ML20034B911

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Operational Environ Radiological Surveillance Program 1989 Annual Rept
ML20034B911
Person / Time
Site: Trojan File:Portland General Electric icon.png
Issue date: 12/31/1989
From: Walt T
PORTLAND GENERAL ELECTRIC CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
POGE-1006-89, NUDOCS 9005010155
Download: ML20034B911 (68)
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PDf0ENict Getierd Bectric Ocmpiairy -

April 30,11990 Trojan Nuclear Plant.

Docket 50-344 License NPF-1' U.S. Nuclear Regulatory Commission

-ATTN:

Document Control. Desk Washinr, ton DC 20555 i

Dear Sir:

Radiological Environmental Monitorina Report Enclosed is one copy of the Portland General' Electric Company's 1989 Operational Environmental Radiological' Surveillance Program Annual Report,.

PGE-1006-89, for the Trojan Nuclear Plant.

'I Sincerely, i

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T. D... Walt, Acting Vice President,' Nuclear

' i Enclosure i

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Mr. John B. Martin

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

Regional Administrator, Region V^

Radiation Control'Section U.S. Nuclear Regulatory Commission: "(Oregon State Health Division 1

Mr. George Knighton Mr. Jerry Leitch)

J Director, PWR-A Radiation-Representative Project Directorate No. V U.S. Environmental' Protection Agency l

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Mr. David Stewart-Smith Mr. Robert R. Mooney. Supervisor.

Staf.e of Oregon Radiation Control Section-Department of Energy Washingt.on Social'and Health Services Mr. R. C. Bare l

NRC Resident Inspector

-1 Trojan Nuclear Plant I

-[Mh 9005010155 891231 PDR ADOCK 05000344 R

PDC i21 S.W Salmon Street. Portand, Oregon 97204 -

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i OPERATIONAL ENVIRONMENTAL RADIOLOGICAL:

SURVEILLANCE PROGRAM 1989 ANNU.AL REPORT l-PORTLAND GENERAL ELECTRIC COMPANY-

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PGE-1006 89 l

I TROJAN NUCLEAR PLANT.

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OPERATIONAL FNVIRONMENTAL RADIOLOCICAL SURVEILLANCE PROGRAM I

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May 1990 t

Prepared by-PORTLAND GENERAL ELECTRIC CdMPANY-With Analyses by j

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ALBUQUERQUE, NEW MEXICO

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TROJAN NUCLEAR-FLANT-OPERATIONAL ENVIRONMENTAL RADIOLOGICAL f

SURVEILLANCE PROGRAM' CONTENTS e

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Section.

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'. ABSTRACT.

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1.0-INTRODUCTION'.

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-2.0 SAMPLING AND PROGRAM PROCEDURES.

iI 2 2.1 SAMPLING LOCATIONS i

t 2.2, SAMPl.1NG PROCEDURES.

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2.2.1 Ain' Particulate and'Radioiodino..

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j g 2.2.2 Anhiont Radiation Measurements' Using; TLDs.

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2.2.3 Food Crops..

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=2-2 2.2.4 Milk.

2.2.5

.Well Water.

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' Drinking Water.

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2.2.7 Shoreline Soll.

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2.2.8 Aquatic Animal.

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2.3 YEARLY AGRICULTURAL' SURVEY WITHIN 3-MILE RADIUS OF TROJAN.

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3.0 ANALY11 CAL PROCEDURES AND COUNTING METHODS. 1

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3.1 ANALYTICAL DETECTION LIMITS AND COUNT-RATE ERRORS.

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l 3.2 AIR PARTICULATES.

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$.3 RADIOIODINE.

3-2' 3,4 DRINKING AND WELL WATER.

3-2' 3.5 SHORELINE SOIL.

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i 3.6 FISH, INVERTEPRATES, AND FOOD CROPS.

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3.7 MILK.

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l 3.8 AMBl;.NT RADIATION MEASUREMENTS.

3-3 3-3 3.9 QUALITY CONTRT.,

3.10 REFERENCES FOR ANALYTICAL PROCEDURES.

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OPERATIONAL ENVIRONMENTAL RADIOLOGICAL g-SURVE1LLANCE PROGRAM CONTENTS-Title Parse Section

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4.0 RESULTS AND' DISCUSSION.

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4.1 SAMPLES FROM T"*. TERRESTRIAD-ENVIRONMENT.

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4.1.1 Air Particuletes and Airborne I-131'.

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4-1 4.1.2 Food Crops.

4.1.3 Well Water.

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.4-2' 4.1.5 Ambient Ihdintion Levels..

4.2 SAMI'LES FROM THE AQUATIC'ENV WsNMENT.

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4.2.1 Drir: king Water Sanples 4-3' B-4.2.2 Shoreline Soil-4-4' 4-4 4.2.3 Fish.

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SUMMARY

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5.0 COMMENTS ON AND TERMS l' SED IN. DATA ' TABLES.

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OPERATIONAL ENVIRONMENTAL > RADIOLOGICAL'

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. SURVEILLANCE PROGEAM-.

TABLES-Humber Title sg

2. l Sn.mpling Locations and Frequency by Type

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.3 2-2 s1989 Land Use census

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2-3 Dsiry Animals --Coats-0 2-4 Vegetable Gardens

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O 31 Program Analyses and Reported Detection; Levels'

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32 1989 U. S. Environmental Protection Agency

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Laboratory Intercomparison Program-j 3-3 1989 Quality contro1, Analyses Summary.

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4-1 Average Gross Beta Concentrations for Air Particulates.

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A-2 Average Ambient Gamma Radiation levels:

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4-3 Average Gross Beta Concentration's-for Drinking Water from Columbia River a

4-4 Radiological Environmental Monitoring Program Summary

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5-1 Airborne Iodine-131 and Gross Meta in Air. Particulate Filters:

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4 5-2 Summary - Gross Beta in. Air Samples

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5-3 Gamma Emitters Concentrations in' Air Particulates Filteis' 5-4 Radioactivity in Food Crops 4

S--S Radioactivity in Well Water j

i 5-6 Radioactivity in Milk 5-7 Actient Camma Radiation Levels for 1989-T 1

5-8 Radioactivity in Drinking Water 5-9 Radioactivity in Shoreline Soil 5-10 Radioactivity in Fish / Invertebrates s

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2-2 Sampling Locations (Detail)

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l ABSTRACT This report presents the data obtained through the analyses of environ mental samples collected through the Portland General Electric Trojat.

Nuclear Plant Environmental Radiological Surveillance Program for the period January 1, 1909 through December 31, 1989.

In several milk samples, levt : ; of radioactivity observed during 1989 were higher than years prior to 1986.

This higher level of radio-activity was due to biota uptake of fallout radioactivity dispersed over Oregon from the April 1986 accident at the Chernobyl Nuclear Power Station in tht Ukrairn, USSR.

In e T case did radioactivity attrib.ted to the Trojan Nuclea: ant exceed the Reporting Leve:Lu of the Trojan Radiologi cal lechnical Speci fica'. ions. "l 9 a nh L Hk p 1 l>j (s.; ' [ ' }, ' 7.N[J,., . dj% ( g - ^-}^, -[..]@((]{ i a r

1.0 INTIiODUCTION The Trojan Nuclear Plant, a 1130 megawatt-electric pressurized water reactor, first achieved criticality on December 15, 1975. This report presents the analytical data f rom the Environmental Radir.. leal Surveillance Program wit.h appr' priate inte,.tation for 1989. 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 t.aken to ensure that differences in procedures between the several contractors are considered This ir parti:ularly true for " gross bet " measurements for which the urc of different reference nuclides may produce appropriately significant di f fi.t enc ( in gross beta concentrations. Information concerning the Environmental Radiological Surveillance Program prior to this period may be found in earlier reports. F !ll 1 1-1 kh * .kh [. h [-

Q* ql: V 2.0 : SAMPLING AND PROGRAM PROCEDURES' 2 l' -- SAMPLING LOCATIO_N_S sixty-seven (67) sampling locations were used inL he Environmental t Radiological Surveillance Program in 1989, 66 on land, and 1-in the Cclumbia River. This is thefsame number of sampling =1ocations in use!at the end of 1988. During'1989, there were no new sample locations added-or any-1988 sample locations deleted -k 4 .i The sampling locations are shown in Figuresj 2-1. and 2-2!- Table 2-1, 'l n . includes ii list ing-of the sites, their dist mee from Trojan, and the' type: and frequency of-sample collection.- 4 2.2 ~ SAMPLING PROCEDURES-2.2.1 AIR PARTICULATE AND,RADI0 IODINE. L Air particulate and radi iodine sampling'was perfcrmeo Meekly.. ' Th'e j. samples were gathered with a low-volume air sampling device which isi 1 designed to draw a constant flow-rate regnedless ofilthe pressure! drop; ~ '/,, i ~ scross the'f11ter. The samplina devices werejset to maintain:1-cfm.:;The= g sv.nple pump, metering' devices. and timer were in a weatherproof houdng. The f11ter and cartridge were located. in anLinlet; paeallel _ to. and about I met.er above the ' ground. Glass fiber f11ters wero used to collect i particulate matter. Activated charcoal cartridges were used:to ? collect a 1 1 radiciodine. L { The glass fiber filter was removed from the ' air saiapler and placed in a j j f 2-inch plastic petri dish. The activated. charcoal / cartridge:was' removed at the sarr.e time. Air flow-readings and other datia required to compute. i the levels. of radioactivity were recorded and submitted to!the ' ns. lysis a laboratory along with the saatples. s i F 1, o l f.' 1 I 'L i 2

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i '2.2.2 AMBIENT RADIATION MEASUREMENTS USING TLDs Thermoluminescent dosimeters-(TLDs) were placed for field exposure and g collected on a quarterly frequoney. The. TLDs.were placed about I ractet 5 above' ground Icvol in plastic containers. The time o'f collection, tht;= 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

q collection and delivery to the laboratory.
The TLDs were transported to the field in shielded boxes to ensure low background levels.

