Text

Trojan Nuclear Plant Operational Environ Radiological Surveillance Program, for 1981
	ML20247E412
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	12/31/1981
From:	Kohl K, Liu C; EBERLINE INSTRUMENT CORP., PORTLAND GENERAL ELECTRIC CO.
To:	;
References
	NUDOCS 8907260157
	Download: ML20247E412 (81)
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'm-J TROJAN NUCLEAR PLANT OPERATIONAL ENVIRONMENTAL PJLDIOLOGICAL SURVEILLANCE PROGRAM J

JANUARY through DE,CEMBER 1981 Prepared for PORTIAND GENERAL ELECTRIC COMPANY by EBERLINE INSTRUMENT CORPORATION MIDWEST FACILITY As a Contractor to PORTIAND GENERAL ELECTRIC COMPANY February 1982 Data Compiled by:

IQathryn A. $ hl, Administrator Written.

Reviewed and

/4P7 Approved by:

Chung-KingLiu, Mand,er O

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INDEX P,3ge -

SECTION 1.0 -- PREFACE Abstract 1-1 In t r od u c t i on...................................

1-2 SECTION 2.0 -- SAMPLING PROGRAM Sampling. Locations..............................

2-1 Sampling Procedures............................

2-1 Yearly Agricultural Survey.....................

2-1 SECTION 3.0 -- ANALYSIS PROGRAM Analytical Procedures and Counting Methods.....

3-1 Quality Contro1.................................

3-4 Results of EFA Interlaboratory Comparisons.....

3-6 Results of USDOE Quality Assessment Program....

3-9 Eberline Ouality Control Analyses Summary......

3-10 EPA Special Laboratory Evaluation Sample....... 3-11 SECTION 4.0 -- RESULTS AND DISCUSSION Samples from the Terrestrial Environment.......- 4-1 Samples from the Aquatic Environment 4-5 SECTION 5.0 -- DATA TABLES Comments on, and Terms Used in Data Tables.....

5-1 Radioactivity in Air Samples...................

S-2 Animal Tissues................

5-13 Produce Samples...............

5-16 Grass Samples.................

5-17 Well Water Samples............

5-18 Milk Samples..................

5-19 S oi l. S aniple s..................

5-22 Precipitation Samples.........

5-23 Ambient Gamma Radiation tevels.................

5-24 Radioactivity in Drinking Water Samples........

5-27 Surface Water Samples.........

5-28 Shoreline Soil Samples........

5-31 Sediment Samples..............

5-31 Aquatic Plant Samples.........

5-32 Fish Samples..................

5-34

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If 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 Veriod January 1,1981 through December 31, 1981.

In several sample types such as air particulate and grasa, the level of radioactivity observed during 1981 was higher than observid during the previous three years. This higher level of radioactivity was due to worldwide fallout from the October 1980 testing of a nuclear device by the Peoples' Republic of China. In no case did radioactivity which may. be attributed to the Trojan Nuclear Plant exceed the design objec-tives of the Trojan Environmental Technical Specifications.

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1.0 INTRODUCTION

i The Trojan Nuclear Plant, a 1130 Mwe pressurized water reactor, first achieved' criticality on December 15, 1975. This report presents the analytical dats fran the Environmental Radiological Surveillance

. Program with appropriate interpretation for 1981.

i The analytical contractor during this period has been"Eberline Instrument i

Corporation, a division of Thermo Electron Corporation.

In comparing data obtained-during this period with those from previous periods, care phould be taken to ensure that differences in procedures between the several contractors are considered. This is particularly true for

" gross beta" measurements for'which the use cf different reference 1

1 nuclides may produce apparently significant differences in gross beta

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concentrations.

1 Information concerning environmental radiological surveillance programs l

prior to thic period may be found in earlier reports.

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'2.0 SAMPLING AND PROGRAM PROCEDURES 2.12 EAMPLING LOCATIONS l

Eighty-three sampling locations are used in the environmental radiological surveillance program, 77 on land and 6 in the Columbia River. This is a net decrease of two sites over 1980. The two deleted sites were 6A and 67.

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Site 6A-Goble was deleted due to the well being condemned by the Oregon i

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' State Health Division. This ground water sample is now taken from a well located at 6B-Goble. The beef sample from Site 67-Shiloh Basin was not taken in 1981 as tl.e goat sample from Site 17A provides a more appropriate sample. The wild terrestrial animal sampling at Sites 1A, II, 5, and 11B was terminated th 1981 since this sampling is not appropriate and depletes the wild animal population. The milk sampling at Site 63-Rinck Dairy was terminated in March 1981 since a complete review of this sampling location proved that the potential radiation dose commitment was not appropriate for continued' milk sampling.

The sampling locations are shown in Figures 2.1 and 2.2.

Table 2.1 in-cludes a listing of the sites, their distance from Trojan, and the type and frequency of sample collection.

2.2 SMTPLING PROCEDURES 2.2.1 AIR PARTICULATE AND RADI0 IODINE Air particulate and radiciodine campling was done week 3y.

The samples were gathered with a portable, low-volume air sampling d s'ce which is i

designed to draw a constant flow rate regardless of filter loading. The sampling devices were set. to mairtain 1-cfm.

The sample pump, metering devices, and timer were in a weatherproof housing. The filter and car-tridge were located in an inlet parallel to and 1 meter above the ground.

i Glass fiber filters were used to collect particulate matter. Ac+1"ated I

charcoal cartridges were used to collect radiciodine.

I The glass fiber filter was removed fron the air sampler and placed in a j

2 in, plastic petri dish. The activated charcoal cartridge was removed 2-1 l

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. at the same time. Air flow readings and other data required to compute 1

the levels of radioactivity were recorded and submitted to the analysis laboratory along with the samples.

2.2.2 AMBIENT RADIATION MEASUREMENTS USING TLDs

~d i

f s

Thermoluminiscent dosimeters (TLDs) were placed for field exposure and

]

_-collected both on either a quarterly or annual frequency. The dosimeters 1

a were placed 1 meter above ground level in plastic containers. The cime of collection, the exposure period, and any abnormal conditions such as mois-ture in the holder, damage donie by animals, etc., were recorded when the dosimeters 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 PRECIPITATION l

Rainwater samples were collected monthly from established precipitation resevoirs. The resevoir was removed from its holder an'd agitated to ensure thorough mixing of the contents. The contents were measured with a graduated cylinder and the volume recorded on the sample label. Four liters, or.the total volume if it was less than 4 liters, were placed in a polyethylene colle tion bottle. Sixty mis samples were taken for tri-tium analysis. Concentrated hcl was added to the large water sample only. Labels were attached to the polyethylene jars and the tritium bottles. The identification number of the sample site, the date collect-ed, and the volume measured were recorded on the data collection form.

