ML20210A893

Trojan Nuclear Plant Operational Environ Radiological Surveillance Program 1986 Annual Rept

ML20210A893
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	12/31/1986
From:	Cockfield D PORTLAND GENERAL ELECTRIC CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
PGE-1006-85, NUDOCS 8705050186
Download: ML20210A893 (76)

Text

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Trojan Nuclear Plant OPERATIONAL ENVIRONMENTAL RADIOLOGICAL SURVEILLANCE PROGRAM 1986 ANNUAL REPORT PORTLAND GENERAL EL ECTRIC COMPANY l

PGE-1006-85 PDR 6

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TROJAN NUCLEAR PLANT j

OPERATIONAL ENVIRONMENTAL RADIOLOGICAL SURVEILLANCE PROGRA.I 4

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e January through December 1986 i

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i May 1987

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Prepared by i

PORTLAND GENERAL ELECTRIC COMPANY With Analyses by TMA/EBERLINE

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THERMO ANALYTICAL, INC.

1 ALBUQUERQUE LABORATORY l

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TROJAN NUCLEAR PLANT OPERATIONAL ENVIRONMENTAL RADIOLOGICAL SURVEILLANCE PROGRAM CONTENTS

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Section Title Page ABSTRACT.

1.0 INTRODUCTION

1-1 2.0 SAMPLING AND PROGRAM PROCEDURES.

2-1 2.1 SAMPLING LOCATIONS.

2-1 2.2 SAMPLING PROCEDURES.

2-1 2.2.1 Air Particulate and Radiolodino.

2-1 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 1

2.3 YEARLY AGRICULTURAL SURVEY WITHIN 5-MILE RADIUS OF TROJAN.

2-4 i

1.

3.0 ANALYTICAL PROCEDURES AND COUNTING METHODS.

3-1 3.1 ANALYTICAL DETECTION LIMITS AND COUNT RATE ERRORS.

3-1 i

3.2 AIR PARTICULATES.

3-1 3.3 RADI0 IODINE.

3-2 3.4 DRINKING AND WELL WATER.

3-2 4

3.5 SHORELINE SOIL.

3-2 3.6-FISM, INVERTEBRATES, AND FOOD CROPS.

3-2 l

3.7 MILK.

3-2 3.8 AMBIENT RADIATION MEASUREMENTS.

3-3 3.9 QUALITY CONTROL.

3-3 3.10 REFERENCES FOR ANALYTICAL PROCEDURES 3-4 I

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TROJAN NUCLEAR PLANT OPERATIONAL ENVIRONMENTAL RADIOLOGICAL SURVEILLANCE 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 Particulates and Airborne I-131.

4-1 4.1.2 Food Crops.

4-2 4.1.3 Well Water.

4-2 4.1.4 Milk.

4-3 4.1.5 Ambient Radiation Levels.

4-4 4.2 SAMPLES FROM THE AQUATIC ENVIRONMENT,

4-5 4.2.1 Surface Water and Drinking Water Samples.

4-5 4.2.2 Shoreline Soil.

4-6 4.2.3 Fish.

4-6 4.3

SUMMARY

OF RESULTS.

4-6 5.0 COMMENTS ON AND TERMS USED IN DATA TABLES.

5-1

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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 1986 Land Use census 3-1 Program Analyses and Reported Detection Levels 3-2 1986 U. S. Environmental Protection Agency - Eber11ne Intercomparison Program 3-3 1986 Quality Control Analyses Summary 4-1 Average Cross Beta Concentrations for Air Particulates 4-2 Radiological Environmental Monitoring Program Summary 5-1 Airborne Iodine-131 and Cross Beta in Air Particulate Filters (Weekly Collections) 5-2 Plots of Air Cross Beta Activity for Each Location 5-3 Summary - Cross Beta in Air Samples 5-4 Camma Emitters Concentrations in Air Particulates Filters 5-5 Radioactivity in Food Crops 5-6 Radioactivity in Well Water 5-7 Radioactivity in Milk 5-8 Ambient Comma Radiation Levels for 1986 5-9 Graphs of Thermoluminescent Dosimeter Data for 1986 thru 5-12 5-13 Radioactivity in Drinking Water j

5-14 Radioactivity in Shoreline Soll 5-15 Radioactivity in Fish / Invertebrates 111 1

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TROJAN NUCLEAR PLANT OPERATIONAL ENVIRONMENTAL RADIOLOGICAL SURVEILLANCE PROGRAM FIGURES Number Title 2-1 Sampling Locations - December 31, 1986 2-2 Sampling Locations (Detail) - December 31, 1986 1

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ABSTRACT This report presents the data obtained through the analyses of environ-mental samples collected through the Portland General Electric Trojan Nuclear Plant Environmental Radiological Surveillance Program for the period January 1, 1986 through December 31, 1986, i

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In several samples, mainly air and milk, levels of radioactivity observed during 1986 were higher than previous years.

This higher level of radio-activity was due to northern hemisphere fallout from the April 1986 acci-dent at the Chernobyl Nuclear Power Station in the Ukraine, USSR.

In no case did radioactivity attributed to the Trojan Nucicar Plant exceed the Reporting Levels of the Trojan Radiological Technical Specifications.

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1.0 INTRODUCTION

i 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 1986.

The analytical contractor during this period has been TMA/Eberline Thermo Analytical. Inc.

In comparing data obtained during this period with those from previous periods, care should be taken to ensure that differ-ences 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 dif-ferences in gross beta concentrations.

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

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2.0 SAMPLING AND PROGRAM PROCEDURES 2.1 SAMPLING LOCATIONS Sixty-seven (67) sampling locations were used in the Environmental Radiological Surveillance Program in 1986, 66 on land, and 1 in the Columbia River.

This is the same number of sampling locations in use at the end of 1985.

The sampling locations are shown in Figures 2-1 and 2-2.

Table 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 radiolodine 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. Class fiber filters were used to collect particulate matter. Activated charcoal cartridges were used to collect radioiodine.

i The glass fiber filter was removed from the air sampler and placed in a 1

2-in. plastic petri dish. The activated charcoal cartridge 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.

2-1

2.2.2 ANBIENT RADIATION MEASUREMENTS USING TLDs Thermoluminescent dosimeters (TLDs) were placed for field exposure and collected on a quarterly trequency. The TLDs were placed about 1 meter above ground level in plastic containers.

The time of collection, the exposure period, and any abnormal conditions such as moisture in the holders, damage done by animals, etc, were recorded when the TLDs were retrieved.

Care was taken to minimize exposure to the TLDs between collection and 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.

2.2.3 FOOD CROPS Representative samples of tuberous and foliar fruits and vegetables were collected during local harvesting.

Samples of leafy vegetables were collected during each of the three summer months of June, July, and August.

Samples were sealed in plastic bags immediately following collection, taking care not to include any soil or foreign material. The sample site identification number, the date collected, the sample type, and the volume obtained were recorded on the data collection forms.

2.2.4 MILK Milk samples (cow or goat) were collected monthly during January, February, and December with twice monthly collections during the other months. Milk was collected in polyethylene bottles (2 gal for cow dairy and 1 gal for goat dairy).

Prior to shipment of samples to the 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

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 min prior to collection.

Sixty ml were drawn from the 1-gal sample for tritium analysis. The remainder of the sample was put in a 1-gal 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 Monthly composite samples of municipal drinking water were collected for Rainier (2) and St. Helens (66) at their respective intake structures on the Columbia River.

Rainier is downstream of the Trojan Nuclear Plant

!!l while St. Helens is upstream. At each location, a compositing sampler took a sample every 2 he and aliquots of this monthly composite were sent for analysis. From these aliquots, 60 ml are sent for tritium analysis and a 1-gal polyethylene bottle is acidified with concentrated hcl and sent for the other analyses. The bottles were securely scaled, labeled, and collection data' forms prepared specifying site, date collected, volume, and sample type.

2.2.7 SHORELINE SO!L Shoreline soil samples of about 1 qt in volume were taken twice a year.

The samples were taken from a 1 sq ft area with the vegetation and large rocks removed before sample collection.

The soil sampling depth varied between 1 to 4 in. 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.

2-3

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 radioactivity analysis was performed on fish muscle or crayfish tail samples.

If needed for a particular sampling location, the fish muscle sample may be a mixture of several panfish species. The sample site identification number, the date collected, the fish species, and the volume obtained were recorded on l

collection data forms.

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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 1986.

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.

2-4

TABLE 2d Sheet 1 of 6 SAMPLING LOCATIONS AND FREQUENCY BY TYPE Terrestrial Aquatic Radial Air Air Well Surf Shore Sample Location Mileare Direction Partic' T-131' TLD Veg Milk' Water' Water Soll Anim ONSITE 1A - U. S. 30 & E-W Road 0.8 IM Q

S/A to Prescott IB - U.

S. 30 W of 0.5 WSW Q

Containment IC - Cemetery on hill 0.7 SW Q

W of Plant ID - Recreation Lake 0.7 S

S/A 1E - S site boundary, 0.8 s

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30 at Railroad (RR)

IF - Meteorology tower 0.5 S

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1H - Plant cooling tower 0.2 ESE Q

II - N site boundary at 0.5 N!N W

W Q

IN Columbia River IJ - RR & E-W road to 0.6 NNW Q

Prescott 20 - S of Plant on O.4 SSE Q

Columbia River shore l

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Legend at bottom of Page 6 of 6 of Table 2-1.

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TABLE 2-1 Sheet 2 of 6 Terrestrial Aquatic Radial Air Air Well Surf Shore Sample Location Mileage Direction Partic' I-131 TLD Ven Milk Water Water Soil ' Anim ONSITE 21 - SE of Plant on 0.3 SE Q

Columbia River shore 22 - Between Recreation 0.4 SSW Q

Lake and U.

