Operational Environmental Radiological Surveillance Program Annual Report, PCE-1006-88, for the Trojan Nuclear Plant.

Sincerely, Enclosure c: Mr. John B. Martin Mr. Ray D. Jaris, Manager (2)

Regional Administrator, Region V Radiation Control Section U.S. Nuclear Regulatory Commission Oregon State llealth Division Mr. George Knighton Mr. Jerry Leitch Director, PWR-A Radiation Representative Project Directorate liG. V U.S. Environmental Protection Agency Mr. William T. Dixon Mr. Robert R. Mooney, Supervisor State of Oregon Radiation Control Section Department of Energy Washington Social and llealth Services Mr. R. C. Barr NRC Resident Inspector Trojan Nuclear Plant n

121 SW Smon SUM Pocyl Oregon 97204

.. _ _ _ - _ _ _ .

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