Control g TLDs were carried-with the field TLDs-during collection ar.d delivery, W 2.2.3 FOOD CRolt

i Representative cumples of tuberous and foliar fruits and vegetables-were.

collected durin: local ;cvosting. Samples of leafy vegotables were collected during e.1ch of he three summer months of June, July, and August. Samp1cc wer? ceCea in plastic bags following collect'_hn, taking j care not to it. lude any soil or foreign material. The. sample site identification number. the date collected, the sample type, and the W j a.w.. t obtained were recorded on the data-collection forms, 2.2.4 MILK IL Milk samples (cow or goat) were collected monthly during January, February, and December with collections every;two weeks during the.other l months. Milh was collected in polyethylene bottles (2 gallons for-cow l J dairy and 1 gallon for goat dairy). Prior to shipment of samples to the i analysis laboratory, an ion exchange resin was used to concentrate any iodine present to ivnore detection sensitivity. The whole slik'(after iodine removal) and resins were labeled and coll' ctiorf data forms : a prepared specifying sample site, date collected, sample type, and volume a obtained. l g. 2-2 8

2.2.5 WELL WATER Well water was collected quarterly either from'the tap that leads.'off thec 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 sampic type. 2.2.6 DRINKING WA'IER Four-week composite sampics of municipal drinking water were collected for Rainier (Sample Location :) 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 hours and aliquots of _ this four-week composite were sent for analysis.. From thesci aliquots, 60 milliliters are sent for tritium analysis and.a 1-gallon polyethylene bottle is acidified with concentrated hcl and sent for tho-1 i other analyses. The bottles were securely. sealed, labeled, and. collection data forms prepared s,pecifying site, date collected,__ volume, and sampic type. l 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. vegetation and large rocks removed befora sample collection. The-soil sampling depth 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 sito identification number, date collected, and' volume obtained were recorded on the collet Mon data forms, t 2-3 -i

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-muscle samples, if needed for a-- particular sampling.-location,'the fish' muscle sample may be.a: mixture of-several panfish. species. The sample site l identification number, the date collected, the fish species, and the amount obtained were' recorded on-collection data forms, s 2.3 YEAl(LY' LAND USE CENSUS WITHIN 5-MILE RADIUS OF TROJAN ~ The annual land use census within a 5-mile' radius of Trojan Nuclear Plant \\ 2 was performed during August 1989. Identified by this cen.;as were the: 3 locat. ions of the nearcot residence as well.as locations within the 5-milo-radius for milk-animals (cow and goat), meat animals.;and vegetable gardenc in each of the 16 meteorological sectors. This censuc was completed by driving the roads within n'.5-mile radius of. Trojan. Table 2-2 presents the nearest locations for these activities in' the 16 sectors. Table 2-3 presents the locations for all=the dairy goats g< (there were no dairy cows) within the 5-mile radius. Table 2-4' presents' = the locations for all the vegetable gardens within the.5 mile radius.' ~ An evaluation of the previous sampling ' locations has shown that the-previous locations are appropriate, and no changes were made in the l sampling locations as a result of the 1989 land use census. 7 4 -Il Il 2-4 1

i. m m-u - l TABLE 2-1 SheQt 1 of 6 SAMPLING LOCATIONS AND FREQUENCY BY TYPE Terrestrial Avluatic Radial Air Air Well Drink Shore Sample Location Mi_learpe Direction Partic' 1-131' TLD' Veg Milk' Water Water Soil Anim ONSITE 1A - U. ' S. 30 & E-W Road 0.8 NW O 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 l' S/A ID - Recreation Lake 0.7 S 1E - S site boundary. 0.8 S Q U. S. 30 at Railroad (RM) IF - Meteorology tower 0.5 S W W Q IG - S of Containment 0.1 SSE Q 1H - Plant cooling tower O.2 ESE Q II - N sit'e boundary at 0.5' NNW W .W Q IIT Co}umbia River ~1J - RR & E-W road to 0.6f NNW; Q. Prescott'- 20 - S:of Plant on 0.4 -SSE Q -Columbia River shore I h NOTE: 'LegenJ'at bottom of Page 6 of.6 of Table 2-J. .. i . _ _ _ _.. _.. _... _ _ ~ _ _.. _ _ _ __.n_._

' TABLE 2-1 Sheet 2 of 6 l Terres_ trial A<uatic' ~ Radial __ Air Air Well Drink Shore Sample Location tileaze' Direction Pa rt.ic '.I-131' TLD' Ver, Milk' Water Water' Soil Anim-3 ONSITE 21 - SE of Plant on C.3 SE Q Columbia River shore 22 - Between Recreation O.4 SSW Q Lake and U. S. 30' i 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 4 64 - NW corner of 0.5 W Q l . Reflection Lake OREGON 2 - P.ainier 3.8 NW W W Q MC 3 - Lindberg (Kelly Res.) -2.0 NNW Q-Q i 4C - Prescott (Jack-Falls-1.6 NW Q residhntial area) 6B - Goble (Neer Res.) 1.2 S* 'W-W Q Q' 4 17A - Beaver Homes (Kandle 2.6 SSW SM. Dairy) 19 - Portland 37.5 S W'. W SM 1 - 4 e . ~ - q .x .-..~.,_z_....,_._ ~ = ~

M M M M 'M M M M M M M M M'M .M M M Ml M TABLE _2-1_ Eheet 3 of 6 -Terrestrial Aquatic Radia_1 Air Air Well Drink Shore Sample Location Milear.e' Direction Partic' I-131' TLD' Veg M,i_1_k ' Water Water' Soil _ _ l Anim I GREGON 25 - Prescott (Shoreline) 0.6 N Q I 26 - Deer Island (Tide 5.0 S Q Creek) 27 - Columbia City (Gensman 9.6 S Q [- Road) 2 28 - Shiloh Basin (Orr 4.7 SSW Q Road) i 29 - Trenholm (Canaan 10.7 SSW Q Road) 30 - Shiloh Basin 5 '. 0 SW Q, (Whitney Road) .1 g + 31 - Aplary (Schaffer Road) 10.1 SW Q i 32 - Fern Hill (Lentz 5.2; WSW Q ] l -Road) 33 - Apiarf (Van Natta Road; 8.6 WSW Q j 'l y 34 - Fern Hill (Lentz -5.0

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Road) p 35 ^Swedetown'(Swedetown 10.0' W,- Q. -Road) 36 - Rainier ~(Doan Road)' 5.2 .;WNW Q_ a '_a i ~ 'l 3:n .._...[ ~,,, .. _y, s , ~., 74.7 ,.,,.;,-., a_ .-,.~;.,,, .4,-...., ..;+,,..~ -,,, ^ .c ~r.

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1 TABLE,2,-j Eheet O of 6 ^ Terrestrial A<luatic Radial Air Air Well. Drink Shore Sample Location Mi l ea_ge ' Direction..Partic' I-131' TLD' Ve3' Milk' Water Water Soil Anim j. OREGON t 37 - Delena (Lost Creek 10.0 WNW Q

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Road) ~ 38.- Rainier (Highway 30) 4.8 UW Q [' 39 - Alston-Mayger Road 9.9 NW Q ~ 56 - Deer Island 3.2 SSE Q 3 ~. l 63 - Rinck. Dairy 8.1 WNW SM 66 - St. Helens'(Municipal 10.5 SSE MC Water Supply) 4 68 - Winans'. Dairy 5.0-SW-SM ~ WASHINGTON-11A - Kalama River ~ 0.8 SE Q (Columbia River)- s. [? 11B - Kalama River. 1.4 'ENE W W (Public. Utility. District ~ Substation); 14 - Longview (Ocean -8.2' NNW. W W -c Beach Substation) i. . c: 40 - Longview-(RR) 5.8; NNW Q 41 - ~ Eufadla '" - 10.~ 7 NNW Q / .A., I W e. C:: m n_'42 -.Kelso (near. Hwy 4). .6.6 N Q + 1 a.. t =4 '.IA r, c' s

.W' m im M M M M M-M M M M M M M M M M TABLE 2-1 Sheet 5 of 6 Terrestrial A< patic

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Radial Air Air Well Drink Shore Sample Location .Milear.e Direction Partic' I-131' TLD' Veg Milk' Water Water Soil Anim WASHINGTON 43 - Lexington 10.3 N Q 44 - Kelso (N Maple Hill 5.2 WNE 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 - Goble Mountain 7.8 ENE' Q 50 - Kalama River 5.0 E Q (Fallert Road) j 51 - Kalama River 10.0 E Q } (Kalama River Road) a 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) 2. 57 - Woodland (Dike. Road) 0.5 SSE Q =

4 = TABLE 2-1 Sheet 6 of 6 l .. l Terrestrial A<ustic Radial Air Air Well Drink' Shore Sample Location Mileage Direction Partic' I-131' TLD Veg.. Milk Water Water' Soil Anim WASHINGTON 58 - Kalama (N of Port of 1.6 SE Q Kalama Marina) t { 59 - Kalama (S of Sports-1.5 ESE Q man Road) 60 - Kalama (N of 1.2 ENE Q Sportsman Road) 61 - Carro11s (W Kingsbury 1.5 NE Q Road) 62 - W of Carro11s Channel 1.0 NNE Q COLUMBIA RIVER CR3 - Trojan 72.4* E S/A S/A i LEGEND: W - Weekly. Q - Quarterly. 4 SM - Every two weeks except monthly during December, ' January, and February. MC - Four-week composite, two-week composite if I-131 analysis required. S/A - Semiannually. HT' - Harvest time. - Columbia River mileage refers to river miles (measured from mouth)'. a. ~.. - - -

[l-TABLE 2-2 1989' LAND USE CENSUS NEAREST LOCATION TO TROJAN WITHIN'A FIVE-MILE RADIUS I Radiation Milear.c for Nearest Location Directional-Meat Sector Residence Garden Milk Cow Milk Goat Animal N 0.6 0.8 None-None None I-NNE 2.0 2.8 None None' 2.7' NE 1.6 2.0 None Nonc Hone-ENE 2.3 2.3 Nonc~ None 2.3 I E -1.3 l '. 4 Nonc. None-1.4 ESE 0.8 1.8 None Nonc' 1.7 SE 2.3 2.3' None -None 2.5 SSF 1.4 '3. 0 None Nonc 3.0 1 S 1.2 1.4 None Nonc 2.0 S SE' O.9 0.9 None. 2.6, 1.0 SW 1.5 1.5 None-3.0 ~1.6. j WSW 1.4 3.0 None None 1.9~ m W 1.7 2.1 None None 2.2 WIN 1.7 1.7 -None None-1.7 NW 1.2 1.2 None None 2.2 I NNW 0.6 0.6 Nonc' Nonc 2.0 1 1 1 = i 9 1

..a, t .a: l TABLE 2-3 . i DAIRY ANIMALS -. GOATS WITHIN 5 MILES OF TROJAN,.. AUGUST 1989-- 1 !I ~ Radial Radial Direction [a] -MileaRe(8) !i SSW 2,6 f SW 3.0-e r t i (a) Measured f rora Trojan Containment. I ~ t (

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TABLE 2-4 Sheet 1 o f I. H VEGETABLE GARDENS WITHIN 5 MILES OF TROJAN - AUGUST 1989 f J Radial Radial Number Direction [a] Mileage [al of Gardens N 0.8 1 NNE 2.8 4 NNE 3.0 3 NtJ E 4.0 2 i 1;t;! 4.8 1 i ~^ 1;in 5.0 1 NE 2.0 1 j NE 2.1 3 NE 3.4 A NE 3.5 3 ENE 2.3 1 ENE 5.0 1 E 1.4 1 E 1.6 1 E 1.8 1 E 2.5 7 ESE 1.8 1 ESE 2.2 1 SE 2.3 1 SE 2.8 2 SE 3.0 4 [a] Measured from Trojan Containment. 7 --ii.