S.

30 23 - U. S.

30 S of E-W O.6 WNW Q

road to Prescott 24 - Recreation Lake near 0.5 WSW Q

E-W road to Plant 64 - NW corner of 0.5 W

Q Reflection Lake ORECON 2 - Rainier

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W Q

MC 3 - Lindberg (Kelly Res.)

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Q 4C - Prescott (Jack Falls 1.6 NW Q

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TABLE 2-1 Sheet 4 of 6 Terrestrial Aquatic Radial Air Air Well Surf Shore Sample Location Mileage Direction Partic' I-131 TLD' Veg Milk Water Water Soil Anim ORECON 37 - Delena (Lost Creek 10.0 WNW Q

Road) l 38 - Rainier (Highway 30) 4.8 NW Q

J 39 - Alston-Mayger Road 9.9 NW Q

l 56 - Deer Island 3.2 SSE Q

63 - Rinck Dairy 8.1 WNW SH 66 - St. IIelens (Municipal 10.5 SSE MC Water Supply) 68 - Winans Dairy 5.0 SW SM WASHINGTON 11A - Kalama River 0.8 SE Q

(Columbia River) 118 - Kalama River 1.4 ENE W

W (Public Utility District Substation) 14 - Longview (Ocean 8.2 N!M W

W Beach Substation) 40 - Longview (RH) 5.8 N!M Q

41 - Eufaula 10.7 N!M Q

42 - Kelso (near IIwy 4) 6.6 N

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TABLE 2-1 Sheet 5 of 6 Terrestrial Aquatic Radial Air Air Well Surf Shore Sample Location MileaRe Direction Partic I-131' TLD Ven Milk Water Water Soil Anim WASHINGTON 43 - Lexington 10.3 N

Q 44 - Kelso (N Maple Hill 5.2 NNE Q

Road) 45 - Mt. Brynion 9.1 NNE Q

46 - Rose Valley 5.3 NE Q

47 - Smith Mountain 9.2 NE Q

48 - Mt. Pleasant 5.6 ENE Q

49 - Coble Mountain 7.8 ENE Q

50 - Kalama River 5.0 E

Q (Fallert Road) 51 - Kalama River 10.0 E

Q (Kalama River Road) 52 - Kalama (China Carden 5.2 ESE Q

Road) 53 - Ross Peak 10.7 ESE Q

54 - Cloverdale 5.2 SE Q

55 - Woodland (Green 10.0 SE Q

Mountain Road) 57 - Woodland (Dike Road) 9.5 SSE Q

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TABLE 2-1 Sheet 6 of 6 Terrestrial l

Acluatic Radial Air Air Well Surf Shore Sample Location Mileage' Direction Partic' I-131 TLD Veg ' Milk Water' Water' Soil 'Anim WASIIINGTON 58 - Kalama (N of Port of 1.6 SE Q

j Kalama Marina) l 59 - Kalama (S of Sports-1.5 ESE Q

man Road) 60 - Kalama (N of 1.2 ENE Q

Sportsman Road) l 61 - Carrolls (W Kingsbury 1.5 NE Q

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Road) l 62 - W of Carrolls Channel 1.0 NNE Q

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CR3 - Trojan 72.4*

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LEGEND:

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~ Weekly.

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SM - Semimonthly exce'pt monthly during December, January, and February.

MC - Monthly composite, semimonthly composite if I-131 analysis required.

S/A - Semlannually.

IIT - Harvest time.

- Columbia River mileage refers to river miles (measured from mouth).

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TABLE 2-2 1986 LAND USE CENSUS NEAREST LOCATION TO TROJAN WITHIN A FIVE-MILE RADIUS Radiation Mileage for Nearest Location Directional Meat Sector Residence Garden Milk Cow Milk Coat Animal N

0.6 0.6 None None None NNE 2.4 2.4 None 3.0 2.7 NE 1.6 1.8 None None 1.8 ENE 2.4 2.4 None None 2.4 E

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ESE 0.8 1.8 None None 1.6 SE 2.5 2.5 None None 2.5 SSE 1.4 1.4 None None 3.0 S

1.2 1.4 None None 2.0 SSW 0.9 0.9 None 2.6 0.9 SW 1.5 1.5 None None 1.5 WSW 1.4 1.9 None None 1.9 W

1.7 2.1 None None 1.7

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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 sensitivity requirements are given in Table 3-1.

3.1 ANALYTICAL DETECTION LIMITS AND COUNT RATE ERRORS In environmental radiological analyses the dominant known uncertainty is usually the sample count rate.

Error terms given in this report are based on this factor since all other analytical uncertainties are relatively small. Uncertainties are calculated by standard nethods (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 PARTICULATES Cross 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.

Camma isotopic analyses are performed with germanium detectors with a routine detection limit of 0.05 pCi/m for the gamma emitters.

3-1 1

1

l 3.3 RADIOIODINE The charcoal cartridges used are of the TEDA-impregnated type. The iodine is extracted from the charcoal, chemically separated, and counted as AgI using the low-background beta counters mentioned in Section 3.2 which yield an LLD of 0.05 pCi/m.

3.4 DRINKING AND WELL WATER Cross beta analysis of water samples is performed by evaporation of a measured aliquot of the sample, digestion, planchetting of the processed sample and radiometric assay by the low-background beta counters men-tiened 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 pCL/1 by liquid scintillation counting. Camma isotopic analysis is performed using germanium detectors with a routine LLD of 10 pCL/1 per gamma emitting radionuclide.

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

I l

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

3.7 MILK The determination of I-131 in fresh milk is based on anion exchange removal of the I-131 followed by radiochemical purification and 3-2

low background beta counting using the systems described in Section 3.2.

The LLD is 0.5 pCi/1 or better. Garma emitters in milk are measured with germanium detectors with an LLD of 10 pCi/1 per nuclide. The analysis for St-89 and Sr-90 is performed on ashed 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 (PCE).

A total of 57 fleid locations were monitored with the dosimeters analyzed quarterly. The ficid dosimeters used thermoluminescent radiation detection materials (CaF2 Dy or TLD-200 chips) with each dosimeter having more than 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 fleid 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.

Calibration of the field dosimeters was performed with Cs-137 sourecs traceable to the U. S. National Bureau of Standards.

Calibration dosimeters were prepared for each readout of the fleid dosimeters.

3.9 OUALITY CONTROL Approximately 15 percent of the analyses performed by Eberline are for quality control purposes.

Eberline participates in EPA, International Atomic Energy Agency Nuclear Regulatory Commission, several states', and other intercalibration programs.

Reports of all quality control analyses are presented monthly to PCE.

Results of EPA intercalibrations (for which "known" data are available) are given in Tabic 3-2.

In those cases where discrepant values are obtained Eberline performs an investigation to determine the cause and corrective action as required.

Table 3-3 summarizes the intralaboratory quality control results for the year 1986.

33

During 1981, 1982, and 1984, PCE participated in the Fifth, Sixth, and Seventh International Intercomparison of Environmental Dosimeters. The results of these participations woro presented in the 1982, 1983, and 1984 reports, respectively.

By the successful PGE participation in these 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 Pubile Health Association, American Water Works Association and Water Pollution Control Federation (1971):

Standard Methods for the Examination of Water and Wastewater. thleteenth edition, pp 583-632; 12th edition, pp 325-352.

APHA, 1740 Broadway, New York, NY 10019.

2.

Department of Health, Education and Welfare, Public Health Service:

Radionssay Procedures for Environmental Samrlos. National Center for RadioloSical Health (1967), Soc. 1, pp 36-115.

3.

Atomic Energy Commission:

Regulatory Guide 4.3 (September 1973).

4 Health and Safety Laboratory, Atomic Energy Commission:

L, _3 procedures Manual (now known as EHL of the Department of Ennegy).

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 Thermoluminescent _Dosimoter for Environmental Honitorinr.", USAEC Heport BNWL-SA-4191 (1972).

3-4

(

TABLE 3-1 i

PROGRAM ANALYSES AND REPORTED DETECTION LEVELS Prorram Analysis Reported Detection Limits (LLD)[a]

3 Air Particulate-gross beta 0.002 pCi/m 3

Air Particulate-gamma scan 0.05 pCi/m /nuclide 3

Air Radiolodine 0.05 pCL/m 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 Milk-gamma scan 10 pCL/ liter /nuclide Water-gross beta 0.5 pCi/ liter Water-tritium 1000 pCl/ liter Water-gamma scan 10 pC1/1lter/nuclide Shoreline Soil-ganma scan 0.1 pCl/g/nuclide (dry)

Fish / Invertebrates-gamma 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.