2.2.4 TERRESTRIAL SOIL Terrestrial soil samples of about one quart in volume were taken twice a year. The soil samples were taken from a 1 sq ft area with the vegetatien 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

{

2-12 i

)

1

-_-_-- _ _ _ _ _ _ a

p before placing in the plastic collection' bottles. The collected terrestrial soil' samples along with information such as the sample site identification number, the date collected, and the volume obtained were recorded on the collection data forms.

2.' 2. 5 TERRESTRIAL VEGETATION Vegetation samples were collected semi-annually. Representative samples of tuberous and foliar fruits and vegetables were collected during local harvesting. Wild fruits were collected when available.

Grass samples were obtained from a sizable area because of the large (2-3 lb) sample size. Grass was removed at ground level.

Samples were sealed in plastic bags immediately following collection tak-ing care not to include any soil or foreign material. The cample site identification number, the date collected, the sample type, and the vol-ume obtair.ad were recorded on the data collection forms.

2.2.6 TERRESTRIAL ANIMALS Animal samples were taken semi-annually from cattle, goats, and wildlife (small mammals). Most samples were edible flesh from domestic animals.

Samples from domestic animals were purchased from local farmers or slaugh-ter houses after determining where the animal was raised and the slaugh-tering date.

Samples were labelled as to type (muscle, heart, liver). Muscle specimens were approximately 3 lb each, but the entire heart and liver were collect-ed.

All specimens were packed in plastic containers.

Specimens of small wild animain such as oppossums and rabbits were taken prior to termination of wild animal sampling. The sample site identifica-tion number, the date collected, the sample type and volume obtained were recorded on the collection data forms.

Samples were refrigerated until shipment.

2-13

__________-_a

1 2.2.7 MILK Milk samples (cow or goat) were collected monthly. Milk was collected in special Nalgene Polyethylene bottles. Prior to shipment of samples to the analysis laboratory an ion exchange resin was used to concentrate any io-dine present to improve detection sensitivity. The whole milk (af ter io-4 dine removal) and the resins were labelled and collection data forms pre-pared with collection data such as sample site identification number, date collected, sample type, and volume obtained.

2.2.8 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 w're 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, labelled, and collection data forms prepared specifying site, collection date, volume, and sample type, t

2.2.9 SURFACE WATER AND DRINKING WATER Surface water was sampled monthly except at sampling locations 2 (Rainier) and 66 (St. Helens) where monthly composites were collected.

Samples were taken by submerging a bucket in the water body. Approximately 1 gal was collected. From that, 60 mis were taken for tritium analysis. The remaining water sample was put in a 1-gal polyethylene bottle and acidified with concentrated hcl. The bottles were securely sealed, labelled, and I

collection data forms prepared specifying site, collection date, volume, and sample type.

2.2.10 BOTTOM SEDIMENT I

I Sediment samples were collected semi-annually.

Sediment samples approxi-l f

mately 4 in. in thickness were collected with an Eckman dredge.

Specimens were packed to within 1/4 in of the top of 1 qt polyethylene containers.

Excess water was decanted before being sealed with a tight-fitting lid.

2-14 i

The sample site identification number, date collected, and volume obtained were recorded on collection data forms.

2.2.11 SHORELINE, SOIL Shoreline soil samples of about 1 qt in volume were taken twice a year.

s The soil samples were taken from a 1 sq f t 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 placing in the plastic collection bottles. The sample site iden-tification number, date collected, and volume obtained were recorded on the collection data forms.

1 2.2.12 AQUATIC VEGEIATION Aquatic vegetation samples were taken semi-annually. Rooted species were obtained in shallow, quiescent areas of the-surface water during the grow-ing season when they were emergent. Filamentous (slime) species and mos-ses were obtained from submerged rocks.

Samples were collected with trowel or clippers where appropriate. Three to 5 lb of aquatic grass were collected.

Samples were sealed in bags with care taken not to include soil or foreign material. The sample site iden-tification number, date collected, sample type, and volume obtained were recorded on collection data forms.

2.3 YEARLY AGRICULTURAL SURVEY WITHIN 5-MILE RADIUS OF TROJAN 2.

3.1 INTRODUCTION

9 The annual survey of agricultural production within a 5-mile radius of Trojan Nuclear Plant was performed on August 12-13, 1981. Observations were nade of the dairy animals (cows and goats), meat animals (cattle and sheep), and vegetable gardens within this area.

This nurvey was completed by driving the roads within a 5-mile radius of Trojan and re-cording the location of any of the above-mentioned agricultural pro-duction activities.

2-15

l

w..

l' L

2.3.2 DAIRY ANIMALS Table 2.2 presents the' locations where cattle dairy animals were observed within the 5-mile radius of Trojan.

In Table 2.s and the following ta-bles the radial direction and' radial mileage from Tr.ojan are presented for each location. The radial direction is one of the 16 different com-I passhoints.. The radial'aileage was estimsted from map positions for each

' location. Each of the location tables is organized into 16 compass direc-tions, starting with the north direction and proceeding in a clockwise manner around the compass. Within each compass direction, the locations are presented in order of increasing radial distance. Table 2.3 presents the. locations where goat dairy animals were observed with the 5-mile radius of Trojan.

2.3.3 MEAT ANIMALS Table 2.4 precents the locations for cattle meat animals. Table 2.5 presents the locations for the sheep' meat animals.

2.3.4 VEGETABLE GARDENS Table 2.6 presents the locations for vegetable gardens within a 5-mile radius of Trojan.

I 2-16

't 6.: '. -.

lc, m

1..

r4 1,

l (q;

TABLE 2.2

- a u:q DAIRY ANIMALS, COWS W'TIIN FIVE MILES OF TROJAN - AUGUST 1981 s.

(a);

(a)

-Radial-Rsdial Number.

+

Direction.

Mileage of Cows NNE 4.7 30 1

a.-

ENE-4.2 1

S 2.3 1-S 2.9 1

SSW 4.4 3

SSW

'4.5 5

SSW 5.0 200

'SW 4.5.

6

SW 4.6 200 WSW 4.9 1

WNW 4.6 3

(a) Measured from Trojan Containment.

t 2 - __-__--_-. _

. r.