.,(. - ~. s I .t G { p TABLE 2i4 Sheet-2 of 4' 'I. VEGETABLE GARDENS- -v - WITHIN 5 MILES OF TROJAN - AUGUST 1989 I" l Radial -Radial -Number Direction [a] Mileaste [a] of-Gardans l SE' 3.1 2 SE: .3.3 1 l SE 3.5 1 SE '3.6 . 1 3 SF 4.3 1 SL 4.5 2 = ! f SSE 3.0 1 + SSE 4.8 1 SSE 5.0 1 S 2.0 ' l' I:. S 2.1 - 1. S 2.3 2 l S 4.6 l' s SSW 0.9 .1-t SSW 2.6 1 SSW-3.0 2 W-SSW 3.1 1 SSW 3.2 - 3 lI SSW ' 3. 4 - 1 SSW 5.0 1 SW 1.5 1 I: i [a] Measured from Trojan Containment. I 1 e v y v ,,-w.,-, m ,,-.m,, 9,,,,.

i i TABLE 2-4 Sheet 3 of 4 = VEGETABLE GARDENS WITHIN 5 MILES OF TROJAN - AUGUST 1989 Radial Radial Number Direction [a] Milestela) of Gardens I SW 2.0 1 SW 2.1 2 SW 2.7 1 SW 2.8 1 Si 3.0 1 S.. 3.5 2 SW 3.8 1 WSW 3.0 1 WSW 3.5 1 WSW 4.5 1 W 2.1 I W 3.8 2 WNW I.7 1 WNW 1.8 1 WNW 4.2 1 NW 1.2 1 NW 2.0 1 NW 2.1 1 NW 2.2 1 NW 4.0 3 NW 4.1 1 (a) Measured from Trojan Containment. --i M'

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g' o TABLE 2 4 Sheet 4 of 4' i 2 l* i VEGETABLE GARDENS -I WITHIN 5 MILES OF TROJAN - AUGUST 1989 l Radial Radial Number Directionla) Mlleatela) of Gardens nW 4.2 1 NW 4.3 1 NW 4.6 1 lI !!W 4.8 2 ? Ir. 4.9 1 11.. 5; O 1 Nt1W .6 1 U m ?\\l .NNW 2.0 1 N!!W 3.0 1 NilW 3.1 1. .t N!!W 3.2 1 = ' > t la) Measured from Trojan Containment. j I I I-I I:

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I. 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. Departmen*, of Energy [ Health and-Safety Labcratory (HASL) Procedures Manual HASL-300,-see references, Section 3.10), or those of the U. S. Environmental Protection Agency. o (EPA). Analyses of individual' sample types, general methods, and routine ana-> I 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 I 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 methods I (HASL-300), and are reported at the 95 percent! confidence icvel (2o). 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 percerit probability with only-i 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 "<". I 3.2 AIR PARTICULATES Cross beta concentrations are measured with-low background, window-type 2 1 (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. I I '1 3-1 I

K Camma isotopic. analyses are performed.with germanium detectors with'a 3 routine detection limit _of 0,05 pCi/m -for the gamma emitters. - 1 l 3.3' RADIOTODINE The charcoal cartridge'.used are of the TEDA-impregnated type. The s lodine is extracted from the charcoal', chemically separated,'and counted ' l as AgI using the. low-background beta counters mentioned in Section 3.2 which yield an LLD of 0.05 pCi/m. Ia 3.4 DRINKING AND WELL WATER Gross beta'analynic of. water samples is performed by evaporation of a measured aliguot of the sample, digestion,;planchetting of the processed sample and radiometric assay by the low-background'bota counters men-: tioned in Section 3.2, with an LLD of 0.5 pCi/1, Tritium-analysis ls performed on all water samples to the required LLD of 1000 pCi/1 by-11guld scintillation counting. Gamma isotopic analysis is' performed using germanium detectors with a routine LLD of 10 pCi/1 per gamma-emitting radionuclide. + 3.5 SHORELINE SOIL Samples are oven dried and results reported based on dry' weight. Gamma emitters are measured with germanium detectors with an LLD of 0.10 pCi/g per nuclide. 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. 'f I - ~

1 {J l 3.7 MILK The deternination of Iodine-131 in f resh milk is based on anion exchange ~ removal of the Iodine.131 followed by radiochemical purification and lo. L background beta counting using the systems described in Section 3.2. The LLD is 0.5 pCi/1 or better. Gamma emitters in milk are measured with germanium detectors with an LLD of 10 pCi/l per nuclide. The analysis f or Strontium-89 and Strontium-90 is performed on ashed samples using a strontium chemical yield and two-separation technique with an LLD of l 1.0 pCi/1. b ,3. 8 AMBIENT RADIATION MEASUREMENTS The responcibility for ambient radiation dose measurements resides with Portland General Electric Company (PGE). A total of 57 field locations were monitored with the dosimeters analyzed quarterly. The fleld dosimeters used thermoluminescent radiation detection materials (CaF2:Dy, TLD-200 chips) with each du lmeter having more than two separate chips or I measurement devices. For each field dosimeter, the chips were packed in a plastic foam and scaled in shielded containers. To minimize radiation energy dependence f or the TLD-200 chips, the field dosimeters were I 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 prepared for each readout of the field dosimeters. 3.9 OUALITY CONTROL I 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 l l 3-3

gj sj are presented monthly to-PCE. Results of. EPA intercalibrations (for

  • g ')

which "known" data are available) are given:in Table 3+ 2. In those' casec W l-where discrepant' values are obtained, the analysis-laboratory performs an investigation to determine the cause and corrective action as~ required. Tahle 3-3 summarizes the intralaboratory quality control results for the ~! year 1989.- ( -i During 1981, 1982, and 1984, PCE participated in the Fif th, Sixth, 'and' Seventh International Intercomparison of Environmental Dosimeters. The results of these participations'were-presented in-the 1982, 1983, and. gi f 1984 reports, respectively. By the successful PGE' participation'in'these. W three intercomparicon projects,' the measurement method - for the' environ- .+ .. l mental ambient radiat ion levels has been shown ti be appropriai.e and accurate. 'l. -W!t 3.10 REFERENCES FOR ANALYTICAL PROCEDURE 3 IJ 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. 'l pp~583-632; 12th edition, pp 325-352. APHA, - 1740. Broadway, New York,- W_ NY 10019. 2. Department of Health, Education and Welfare, Public Health Service: Radioassay Procedures for Environmental Samples. National Center for Radiological Health (1967), Sec. 1, pp 36-115. I. 3. Atomic Energy Commission: Regulatory' Guide 4.3 (September 1973). 4. Health and Safety Laborat'ory, Atomic Energy Commissiotu iHASL HASL, 376 Hudson Street, New York, NY 10014. .'j Procedures Manual (now known as EML of the Department of Energy). S. National Environmental Research Center, Environmental Protection Agency; Handbook of'Rediochemical Analytical Methods. Program Element 1HA 325. Office of Research and Development, Las Vegas, NV 89114. .ID D.H.Denham,R.L.Kathren,and-J.P.Corley,"ECa2:Dy 6. Thermoluminescent Dosimeter for Environmental Monitorint", USAEC Report BNWL-SA-4191 (1972). I 3-4

( I TABLE 3-1 PROGhAM ANALYSES AND REPORTED DETECTION LEVELS Pror. ram Analysis Reported Detection Limits (LLD)[a] Air Particulate-gross beta 0.002 pCi/m3 Air Particulate-gamma scan 0.050 pCi/m3/nuclide Air Radioiodine 0.05 pCi/m3 i l Food Crops-gamma scan 0.020 pCi/g/nuclide (wet) Milk-lodine 131 0.5 pCi/ liter Milk-S t ront iur, 8 9 / % 1.0 pCi/ liter Milk-gamma scan 10 pCi/ liter /nuclide Water gross teta 0.5 pCi/ liter Water tritiun 1000 pCi/ liter Water-gamma sc an 10 pC1/ liter /nuclide Shoreline Soil-gamma scan 0.10 pCi/g/nuclide (dry) Fish / Invertebrates gamma scan 0.10 pCi/g/nuclide (wet) Direct Radiation 0.04 mR/ day

I (a) Reported de etion level or LLD is defined in Section 3.1.

um ni-i i

J' TABLE 3 Sheet.1 of:2 1989 U.S. EN'J1RON ENTAL PROTECTION AGENCY (EPA) ANAL.YSIS LABORATORY INTERCOMPARISON PROGRAM Eberline Sample Type Analysis EPA Value Value Units Water I-131 115112 39.313.11 pCi/1,

g Water Alpha 41.0110.0 49.011.0 pCi/1-Water Beta 54.015.0 53.011.7 pCi/1-

.g, Water-Cs-134 15.015.0 15.710.6 pCi/1-Water Cs-137 15.015.0 14.710.6 'pci/1: Water Ra-226 5.010.8 5.510.3 pCi/1- .a