TABLE 3-2 Sheet 1 of 2 1986 U. S. ENVIRONMENTAL PROTECTION ACENCY (EPA)

EBERLINE INTERCOMPARISON PROCRAM Eberline Sample Type Analysis EPA Value Value Units b

Water Alpha 10i5 10i2 pCi/l Water 3 eta 13 5 14 1 pCi/1 Water I-131 45.0016.00 3614 pCi/1 Water Alpha 52t13 3712 pCi/l Water Ra-226 6.3010.95 7.23 1.02 pCi/1 Water Ra-228 10.1011.52 liti pCi/1 Water U (Nat) 8.016.0 7.0il.3 pCi/1 Water Beta 7515 52i5 pCi/1 Water Sr-89 27i5 10t2 pCi/1 Water Sr-90 9.011.5 51 pCi/l Water Co-60 1815 1811 pCi/l Water Cs-134 18 5 1511 pCL/1 Water Cs-137 1815 20!1 pCi/l

{

Water Se-89 31t5 2314 pCi/l Water Sr-90 15i2 12t2 pCi/l Water Pu-239 7.110.7 7.410.5 pCi/l 1

c-Water Alpha 3.015.0 2.3 0.6 pCi/1 Water Beta 7.015.0 6.7t0.6 pCi/1 Water Cc-51 38 5

<41 pCi/l Water Co-60 1815 15i3 pCi/l Water 2n-65 4015 3515 pCL/1 Water Ru-106 Oi5

<25 pCi/1 Water Cs-134 3015 2112 pCi/l Water Cs-137 22t5 2112 pCi/l Water H-3 52301520 44001570 pCi/l Water Ra-226 4.110.6 3.11 3 pCi/1 0

Water Ra-228 12.4tl.9 19.113.0 pCi/l Water H-3 3125 360 39931405 pCi/l Water Alpha 17 5 16.711.5 pCi/l 1

Water Ra-226 2.9010.44 3.0310.06 pCi/l Water Ra-228 2.0010.30 1.7010.70 pCi/l Water U (Nat) 5.016.0 4.3310.58 pCi/l Water Bota 35i5 30.7io.6 pCi/l Water Sr-89 7.015.0 6.010.0 pCi/l Water Sr-90 7.0il.5 5.010.0 pCi/l r

Water Co-60 1015 11.7t0.6 pCi/1 Water Cs-134 5.015.0 3.66 1.15 pCi/l Water Cs-137 5.0 5.0 4.66 1.52 pC1/1 1

Water Alpha 6.015.0 5.3310.58 pCi/l Water Ra-226 8.6011.29 8.2710.11 pCi/l Water Ra-228 16.70i2.51 27.6613.13 pC1/1 Water Beta 18.0t5.0 18.3310.58 pCi/l Water Pu-239 10.111.0 11.010.6 pCi/l Water Alpha 15.015.0 8.3t2.8 pCi/l Water Beta 8.015.0 6.0i2.3 pCi/l

TABLE 3-2 Sheet 2 of 2 Eberline Sanele Type Ana' lysis EPA Value Value Units Air F11ter Alpha 15i5 1311 pCi/f11ter Air Filter Beta 4715 5315 pCi/ filter Air Filter Cs-137 1015 1914 pCi/ filter I

Milk I-131 9.016.0 5.7!2.1 pCi/1 Food Cs-137 20.015.0 23.312.5 pC1/kg Food K

1150 58 960t150 mg/kg f

I i

TABLE 3-3 Sheet 1 of 2 1986 QUALITY CONTROL ANALYSES

SUMMARY

i The table below summarizes results of samples run for process 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 laboratory and are available for inspection if required.

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

Cross Alpha 66 0

Cross Beta 69 0

J H-3 26 0

i U-234 27 0

Th-230 58 0

Ra-226 98 0

Pb-210 8

0 Sr-90 25 0

Pu-239 20 0

Am-241 5

0 4

Spiked Samples Nuclide Number of Within 2 Sigma Within 3 Sigma Differing From Analyzed Determs.

of Known of Known Known by >3 Sigma 1

Cross Alpha 66 66 j

Gross Beta 69 69 H-3 26 26 U-234 27 27 Th-230 58 58 Ra-226 98 98 Pb-210 8

8 Sr-90 25 25 Pu-239 20 20 Am-241 5

5 l

1

TABLE 3-3 Sheet 2 of 2 Split Samples Nuclide Number of No. Agreeing No. Agreeing No. Differing Analyzed Determs.

Within 2 Sigma Within 3 Sigma by >3 Sigma Cross Alpha 54 54 Cross Beta 59 59 H-3 26

^26 U-234 18 18 Th-230 37 37 Ra-226 78 78 Sr-90 13 13 Pu-239 3

3 Pb-210 7

7 m

i i

i I

4.0 RESULTS AND DISCUSSION 4.1 SAMPLES FROM THE TERRESTRIAL ENVIRONMENT 4.1.1 AIR PARTICULATES AND AIRBORNE I-131 I

The gross beta air particulate data obtained during 1986 were comparable to the data obtained during the years of 1982, 1983, 1984, 1985, and the I

preoperational period, except for the month of May samples.

Data from the samples collected at all seven sampling locations during the interval May 7 through June 3, 1986, were higher than previous values due to Chernobyl fallout radioactivity. Cross beta concentrations for air i

particulates for all other sampling periods in 1986 remained generally at low levels.

]

Average concentrations with their average standard deviations for the l

years 1986 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 1

levels from the October 1980 Chinese test and not from operation of the Trojan Nuclear Plant. The increased gross beta activity seen during the Chernobyl incident did not significantly affect the annual average values. However, it did contribute to the increase seen in the average standard deviation for the data.

Airborne I-131 concentration values for 1986 were below the detection l

limit of 0.05 pC1/m3 (at collection time) in all cases, except for the j

samples collected during the interval May 7 through 27, 1986.

4 For 1986, the measurement of gamma emitting radionuclides in quarterly i

composites of air particulate filters for each monitoring location did f

not show detectable activity above the detection limit of 0.05 pCi/m,

3 except for the second quarter coinposites.

I i

i 4-1

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

The accident at the Chernobyl Nuclear Station, Ukraine, USSR, resulted in large amounts of radioactivity, particularly radiocesiums and radio-iodines, being released into the atmosphere. Atmospheric dispersion brought this radioactivity into the Pacific Northwest during the month of May, res*41 ting in radioactivity being deposited into the environs sur-rounding the Trojan Nuclear Plant. The I-131 measured in the May samples, the increased gross beta activity, and the Cs-134 and Cs-137 measured in the second quarter particulate filters were the results of this Chernobyl fallout radioactivity, and not from the operation of the Trojan Nuclear Plant.

Data for these air monitoring samples are listed in Chapter 5, Tables 5-1, 5-3, and 5-4.

The air pat ticulate gross beta concentration data are plotted vs time throughout 1986 for each air monitoring station and are listed in Chapter 5. Table 5-2.

4.1.2 FOOD CROPS Samples of food crops (garden produce) were collected and analyzed for gamma emitters. The sample collections of these garden produce were made during the harvest months of June, July, and August 1986. Camma emitting radionuclides were not detected in the food crop samples, except for apples harvested in August. This sample showed Cs-137 just above the LLD level. This activity was attributed to the Chernobyl fallout radioactiv-ity which occurred over the Pacific Northwest in May 1986. The data are presented in Chapter 5, Table 5-5.

4.1.3 WELL WATER Well water samples were collected quarterly from three locations.

Tritium and gamma emitting radionuclide levels were below the sensitivity requirements of the program. The data are presented in Chapter 5, Table 5-6.

4-2

1 4.1.4 MILK Milk samples were collected from five locations, and were analyzed for I-131, and radiostrontium and gamma emitters. Most samples contained Sr-90, which is attributable to worldeide fallout due to atmospheric j

weapons tests.

During the months May through December, 38 of 64 milk samples contained detectable levels of radioactivity. The data for the i

samples collected in May and June were reported by telephone to tha Nuclear Regulatory Commission per Inspection Enforcement Information Notice No. 86-32.

4 Eighteen of the 38 samples with detectable activity contained levels of i

I-131, Cs-134, and/or Cu-137 at or exceeding the Trojan Technical j

Specification 3.12.1 Reporting Levels of 1 pCL/1 for iodine and 20 pC1/1 i

for cesiums. Tre radioactivity measured in milk samples were not the 1

1 result of Trojan effluent releases, but, rather, the result of northern i

hemisphere fallout contamination originating from the Chernobyl 4 nucicar plant accident in Russia. The following facts supported this conclusion:

4 (1) The reactor accident at Chernobyl, Russia released megacuries of radioactivity into the environment from April 26-May 10, 1986. This activity was detected, measured, and tracked throughout the northern hemisphere by numerous organizations.

(2) Radioactivity began being detected in air particulato and

[

lodino comptes collected the second week of May, and continued I

l to be detectablo above background icvols in these media f

throughout the month of May. The onset of this occurrenco

{

coincided with the arrival of the first Chernobyl plume over the pacific Northwest. Detectabic activity showed up in milk 1

samples one week later.

f (3) The radioactivity levels measured are comparable to those reported by the states of Oregon and Washington and Washington c

j Public power Supply, for sample locations distant from Trojan.

(

4-3 1

i l

~. - - -.

1 (4) Fallout of significant quantitles of radiocesium occurred in Northwest Oregon as the Chernobyl plumes passed over.

This radioactivity will remain in the environment for a long time to be detected in the grass to cow or goat to milk pathway.

The analysis of the May 19 milk samples for radiolodine showed unusual results.

The majority of the iodine did not carryover with the resin extraction but remained in the liquid mLik. The con-tractor laboratory investigated this anomaly. The likely cause was determined to be an ineffective batch of resir.. The resin was discarded and a new batch used for the next sample collections. The June 9 and 12 samples showed the iodine extracted with the resin.

The lack of detectable I-131 (except for that seen in May and June from Chernobyl fallout) and St-89 radioactivity in the milk samples shows that the detectable St-90 and Cs-137 are attributable to worldwide fallout rather than operational activity of the Trojan Nuclear Plant. The data are presented in Chapter 5. Table 5-7.

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 8.

Several of these measurement locations were established before the Plant became operational.

The mean and standard deviation for the quarterly dosimeters data has been calculated for the three geo-graphleal groups of Oregon, Washington, and Trojan onsite locations.

For 1986, the mean amblent dose rates were:

0.1210.03 mR/ day for the 14 Trojan onsite locations. 0.1410.03 mR/ day for the 20 Oregon locations, and 0.1210.02 mR/ day for the 23 Washington locations. These background 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 dLatance from Trojan:

the close ring (24 locations) at distances from 4-4

0.2 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 miles. The lo-mile ring serves as the control locations for the ambient radiation measurements. Each ring has at least one measurement location in each of the 16 directional sectors. The measurement mean and standard deviations were calculated to be 0.1310.03 mR/ day for all locations, with the close, 5-mile, and 10-mile rings being 0.1210.03 mR/ day, 0.1310.03 mR/ day, and 0.1310.02 mR/ day, respectively. These data indicate that the operational activities of the Trojan Nuclear Plant do not affect t'no ambient radiation levels around the Plant.