J TABLE 2.3 DAIRY ANIMALS - COATS

-l WITHIN FIVE MILES OF TROJAN - AUGUST 1981

~

(a)

Radial Radial

. Number Radial Radial Number Direction Milease of Goats Direction Mileage of Goats

~

N 4.9 2

SSW 3.8 1

NNE 3.0 1

SSW 4.4 21 NNE 3.1 1

SSW 4.5 1

NNE 4.1 1

SW l.5 1

NE 1.7 1

SW 3.4 1

NE 3.5 3

SW 4.0 1

NE 3.6 2

WSW 4.7 1

ENE 4.4 2

WSW 4.9 3

E 3.2 1

W 3.3 1

SE 4.6 2

WNW 4.6 1

SSE 1.8 1

NW 4.5 1

S 1.2 1

NW 4.8 25 S

1.3 2

NNW 3.0 1.

SSW l.3 I

NNW 3.1 1

SSW 2.0 11 NNW 3.2 1

(a) Measured from Trojan Containment.

2-18

i o*

' * ^ *

' TABLE 2.4 Sheet 1 of 2 p

W.AT ANINALS - CATTLE

.NITNIN FIVE MILES OF TROJAN - AUGUST 1981 (a)i..

. (a)

(a).

' (a)

-Radial v

- Radia].

Number Radial Radial Number Direction Milaase of Cattle Direction-Milease of Cattle-NNE 2.3 30 ENE.

4.0 24 NNE 3.9 1

ENE 4.3 17 NNE 4.0 2

ENE 4.4

'9 NNE:

4.2 "3

E 1.5 30 NNE

'4.3

-14 E

'2.3 15

.NNE 4.4.

5 E

2.6 3

NNE 4.5 2

E 2.7 4

NNE..

4.7 4

E 2.9' 3'

'FE 1.6 4

ESE

.3.7 9

NE 1.8 4

ESE 2.8 5

NE 2.2 1

ESE 4.6 2

NE 2.9 4

SE.

4.5 17 NE 3.5 2

SE 4.6 2

NE' 3.7 3

SE 5.0 10 NE 3.8 6

S 1.3 21 NE 4.3 28 S

2.3 4

NE 4.4 18 S

2.9 1

NE 4.5 7

s 4.8 31 NE 4.6 2

S 4.9 20 ENE 1.4 11 S

5.0 75 ENE 3.8 6.

SSW 1.3 4

(a) Measured from Trojan Containment.

2-19 e __ z m,,

-n:-

v j

TABLE 2.4 Sheet 2 of'2' ll (a)

(a)

- Radial Radial Number Radial' Radial Number Direction

.Ndlease

.of Cattle Direction Mileage of Cattle s.

SSW 1.4 15 WSW 3.3 15 SSW.

3.0 8

WSW 4.9 1

SSW 3.5 11 W

1.7 10 SSW 3.8 27 W

1.8 23 SSW-

'3.9 13 W

3.2 5

SSW 4.1 4

W 3.3 2.

SSW 4.4 9

W 4.0 13 SSW 4.5 3

W 4.1 6

SSW 4.8 5

W 4.9 11 SSW 5.0 7

W 5.0 2

SN 1.5 10 WNW 4.3 10 SW 1.8 12 WNW 4.6 5

SW 1.9 8

WNW 4.7 4

SW 3.2 5

NW 2.2 15 SW 3.3 10 NW 3.6 3

SW 3.4 6

NNW 2.4 25 SW 3.7 1

NNW 3.0 28 SW 4.0 16 NNW 3.2 2

SW 4.5 4

KNW 3.3 10 WSW 2.9 2

(a) Measured from Trojan Containment.

2-20 1

m _ _ _ _. - _. _ _.,.

5..'

.o

.O <

l

. :c'

T-e I

~

l i

s TABLE 2.3 NEAT AN1MALS - SHEEP 8

WITHIN FIVE MILES OF TROJAN - AUGUST 1981' (a)

(a) y Radial Radial Number i

J Direction Mileage of Sheep NE 3.1 5

E 2.2 20 j

SSW 4;4 5

(a) Measured from Trojan Containment.

t L

l-2-21 i

h b _' im___

41.) :

if TABLE.2.6 Sineet 1 of 4 VEGETABLE GARDENS WITElIN FIVE MILES OF TROJAN - AUGUST 1981 (a),

(a)

(a)-

Radial

~ Radial Number Radial Radial Number

_ Direction Ndlease of Gardens Direction Ndleage of Gardens N

4.9 1

NE 3.6 3

NNE 1.7 1

NE 3.7 3

NKE 1.8 1

NE 4.1 3

NNE 2.2 1

NE 4.2 4

NME 2.5 4

NE 4.3 4

NNE 2.6 1

NE 4.4 4

NNE-2.7 4

NE 4.5 2

NNE 3.1 1

NE 4.6 1

NNE 3.3 1

NE 4.7 2

NNE' 4.0 2

PE 4.8 1

NNE 4.1 4

ENE 3.6 1

NNE 4.2 3

ENE 3.7 1

NNE 4.3 2

ENE 4.0 1

NNE 4.7 1

ENE 4.I'

.1 NE 1.6 3

ENE 4.2 1

NE 1.7 3

ENE 4.3 2

NE 2.9 1

ENE 4.4 2

NE 3.3 2

E 1.6 2

NE 3.4 1

E 1.9 1

NE 3.5 3

E 2.0 1

(a) Measured from Trojan Containment.

2-22

(

1 l

l TABLE 2.6.

Sheet 2 of 4 l

(a)

Radial Radial Number Radial

' Radial Number Direction Mileage of Cardens Direction Mileage of Gardens

_. E 2.2 1

SE 3.4 2

E 2.3 3

SE 3.8 1

E 2.4 2

SE 3.9

.I E

2.6 6

SE 4.0 1

E 2.7 2

SE 4.5 1

E 2.9 1

SE 4.6 1

E 3.0 2

SE 4.7 1

1 E

3.1 1

SE 5.0 1

E 3.2 2

SSE 1.8 1

E 4.7 1

S 1.2 1

E 4.8 1

S 1.3 2

ESE 2.3 1

S 1.8 2

l ESE 2.5 1

S 2.9 3

ESE 2.7 1

S 3.0 2

ESE 2.8 1

S 4.8 2

ELE 4.7 1

SSW 1.5 1

f SE 2.4 1

SSW 3.0 1

SE 2.7 1

SSW 3.6 10 acres of straw-SE 2.9 2

berries SE 3.2 2

SSW 3.8 2

(a) Measured from Trojan Containment.

2-23

4, 9...