W Water Ra-228 5.210'8 6.110.2

~ pC1/1 l Water Sr-89 11.015.0 11.011.0 .pci/1 1 43 Water Sr.90 10.0il.5 8.710.6 pCi/1 J Water Uranium 5.016.0 ' 5.3io.6 pCi/1 Water Ra 226 3.5010.50 3.6710.06 pCi/1' Water Ra-228 10.311.5. 11.310.7 PCi/1 Water Alpha 8.015.0 13.011.0-pC1/1'

W Water Beta 4.015.0 5.310.6 pC1/1' Water Pu-239 4.2010.40 3.9710.12 pC1/1 Water Sr-89 40.015.0 39.312.5 pCi/1

'I Water Sr-90 25.011.5 23.710.6 pC1/1~ i Water Cr-51 235124 '209113 ~ pCi /1 - lg Water Co-60 10.015.0 9.311.2 pCi /1 ~ g Water 2n 65 159116-161113 pCi/1 t Water Ru-106 178i18 ~ 195112 pCi/1-Water Cs-134 10.0+5.0 8.7+2.5 pC1/1 13 j Water Cs-137 10.015.0 11.711.5_ pCi/1 'I lW Water U-Nat 5.016.0 5.010.0' pCi/1-j. Water Ra-226 4.9010.7 4.0310.25" -pC1/1 j Water Ra-228 -1.7010.30-1.7710_.30" pCi/1 Ig Water Alpha 30.018.0-33.012.7 pCi/1 Water Beta 50.015.0 58.311.5-pCi/1 Water Alpha 29.017.0 30.312.1 pC1/1 ,a Water Beta 57.0 5.0 51.013.0 .pci/1 lg' l Water Ra-226 3.5010.50. 3.8710.15 pCi/1 Water Re.-228 3.6010.50 5.2011.04 pC1/1 Water U-Nat 3.0016.00 3.0010.00 pC1/1 I Water Sr-89 8.0015.00 8.0010.00- .pC1/1 Water Sr-90 8.0011.50 7.6710.58 pCi/1 Water Cs-134 20.015.0 20.011.0 pCi/1 Water Cs-137 20.015.0 21,310.6 pC1/1 Water Sr-89 6.0015.00 6.3310.58 pCi/1 Water Sr-90 6.0011.50 6.6710.58 pCi/1 I Water H-3 45031450 47701147 pCi/1 l Water Ba-133 55.011.0 49.015.0 pci/1 l Water Co-60 36.310.6 31.015.0 pC1/1 Water 2n-65 20413-165117 pCi/1-I Water Ru-106 15117 128113 pCi/1-Water Cs-134 42.310.6 39.015.0 pC1/1 I !I I,

TABLE 3-2 sheet 2 of 2= Eberline Sample Type Analysis EPA Value Value Units Water Cs-137 26.011.0 20.015.0 pCi/1 Water Ra-226 17.712.7 17.210.5 pCi/1 Water Ra-228 18.312.7 24.810.3 pC1/1 Water Pu-239 2.810.3-2.710.1 pCi/1. Water Alpha _4.015.0 4.310.6 pC1/1 Water Bets 6.015.0 6.710.6 pCi/1-Water Ba-133 59.016.0 52.312.1 pCi/1 Water Co-60 30.015.0 27.312.3 pCi/1 Water 2n-65 129113 96.713.5 pCi/1 l Water Ru.106 161116 11618 .pCL/1 g Water Cs.134 '29.015.0 20.310.6: 'pC1/1 Water cs.131 59.015.0 57.711.2 pC1/1 Water H3 34961364 3467125

pci/1 Air Filter Alpha 21.015.0 20.010.0 pC1/ sample

-{ Air Filter Beta 62.015.0 60.010.0 pCi/ sample, Air Filter S r 20.011.5 16.310.6 pCi/ san @le Air Filter Cs-137 20.0i5.0 -22.312,1 pC1/ sample Air Filter Alpha 6.015.0 5.710.6 pC1/ sample ~ Air Filter Cs-137 10.015.0 8.011.0 pCi/ sample Milk 1-131 91.019.0 81.012.0 pCi/1 Milk Cs-137 50.015.0 -53.713.2 pCi/1 l Data for EPA reported i 1 sigma of the mean. ll ll }

I. E y TABLE 3-3 '1989. QUALITY CONTROL ANALYSES

SUMMARY

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. -l ' 5 listings of each measurement are maintained at the analysis. laboratory-and are available for inspection if required. Blank Samples Nuclide Number of Number of Analyses Exceeding 1 _ Analyzed, peterminations lhe LLD for that Analysis i Gross Alpha 154 0' Gross Beta 96 'O I H-3 115 0-Uranium 155 0 Th 230 20 0 i Ra-226 66 0 Ra-228 14 0. Sr-90 60 0 Pu-239 40' .0 I Am-241 27 0 1-131 -6 0 Spiked Samples Nuclide Number of Within 2 Sigma Within 3 Sigma Analyzed

Determs, of Known of Known Gross Alpha 154 154 g

Gross Beta 96 96 3 H-3 115 115 Uranium 155 155 1 - Th-230 22 22 Ra-226 69 69 Ra-228 14 14 Sr-90 58' 58 I Pu-239 40 40 Am-241 27 27 1-131 6 6 4 g ~ - -

l i 4.0 RESULTS AND DISCUSSION l 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 1989 were comparable to the data obtained during the years of 1982, 1983, 1984, 1985, 1986 (except May 1986), 1987, 1988, and the preoperational period. Gross beta I concentrations for air particulates for all sampling periods in 1989 remained generally at low levels. Average cotaentrations with their average standard deviations for the years 1989 and before are presented in Table 4-1 for both onsite and offsite locations. In October 1980, the People's 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 i Trojr-Nuclear Plant. The larger average standard deviation for the 1986 data was due to the increased gross beta activity for May 1986 resulting f rom the Chernobyl incident. Airborne I-131 concentration values for 1989 were below the detection limit of 0.05 pCi/m (at collection time) for all samples. For 1989, 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 0.050 pCi/m. 1 Data for these air monitoring samples are listed in Chapter 5, Tables 5-1, 5-2, and 5-3. 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 4-1

s.: during'the harvest months of June, July,'Aug'ust, and September 1989. "I Camma emitting radionuclides were not detected in the food crop samples. l The data are presented in. Chapter 5, Table 5-4 i 4.1.3 WELL WATER Well water samples were collected quarterly from three locations. Tritium and gamma emitting radionuclide-levels were below tho' sensitivity. requirements of the program. The data are presented in Chapter 5,. Table 5-5. $.1.4 Mll! Milk sampler were collected from four locations and were analyzed for' g I-131, Sr-89. Sr-90, and and gamma emitters. No samples contained 1-131 g or Sr-89 at detectable levcis. Most. samples contained Sr-90 which is. attributable to worldwide fallout due to atmospheric weapons tests. i For the Rinck Goat Dairy (Location 63), during the monthe' March through June and in December, 12 of 23 milk samples coll'ected'for the year showed detectable levels of radiocesiums. Six of-these samples exceeded-4 20 pC1/1, all Cs-137. The lack of I-131 and Sr-89 radibactivity in the w 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. Refer to the 1986 report for discussion'of this incident. The milk sample data are presented in Chapter 5, Table 5-6. 4.1.5 AMBIENT RADIATION LEVELS B E, Ambient dose rates in mR/ day for dosimeters at measurement locations in the environs around the Trojan Nuclear plant are shown in Chapter 5, 5 Table 5-7. Several of these measurement locations were established-D before the plant became operational. -The mean and standard deviation for the quarterly dosimeters data has been calculated for the three 4-2

l l geographical groups of Oregon, Washington, and Trojan onsite locations. l l For 1989, the mean ambient dose rates were: 0.1110.02 mR/ day for th( 14 Trojan onsite locations, 0.1470.02 mR/ day for the 20 Oregon locations, and 0.12!0.02 mR/ day for the 23 Washington locations. Table 4 2 presentt-this same inf armation f or the years 1976 through 1989. As Table 4-2 indicates, the 1989 values do not differ significantly from the results of previous years. I Another manner for review of the ambient ra diation measurements is to divide the results between three t-ings which are grouped as to radial I distance frce Trojan: the close ring (24 locations) at distances from 0.1 t o 2. 0 tr i l s t, t he 5 mile ring (17 locations) at distances from 2.1 to 7. 0 in i l e t, t h( 10 rile ring (16 locations) at distances from 7.1 to 10.7 miles. Thc 10 rile ring serves 80 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 0.12 0.02 mR/ day for all locations, with 1 the close, 5-mile, and 10-mile rings being 0.1110.02 mE/ day, t 0.13f0 12 mR/ day, and 0.13f0.02 mR/ day, respectively. Theco data indicatt that the operational activities Of the Trojan Nuclear Plant do not affect the ambient radiation levels around the Plant. The ambient ganna radiation data in Table 5-7 were also analyzed f or doce 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 1988 and before. The values were: 0.1210.02 mR/ day for the 16 north locations. 0.1110.01 mR/ day for the 9 east locations. 0.1510.02 mR/ day for the 12 south locations, and 0.1310.01 mR/ day for the 6 west locations. 4.2 SAMPLES FROM THE 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 4-3

^ ^ -1 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. Tabic 5-8. -R .5: 7 No radioactivity attributable to operation of the Trojan Nuclear Plant was detected in any of the water samples. I Table 4-3 presents the annual average of.the gross beta activity for the two water samples from 1980 through 1989. These samples were not. collected pr'ior to 1980. The annual average values are fairly consistent ~ over the yearc, 4,2 2 SHOREl.lHL S0)L 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 shoreline soll samples showed detectable levels of gamma emitters. 4.2.3 FISH g I-Fish and crayfish woro collected twice during the year and the fillets W and/or tails were analyzed for gamma emitters. None of the' fish or. i crayfish samples contained gamma emitting radionuclides larger than the detectability level of 0.10 pC1/g. The data are presented in Chapter 5 Tabic 5-10. l 4.3