The ambient gamma radiation data in Table 5-8 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 1985 and before. The values were: 0.1310.02 mR/ day for the 16 north locations, 0.1110.01 mR/ day for the 9 east locations. 0.1410.03 mR/ day for the 12 south locations, and 0.1310.01 mR/ day for the 6 west locations.

Tables 5-9 through 5-12 present plots of the environmental dosimeter data for 1986. Ceparate plots are presented for those dosimeters within the Trojan Nuclear Plant exclusion area boundary and for increasing radial distance groupings from the Plant.

4.2 SAMPLES FROM T!IE AQUATIC ENVIRONMENT 4.2.1 DRINKING WATER SAMPLES Composited drinking water samples were collected from municipal water supply locations on the Columbia River that are downstream (Sample Location 2) and upstream (Sample Location 66) of the Trojan site.

The samples were analyzed monthly for gross beta activity, tritium, and gamma emit ters. The data are presented in Chapter 5, Table 5-13.

No activity which is attributable to operation of the Trojan Nuclear Plant was detected in any of the water sampics, 4-5

. - ~.. _

i A

l 4.2.2 SHORELINE SOIL Shoreline soil samples were collected from a location on the bank of the

)

l Columbia River near the Trojan site. Analyses were performed for gamma emitters. The data are presented in Chapter 5. Table 5-14.

None of the shoreline soil samples showed detectable levels of gamma emitters.

4.2.3 FISH l

Fish and crayfish were collected twice during the year and the fillets I

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

1evel of 0.1 pCi/s. The crayfish samples collected in August 1986 showed l

detectable Cs-134 and Cs-137 just at the LLD level. This activity was attributed to the Chernobyl fallout that occurred in May 1986 (coc Sections 4.1.1 and 4.1.4).

The octa are presented in Chapter 5, l

Table 5-15.

4.3

SUMMARY

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

each medium or pathway sampled for the 1986 Radiological Environmental

)

l Monitoring Program around the Trojan Nuclear Plant.

The format of I

Table 4-2 is that which is required by Trojan Technical Specification 6.9.1.5.2.

i 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 Technical Specification 3.12.1.

The milk samples that exceeded the 1

Reporting Levels were determined to be caused by Chernobyl fallout and not Trojan Plant operations (see Section 4,1.4).

1 For the gross beta analyses of the air particulate samples, the value for j

the location with the highest annual mean was not significantly different l

l from the the values for the control location or all locations.

j l

I j

4-6 I__..._..~._,

- _, _.. ~,

l For the milk samples, the only detectable radioactivity was due to the atmospheric weapons testing fallout radionuclides, Sr-90 and Cs-137 and to Chernobyl fallout radionuclides I-131, Cs-134, and Cs-137.

Also, the dairies with the highest measured values of Sr-90, Cs-134, and Cs-137 were goat dairies since the goat tends to concentrate radioactivity in the milk to a greater degree than does the cow.

For the ambient radiation measurements, the mean value for the control locations (10-mile ring) was not significantly different than the mean values for all locations or the close ring (see Section 4.1.5).

For the radioactivity measurements in drinking water, the annual mean for the gross beta determination was higher for the upstream (Columbia River) or control location (St. Helens) than it was for the downstream location (Rainier).

As is shown by Table 4-2, except for milk, most of the radioactivity measurements performed for the 1986 Trojan Nuclear Plant. Radiological Environmental Monitoring Program were at or below the level of detect-ability. There is no indication that the operations of the Trojan Nucicar Plant had a radiological impact on the environs around the Plant.

I I

4-7

TABLE 4-1 AVERAGE CROSS BETA CONCENTRATIONS FOR AIR PARTICULATES (Units:

10

• DCi/m*)

Troj an Oregon Washington (onsite)

(offsite)

(offsite)

Preop 212 212 312 1976 216 318 214 1977 314 414 52 1978 212 21 21 1979 111 11 11 1980 '

314 314 214 1981 11t2 1114 11t1 1982 215 217 216 1983 2i2 212 212 1984 22 212 212 1985 212 2i1 211 1986 3!7 316 317 i

l I

TABLE 4-2 Sheet 1 cf 2 RADIOLOGICAL E1VIRONMENTAL MONITORING PROGRAM

SUMMARY

Trojan Nuclear Plant, Columbia County, Oregon, Docket 50-344 Reporting Period: January 1-December 31, 1986 type and All Indicator Location With Highest Annual Mean Control Locations M:dium or Pathway Total Number Lower Limit Locations Name Number of Sampled (Unit of of Analyses of Detection Mean(f)[a]

Distance and Mean(f)[a]

Mean(f)[a] Reportable Me*surement)

. Performed (LLD)

Range Direction Range Range Events Air Particulates Cross 8 0.002 0.033(364/364)

II-North Site 0.033(52/52) 0.031(52/52) N/A[b]

Boundary 3

(pC1/m )

364 0.003-0.471 0.5 mi - South 0.004-0.471 0.003-0.399 I-131 0.05 0.12(20/364) 11B-Kalama 0.14(3/52) 0.13(3/52) 0 364 0.003-0.24 1.4 mi - SE 0.05-20 0.04-0.24 y-scan 0.05/nuc11de 0.08(7/28) 14-Longview 0.12(1/4) 0.05(1/4) 0 28 0.05-0.12 8.2 mi - NNW N/A-one NA-one sample sample Food Crops y-scan 0.02/nuclide <LLD

<LLD N/A[b]

o (pCi/g - wet) d Well Water Tritium 1000

<LLD

<LLD N/Alb) o (pCL/ liter) 12 y-scan 10/nuclide

<LLD

<LLD N/A[b]

o 12 Milk I-131 0.5 32.2(9/84) 17A-Kandle Diary 74.6(3/21) 3.3(1/21) 0 (pCl/ liter) 84 0.9-220 2.6-SSW 0.9-220 N/A - one sample Sr-89 1.0

<LLD

<LLD

<LLD N/A[b]

84 Sr-90 1.0 2.8(66/84) 17A-Kandle Dairy 3.6(17/21) 1.4(14/21)

N/A[b]

84 0.6-13.3 2.6 mi - SSW 0.9-13.3 0.7-3.4

TABLE 4-2 Sheet 2 of 2 Type and All Indicator Location With HlRhest Annual Mean Control Locations Mrdium or Pathway Total Number Lower Limit Locations Name Number of Sampled (Unit of of Analyses of Detection Mean(f)[a]

Distance and Mean(f)(al Nean(f)[a] Reportable

_ Measurement)

Performed

_ (LLD)

Range Direction Range Range Events y-scan, IO/nuclide 0

84 Cs-134 12(11/84) 17A-Kandle Dairy 16(3/21) 12(2/21) 0 8-19 2.6 mi - SSW 11-19 8-16 Cs-137 17(38/84) 63-Rinck Dairy 19(10/21) 21(5/21) 0 9-40 8.1 mi - WNW 9-39 8-32 Ambient Radiation Y-exposure 0.04 0.13(223/223) 1H-Plant Cooling 0.19(4/4) 0.13(62/62)

N/A(b)

(mR/ day) 223 0.06-0.22 Tower 0.17-0.22 0.08-0.18 0.2 mi - ESE Drinking Water Cross 8 0.5 2.6(23/24) 66-St. Helens 2.7(11/12) 2.7(11/12)

N/A[b]

l (pci/ liter) 24 1.1-6.6 (control) 1-5.9 1.1-5.9 10.5 mi - SSE Tritium 1000

<LLD

<LLD

<LLD 0

l 24 y-scan 10/nuclide

<LLD

<LLD

<LLD 0

+

l 24 l

Shoreline Soll y-scan 0.1/nuclide

<LLD

<LLD N/A[b]

N/A(b]

(pci/g - dry) 2 Fish / Invertebrates y-scan 0.1/nuclide 0.3(1/9)

N/AIDI N/A[b]

<LLD 0

(pC1/g - wet) 9 single sample (single sample)

(single at CR3 -

sample)

Columbia River l

(al Mean and range based upon detectable measurements only. The fraction of detectable measurements at specified locations j

is indicated in parentheses (f).

l

[b] N/A - Not applicable.

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 from the field with no moisture removed.

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 hr.

pCi/m A reporting unit used with air particulate and radio-iodine data which refers to the radioactivity content expressed in picoeuries of the volume 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.

Gamma Emitters Samples were analyzed by high resolution germanium gamma or spectrometry.

The resulting spectrum is analyzed by a Gamma Isotopic computer program 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.

i l

Error Terms Figures following "i" are error terms based on counting uncertainties at the 2o (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 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.

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

-finite data are given as footnotes.