4

)

TABLE 2.6 Sheet 3 of 4 l

(a)

(a) l Radial-Radial Number

' Radial Radial Number-

. Direction Mileage of Gardens-Direction Mileage of Gardens

'SSW 3.9 2

WSW 4.6 2

SSW 4.0 2

W 1.7 1

SSW 4.1 2

W 1.8 2

2 4

SSW 4.4 3

W 3.1 1

SSW 4.5 1

W 3.2 1

'SSW.

4.6 1

W 3.3 3

SSW 4.?

1 W

4.0 2

SSW 4.8 2

W 4.1 1

SSW 5.0 1

W 4.8 1

l SW 1.5 1

W 5.0 6

SW 3.3 3

WNW 4.3 1

SW 3.7 2

WNW 4.5-2 SW 3.8 3

WNW 4.6 2

SW 3.9 1

WNW 4.7 2

SW 4.0 2

WNW 4.8 1

SW 4.5 1

NW 2.2 2

SW 4,6 1

NW 2.3 1

WSW 3.2 1

NW 3.7 5

WSW 3.3 2

NW 3.8 5

WSW 4.5 1

NW 3.9 7

(a) Measured from Trojan Containment.

2-24 r

O._ _, '

l i

l:

.i TABLE.2.6 Sheet'4 of 4-1:

.i i

'(a)

(a)

-(a)

(a)

Radial Radial Number Radial Radial Number i

Direction Mileage of Gardens, Direction Mileage.

of Gardens

_NW

'4.0 6-NNW 1.0 1

EW 4.1 10 NNW 1.1 3

l NW 4.2 2

NNW 2.2 1

NW 4.3 13 NNW 2.4 1

l NU 4.4 5

NNW 3.0 4

NW 4.5 2

NNW 3.1 3

NEW

.6 7

NNW 3.2 1

(a) Measured from Trojan Containment.

l 6

2-25

...-.__,_my_..-__.

_.v._

~

3.0 ANALYTICl:.L 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 USDOE (HASL' Procedures

Manual. HASL-300, Hecith and Safety Laboratory, U. S. Atomic Energy Commission, 376 Hudson Street, New York, NY 100:4) or those of the Federal Environmental Protection Agency (EPA).

Analyses or individual wample types, general methods, and routine anal-ytical 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 atandard methods (see Ref. 4), and are reported at the 95 percent confidence level (2a). The lower limit of detection (LLD) is defined as "that concentration which is 3 times the i

standard deviation error of the average concentration in a blank or back-ground sample". Analytical data for samples for which concentrations are less than or equal to the LLD are preceded by the symbol "(,".

3.2 AIR PARTICULATE _S 4

Gross beta concentrations are measured with low background gas flow (pro-portional and/or Geiger) counting systems with anti-coincidence background suppression.

The routine detection limit (LLD) is 0.002 pCi/m3 for gross 3

beta or gross alpha based on 300 m / week.

Gamma isotopic analyses are performed with a GeLi detector with a routine detection limit of about 0.05 pCi/m3 for most gamma emitters for single filters and about 0.01 pCi/m3 for monthly composite samples.

3-1 1

- ___ a

Table 3.1 TECHNICAL SPECIFICATION REQUIRED LIMITS AND REPORTED DETECTION LEVELS **

_ Required Analysis Required and Reported Detection Limits Air Particulate-gross beta 0.002 pCi/m3 Air Particulate-gross alpha 0.002 pC1/m3 Air PErticulste-gamma scan 0.3 pCi/m /nuclide 3

Air Radiciodine 0.1 pCi/m3 Precipitation-gross beta 0.3 pCi/ liter Precipitation-tritium 1000 pCi/ liter Precipitation-gamma scan 25 pCi/ liter /nuclide Terrestrial Soil-strontium 89/90 0.1 pCi/g(dry)

Terrestrial Soil-gacea scan 0.1 pCi/g/nuclide(dry)

Terrestrial Vegetation-strontium 89/90 5.0 pCi/Kg(wet) 0.4 pCi/g(dry)*

Terrestrial Vegetation-gamma scan 50 pci/Kg/nuclide(wet) 0.4 pCi/g(dry)*

Terrestrial Animal-strontium 89/90 5 pC1/Kg(wet)

Terrestrial Animal-gamma scan 50~pC1/Kg/nuclide(wet)

Milk-iodine-131 0.5 pCi/ liter Milk-strontium 89/90 1.0 pCi/ liter Milk-gamma scan 50 pCi/ liter Surface Water-gross beta 0.5 pCi/ liter Surface Water-tritium 1000 pCi/ liter Surface Water-Fanma scan 25 pCi/ liter Well Water-gross beta 0.5 pCi/ liter Well Water-tritium 1000 pCi/ liter Well Water-gamma scan 25 pCi/ liter Bottom Sediment-gamma scan 0.1 pCi/g/nuclide(dry)

Shoreline Soil-gamma scan 0.1 pCi/g/nuclide(dry)

. Aquatic Vegetation-st'ontium 89/90 5 pCi/Kg(wet) 0.04 pCi/g(dry)*

r Aquatic Vegetation-ganma scan 100 pCi/Kg/nuclide(wet) 0.9 pCi/g(dry)*

l Aquatic Animal-strontium 89/90 5 pCi/Kg(wet)

Aquatic Animal-gamma scan 100 pCi/Kg/nuclide(wet)

Direct Radiation 1.25 mR/ quarter change

It is assumed that 90 percent of gross weight'Is water.

- Stated as three standard deviations above average concentration in a blank

sample, 1

3-2 o_________

a

j.. y.

h 4

3.3 RAD 70 IODINE The charcoal cartridges used are of the TEDA-impregnated rype. The iodine-is extracted from the charcoal, chemically separated, and counted as Ag1 3

dsing wide beta or low beta counters which yield an-LLD of 0.1'pci/m.

l s

?.4 RAINFALL, SURFACE WATER, WELL WATER l Gross beta analysis of water samples is performed by evaporation of a measurea aliquot of the sample, digestir1, planchetting of the processed sample and radiometric assay by low-level beta counting, with en LLD of 0.5 pCi/1. Tritium analysis is performed on all vater samples to the required LLD of 1000 pCi/1 by liquid scintillation counting. Canna isotopic analysis is performed using a Celi detector with a routine LLD of 25 pCi/1 per gamma emitting radionuclides.

3.5 SOIL OR SEDIMENT Samples are oven-dried and results reported based on dry weight. Gamma emitters'are measured with a GeLi detector with an LLD as specified.