SUMMARY

OF RESULTS i Table 4-4 presents a summary of the radioactivity analysis reFults for l each medium or pathway sampled for the 1989 Radiological Environmental Monitoring Program around the Trojan Nuclear Plant. The format of Table 4-4 is that which is required by Trojan Technical Specification 6.9.1.5.2. I i I, ) 4-4

a. 0~ I'8 '4. A review of Table 4-4 shows that, except for_ milk, none of the radio-activity measurements were larger than the Reporting Levels defined by Technical Specification 3.12.1.- An evaluation was performed which showed I. that the milk samples exceeding the Reporting Levels were related to fallout radioactivity and not Trojan Nuclear Plant operations. For the gross beta analyses cf the air particulate samples, the control location was the location with the highest annual mean, its mean wasLnot significantly different from the mean value for all locations.- Foi the milk samples, the only detectable radioactivity was due to the. at.nospheric weaponc testing and.the Chernobyl nuclear accident fallout I ri.dionu$lideo, Sr 90, Cs-13A, and Cs-137. Also, the dairy with the highest measured values of Sr-90 and only measured values of Cs-134 and Cs 137 was a goat dairy (Location 63). Goats tend to concentrate radioactivity in the milk to a greater degree than do cows. A performed evaluation has shown that these measured radioactivities in milk were due to world-wide fallout and not the operations of the Trojan' Nuclear Plant. 8-J For the ambient radiation measurements. the mean value lor ~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 (though not significantly) for-the upstream (Columbia River) or control location (St. Helens) than it was for the downstream location (Rainier). l 1 .i As is shown by Table 4-4, except for milk, most of the radioactivity I-- measurements performed for the 1989 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-Nuclear Plant had a radiological impact on the environs-around the: Plant. I I I

TABLE 4-1 AVERAGE GROSS BETd CONCENTRATIONS-FOR AIR PARTICULATES-: (Units: 10

  • DCi/m')

~ Trojan Oregon. Washington ? (onsite) (offsite) (offaite) Preop 212 212' 312 1976 216 318 214-44 512 1977 314 1 1918 232 211 .211 1979 111 111 lil-1980 314 314 214 1981 11 2 1114-1111 1982 215 217 216 1983 212 212 212 1984 212 212 212. 1985 22 2i1 211 1986 3 7-316 317 1987 111 111 lil 1988 111 111 111 1989 212 2i2 212 I I I I I I I

m ] TABLE 4-2 ) I AVERAGF. AMBIENT CA)DIA RADI ATION LEVELS h mR/ Day (1 2o Error) 1 J Trojan Year Site Oregon Washington 1976 0.13 0.14 0.13 I 1977 0.13 0.15 0.14 1978 0.11 0.13 0.13 1979 0.11! 02 0.1410.02 0.1310.03 O 1980 0.11tc.02 0.1410.02 0.1210.01 1981 0.1110.03 0.1410.02 0.12t0.02 1982 0.1410.03 0.1610.02 0.1510.02 1983 0.1210.02 0.1410.02 0.1310.01 l-1984 0.12io.03 0.1310.02 0.1210.02 1985 0.1210.03 0.1410.02 0.1210.02 1 1986 0.1210.03 0.1410.03 0.1210.02 1987 0.13 0.03 0.1510.03 0.1210.02 1988 0.121 02 0.1410.02 0.1210.02 0 1989 0.1110.02 0.1410.02 0.1210.02 1 4 I I I 1 I

I' TABLE e-3 AVERAGE GROSS BETA CONCENTRATIONS t'OR DRINKING WATER FROM COLUMBIA RIVER I (Units: pCi/1) I No. 2 - Rainier No. 66 - St. Helens Year (Downstream) (Upstream) 1980 21.2 211 1981 2fl 311 I 1982 32 4I2 1983 312 412 19 8 <, 3f2 412 I 1981 3f2 411 1980 312 3I2 1987 312 'Il 1988 412 6f3 1989 312 412 I ,__..-i... ii

N; O E E TABLE 4-4 Sheet 1 of-2.,. RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

Trojan Nuclear Plant, Columbia County, Oregon, Docket 50-344, Reporting Period: January 1-December 31, 1989 Type and All Indicator Location With Highest Annual Mean Control Locations Medium 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-Measurement) Performed (LLD) Ranr.e Direction Range Range Events Air Particulates Gross B 0.002 0.018(363/363) 19 - Portland 0.019(52/52) .0.019(52/52) N/Alb) (pCi/m ) 363 0.003-0.058 37.5 mi - S 0.005-0.047 0.005-0.047 3 I-131 0.05 <LLD <LLD <LLD 0 363 y-scan 0.050/ <LLD <LLD <LLD 0 28 nuclide Food Crops T-scan 0.020/ <LLD <LLD N/A 0 (pC1/g - wet) 13 nuclide Well Water Tritium 1000 <LLD <LLD N/A 0 4 (pC1/11ter) 12 y-scan 10/ . <LLD <LLD N/A 0 12 nuclide Milk I-131 0.5 <LLD '<LLD ~ <LLD 0 (pCi/ liter) 91 Sr-89 1.0 <LLD <LLD <LLD N/AIDI 91' Sr-90 1.0 2.7(65/91) 63-Rink Dairy 3.4(19/23) 1.9(19/24) N/Alb) 91 0.6-8.2 8.1 mi - WWW 0.7-6.7 0.6-8.2 --._.--r--.-

4 TABLE 4-4 Sheet 7 of 2 Type and All Indicator Location With Illghest Annual Maan Control Locations Medium or Pathway Total Number Lower Limit Locations Name Number of Sampled (Unit of of Analyses of Detection Mean(f)I8I Distance and Mean(f)[a] Nean(f)(al Reportable Measurement) Performed (LLD) Range _ Direction _ Range Range __ Events y-scan, 10/ 0 l 91 nuclide t Cs-134 13(1/91) 63-Rink Dairy 13(1/23) <LLD 0 i N/AIDI B.1 mi - WWW M/Alb] Cs-137 23(12/91) 63-Rink Dairy 23(12/23) <LLD 0 7-49 8.1 mi - WWW 0-30 Ambient Radiation y-exposure 0.04 0.12(220/220) 27 - Columbia City 0.17(4/4) 0.13(62/62) N/Alb) (mR/ Cay) 219 0.07-0.19 (Censman Road) 0.16-0.17 0.09-0.17 (control) 9.6 mi - S f Drinking Water Cross B 0.5 3.9 24/24) 66-St. Helens 4.4(12/12) 4.4(12/12) N/Alb) (pci/ liter) 24 1.6-10.3 (control) 2.6-10.3 2.6-10.3 10.5 mi - SSE Tritlum 1000 <LLD <LLD <Lt.D 0 24 y-scan 10/ <LLD <LLD <LLD 0 24 nuclide s shoreline Soil y-scan 0.10/. <LLD <LLD N/AIDI N/Alb) (pci/g - dry) 2 nuclide Fich/ Invertebrates T-scan 0.10/ <LLD <LLD <LLD 0 (pci/g - wet) 8 nuellde 10] Neon and range based upon detectable measurements only. The fraction of detectable measurements at specified locations is. indicated in parentheses (f). Ib] C/A Not applicable. ~ ~. m.

4 o J 5.0 COMMENTS ON AND TERMS USED IN DATA TABLES L 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 ar 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 I after removal of moisture by drying in an oven at about 110*C for about 15 hours. pCi/m A reporting' unit used with air particulate and radio-iodine data which refers to the radioactivity content j 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 progrwn which scans about 50 to 2000 kev and lists the energy peaks of any nuclides pre unt in concentrations exceeding the sensitivity limits set for that particular experiment. 1 Error Terms Figures following "i" are error terms based on counting 'I uncertainties at the 2e (95 percent confidence)

level, values preceded by the "<" symbol were below the stated concentration at the 3o (99 percent confidence) level.

~ 5-1 l l 4 _,e,

4 3 Sensitivity All analyses meet the sensitivity requirements of the g program as given in Tabic 3-1. For the few samples that 5 do not (because of inadequale sample quantities, analytical interference, etc), the sensitivity actually obtained in the analysis is given. 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 presentint a whole page of "<" data. If all but one or g 'wo dato points are below the sensitivity limits, the 5 previou ly mentioned convention is followed and the f inite data are given ac footnotes. I I I I I I I I I I 5-2 I g

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

== Location 1F* Location 1F* Collection Volume Gross 8 Collection Volume Gross B .m) (cci/m ) Date (m ) (pCi/m ) Date ( l 01/03/89 285 0.01310.003 07/03/89 245 0.01910.003 p 01/10/89 285 0.01010.003 07/11/89 325 0.01810.003 01/17/89 285 0.00510.003 07/18/89 285 0.01810.003 01/24/89 285 0.00910.003 07/25/89 285 0.01710.003 01/31/89 285 0.0161 003 08/01/89 285 0.01510.003 0 02/07/89 285 0.02510.003 08/08/89 285 0.01610.003 02/14/89 285 0.0581 003 08/15/89 280 0.01710.003 0 02/21/89 285 0.01510.003 08/22/89 275 0.01510.003 02/28/89 285 0.007io.003 08/29/89 285 0.01410.002 03/07/89 285 0.01410.003 09/05/89 290 0.01710.002 03/14/89 290 0.01210.003 09/12/89 285 0.02610.003 03/21/89 285 0.00310.002 09/19/89 285 0.02810.003 03/28/89 285 0.00610.003 09/26/89 290 0.03210.003 c Oa/04/89 285 0.00710.003 10/03/89 280 0.02210.003 04/11/89 285 0.01110.003 10/10/89 285 0.01810.003 04/18/89 285 0.01410.003 10/17/89 285 0.02310.002 04/25/89 280 0.0111 003 10/24/89 285 0.02810.002 0 05/02/89 285 0.01110.003 10/31/89 285 0.02010.002 05/09/89 285 0.01210.003 11/07/89 285 0.02810.003 0.015 0.003 11/14/89 285 0.01910.002 05/16/89 295 1 05/23/99 285 0.01610.003 11/21/89 285 0.02210.003 05/30/89 285 0.01d10.003 11/28/89 285 0.01110.002 0.029 0.003 12/05/89 285 0.034!0.003 06/06/89 285 1 06/13/89 275 0.01810.003 12/12/89 290 0.01310.002 06/20/89 285 0.01510.003 12/19/89 285 0.02710.003 06/27/89 285 0.01810.003 12/26/89 285 0.04110.003

  • Iodine cartridge concentrations are <0.05.