5-2

TABLE 5-1 Sheet 1 of 8 AIRBORNE IODINE-131* AND CROSS BETA IN AIR PARTICULATE FILTERS (Weekly Collections)

Location IF*

Location II*

CD11cetion Volume Gross B I-131 Collection Volume Gross B I-131 3

3 3

3 3

3 Dato (m )

(pC1/m )

(pci/m )

Date (m )

(pci/m )

(pci/m )

01/07/86 325 0.036i0.003 01/07/86 330 0.036 0.003 01/14/86 285 0.021 0.003 01/14/86 285 0.01910.003 01/21/86 280 0.01010.003 01/21/86 280 0.008 0.003 01/28/86 285 0.019 0.003 01/28/86 285 0.014 0.003 02/04/86 285 0.00610.003 02/04/86 285 0.009io.003 02/11/86 285 0.017 0.003 02/11/86 285 0.017 0.003 02/18/86 285 0.02310.003 02/18/86 225 0.017 0.003 02/25/86 285 0.02210.003 02/25/86 285 0.00510.003 03/04/86 285 0.01710.003 03/04/86 285 0.015io.003 03/11/86 285 0.014io.003 03/11/86 285 0.010 0.003 03/18/86 290 0.01110.003 03/18/86 290 0.00910.003 03/25/86 285 0.010 0.003 03/25/86 285 0.009 0.003 04/01/86 285 0.014 0.003 04/01/86 285 0.017 0.003 04/08/86 285 0.00910.003 04/08/86 285 0.01010.003 04/15/86 285 0.01610.003 04/15/86 285 0.01410.003 04/22/86 280 0.00910.003 04/22/86 280 0.00810.003 04/29/86 285 0.00610.003 04/29/86 285 0.00710.003 05/06/86 285 0.009 0.003 05/06/86 285 0.01010.003 05/13/86 285 0.255i0.008 0.1910.01 05/13/86 285 0.26510.008 0.17 0.01 05/20/86 285 0.443io.010 0.1410.01 05/20/86 285 0.471t0.010 0.12 0.01 05/27/86 285 0.12510.006 0.04 0.01 05/27/86 285 0.141 0.006 0.04 0.01 06/03/86 285 0.06510.004 06/03/86 285 0.064 0.004 06/10/86 285 0.036!0.004 06/10/86 280 0.03710.004 06/17/86 290 0.02210.003 06/17/86 290 0.01810.003 06/24/86 240 0.00910.003 06/24/86 285 0.00710.003 07/01/86 285 0.009io.003 07/01/86 285 0.015io.003 07/08/86 285 0.009 0.003 07/08/86 285 0.007 0.003 07/15/86 285 0.00510.006 07/15/86 285 0.004 0.003 07/22/86 285 0.006 0.003 07/22/86 285 0.007 0.003 07/29/86 285 0.00610.003 07/29/86 285 C 005io.003 08/05/86 285 0.004 0.003 08/05/86 285 0.00610.003 08/12/86 285 0.010 0.003 08/12/86 285 0.01010.003 08/19/86 285 0.01210.003 08/19/86 290 0.009 0.003 08/26/86 285 0.01310.003 08/26/86 285 0.01210.003 09/02/86 285 0.010 0.003 09/02/86 285 0.01010.003 09/09/86 290 0.01410.003 09/09/86 290 0.02210.003 09/16/86 280 0.00710.003 09/16/86 280 0.01610.004 09/23/86 285 0.02010.004 09/23/86 285 0.022io.004 09/30/86 290 0.01310.003 09/30/86 285 0.011t0.003

• Iodine cartridge concentrations are <0.05 unless otherwise noted.

TABLE 5-1 Sheet 2 of 8 Location IF*

Location II*

Collection Volume Cross B I-131 Collection Volume Gross B I-131 3

3 3

3 3

Date (m )

(pci/m3)

(pci/m )

Date (m )

(pci/m )

(pci/m )

10/07/86 285 0.01610.003 10/07/86 285 0.01510.003 10/14/86 285 0.02210.004 10/14/86 285 0.014 0.003 10/21/86 280 0.04710.004 10/21/86 280 0.051io.004 10/28/86 280 0.06110.004 10/28/86 295 0.053 0.004 11/04/86 285 0.01410.004 11/04/86 285 0.011io.003 11/10/86 245 0.01410.004 11/10/86 245 0.01510.004 11/18/86 325 0.03310.003 11/18/86 325 0.02810.003 11/25/86 285 0.007io.003 11/25/86 285 0.007 0.003 12/02/86 255 0.01510.003 12/02/86 285 0.00910.003 12/09/86 285 0.029 0.003 12/09/86 285 0.027io.003 12/16/86 285 0.02610.003 12/16/86 290 0.02610.003 12/23/86 275 0.03410.004 12/23/86 285 0.02710.004 12/30/86 285 0.01110.003 12/30/86 285 0.01410.003

• Iodine cartridge concentrations are <0.05 unless otherwise noted.

TABLE 5-1 Sheet 3 of 8 Location 6B*

Location lib

• C211cetion Volume Cross B I-131 Collection Volume Gross B I-131 3

3 3

3 3

3 D'to (m )

(pci/m )

(pci/m )

Date (m )

(pci/m )

(pci/m )

01/07/86 330 0.03610.003 01/07/86 325 0.03310.003 01/14/86 285 0.022 0.003 01/14/86 280 0.02010.003 01/21/86 280 0.008 0.003 01/21/86 280 0.008 0.003 01/28/86 285 0.01310.003 01/28/86 285 0.00910.003 02/04/86 285 0.011 0.003 02/04/86 285 0.00710.003 02/11/86 285 0.01910.003 02/11/86 285 0.01510.003 02/18/86 285 0.01810.003 02/18/86 285 0.013 0.003 02/25/86 285 0.005io.003 02/25/86 285 0.005io.003 03/04/86 285 0.01510.003 03/04/86 285 0.01310.003 03/11/86 285 0.01310.003 03/11/86 285 0.01210.003 03/18/86 285 0.012 0.003 03/18/86 290 0.010 0.003 03/25/86 285 0.025t0.004 03/25/86 285 0.00810.003 04/01/86 285 0.008io.003 04/01/86 285 0.011 0.003 04/08/86 285 0.009 0.003 04/08/86 285 0.01010.003 04/15/86 285 0.01310.003 04/15/86 280 0.01610.003 04/22/86 280 0.009i0.003 04/22/86 280 0.008io.003 04/29/86 285 0.009 0.001 04/29/86 285 0.00610.003 05/06/86 285 0.00910.003 05/06/86 285 0.00910.003 05/13/86 285 0.25110.008 0.16io.01 05/13/86 285 0.292t0.008 0.20 0.01 05/20/86 285 0.38310.009

<0.05 05/20/86 285 0.451t0.010 0.1620.01 05/27/86 285 0.12710.006 0.03t0.01 05/27/86 290 0.149io.006 0.05io.01 06/03/86 285 0.066 0.005 06/03/86 285 0.071 0.005 06/10/86 285 0.034 0.005 06/10/86 280 0.037 0.004 06/17/86 290 0.017 0.003 06/17/86 290 0.01610.003 06/24/86 285 0.00810.003 06/24/86 285 0.008t0.003 07/01/86 285 0.00910.003 07/01/86 285 0.00810.003 07/08/86 285 0.00810.003 07/08/86 285 0.007 0.003 07/15/86 285 0.007 0.003 07/15/86 285 0.005 0.003 07/22/86 285 0.01510.003 07/22/86 285 0.01110.003 07/29/86 285 0.019 0.003 07/29/86 265 0.006io.003 l

l 08/05/86 285 0.015+0.003 08/05/86 285 0.004+0.003

~

08/12/86 285 0.006 0.003 08/12/86 285 0.011 0.003 08/19/86 290 0.012io.003 08/19/86 290 0.018io.003 l

08/26/86 285 0.01210.003 08/26/86 285 0.01310.003 l

09/02/86 285 0.009to.003 09/02/86 285 0.01110.003 l

09/09/86 290 0.01110.003 09/09/86 290 0.01210.003 l

09/16/86 285 0.011 0.003 09/16/86 265 0.00810.003 l

09/23/86 285 0.017to.003 09/23/86 270 0.032io.004 09/30/86 285 0.012io.003 09/30/86 255 0.013 0.003 10/07/86 285 0.01310.003 10/07/86 285 0.012io.003 10/14/86 285 0.024 0.004 10/14/86 285 0.016 0.003 10/21/86 280 0.05910.004 10/21/86 285 0.055io.004 10/28/86 295 0.079 0.005 10/28/86 290 0.060io.004

• Iodine cartridge concentrations arc <0.05 unless otherwise noted.

TABLE 5-1 Sheet 4 of 8 Location 6B*

Location lib

• Collection Volume Cross B I-131 Collection Volume Cross B I-131 3

3 3

3 3

3 Date (m )

(pci/m )

(oci/m )

Date (m )

(oci/m )

fpci/m )

11/04/86 285 0.014 0.003 11/04/86 285 0.011io.003 11/10/86 245 0.02210.004 11/10/86 245 0.01710.004 11/18/86 325 0.04110.004 11/18/86 325 0.03110.003 11/25/86 285 0.00710.003 11/25/86 285 0.006t0.003 12/02/86 285 0.010 0.003 12/02/86 285 0.010 0.003 12/09/86 285 0.035 0.004 12/09/86 285 0.03110.004 l

12/16/86 285 0.032io.004 12/16/86 285 0.03010.004 12/23/86 285 0.03210.004 12/23/86 285 0.03510.004 12/30/86 285 0.011 0.003 12/30/86 285 0.013 0.003

• Iodine cartridge concentrations are <0.05 unless otherwise noted.

l

TABLE 5-1 Sheet 5 of 8 Location 14*

Location 2*

Collection Volume Cross B I-131 Collection Volume Gross B I-131 3

3 3

3 3

3 Date (m )

(pci/m )

(pci/m )

Date (m )

(pci/m )

(pci/m )