3.6 VEGETATION, MEAT, POULTRY, FISH, FOOD CROPS Measured amounts of these types of samples are analyzed for gamma emitters by gamma spectrometry with cotmting 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 low background beta counting. The LLD is 0.2 pC1/1 or better and the overall accuracy at 0.5 pCi/1 is 125 percent or better at the 95 percent confidence level.

Gamma emitters in milk are measured with a deli detector.

3-3

18 AMB!.ENT RADIATION MEASUREMENTS The responsibility for ambient radiation dose measurements resides with 1

1 fortland General Electric Company. A totc1 of 66 field locations were i

monitored with two dosimeters (one analyzed quarterly and one analyzed l

annually) at 22 locations and one dosimeter (analyzed quarterly) at 44 I

locations. The field dosimeters used thermoluminiscent radiation detec-tion materials with each dosimeter having more than two separate chips or measurement devices. The quarterly field dosimeters used Car 2:Dy (TLD-200) chips and the annual field dosimeters used Li-7 enriched LiF (TLD-700). For each field dosimeter, the chips were packed in a plastic foam and sealed in plastic containers. To minimize radiation enerEy depend-ence for the TLD-200 chips, the quarterly field dosimeters were shielded with a two-element filter of 30 mil tantalum and 2 mil lead as described in the report by Denham, et. al.

Calibration of the field dosimeters was performed with a 2.5 mci Cs-137 source traceable to the U. S. National Bureau of Standards. Calibration dosimeters were prepared fcr each readout of the field dosimeters. The dosimeter readout was done with an Eberline Model TLR-1 reader.

3.9 QUALITY CONTROL Approximately 15 percent of the analyses performed by the laboratory are for quality control purposes. The laboratory participates in Environ-mental Protection Agency, International Atomic Energy Agency, Nuclear Regulatory Commission, several states', and other intercalibration prco-grams. Reports of all quality control analyses are reported monthly to the osner.

Results of EPA intercalibrations (for which "known" data are available) are given in Table 3.2.

Table 3.3 presents the results from participation in the U.CDOE Quality Assessment Program. In those cases where discrepant values are obtained, an investigation is undertaken to determine the cause, and corrective action as required. Table 3.4 sum-marizes the intraleboratory quality control results for the year 1981.

Table 3.5 presents the results for an EPA special laboratory evaluation sample.

3-4

.~4 :. p '

4 4

3.10 REFERENCES POR ANALYTICAL PROCEDURES l'. 'American Pulbic Health Association, American Water Works Association p

t_

and Water Pollution Control Federation (1971): Standard Methods for.

the Examination of Water and Wastewater. Thirteenth edition, pp. 583-632; 12th edition, pp. 325-352. APHA, 1740 Broadway, New York, 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.

3.

Atomic Energy Commission: Regulatory Guide. 4.3 (September 1973) 4.

Health and Safety Laboratory, Atomic Energy Commission: HASL Procedires M.mual (now known as EML of the Department of Energy). - HASL, 376 Hu 3 son Street, New York, NY 10014.

~

5.

National Environmental Research Center, Environmental Protection Afency; Handbook of Radiochemical Analytical Methods. Program Element IMA 325.

Office of Research and Development, Las Vegas, NV 89114.

6.

Denham, D.

H., R. L. Kathren, and J. P. Corley, "A CaF.Dy Thermolumin-2 escent Dosimeter for Environmental Monitoring", USAEC Report BNWL-SA-4191 (1972).

9 e

3-5

TABLE 3.2, Sheet 1 of 3 1981 EPA INTERCOMPARISON RESULTS Control NWF

' Sample Agency Limits Measured Month / Year' Type Analysis Valve 13 0. n= 3) 12e error

Units Dect:iber 1980 UAter Iodine-131 22 6

1712 pCi/ liter D:csaber 1980 Water Tritium 2240 604 26001300 pCi/ liter DJcuber.19'80 Air Filter Gross Alpha 21 9.1 2112 pCi/ filter December 1980 Air Filter Gross Beta 19 8.7 2813 pCi/ filter December 1980 Air Filter Strontium-90 0

0

<1 pCi/ filter

'Dece ber 1980. Air Filter Cesium-137 19 d.7 1912 pCi/ filter Jnnusry 1981 Water Cross Alpha 9

8.7 1011 pCi/ liter Janusry 1981 Water Gross Beta 44 8.7 4314 pCi/ liter January 1981 Water Strontium-89 16 8.7

<5 pCi/ liter January 1981 Water Strontium-90 34 2.9 3524 pC1/ liter Janu ry 1981 Milk Strontium-89 0

0 (2

pCi/ liter January 1981 Milk Strontium-90 20.2 2.6 1411 pCi/ liter January 1981 Milk Iodine-131 25.8 10.4 2913 pCi/ liter J:nutry 1981 Milk Cesium-137 43.5 8.7 4715.

pCi/ liter

. January 1981 Milk Barium-140 0

0

<25 pCi/ liter January 1981 Milk Potassium 1551 134 13501140 pCi/ liter February 1981 Water Tritium 1760 590 16801170 pCi/ liter February 1981 Water Chromium-51 0

0

<100 pci/ liter F4brurry 1981 Water Cobalt-60 25 8.7 2915 pct / liter February 1981 Water Zinc-65 85 8.7 9219 pCi/ liter February 1981 Water Ruthenium-106 0

0

<100 pCL/ liter February 1981 Water Cesium-134 36 8.7 2915 pCi/ liter F2bru:ry 1981 Water Cesium-137 4

8.7 923 pCi/ liter March 1981 Water Gross Beta 25 8.7 2713 pCi/ liter March 1981 Water Cross Alpha 25 10.4 2012 pCi/ liter March 1981 Air Filter-Cross Alpha 30 13 30 3 pCi/ filter March 1981 Air Filter Gross Beta 50 8.7 6627 pCi/ filter March 1981 Air' Filter Strontium-90 18 2.6 1714 pCi/ filter March 1981 Air Filter cenium-137 14 8.7 1512 pCi/ filter April 1981 Water Tritium 2710 615 30001300 pCi/ liter April 1981 Water Cesium-134 10 8.7 712 pCi/ liter April.

1981 'ater Cesium-137 15 8.7 1311 pCi/ liter April 1981 Water Strontium-89 38 8.7 3527 pCi/ liter April 1981 Water.