M

c g 5' l TABLE 5-1 sheet 2 of 7 gi 5 l I Location 11* Location 11* Collection Volume Gross B Collection Volume Cross D ( 3 3 Date (m3) (DCi/m ) Date (m ) (DC1/m3) I, 01/03/89 285 0.00910.003 07/03/89 245 0.02210.003 01/10/89 285 0.00810.003 07/11/89 325 0.01510.003 01/17/89 285 0.00510.003 07/18/89 285 0.01610.003 3l 01/24/89 285 0.011 0.003 07/25/89 285 0.01510.003 3 01/31/89 285 0.01610.003 08/01/89 285 0.017 0.003 1 02/07/89 285 0.02710.003 08/08/89 285 0.01610.003 g 02/14/89 285 0.045 0.004 08/15/89 285 0.01810.003-g- 02/21/89 285 0.019t0.003 08/22/89 285 0.01610.003 3 02/28/89 281 0.0091 003 08/29/89 285 0.01810.002 0 03/07/89 285 0.01610.003 09/05/89 290 0.01610.002 l, 03/14/89 290 0.01010.002 09/12/89 285 0.02410.003 m 03/21/89 285 0.004 0.003 09/19/89 285 0.027 0.003 1 1 03/.28/89 285 0.00510.003 09/26/89 285 0.02710.003 3 04/04/89 285 0.00910.003-10/03/89 200 0.02110.003 5t 04/11/89 285 0.01110.003 10/10/89 285 0.02010.002 04/18/89 285 0.013+0.003 10/17/89 285 0.022+0.002 04/25/89 285 0.00910.003 10/24/89 285 0.02710.002 05/02/89 285 0.01210.003 10/31/89 285 0.01910.002 05/09/89 285 0.014 0.003 11/07/89 285 0.02310.003 1 05/16/89 285 0.01610.003 11/14/89 285 0.01910.002 l; 05/23/89 285 0.01610.003 11/21/89 270 9.02310.003 5 ' 05/30/89 285 0.01210.003 11/28/89 285 0.01410.002 06/06/89 285 0.02610.003 12/05/89 285 0.03110.003 g 06/13/89 285 0.01710.003 12/12/89 290 0.00910.002 g,> 06/20/89 285 0.01510.003 12/19/89 285 0.02210.003 06/27/89 285 0.01810.003 12/26/89 280 0.03010.003 I g

  • loe ne o.,m oe concee,.u ons

.,e 05. I I g. I. I' I

TABLE 5-1 Sheet 3 of 7 Location 6B* Location 6B* Co11cetion volume Gross B Collection volume Gross B s 3 3 3 3 Date (m ) (pCi/m ) Date (m ) (DCi/m ) 01/03/89 285 0.01210.003 07/03/89 245 0.01910.004 01/10/89 285 0.00710.003 07/11/89 325 0.01310.003 01/17/89 285 0.00410.003 07/18/89 285 0.02010.003 1 01/24/89 285 0.0101 003 07/25/89 285 0.01710.003 0 01/31/89 285 0.02010.003 08/01/89 285 0.01810.003 02/07/89 285 0.0271 003 08/08/09 285 0.01410.003 0 02/14/89 285 0.04810.004 08/15/89 285 0.01710.003 0.017 0.003 08/22/89 285 0.01410.003 02/21/89 285 1 02/28/89 285 0.0091 003 08/29/89 285 0.01610.002 0 1 03/07/89 285 0.01410.003 09/05/89 290 0.016iO.003 03/14/89 290 0.00910.002 09/12/89 285 0.022io.002 03/21/89 285 0.00610.003 09/19/89 285 0.02910.003 0.005 0.003 09/26/89 285 0.03010.003 03/28/89 285 1 1 04/04/89 285 0.00910.003 10/03/89 280 0.02610.003 04/11/89 285 0.009+0.003 10/10/89 285 0.019+0.002 04/18/89 285 0.01310.003 10/17/89 285 0.031[+0.002 E ~ 1 0.010 0.003 10/24/89 285 0.03010.002 04/25/89 285 1 05/02/89 285 0.0111 003 10/31/89 285 0.02110.002 0 05/09/89 285 0.0111 003 11/07/89 285 0 0.028 0.003 1 l 05/16/B9 280 0.0191 003 11/14/89 285 0.01010.002 0 l 05/23/89 290 0.01110.003 11/21/89 285 0.02510.003 05/30/89 285 0.01010.003 11/28/89 285 0.01010.002 06/06/89 285 0.03110.003 12/05/89 285 0.035f0.003 1 06/13/89 285 0.0231 003 12/12/89 285 0.01210.002 0 06/20/89 285 0.01610.003 12/19/89 285 0.03010.003 06/27/89 285 0.01910.003 12/26/89 280 0.03010.003 lodine cart ridge concentrations are <0.05.

~ 's o ? TABLE 5-1 Sheet 4 of 7 W I Location 11B* ls Location 11B* Collection Volume Gross B Collection Volume-Gross b W Date (m ) (pcl/m3) Date (m3) (pci/m ) 3 3 01/03/89 285 0.01310.003 07/03/89 245 0.02310.003 01/10/89 285 0.00710.003 07/11/89 325 0.02010.003 01/17/89 285 0.00510.003 07/18/89 285 0.02010.003 01/24/89-285 0.00910.003: 07/25/89 '285 0.01510.003 01/31/89 285 0.01610.003 08/01/89 285 0.01910.003 02/07/89 285 0.02310.003 08/08/89 285 0.01510.003 i 02/14/89 285 0.04510.003 08/15/89 285 0.01910.003 02/21/89 280 0.01610.003 08/22/89 285 0.01710.003 02/28/89 285 0.01010.003 08/29/89 285 0.01510.002 03/07/89 28b 0.01410.003 09/05/89 290 0.01810.003 03/14/89 290 0.00910.002 09/12/89 285 0.02510.003 03/21/P9 285 0.00410.003 09/19/89 285 0.02910.003 03/28/89 280 0.00710.003 09/26/89 285 0.02910.003 04/04/89 285 0.00810.003 10/03/89 280 0.02110.003 04/11/89 285 0.01110.003 10/10/89 285 0.02110.002 04/18/89 285 0.01410.003 10/17/89 285 0.02210.002 04/25/89 285 0.01110.003 10/24/89 285 0.031t0.002 05/02/89 285 0.01510.003 10/31/89 285 0.01910.002 05/09/89 285 0.00910.002 11/07/89 285 0.02110.003 05/16/89 285 0.02110.003 11/14/89 285 0.01010.002 05/23/89 285 0.015 0.003 11/21/89 285 0.02110.003 05/30/89 285 0.01410.003 11/28/89 285 -0.01410.002 06/06/89 285 0.02410.003 12/05/89 285 0.03110.003 r 06/13/89 285 0.01910.003 12/12/89. 285 0.01010.002 06/20/89 285 0.01210.003 12/19/89 285 0.02810.003 06/27/89 285 0.01710.003 12/26/89 285 0.03510.003

  • lodino carteldt,e concentrations arc <0.05, ag,

.r l I I-l I' I I.

s TABLE 5-1 Sheet 5 of 7 ) Location 14' Location 14' Collection Volume Cross B Collection Volume Cross t 3 3 3 3 Date (m ) (pCi/m ) Date (m ) (PCi/n ) = 01/03/89 290 0.011 0.003 07/03/89 245 0.01910.004 01/10/89 285 0.007 0.003 07/11/89 325 0.01310.003 01/17/89 285 0.00520.003 07/18/89 285 0.01910.003 ~ 01/24/89 285 0.000 0.003 07/25/89 285 0.02410.003 f 01/31/89 285 0.015 0.003 08/01/89 285 0.02010.003 2 02/07/89 285 0.027 0.003 08/08/89 285 0.01810.003 t 02/14/89 285 0.050 0.004 08/15/89 285 0.0131 003 f 0 02/21/89 280 0.018 0.003 08/22/89 285 0.01310.003 f = O2/28/89 285 0.008 0.003 08/29/89 285 0.01710.002 f = 03/07/89 285 0.014 0.003 09/05/89 290 0.01710.002 f 03/14/89 290 0.010 0.002 09/12/89 285 0.02510.003 3 = 03/21/89 285 0.004 0.003 09/19/89 285 0.025 0.003 f 03/28/89 280 0.007 0.003 09/26/89 265 0.02910.003 1 04/04/89 285 0.007 0.003 10/03/89 280 0.02010.003 1 04/11/89 285 0.011!0.003 10/10/89 285 0.02110.002 r 04/18/89 285 0.071 o.003 10/17/89 285 0.02310.002 i 04/25/89 285 0.007 O.003 10/24/89 285 0.02810.002 05/02/89 285 0.012 0.003 10/31/89 285 0.02110.002 2 05/09/89 285 0.013 0.003 11/07/89 285 0.02610.003 f 05/16/89 285 0.012 0.003 11/14/89 285 0.03410.002 05/23/89 285 0.014 0.003 11/21/89 285 0.02210.003 2 05/30/09 285 0.010 0.003 11/28/89 285 0.01410.002 f 06/06/89 285 0.022 0.003 12/05/89 285 0.03410.003 1 06/13/89 275 0.019 0.003 12/12/89 285 0.01310.002 1 06/20/89 245 0.01410.003 12/19/89 290 0,02610.003 06/27/89 285 0.015 0.003 12/26/89 285 0.03910.003 2 lodine cartridge concentrations are <0.05. l siMOh im==immiiisi-isi _im -in-imi iiiisii