01/07/86 325 0.044t0.004 01/07/86 330 0.040i0.003 01/14/86 285 0.016 0.003 01/14/86 285 0.025 0.003 01/21/86 280 0.00410.003 01/21/86 280 0.00810.003 01/28/86 285 0.01010.003 01/28/86 285 0.014 0.003 02/04/86 285 0.007 0.003 02/04/86 285 0.007to.003 02/11/86 285 0.021 0.003 02/11/86 285 0.01710.003 02/18/86 285 0.02010.003 02/18/86 285 0.02010.003 02/25/86 285 0.007io.003 02/25/86 285 0.00810.003 03/04/86 285 0.014 0.003 03/04/86 285 0.01410.003 03/11/86 285 0.018 0.003 03/11/86 285 0.018io.003 03/18/86 290 0.01210.003 03/18/86 290 0.011iO.003 03/25/86 285 0.010io.003 03/25/86 285 0.009iO.003 04/01/86 285 0.00910.003 04/01/86 285 0.00710.003 04/08/86 285 0.01010.003 04/08/86 285 0.008 0.003 04/15/86 280 0.016io.003 04/15/86 280 0.014 0.003 04/22/86 280 0.009 0.003 04/22/86 280 0.011io.003 04/29/86 265 0.004 0.002 04/29/26 280 0.00410.003 05/06/86 265 0.010 0.003 05/06/86 280 0.010 0.003 05/13/86 285 0.25910.008 0.19 0.01 05/13/86 285 0.25310.008 0.1910.01 05/20/86 285 0.43320.010 0.12!0.01 05/20/86 285 0.41410.010 0.11 0.01 05/27/86 290 0.137 0.006 0.05 0.01 05/27/86 275 0.141 0.006 0.05 0.01 06/03/86 285 0.063 0.004 06/03/86 285 0.065 0.005 06/10/86 280 0.040iO.004 06/10/86 280 0.03110.004 06/17/86 290 0.01710.003 06/17/86 290 0.02610.003 06/24/86 285 0.00910.003 06/24/86 285 0.010t0.003 07/01/86 285 0.02110.003 07/01/86 285 0.01110.003 07/08/86 285 0.00810.003 07/08/86 285 0.00910.003 07/15/86 285 0.004 0.003 07/15/86 285 0.005 0.001 07/22/86 285 0.006 0.003 07/22/86 285 0.00710.003 07/29/86 285 0.00510.003 07/29/86 285 0.01310.003 08/05/86 285 0.005 f.003 08/05/86 285 0.01010.003 08/12/86 285 0.0171t.003 08/12/86 285 0.01310.003 08/19/86 290 0.021iO.003 08/19/86 290 0.01010.003 08/26/86 285 0.01210.003 08/26/86 285 0.02510.003 09/02'86 285 0.01110.003 09/02/86 285 0.01410.003 09/09/t".

290 0.01310.003 09/09/86 290 0.01910.003 09/16/8s 280 0.00710.003 09/16/86 280 0.01210.003 09/23/86 285 0.01710.003 09/23/86 285 0.020 0.004 09/30/86 250 0.01310.003 09/30/86 285 0.01310.003 10/07/86 285 0.01010.003 10/07/86 285 0.011 0.003 10/14/86 285 0.016io.003 10/14/86 285 0.01710.003 10/21/86 285 0.05010.004 10/21/86 280 0.04410.004 10/28/86 290 0.055 0.004 10/28/86 290 0.057t0.004

• Iodine cartridge concentrations are <0.05 unless otherwise noted.

TABLE 5-1 Sheet 6 of 8 Location 14*

Location 2*

Collection Volume Gross B I-131 Collection Volume Cross B I-131 3

3 3

3 3

3 Date (m )

(pci/m )

(pci/m )

Date (m )

(pci/m )

(pci/m )

11/04/86 285 0.01110.003 11/04/86 285 0.012 0.003 11/10/86 195 0.016 0.004 11/10/86 245 0.017 0.004 11/18/86 325 0.030io.003 11/18/86 325 0.025 0.003 11/25/86 285 0.007 0.003 11/25/86 285 0.005 0.003 12/02/86 285 0.310io.003 12/02/86 285 0.01110.003 12/09/86 285 0.02810.003 12/09/86 285 0.029 0.003 12/16/86 285 0.02410.003 12/16/86 285 0.026t0.003 12/23/86 285 0.032 0.004 12/23/86 285 0.024 0.003 12/30/96 285 0.015to.003 12/30/86 285 0.00910.003 0 Iodine cartridge concentrations are <0.05 unless otherwise noted.

E

TABLE 5-1 Sheet 7 of 8 Location 19*

Collection Volume Gross B I-131 3

3 3

Date (m )

_(oci/m )

(pci/m )

01/07/86 325 0.03410.003 01/14/86 285 0.019 0.003 01/21/86 285 0.00910.003 01/28/86 285 0.01110.003 02/04/86 285 0.00910.003 02/11/86 285 0.019 0.003 02/18/86 285 0.017 0.003 02/25/86 285 0.00810.003 03/04/86 285 0.02310.003 03/11/86 285 0.016io.003 03/18/86 285 0.01210.003 03/25/86 285 0.010 0.003 04/01/86 285 0.01210.003 04/08/86 285 0.01210.003 04/15/86 285 0.013 0.003 04/22/86 280 0.010t0.003 04/29/86 285 0.005t0.003 05/06/86 285 0.011 0.003 05/13/86 290 0.24210.008 0.2410.01 05/20/86 285 0.399 0.010 0.1010.01 05/27/86 285 0.15310.006 0.0410.01 06/03/86 285 0.06510.005 06/10/86 285 0.04310.004 06/17/86 285 0.02010.003 06/24/86 285 0.011t0.003 07/01/86 285 0.01210.003 07/08/86 285 0.01210.003 07/15/86 285 0.00510.003 07/22/86 285 0.010 0.003 07/29/86 285 0.007io.003 08/05/86 285 0.00810.003 08/12/86 285 0.01610.003 08/19/86 285 0.01610.003 08/26/86 285 0.015 0.003 09/02/86 285 0.01410.003 09/09/86 285 0.00310.003 09/16/86 285 0.00910.003 09/23/86 285 0.017io.003 09/30/86 285 0.016io.003 10/07/86 285 0.01710.003 10/14/86 285 0.01710.003 10/21/86 285 0.04410.004 10/28/86 285 0.05010.004 o Iodine cartridge concentrations arc <0.05 unless otherwise noted.

TABLE 5-1 Sheet 8 of 8 Location 19*

Collection Volume Cross B I-131 3

3 3

Date (m )

_ foci /m )

(pci/m )

11/04/86 285 0.01110.003 11/10/86 245 0.015 0.004 11/18/86 325 0.02910.003 11/25/86 285 0.006 0.003 12/02/86 285 0.009 0.003 12/09/86 285 0.03110.003 12/16/86 285 0.026io.003 12/23/86 285 0.026 0.004 12/30/86 285 0.010io.003 4

O Iocine cartridge concentrations arc <0.05 unless otherwise noted.

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TABLE 5-3

SUMMARY

- GROSS BETA IN AIR SAMPLES pC1/m3 Average Maximum Minimum Trojan Onsite Stations IF 0.03210.069 0.443 0.004 II 0.033to.074 0.471 0.004 Oregon Stations 2

0.03210.066 0.414 0.004 6B 0.03210.063 0.383 0.005 19 0.03110.064 0.399 0.003 Washington Stations 11B 0.03310.074 0.451 0.004 14 0.032 0.069 0.433 0.004

TABLE 5-4 CAMMA EMITTERS CONCENTRATIONS IN AIR PARTICULATE FILTERS (Quarterly Composites) 3 Collection (pC1/m /nuclide)

Date IF II 6B 11B 1st Quarter

<0.05

<0.05

<0.05

<0.05 2nd Quarter Cs-134 0.0310.01 0.0410.01 0.0410.02 0.06 0.01 Cs-137 0.05 0.01 0.06 0.02 0.08io.02 0.0710.02 3rd Quarter

<0.05

<0.05

<0.05

<0.05 l

4th Quarter

<0.05

<0.05

<0.05

<0.05 1

3 Collection (pci/m /nuclide) l Date 14 2

19 1st Quarter

<0.05

<0.05

<0.05 l

2nd Quarter Cs-134 0.0410.02 0.03t0.01 0.02io.01 l

Cs-137 0.12iO.02 0.1110.01 0.0510.02 3rd Quarter

<0.05

<0.05

<0.05 4th Quarter

<0.05

<0.05

<0.05

TABLE 5-5 RADIOACTIVITY IN FOOD CROPS

[pci/g/nuclido (wet))

Location Il Sample Collection Type Date Camraa Emitters Lettuce [a]

06/20/86

<0.02 Onions 06/20/86

<0.02 Carrots 07/14/86

<0.02 Swiss Chard 07/14/86

<0.02 Lettuce 08/06/86

<0.02 Beets 08/06/86

<0.02 Blackberries 08/06/86

<0.02 Apples 08/20/86 Cs-137 0.02 0.01

[a] Split with State of Oregon.