Strontium-90 28 2.6 2413 pCi/ liter

. April 1981 Water Radium-226 15.0 4.0 13.211.3 pCi/ liter April 1981 Water Radium-228 12.0 3.1 1012 pCi/ liter April 1981 Water Uranium 12 10 612 pCi/ liter May 1981 Water Strontium-89 36 8.7 2913 pCi/litar May 1981 Water Strontium-90 22 2.6 2623 pCi/ liter May 1981 Water Strontium-89 25 8.7 3018 pCi/ liter May 19,81 Water Strontium-90 11 3.6

'422 pCi/ liter i May 1981 Water Iodine-131 26 10 40120 pCi/ liter l

May 1981 Water Cesium-137 22 8.7 2015 pCi/ liter

When analyses of a particular type result in concentrations below the detection limits, the term "LT" is used to indicate "Less Than" values for that measurement based on 3a (99.5%) confidence level.

3-6

4 TABLE 3.2 Sheet 2 of 3 Control MWF Sample Agency Limi.ts Measured Month / Year Type Analysis Value (3o.n= )

12e error Units May 1981 Water Barium-140 0

0

< 20 PCi/ liter May

--1981 Water Potassium 1559 135 14001140 mg/ liter Juns 1981 Water Chromium-51 0

0

< 20 PCi/ liter Juns 1981 Water Cobalt-60 17 8.7 1612 pCi/ liter

. June 1981 Water Zine-65 0

0

< 20 pCi/ liter June 1981 Water Ruthenium-106 15 8.7 1514 pCi/ liter Juns 1981 Water Cesium-134 21 8.7 1312 pCi/ liter June 1981 Water Cesium-137 31 8.7 2513 pCi/ liter June 1981 Water Tritium 1950 596 23001200 pCi/ liter Juns 1981 Water Radium-226 6.7 1.7 5.910.4 pCi/ liter

~

Juna 1981 Water Radium-228 8.0 2.1 10.611.6 pCi/ liter June 1981 Air filter Gross alpha 28 12 3116 pCi/ filter June 1981 Air filter Gross beta 54 8.7 7418 pC1/ filter June 1981 Air filter Strontium-90 19 2.6 2115 pCi/ filter June 1981 Air filter Cerium-137 16 8.'7 1512 pCi/ filter July 1981 Food Strontium-89 44 8.7 3814 pCi/ kilogram July 1981 Food Strontium-90 31 2.8 2813 pCi/ kilogram July 1981 Food lodine *131 82 14 7510 pC1/ kilogram July 1981 Food Cesium-137 45 8.7 4014 pCi/ kilogram July.

1981 Food Barium-140 0

0

<25 pCi/ kilogram July 1981 Food Potassium 2640 229 22671227 mg/ kilogram July 1981 Milk Strontium-89 25 8.7 1313 pCi/ liter July 1981 Milk Strontium-90 17 2.6 1613 pCi/ liter July 1981 Milk Iodine-131 0

0

<5 pC1/11ter July 1981 Hilk Cesium-137 31 8.7 35112 pCi/ liter July 1981 Milk Barium-140 0

0

<16 pCi/ liter July 1981 Milk Potassium 1600 139 14631305 mg/ liter Aunust 1981 Water Iodine-131 73 13 53111 pCi/ liter August 1981 Water Tritium 2630 613 29731878 pCi/ liter August 1981 Water Uranium 23 10 1412 pCi/ liter September 1981 Water Strontium-89 23 8.7 1815 pC1/ liter September 1981 Water Strontium-90 11 2.6 1412 pCi/ liter September 1981 Urine Tritium 2050 599 21661624 pCi/ liter

{

September 1981 Water Radium-226 8.3 2.2 8.410.8 pCi/ liter i

Feptember 1981 Water Radium-228 11.7 3.0 4.613.7 pCi/ liter September 1981 Water Cross alpha 33 4

32114 pCi/ liter September 1981 Water Gross beta 28 8.7 3016 pCi/ liter September 1981 Air filter Gross alpha 25 11 2516 pCi/ffiter Septer.ber 1981 Air filter Gross beta 52 8.7 7117 PCi/ filter September 1981 Air filter Strontium-90 16 2.6 1812 pCi/ filter September 1981 Air filter Cesium-137 19 8.7 2012 pCi/ filter

)

i 3-7 j

,{

I TABLE 3.3 Sheet 3 of 3 Control MWF i

Sample Agency Limits.

Measured Month / Year Type Analysis Value (3a.n= )

2 20 error Units Oct:bar 1981 kater Gross alpha 80 35 91126 pCi/ liter Octtber 1981 Water Gross beta 96 8.7 112111 pCi/ liter Octcber 1981 Water Cobalt-60 0

0

<5 pCi/ liter

' Octtber 1981 Water Strontium-89 21 8.7 1316 pCi/ liter Octcber 1981 Water Strontium-90 14.4 2.6 14.612.0 pCi/ liter Octcher 1981 Water Cesium-134 12 2.6 1422 pCi/ liter l Octobr.r 1981 Water Cesium-137 15 8.7 20114 pCi/ liter i

October 1981 Water Radium-226 12.7 3.3 11.813.5 pCi/ liter Octohsr 1981 Water Radium-228 9.2 2.4 8.315.1 pCi/ liter Octab r 1981 Water Cross Uranium 15 10 912 pCi/ liter Octtber 1981 1111k Strontium-89 23 8.7 2418 pC1/ liter Octcbar 1981 Milk Strontium-90 18 2.6 1425 pci/ liter Octcber 1981 Milk Iodine-131 52 10 58211 pCi/ liter October 1981 Milk Cesium-137 25 8.7 2919 pCi/ liter Octcher 1981 Milk Earium-140 0

0

<16 pCi/ liter Octcber 1981 Milk Potassium 1530 133 17001240 mg/ liter November.