y . t i IABLE 5-1 Sheet 0 of 7 f Location 2* Location 2* Collection Volume Gross 8 Collection Volume Cross D (m ) (DC1/m ) Date (m ) (DC1/m ) 3 3 3 3 Date_,. I. 01/05/39 285 0.01410.003 07/03/89 245 0.01610.003 01/10/89 285 0.00710.003 07/11/89 325 0.015to.003 01/17/89 285 0.00510.003 07/18/89 285 0.01910.003 01/24/89 285 0.01010.003 07/25/89 285 0.01510.003 01/31/89 285 0.01610.003 08/01/89 285 0.01910.003 02/07/89 285 0.02510.003 08/08/89 285 0.01410.003 t 02/14/89 285 0.043f0.004 08/15/09 285 0.01110.003 i 02/21/89 265 0.01710.003 08/22/89 285 0.01410.003 02/28/89 285 0.00910.003 08/29/89 285 0.01510.002 03/07/89 2b5 0.01430.003 09/05/89 290' O.01310.002. l 03/14/89 290 0.00910.002 09/12/89 285 0.02510.003 03r21/89 285 0.00510.003-09/19/89 285 0.02310.003 i R3/28/89 130 0.01410.006 09/26/89 290 0.03010.003 g, b4/04/89 285 0.00910.003 10/03/89 285 0.02210.002 3 04/11/89 285 0.00910.003 10/10/89 285 0.01710.002 + 04/18/89 285 0.01310.003 10/17/89 285 0.02610.002 04/25/89 285 0.01010.003 10/24/89 285 0.03010.002 05/02/89 285 0.01210.003 10/31/89 285 0.01710.002 05/09/89 285 0.01110.003 11/07/89 285 0.02410.003 05/16/89 285 0.01610.003 11/14/89 285 0.01910.002 05/23/89 285 0.01510.003 11/21/89 285 0.02510.003 05/30/89 285 0.01310.003 11/28/89 285 0.01010.002 06/06/89 12/05/89 285 0.03610.003 06/13/89 285 0.01810.003 12/12/89 290 0.01110.002 06/20/89 285 0.01710.003 12/19/89 285 0.03010.003 06/27/89 285 0.01710.003 12/26/89 285 0.02710.003 I.

  • lodino cartridge concentrations arc <0.05.
    • Discovered unplugged.

I I' I' I I" 17

TABLE 5-1 sheet 7 of 7 ] Location 19* Location 19* J Collection Volume Gross 8 Collection Volume Crost B Date (m ) (pCi/m ) Date (m3) (pCi/m ) 3 3 3 01/03/89 285 0.01210.003 07/03/89 245 0.02210.003 01/10/89 285 0.00810.003 07/11/89 32S 0.01610.003 01/17/89 285 0.00610.003 07/18/89 285 0.02010.003 01/24/89 285 0.00810.003 07/25/89 285 0.02010.003 01/31/89 285 0.02010.003 08/01/89 285 0.01810.003 02/07/89 285 0.03010.003 08/08/89 285 0.01710.003 0.047 0.004 08/15/89 285 0.017 0.003 02/14/89 285 1 1 02/21/89 280 0.01610.003 08/22/89 285 0.01710.003 02/28/89 285 0.01110.003 08/29/89 285 0.01810.002 03/07/89 28! 0.0181 003 09/05/89 290 0.02610.003 0 03/14/89 290 0.01010.002 09/12/89 285 0.02910.003 03/21/89 285 0.00510.003 09/19/89 285 0.04010.003 03/28/89 285 0.00610.003 09/26/89 285 0.03410.003 04/04/89 285 0.00710.003 10/03/89 280 0.02510.003 04/11/89 285 0.01210.003 10/10/89 285 0.02410.003 04/18/89 285 0.01510.003 10/17/89 285 0.02410.002 04/25/89 285 0.00910.003 10/24/89 285 0.03210.002 05/02/89 285 0.01210.003 10/31/89 285 0.02010.002 05/09/89 285 0.0141 003 11/07/89 285 0.02910.003 0 05/16/89 285 0.01910.003 11/14/89 285 0.01310.002 05/23/89 285 0.01610.003 11/21/89 285 0.02710.003 0.010 0.003 11/28/89 285 0.01210.002 05/30/89 285 1 06/06/89 285 0.025!.003 12/05/89 285 0.03610.003 0 f 06/13/89 285 0.02110.003 12/12/8C 285 0.01010.002 0.017 0.003 12/19/89 285 0.02610.003 / 06/20/89 285 1 0.020 0.003 12/26/89 285 0.03010.003 [ 06/27/89 285 1 l \\

  • lodine cartridge concentrations are <0.05.

I 1 ) l 1

L 6 i TABLE 5-2

SUMMARY

- GROSS BETA IN AIR SAMPLES I

3 oci/m Averate Maximum Minimum Trojan Onsite Stations IF 0.01810.010 0.058 0.003 11 0.01710.008 0.045 0.004 Oregon Stations ? 0.01710.008 0.048 0.005 .I 6B 0.01810.009 0.047 0.004 19 0.01910.009 0.047 0.005 Washingtosi St et loiic 11B 0.01810.008 0.045 0.004 14 0.01710.009 0.050 0.004 I I I I I 1 I _j

e-Il Il TABLE 5-3 i i cAMMA EMITTERS CONCENTRATIONS IN AIR PARTICULATE FILTERS (Quarterly Composites) I! 3 (cci/m /nuellde) i Collection Date IF 11 6B 11B g, 3 i Ir.t Quarter <0.050 <0.050 <0.050 <0.050 2nd Quarter <0.050 <0.050 <0.050 <0.050 3rd Quarter <0.050 <0.0$0 <0.050 <0.050 Ir 4th Quarter <0.050 <0.050 <0.050 <0.050 toci/m3 nuclide) i / Collectiot, ..30J1..... 14 2 19 l! ist Quarter <0.0$0 <0.050 <0.050 2nd Quarter <0.050 <0.050 <0.050 3rd Quarter <0.0$0 <0.050 <0.050 W 4th Quarter <0.050 <0.050 <0.050 I' I: I I I: I' I, I I.

s 4 s TABLE 5-4 RADICACTIVITY IN FOOD CROPS w [pci/g/nuclide (wet)) Location 11 Sample Collection Gamma type Date 1-131 Emitters Swiss Chard "I 06/12/89 <0.020 <0.020 carrots 06/30/89 <0.020 <0.020 I ( Swisc Chard *I 07/18/89 <0.020 <0.020 Bect Creenr. 07/18/89 <0.020 <0.020 Bec t r. 07/18/89 <0.020 <0.020 Potatoes 07/18/89 <0.020 <0.020 Cabbage 08/08/89 <0.020 <0.020 Lettuce 08/08/89 <0.020 <0.020 Onions 08/08/89 <0.020 <0.020 Blackberriec 08/08/89 <0.020 <0.020 Cabbage 09/06/89 <0.020 <0.020 Carrots 09/06/89 <0.020 <0.020 Applec 09/06/89 <0.020 <0.020 ka)SplitwithStateofOregon. l L

Il f TABLE 5-5 l RAD 10 ACTIVITY IN WELL WATER I!' 901/1 J Collection Location 10 Location 3 Location 6B-Gamma Gamma Gamma Date Tritium Emitters Tritium Emitters Tritium Emitters l l 03/06/89 <1000 <10 <1000 <10 <1000 <10 06/05/89 <1000 <10 <1000 <10 <1000 <10 09/06/89 <1000 <10 <1000 <10 <1000 <10 12/11/89 <1000 <10 <1000 <10 <1000- <10 I; i l' I: I: I: I I; l I: 1 I I! .-m

e L s a o / - TABLE 5-6 Sheet 1 of 4 r' RADICACTIVITY IN MILK L f DC1/1 Location 17A Collection Gamma-Date I-131 8r-89 Br-90 Emitters 01/09/89 (b) (b) (b) (b) ~ 02/13/89 (b) (b) (b) (b) 03/06/89 <0.5 <1 <1 <10 03/20/89 <0.5 <1 0.810.7 <10 04/03/89 <0.5 <1 2.010.8 <10 04/17/89 <0.5 <1 <1 <10 05/01/89 <0.5 <1 3.310.9 <10 05/15/89 <0.5 <1 6.311.0 <10 05/29/89 <0.5 <1 2.410.9 <10- _5 06/12/89 <0.5 <2(a) <1 <10 06/26/89 <0.5 <1 7.311.2 <10 07/10/09 <0.5 <1 2.010.8 <10 07/24/89 <0.5 <1 3.810.9 <10= 08/07/89 <0.5 <2(a) 2.810.8 <10 08/21/89 <0.5 <1 <1 <10' 09/05/89 <0.5 <1 4.110.9 <10 09/18/89 <0.5 <1 1.910.9 <10 10/02/89 <0.5 <1 1.811.0 <10 10/16/89 <0,5 <1 2.911.1 <10 19/30/89 <0.5 <1 4.311.0 <10 11/13/89 <0.5 <1 2.710.8 <10 11/27/89 <0,5 <1 2.110.8 <10 12/11/89 <0.5 <1 <1 <10 (a) Due to low chemical recovery. (b) No milk sample available; goats were dry.

o e' I' B 7ABLE 5-6 Sheet 2 of 4 I Il 9C1/1 l Location 19 gi Collection Gamma 3 ; Dete 1 131 Sr-89 Sr-90 Emitters It 01/09/89 <0.5 <1 1.710.8 <10 02/13/89 <0.5 <1 0.910.7 <10 03/06/89 <0.5 <1 <1 <10 03/20/89 <0,5 <1 0.910.7 <10 04/03/89 <0.5 <1 <1 <10 04/17/89 <0,5 <1 4.611.0 <10 05/01/89 <0.b <1 1.810,8 <10 05/15/89 <0.5 <2(a) 1.410.7 <10 05/29/89 <0.5 <1 0.910.7 <10 g; 06/12/89 <0.5 <1 3.6f1.0 <10 3 06/26/89 <0.5 <1 1.310.8 <10 07/10/89 <0.5 <1 1.210.8 <10 07/24/89 <0.5 <1 8.210.9 <10 l 08/07/09 <0.5 <1 <1 <10 08/21/89 <0,5 <1 1.110.8 -<10 09/05/89 <0.5 <1 0.710.6 <10 gr 09/18/89 <0.5 <1 <1 <10 W 10/02/89 <0.5 <1 <1 <10-i 10/16/89 <0.5 <1 <1 <10 10/30/89 <0.5 <1 <1 <10 11/13/89(b) <0.5 <1 0.610.6 <10 11/13/89(b) <0.5 <1 0.910.6 <10 11/27/89 <0.5 <1 <1 <10 12/11/89 <0.5 <1 1.310.7 <10 (a) Due to low chemical recovery. (b) Duplicate samples. I: I' I +. _ _ -