TABLE 5-6 RADIOACTIVITY IN WELL WATER pC1/1 Collection Location IG Location 3 Location 6B Gamma Gamma Gamma Date Tritium Emitters Tritium Emitters Tritium Emitters 03/05/86

<1000

<10

<1000

<10

<1000

<10 06/11/86

<1000

<10

<1000

<10

<1000

<10 09/12/86

<1000

<10

<1000

<10

<1000

<10 12/10/86

<1000

<10

<1000

<10

<1000

<10 l

l

TABLE 5-7 Sheet 1 of 4 RADI0 ACTIVITY IN MILK pCi/l Collection Location 17A Date I-131 Sr-89 Sr-90 Nuclides y Emitters 01/06/86

<0.5

<1 6.811.3

<10 02/03/86

<0.6 *

<1 8.712.6

<10 03/03/86

<0.5

<1 1.510.5

<10 03/24/86

<0.5

<1 2.510.7

<10 04/07/86

<0.5

<1 4.Stl.2

<10 04/21/86

<0.5

<1 3.510.8

<10 05/05/86

<0.5

<1 2.310.8

<10 05/19/86

<0.5

<1 3.3il.0 I-131 220 10 Cs-134 1912 Cs-137 3514 06/09/86 3.010.1

<1 1.0io.5 Cs-134 1713 Cs-137 23 5 06/23/06 0.910.1

<1 1.9il.0 Cs-134 11 2 Cs-137 24t3 07/07/86

<0.5

<3[c]

2.7 1.5

<10 07/21/86

<0.5

<1 1.710.4

<10 08/04/86

<0.5

<1 0.910.7 Cs-137 13 3 II 08/18/86

<0.5

<1 4.6tl.0 Cs-137 14 3 09/08/86

<0.5

<1

<1

<10 I

09/22/86

<0.5

<1 1.610.7 Cs-137 1012 I

10/06/86

<0.5

<1 13.311.4 Cs-137 1214 I

10/20/86

<0.5

<1 0.910.A Cs-13 7 2114 11/03/86

<0.5

<1

<1 Cs-137 1413 11/17/86

<0.5

<1 3.111.0 Cs-137 1814 12/08/86

<0.5

<1 1.010.8 Cs-137 9!3

[a] Lower sensitivity due to lower volume of sample and decay.

[b] See Section 4.1.4 of this report.

[c] Due to low chemical recovery.

[d] All other gamma emitters <10.

TABLE 5-7 Sheet 2 of 4 pCi/1 Collection Location 19 Date I-131 Sr-89 Sr-90 Nuclides y Emitters 01/06/86

<0.5

<1 0.810.5

<10 02/03/86

<0.5

<1

<0.6

<10 03/03/86

<0.5

<1 0.610.5

<10 03/24/86

<0.5

<1

<1

<10 04/07/86

<0.5

<1 2.611.4

<10 04/21/86

<0.5

<1 0.710.5

<10 05/05/86

<0.5

<1

<1

<10 05/19/86 3.3+0.1

<1 1.4+1.1

<10 06/09/86

<0.5

<1 1.210.6 Cs-134 16!3 Cs-137 3213 2514(d]

06/23/86

<0.5

<1

<1 Cs-137 07/07/86

<0.5

<1 1.710.6

<10 07/21/86

<0.5

<1 0.7 0.4

<10 08/04/86

<0.5

<1 0.810.6

<10 08/18/86

<0.5

<1

<1 Cs-137 23!3 09/08/86

<0.5

<1

<1 Cs-134 814 Cs-137 1316 09/22/86

<0.5

<1 3.lt0.8

<10 1014(d]

10/06/86

<0.5

<1 3.410.8 Cs-137 10/20/86

<0.5

<1 0.610.4

<10 11/03/86

<0.5

<1

<1

<10 11/17/86

<0.S

<1 0.810.4

<10 12/08/86

<0.5

<1 0.8 0.4

<10 (d) All other gamma emitters <10.

TABLE 5-7 Sheet 3 of 4 pCi/l Collection Location 68 Date I-131 Sr-89 Sr-90 Nuclides y Emitters 01/06/86

<0.5

<1 1.8io.9

<10 02/03/86

<0.5

<1 0.7t0.6

<10 03/03/86

<0.5

<1 0.710.6

<10 03/24/86

<0.5

<1 2.010.6

<10 04/07/86

<0.5

<1 1.5t0.6

<10 04/21/86

<0.5

<1 1.810.6

<10 05/05/86

<0.5

<1

<1

<10 II 05/19/86

<0.5

<1 1.110.7 I-131 2814 Cs-134 1112 Cs-137 1712 06/09/86 (e]

<1 1.210.7 Cs-134 1012 Cs-137 17 3 06/12/86 0.910.1 (f]

[f]

Cs-137 24t3[d]

1513(d]

i 06/23/86

<0.5

<1

<1 Cs-137 07/07/86

<0.5

<1 4.Stl.0

<10 813[d]

07/21/86

<0.5

<1 2.3 0.5 Cs-137 8t3(d]

08/04/86

<0.5

<1 1.610.6 Cs-137 II 08/18/86

<0.5

<1 6.9 1.1 Cs-137 1013 09/08/86

<0.5

<1 3t1 Cs-134 2418 Cs-137 40 7 09/22/86

<0.5

<1 4.710.7 Cs-137 912 10/06/86

<0.5

<1 8.210.7

<10 10/20/86

<0.5

<1

<1

<10 11/03/86

<0.5

<1

<1

<10 11/17/86

<0.5

<1 0.810.6 Cs-137 10 3[d]

12/08/86

<0.5

<1

<1

<10 (b) See Section 4.1.4 of this report.

(d) All other gamma emitters <10.

[e] Resin lost in transit, replacements collected 06/12/86.

(f) Same as 06/09/86 replacements were analyzed for I-131, gamma only.

l l

l TABLE 5-7 Sheet 4 of 4 0C1/1 Collection Location 63 Date I-131 Sr-89 Sr-90 Buclides Y Emitters 01/06/86

<0.5

<1 1.0 0.6

<10 02/03/86

<0.6 *I

<1 4.811.2

<10 I

03/03/86

<0,5

<1 2.010.7

<10 I

03/24/86

<0.5

<3 7.0 0.8

<10 04/07/86

<0.5

<1 1.3 1.0

<10 j

04/21/86

<0.5

<1 2.411.1

<10 05/05/86

<0.5

<1 2.310.9

<10 I

05/19/86 4.010.1

<1 2.610.6 I-131 20iS Cs-137 912 06/09/86 (e]

<1 4.011.0 Cs-134 1112 Cs-137 2f,t4 06/12/86 12.4 0.6 (f]

[f]

[f]

06/23/86 1.510.1

<1 4.011.0 Cs-134 12 2 Cs-137 2713 07/07/86

<0.5

<1 6.711.2 Cs-134 813 Cs-137 2414 07/21/86

<0.5

<2 3.9 1.2 Cs-134 1112 Cs-137 39i3 08/04/86

<0.5

<1 2.910.8 Cs-137 1313 I

08/18/86

<0.5

<1

<1 Cs-137 11 3 814[d]

09/08/86

<0.5

<1

<1 Cs-137 09/22/86

<0.5

<1 3.910.9

<10 10/06/86

<0.5

<1 5.6 1.0

<10 10/20/86

<0.5

<1 0.810.4 Cs-137 10 3[d]

11/03/86

<0.5

<1 1.110.7

<10 2414(d]

11/17/86

<0.5

<1 2.610.6 Cs-137 12/08/86

<0.5

<1 3.010.6

<10 (a) Lower sensitivity due to lower volume of sample and decay.

[b] See Section 4.1.4 of this report.

[c] Due to low chemical recovery.

[d] All other gamma emitters <10.

[e] Resin lost in transit, replacements collected 06/12/86.

[f] Same as 06/09/86 replacements were analyzed for I-131 only.

TABLE 5-8 Sheet 1 of 2 AMBIENT GAMMA RADIATION LEVELS FOR 1986 mR/ Day (Mean Daily Exposure 12o Error)

First Quarter Second Quarter Third Quarter Fourth Quarter Site 02/12/86-05/14/86 05/14/86-08/06/86 08/06/86-11/12/86 11/12/86-02/11/87 1A O.1010.02 0.10 0.02 0.1010.02 0.10 0.02 IB 0.1110.02 0.11 0.03 0.1010.02 0.1010.03 1c 0.13 0.03 0.1210.03 0.12 0.02 0.11 0.03 1E 0.1010.02 0.1010.02 0.09 p.02 0.0910.02 IF 0.1310.03 0.12 0.03 0.1210.03 0.12 0.03 1H 0.20iO.04 0.2210.06 O.17 0.04 0.1810.05 II 0.1110.02 0.11io.03 0.10 0.02 0.12 p.03 IJ 0.1010.02 0.10t0.02 0.11io.02 0.1010.02 2

0.16 0.03 0.15 0.04 0.16 0.03 0.15 0.04 3

0.14io.03 0.14 0.04 0.14 0.03 0.14 p.04 Ac 0.13 0.03 0.12 0.03 0.12 0.03 0.12+0.03 6B 0.11t0.02 0.1110.03 0.1110.02 0.1010.02 11A 0.1010.02 0.11io.02 0.1010.02 20 0.10 0.02 0.10 0.02 0.09 0.02 0.10io.02 21 0.0910.02 0.0910.02 0.08 0.02 0.08io.02 l

22 0.10 0.02 0.10 0.02 0.09t0.02 0.1010.02 23 0.11 0.02 0.11 p.03 0.10 0.02 0.10 0.02 24 0.15io.03 0.16 0.04 0.15 0.03 0.14 0.04 25 0.12 p.03 0.11 0.03 0.11to.02 0.11to.03 26 0.15 p.03 0.1619 04 0.15 0.03 0.15i0.04 27 0.1619 04 0.17 0.04 0.17 0.04 0.16t0.04 28 0.16 0.04 0.15 0.04 0.15 0.03 0.14 0.04 29 0.1710.04 0.17 0.04 0.17 0.04 0.18 0.05 30 0.1410.03 0.16 0.04 0.17tp.04 0.1510.04 31 0.14 0.03 0.15 0.04 0.16 0.03 0.14 0.05 32 0.12t0.02 0.13 p.03 0.13t0.03 0.11t0.04 33 0.13 p.03 0.14 0.04 0.15 0.03 0.12to.04 34 0.13io.03 0.13 0.04 0.15io.03 0.13 0.05 L

• Dosimeter vandalized during field exposure.