1981 Food Strontium-89 38 8.7 4116 pCi/ kilogram November 1981 Food Strontium-90 23 2.6 2115 pC1/ kilogram

' November 1981 Food Cobalt-60 30 8.7 3528 pci/ kilogram Nov= ber 1981 Food Cesium-137 33 8.7 3218 pC1/ kilogram N:vember_

1981 Food Barium-140 0

0

<31 pCi/ kilogram

{

November 1981 Food Pctassium 2730 236 27001270 mg/ kilogram Decemb3r 1981 Water Tritium 2700 615 2950*127 pCi/ liter l

i d

j l

3-8

_______2__---_

j

TABLE 3.3 1981 USDOE QUALITY ASSESSMENT PROGRAM i

sample Measured Type Nuclide Known 12e error Units Air (81-04)

Be-7 0.244 E+04 0.24720.015 E+04 pCi/ filter Air (81-04)

Mn-54 0.117 E+03 0.09320.006 E+03 pCi/ filter

~ Air (81-04)

Sr-89 0.450 E+02 0.51510.087 E+02 pCi/ filter l

Air (81-04)

Sr-90 0.630 E+01

<0.100 E+02 pCi/ filter Air (81-04)

Zr-95 0.122 E+03 0.82810.048 E+02 pCi/ filter Air (81-04)

Sb-125 0.139 E+04 0.13320.006 E+04 pCi/ filter Air (81-04)

Cs-134 0.190 E+04 0.13310.007 E+04 pCi/ filter Air (81-04)

U 0.223 E+01 0.75010.053 E+01 pCi/ filter Soil (81-04)

K-40 0.213 E+02 0.29020.017 E+02 pC1/g Soil (81-04)

Cs-137 0.200 E+00 0.25010.070 E+00 pCi/g Soil (81-04)

Ra-226 0.770 E+00 0.66810.057 E+00 pCi/g Tissue (81-04)

K-40 0.158 E+01 0.43320.058 E+01 pCi/g Tissue (81-04)

Sr-90 0.240 E+01 0.18820.016 E+01 pCi/g Tissue (81-04)

Ra-226 0.450 E+00 0.43320.058 EMO pCi/g Tissue (81-04)

U O.290 E-01 0.85010.333 E-01 pCi/g Vegetation (81-04)

K-40 0.224 E+03 0.27710.018 E+03 pCi/g Vegetation (81-04)

Sr-90 0.560 E+01 0.25820.016 EMI pCi/g Vegetation (81-04)

Cs-137 0.230 E+00 0.20010.058 E+00 pCi/g Vegetation (81-04)

U 0.310 E+00 0.13310.058 E+00 pCi/g Water (81-04)

H-3 0.246 E+02 0.19710.012 E+02 pCi/ml Water (81-04)

Co-57 0.118 EMI 0.24320.018 E+01 pCi/ml Water (81-04)

Co-60 0.129 EMI 0.13310.006 E+01 pCi/mi Water (81-04)

Sr-90 0.440 E-01 0.40520.063 E-01 pCi/ml Water (81-04-)

Cs-137 0.137 E+01 0.15010.012 E+01 pti/ml Water (81-04)

Ce-141 0.527 E+01 0.19310.012 E+01 pCi/ml Water (81-04)

U 0.145 E-01 0.20010.026 E-01 pg/ml Water (81-04)

U 0.102 E-01 0.75010.140 E-02 pCi/ml i

3-9

.-p 1

1 l

CABLE 3.4 1

1981 QUALITY CONTROL ANALYSES

SUMMARY

l i

The tables below summarize results of samples run for process quality contol purposes during the subject year. These listings are in addition i

to.such measurements as detector backgrounds, check source values, ra-diometric-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 Anulyses Exceeding Analyzed Determinations the LLD for That Analysis Gross beta 46

?*

i Gross alpha 47 0

Strontium-89 95 0

Strontium-90 95 0

Tritium 61 1*

Gamma emitters 64 0

Iodine-131 191 0

Calcium-45 3

0 SPLIT SAMPLES Nuclide Number of No. Agrecing No. Agreing No. Differing Analyzed

, Det'ns Within 2a Within 3o by > 3a Gross beta 142 138 4

0 Gross alpha 39 38 1

0 Gamma emitters 126 122 4

0 Iodine-131 146 146 0

0 Strontium-89 38 38 0

0 Strontium-90 44 42 2

0 Tritium 89 89 0

0 Calcium-45 8

8 0

0 Uranium 71 71 0

0 SPIKED SAMPLES Nuclide Number of Within 2g Within 3a Differing From Analyzed Det'ns of Known of Known Known by > 3a Gross beta 55 53 1

1*

Gamma emitters 44 43 1

0 Iodine-131 11 11 0

0 Strontium-89 18 18 0

0 Strontium-90 94 93 1

0 Tritium 45 44 1

0

Corrective actions were taken to eliminate the problen.

3-10

^

TABLE 3.5 f~

L 1981 EPA SPECIAL LABORATORY EVALUATION SA'fPLE Lab Performance Evaluation Study-EMSL-LV Control MWF Sample Agency Limits Mea'sured Type Analysis Value (3o.n=1) 22o error Units Water Gross alpha 39 10 3914 pCi/ liter Water Cross beta 60 5

7017 pCi/ liter Water Cobalt-60 12 5

<20 pCi/ liter Water Cesium-134 12 5

1112 pCi/ liter Water Cesium-137 20 5

2012 pCi/ liter Water Ruthenium-106 b

<100 pCi/ liter 1

Water Zine-65 0

<20 pCi/ liter

- Water Strontium-89 6

5 511 pCi/ liter Water Strontium-90 0

<1 pCi/ liter Water Radium-226 12.8 1.8 12.621.3 pC1/ liter Water Uranium 5

6 412 pCi/ liter 9

3-11

1 4.0, RESULTS AND DISCUSSION lL 4.1 SAMPLES FROM THE TERRESTRIAL ENVIRONMENT 4.1.1 AIR PARTICULATE AND AIRBORNE I-131 s

The gross beta particulate data obtained Curing the first six-month period of 1981 are higher than the data obtained during the latter half of 1981. For example, a review of the data in Section 5 indicates that the gross beta particulate radioactivity was usually greater than 0.1 j;

pCi/m3 until about June 1981. From June 1981 until mid-August'1981, these values decreased to levels of less than 0.01 pCi/m3 by: late Decem-ber 1981. Average concentrations.for the yearn 1981 and before are com-

. pared below between onsite and offsite locations.

pCi/m3 Preoper-ational 1976 1977 1978 1979 1980 1981 Trojan

.021.02.021.06

.03.04

.02.02

.01.01

_.03.04

.111.02 (Onsite) l Oregon'

..02.02

.03!.08

.04.04.021.01

.01.01

.031.04.11.04

-(Offsite)

Washington.03.02-.02.04.051.02

.02!.02

.01!.01

.02.04

.112.01.

(Offsite)

The' decreased concentrations in 1977 and 1978 vere due to reduction in the amottnt of fallout from recent atmospheric explosions.

In October 1980, the Peoples' Republic of China tested a nuclear device in the atmosphere.

For the above reasons, the: increased concentrations in 1981 were due to increased fallout levels from the October 1980 Chinese test and not Trojan operations.

Air Particulate filters with gross beta levels exceeding 0.1 pCi/m3 were analyzed by gamma spectrometry and were 1:elow the detection limit of 0.3 3

pCi/m /nuclide.