.e s 7ABLE 5-6 Sheet 3 of 4 L 0C1/1 Collection Location 63 7 Date 1-131 fr-89 Sr-90 Nuclides Y Emitters L 01/09/89 <0.5 <1 3.710.9 Cs-137 33ie(a) 02/13/89 <0.5 <1 1.010.8 <10 03/06/89 <0.5 <1 4.611.0 Cs-134 1313 Cs-137 381 (a) 5 ( 03/20/89 <0.5 <1 4.011.0 Cs-137 1413(a) 04/03/89 <0.5 <1 4.3io.9 <10 { 04/17/89 <0.5 <2(b) 4.710.9 Cs-137 912(a) 05/01/89 <0.5 <1 3.011.0 Cs 'i37 1313(a) (' 05/15/89 <0.5 <1 4.111.0 Cs-137 2814(a) 05/29/89 <0.5 <2(b) 6.711.0 -Cs-137 1413(a) 06/12/89 <0.5 <1 3.510.9 Cs-137 2413(a) ( 06/26/89 <0.5 <1 5.111.1 Cs-137 3913(a) 07/10/89 <0.5 <1 <1 Cs-137 2613(a) 07/24/89 <0,5 <1 <1 <10 08/07/89 <0.5 <1 <1 <10 08/21/89 <0.5 <1 0.710.3 <10 09/05/89 <0,5 <1 3.011.0 Cs 137 1412(a) 09/18/89 <0.5 <1 2.010,9 <10 10/02/89 <0.5 <1 <1 <10 10/16/89 <0,5 <1 1.5io.8 <10 ( 10/30/89 <0.5 <1 4.411.1 <10 11/13/89 <0.5 <1 2.210.7 <10 11/27/89 <0.5 <1 3.910.9 <10 12/11/89 <0.5 <1 2.410.9 Cs-137 2014(a) (a) All other sama emiters <10. (b) Due to low chemical recovery.

_,g m ,,, Il IA_BLE 5-6 Sheet 4 of 4 901/1 t,ocation 68(a) u Collection camn.c Date L-Jl11 ff,1j! ,_Sr-90_ Emitters L i Il, 01/09/89 <0.5 <1 1.410.8 <10 02/13/89 <0.5 <1 1.510.7 <10 03/06/89 <0.5 <1 <1 <10 [ t 03/20/89 <0.5 <1 <1 <10 04/03/89 <0.5 <1 0.810.8 <10 04/17/89 <0,5 <1 2.310.9 <10 05/01/89 <0,5 <1 <1 <10 q 05/15/89 <0.5 <1 1.610.8 <10 05/29/89 <0.5 <1 1.210.8 <10 06/12/89 <0.5 <1 <1 <10 06/26/89 <0,5 <1 5.111.0 <10 07/10/89 <0.5 <1 <1 <10 07/24/89 <0.5 <2(b) 5.910.9 <10 r 08/07/69 <0,5 <1 0.9f0.7 <10 08//1/89 <0,5 <1 0.810.8 <10 09/05/89 <0.5 <1 2.710.8 <10 09/18/89 <0.5 <1 <1 <10 I 10/02/89 <0.5 <1 <1 <10 10/16/89 <0.5 <1 <1 <10 W 10/30/89 <0,5 <1 1.410.8 <10 l 11/13/89 <0.5 <1 0.810.7 <10 11/27/89 <0.5 <1 2.210.7 <10 12/11/89 <0.5 <1 <1 <10 l (a) Split sample with State of Oregon. (b) Due to low chemical recovery. I I. 1 l I:

) TABLE 5-7 Sheet 1 of 2 s AMBIENT GAMMA RADIATION LEVELS FOR 1989 ) mR/ Day (Mean Daily Exposure 12o Error) ) First Quarter Second Quarter Third Quarter Fourth Quarter fj.11 02/08/89-05/10/89 05/10/89-08/17/89 08/17/89-11/15/89 11/15/89-02/15/90 1A 0.1010.02 0.091 02 0.0910.02 0.1210.03 0 IB 0.101 02 0.0910.02 0.0910.02 0.1010.03 0 1C 0.121 03 0.1110.03 0.1110.02 0.1210.03 0 0.10 0.02 0.09 0.02 0.0910.02 0.0910.02 1 ) ll f IF 0.12f0.03 0.1210.03 0.1110.02 0.1210.03 0.15 0.04 0.17 0.05 0.1410.03 1 1H 0.1(+0.04 1 f 0.1410.04 11 0.1JfO.03 ) IJ 0.1010.02 0.09t0.02 0.091 02 0.1010.03 0 0.15 0.03 0.1610.04 2 0.1510.04 0.1 0.04 1 3 0.1430.03

r10.04 0.1310.03 0.1410.04 I

0.12 0.03 v.1210.03 0.1210.02 0.13+0.04 AC 3 0.11 0.03 0.1010.02 0.1210.02 6B 0.1210.03 1 0.14 0.04 0.1510.05 0.1010.03 11A 1 0.10 0.02 0.1010.02 0.1010.03 0.10 0.02 20 1 1 0.08 0.02 0.0810.02 0.0910.02 21 0.0910.02 1 22 0.101 02 0.0910.02 0.1010.02 0.1010.03 0 23 0.1110.03 0.1110.03 0.1110.02 0.1110.03 0.15 0.03 0.1510.04 24 0.1510.04 0.1410.04 1 25 0.121 03 0.1210.03 0.111 02 0.1210.03 0 0 26 0.151 04 0.1610.04 0.1510.03 0.1510.04 0 0.17 0.04 0.1710.05 0.1710.04 0.1610.04 27 1 0.17 0.04 0.161 04 0.1510.03 0.1510.04 t 0 28 29 0.1710.04 0.1610.05 0.1610.04 0.1610.04. 30 0.1610.04 0.1610.04 0.1610.04 0.1510.04 31 0.1510.04 0.1410.04 0.1310.03 0.1210.03 32 0.12io.03 0.11 0.03 0.1010.02 0.1210.03 33 0.1510.04 0.1410.04 0.1310.03 0.1410.04

  • Dosimeter vandalized during monitoring period.

. I TABLE 5,1 sheet 2 of a ; First Quarter Second Quarter Third Quarter Fourth Quarter F_ Life 02/08/89-05/10/89 05/10/89-08/17/89 08/17/89-11/15/89 11/15/89-02/15 m, 51 34 0.1410.03 0.1310.03 0.1210.03 0.1310.04 35 0.1410.03 0.1310.03 0.1210.03 0.1410.04 36 0.1410.03 0.1210.03 0.1210.02 0.1210.03 37 0.1410.03 0.1310.03 0.1410.04 l 38 0.1210.03 0.1010.03 0.1010.02 0.1210.03 39 0.1510.04 0.1410.04 0.1410.03-0.1510.04 40 0.1210.02 0.1210.04 0.1210.02 0.1010.03 41 0.1210.02 0.1310.04 0.1210.02 0.1110.03 42 0,1110.02 0.1110.04 0.1110.02 0.1010.02 43 0.1310.02 0.1210.04 0.1310.02 0.1110.03 0.14 0.05 0.1410.02 0.1110.03 44 0.1310.02 1 45 0.1210.02 0.1310.04 0.1310.02 0.11 0.04 0.1110.02 0.1010.02 46 0.1110.02 1 47 0.1210.02 0.111 04 0.1210.02 0.1110.03 0 48 0.1110.02 0,1210.04 0.1010.02 g 0.09 0.02 0.0910.02 0.1010.01 0.1010.02 m 49 1 50 0.1010.02 0.1110.03 0.1110.02 0.1010.02 51 0.1210.02 0.1210.04 0.1210.02 0.1010.02 52 0.1110.02 0.1010.03 0.1010.02 0.0910.02 53 0.1010.02 0.1110.03 0.1010.02 0.0910.02 54 0.1610.03 0.1910.07 0.1710.03 0.1410.04 55 0.1110.02 0.1010.03 0.1110.02 0.0910.02 56 0.1610.04 0.1410.03 0.1510.04 57 0.1410.03 0.1310.04 0.1310.02 0.1210.03 l 58 0.1410.03 0.1410.05 0.1410.02 0.13t0.03 59 0.10 0.02 0.1010.03 0.1210.02 0.0910.02 g 60 0.1110.02 0.1010.03 071010.02 0.0910.02 3 61 0.1510.03 0.1410.05 0.14io.02 0.1310.03 62 0.1510.03 0.0710.01 64 0.1210.03 0.1010.03 0.1010.02 0.1210.03 I

  • Dosimeter vandalized during monitoring period.

I,

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C w 0 .e L hhh .i a. e. aan l N w w 4 4 4 r e 4b d G i m 00 00 to 80 in) 40 40 00 00 W 00 00 N N ,4,W N M 4 m ,8 N O N 00 N O N m =e e c4 e Q O O O O m N N N N ce M C Q N N 0 N m e m e e N e0 O ** N C O O O O O O O O O M ee M eae +3 0 e i i i I i i i e I i i W

  • M Ch

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~ e I1 TABLE 5-9 RADIDACTIVITY IN SHORELINE SOIL (Semiannual Collections) i pC1/t/nuclide (dry) Location CR3 Collection Gansna Date Etnit ters 03/23/89 <0.10 09/07/09 <0.10 i t T F I \\ I I! I> I' I. I-I: I --..-e.-- ,,,,m ,-,s.-,,,w.,w... .w ,wy -v, -,-r..,,.w+, ~-,-we = w

, e s s TABLE 5-10 RADIOACTIVITY IN FISH / INVERTEBRATES (Semiannual Collections) r pCi/g/nuclide (wet) L Collection ( Location Date Species Gamma Emitters IA 03/15/89 Carp (3), Bridgelip Sucker (1) <0.10 ( 09/13/89 Bridge 11p sucker (2), Carp (1), <0.10 1D 03/25/89 Corp (4), Smallmouth Bass (1) <0.10 09/12/89 Carp (1), Largemouth Bass (1), <0.10 f CR3 03/18/89 Chinook Salmon <0.10 { 06/30/89 Crayfish Tails <0.10 I 09/06/89 Chinook Salmon *I <0.10 09/29/89 Crayfish Tails <0,10 (a) Split sample with State of Oregon. S S = i me sma-mi i i .}}

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