TABLE 5-8 Sheet 2 of 2 First Quarter Second Quarter Third Quarter Fourth Quarter Site 02/12/86-05/14/86 05/14/86-08/06/86 08/06/86-11/12/86 11/12/86-02/11/87 35 0.11 p.02 0.13 p.03 0.13 0.03 0.11 0.04 36 0.12 0.03 0.13 0.04 0.13 p.03 0.11 0.04 37 0.13 0.03 0.15 0.04 0.15 0.03 0.12 0.04 38 0.12 0.02 0.12 p.03 0.12 p.03 0.11 0.04 39 0.1510.03 0.15to.04 0.16 0.03 0.14io.05 40 0.11 0.02 0.12 0.03 0.12 0.03 0.10 0.04 41 0.12 0.02 0.13to.04 0.14 0.03 0.11 0.04 42 0.11 0.02 0.11 p.03 0.12 p.03 0.10 0.04 43 0.12 0.03 0.13 0.04 0.13 0.03 0.11 0.04 44 0.13 0.03 0.14 0.04 0.14 0.03 0.15 0.05 45 0.12io.02 0.13 p.04 0.14 0.03 46 0.11to.02 0.12 0.03 0.12 0.03 0.10 0.04 47 0.12 p.02 0.12 p.03 0.13 0.03 0.1110.04 48 0.1210.02 0.12 p.03 0.12 0.03 0.11 0.04 49 0.0910.02 0.10io.03 0.11 0.02 0.0810.03 50 0.10 0.02 0.11 p.03 0.11 0.02 0.10 0.03 51 0.11 0.02 0.13 0.03 0.13 0.03 0.11 0.04 52 0.1010.02 0.10iO.03 0.1019 02 53 0.10 0.02 0.11to.03 0.12 0.03 0.10io.04 54 0.16 0.02 0.17 0.04 0.17 0.04 0.14 0.05 55 0.10 9 02 0.11 0.03 0.11 p.02 0.11 0.04 56 0.07to.01 0.06to.02 0.07 0.02 0.07 0.02 57 0.13 0.03 0.13 0.03 0.14 0.03 0.12 0.04 58 0.14 0.03 0.14 0.04 0.15 0.03 0.12io.04 59 0.10 0.02 0.10to.03 0.11 0.02 60 0.10 0.02 0.11 0.03 0.12 0.03 0.10 0.03 61 0.14 0.03 0.15io.04 0.15 0.03 0.13io.05 62 0.0710.01 0.0710.02 0.0610.02 64 0.11 p.02 0.1110.03 0.11 0.02 0.10io.03

• Dosimeter vandalized during field exposure.

i

TROJAN NUCLEAR PLANT-1986 AMullt1I ENVIRONMLt1TAL LXPOSURLS TLD LOCAflONS WITHIN PLANT EXCLUSION AREA UOUtlDARY 0.25-o 0

0.20 ~

1 2

+

n'a o

Y O

S 0.15' O

a.

N L't O

g n

O 6

A 4

z 3

O

+

0 A

D L

2 0.10 L2 A

La a

e m

o A

4 A

A O

a A

0.0 $ -.) _ _ _ _ _ 7 7

3. _. _. r 1-- - --- I

' i

- -~ ~l i

i T

1A 18 1C ll if IH 11 IJ 20 21 22 2.5 24 64 FikST CUARTER - LCilAkts 1LD LOCATIOt1 iluMBU:

TillRD OUARTER - TRIAtlGLES FOURTH OUARTER - STARS trc0His cu,,wTER - DIA1A0Nbt

TABLE 5-10 TROJAN NUCLEAR PLANT 1936 AMU!ENT LNVIRONMEtlTAL EXPOSURES TLD LOCATIONS BETWEEN PLANT EXCLUSION AREA BOUNDARY AND 2.5 MILE RADIUS 0.25-0.20-3 Ed 5

S 0.15-A a

o h

Q O

u b

U

+

ao a

a A

z n

n A

0

i 0.10-4 m

a m

CJ 4

0.06.,

__7

) _.

d 4C 60 11A 25 58 69 60 61 62

1 4

-j m

o 1-o a

4 n

e e

U d-c.

-y j@

m

>= l

'u$

r WW

-3gj 4 8 z o 1

oz ou l

so C

+

BO I

g c

a

-t

=

.o<

=

MW L **

1 ud

+

o a x2 DAo 2

Hod i

J Z3o e

a 4

-4 a

x t

4 3

jwZ o

a<

-z 1

4e

% EEd i

z i <u-e a

4

_ e op

. e Wsz i

Jz a

oc5

- w 4.m a2

{

o a

0-i- $ Z 5Z a

+

L Mm a zu a

1 w

Zw

,4 ; 3:

l G $ w" n

a

+

i ps z 4 0 i

op 4

a I

~o

.a Q

72 t

J t

~

a a

+

- :o do 1

i i

i 3

a$

4 l-l' o

o

+

a

-Q

• l b w

un l

MM i

42 4

<o i

l 0

4 4

- N 5@

Ho Oy 3w w 01 o

a

.a 4,

i i

i i

n o

a o

n N

D R

M 0,

o o

o o

o W38MTW 3MOSOdX3 filVG NV3W

TABLE 5-12 TROJAN NUCLEAR PLANT 1986 AMulEtti LNVIRONMENTAL MOillTORiflG TLD LOCATIONS BETWEEN PLANT 5.0 AND 10.0 MILE RADll 0.25-0.20-1 m'

+

a y

a a

a a

r wm 3 0.15--

0

^

^

U o

Q.

W O

A A

O u

O a

O O

a 0

o a

CI o

+

4 0

r1 O

D A

z m

+

+

+

a e

o a

0.10 ~

0 4

0.05 i i

r~-

r'---~ --- r r

r-

--- - r r

i -

-r i

2/

29 31

.s3 ab 3/

a9 41 43 45 47 49 51 53 55 S7 e m

TABLE 5-13 RADI0 ACTIVITY IN DRINKING WATER Location 2 - Rainier Municipal Water Supply Location 66 - St. Helens' Municipal Water Supply pCi/1 pC1/1 camma canuna Collection Dates Cross Beta Tritium Emitters Collection Dates Cross Beta Tritium Emitters 01/06/86-02/03/86 2.110.8

<1000

<10 01/06/86-02/03/86 3.610.9

<1000

.<10 02/03/86-03/03/86 1.110.7

<1000

<10 02/03/86-03/03/86

<0.6

<1000

<10 03/03/86-04/07/86 2.910.8

<1000

<10 03/03/86-04/07/86 1.910.8

<1000

<10 04/07/86-05/05/86 2.411.1

<1000

<10 04/07/86-05/05/86 2.410.8

<1000

<10 05/05/86-06/02/86 2.010.8

<1000

<10 05/05)86-06/02/86 1.710.8

<1000

<10 06/02/86-07/07/86 2.011.2

<1000

<10 06/02/86-07/07/86 2.110.8

<1000

<10 07/07/86-08/04/86 1.010.8

<1000

<10 07/07/86-08/04/86 2.610.8

<1000

<10 08/04/86-09/08/86 6.611.2

<1000

<10 08/04/86-09/08/86 1.410.8

<1000

<10 09/08/86-10/06/86 1.410.8

<1000

<10 09/08/86-10/06/86 1.110.8

<1000

<10 10/06/86-11/03/86 3.811.2

<1000

<10 10/06/86-11/03/86 S.911.3

<1000

<10 11/03/86-12/01/86 2.411.1

<1000

<10 11/03/86-12/01/86 2.911.2

<1000

<10 12/01/86-01/05/87 2.711.1

<1000

<10 12/01/86-01/05/87 4.211.1

<1000

<10

= _ _ _ _

TABLE 5-14 RADIOACTIVITY.IN SHORELINE SOIL pCi/g/nuclide (dry)

Location CR3 Collection Ganma Date Emitters 03/16/86

<0.1 09/17/86

<0.1 i

i l

1 I

i I

r.

TABLE 5-15 RADIOACTIVITY IN FISH / INVERTEBRATES pCi/g/nuclide (wet)

Collection Location Date Species Camma Emitters CH3 03/12/86 Rainbow Trout (Steelhead) *

<0.1 1A 03/14/86 Northern Squawfish (16)

<0.1 and Suckers (2) 1D 03/14/86 Bluegills (4) and Carp (4)

<0.1

.,CR3 08/06/86 Crayfish Cs-134 0.210.1 Cs-137 0.3 0.1 CR3 09/05/86 Coho Salmon

<0.1 Rainbow Trout (Steelhead)I"I

<0.1 1A 09/19/86 Sunfish (1), Carp (1),

<0.1 Bullhead (4), Northern Squawfish (8) 1D 09/18/86 Perch (1),

<0.1 Northern Squawfish (4)

CR3 10/03/86 Crayfish

<0.1

[a] Split sample with State of Oreson.

.I r

M M

RE NUMM David W. Cockfield Vice President, Nuclear April 30, 1987 Trojan Nuclear Plant Docket 50-344 License NPF-1 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington DC 20555

Dear Sir:

Radiological Environmental Monitoring Report Enclosed is one copy of the Portland Conoral Electric Company's 1986 Operational Environmental Radiological Surveillance Program Annual Report, PGE-1006-86, for the Trojan Nucicar Plant.

Sincerely,

{

e Enclosure c: Mr John B. Martin (2 enclosures)

Mr. Ray D. Paris, Manager (2 enclosures)

Regional Administrator, Region V Radiation Control Section U.S. Nuclear Regulatory Commission Oregon State Health Division Mr. Coorge Knighton Mr. Jerry Leitch l

Director, PWR-A Radiation Representative l

Project Directorate No. V U.S. Environmental Protection Agency l

l Mr. David Kish, Director Mr. Robert R. Mooney, Supervisor l

State of Oregon Radiation Control Section Department of Energy Washington Social and Health Services Mr. R. C. Barr NRC Resident Inspector Trojan Nuclear Plant 9h i

121 SW Sa mon Ercet. Poor'd Cro pn 97204 i

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