Grocs alpha concentrations were at or below the detection limit of 0.002 3

.pCi/m -for all samples. Airborne I-131 collected in charcoal cartridges l"

4 4-1

{

t 1

ll 0

';e p-i'

.wasubelow the detection limit of 0.1 pCi/m3'(at collection) in all i

1 cases.-

Data for these samples are listed in Section 5.0, Pages 5-2 through 5-12.

.~

1' 4.1.2 TERRESTRIAL ANIMALS

~5emples of various organs from beef cattle, goats, oppossums, and a rabbit were collected and analyzed for gross beta, radiostrontium, and gamma emitters. The only radioactivity detected in the samples originated from either fallout or natural sources.

Data are listed in Section 5.0 on Pages 5-13 through 5-15.

4.1.3 FOOD CROPS Samples of food crops were collected from two locations and analyzed for gross beta, radiostrontium, and gamma emitters.

Sr-90, Ce-144, and Cs-137 were detected at low concentrations in many samples and are attribu-ted to worldwide fallout. Gross beta activity was detected and is due to either other then natural fallon; or natural radioactivity.

Sr-89 and gamma emitting radionuclides were not detected in food crop samples. The data are presented in Section 5.0, Page 5-16.

4.1.4 TERRESTRIAL VEGETATION Samples of grass were taken at six locations and analyzed for gioss beta, radiostrontium, and gamma emitters. The radioactivity observed in these samples was typical in type and concentration to what is to be expected from natural, fallout, and cosmogenic origins. As has been discussed in Section 4.1.1, the activity detected in these grass samples was from the October 1980 nucicar device test by the People' Republic of China and is not attributable to operation of the Trojan Nuclear Plant. Data are presented in Section 5.0, Page 5-17.

4-2

K p,

,0 h

4.1.5 WELL WATER 1Well water samples'were collected quarterly from five locations. Low levels of gross beta radioactivity were. detected which are to be expected from natural sources. Tritium and gamma emitter levels were below the y

lt<

,sensitiv,ity requirements of.the program. Data are presented in Section 5.0 on Page 5-18.

4.1.6 MILK Milk samples were collected from six locations, although the Rinck Dairy in Alston (63) was deleted from the program-following the February col-

'lection-(Sie Section 2.1).

Samples were analyzed for I-131, radio-strontium, and gamma emitters. Most samples contained Sr-90 which is attributable to worldwide fallout. No samples contained I-131, Sr-89, or' gamma emitters-(other than naturally occurring nuclides) at' detect-able: levels, which confirms that the Sr-90 is attributable to worldwide

~

fallout.. Data are presented in Fection 5.0 on Pages 5-19 through 5-21.

4.1.7 SOIL Soil. samples were collected from seven locations an'd analyzed for gross beta, gamma' isotopic, and radiostrontium concentrations. Data indicate the presence of no radioactivity attributable to the operation of Tro-jan. Traces of Cs-137 and Sr-90 were found in most samples. The pres-ence-of these two nuclides is attributed to worldwide fallout from

~

atmospheric nuclear tests (See Section 4.1.1).

Data are presented in Section 5.0, Page.5-22.

4.1.8 PRECIPITATION Monthly samples of precipitation were collected from three locations and analyzed for gross beta and tritium content.

Samples with a gross beca

-concentration of greater than 10 pCi/1 were analyzed for gamma emitters by gamma spectrometry (GeLi). During the period, 14 samoles were analyzed for gamma emitters.- Radionuclides (other than natural) were not detected 4-3 i

2

4

. in.any of the.14.' samples.

1though numerical' differences in gross beta o-

~ concentrations were observed in the samples, there were no significant

' differences between stations based on the samma data which are much more useful for; comparison that are the beta data. It should be noted that for these samples, as for the.tir particulate, the use"of different nuclides as re(erences for gross beta measurements may produce apparent differences between the data in:this report and those provided by other contractors.

Since gross beta analyses are'" survey" data, these differences are not.

significant. -Data are presented in Section 5.0 on Page 5-23.

~ 4.1.9' AMBIENT RADIATION LEVELS Ambient dose rates in mR/ day from the quarterly and annual dosimeters for 22 measurement. locations that have been established since before the Tro-jan Nuc1'ar Plant began operations are shown on Page 5-24.

The mean and e

standard deviation for the quarterly dosimeter data from these 22 locations was calculated to be 0.1310.02 mR/ day, which does not differ afsnificantly

. from the ambient dose rate of about 0.13 mR/ day measured in previous years. -

The means and standard deviations were also calculated for the three geographical. groups in 1981, the mean daily dose rates were 0.1120.03 mR/ day for the eight Trojan.onsite locations, 0.1410.02 mR/ day for the seven Oregon locations, and 0.1210.02 mR/ day for the seven Washington locations, which also agrees with the similar data from 1980 and'before.

Furthermore, the ambient gamma radiation data on Pages 5-24 through 5-26 were analyzed for dose rate differences in the four major compass direc-tions from the Trojan Nuclear Plant and no significant differences were found.

The mean and standard deviation for the annual dosimeter data was calcula-ted to be 0.1220.02 mR/ day. The annual dosimeter data for 1981 agrees with the quarterly dorimeter data for 1981 and does not differ signifi-

. cantly frc a the ambient dose rate of about 0.13 mR/ day measured in previous years.

t.

4-4

_ = _ - _ _ =

4.2 SAMPLES FROM THE AQUATIC ENVIRONMENT 4.2.1 SURFACE WATER AND DRINKING WATER SAMPLES Surface water samples were collected monthly and quartet 1y from locations near the, Trojan site and included samples from the Columbia River, ponds, and municipal water supplies.

Analyses were made for gross beta activity, tritium, and gamma emitters with the data presented in Section 5.0, Pages 5-27 through 5-30.

No activity which is attributable to operation of the Trojan Nuclear Plant was detected in any of the water samples.

4.2.2 SEDIMENT AND SHORELINE SOIL Sediment and shoreline soil were collected from lakes and streams

'.n the Trojan area as well as from the Columbia River. Naturally occurring radionuclides.s and fallout radioactivity are present in these samples.

Samples from the river may also contain traces of longer-lived activity from operations at the Hanford Project. Data are presented in Section 5.0, Page-5-31.

4.2.3 AQUATIC PLANTS Aquatic plants were sampled semi-ennually from the Columbia River and ponds in the vicinity of the Trojan Nuclear Plant and analyzed for gross beta, Sr-89/90, and gamma emitter concentrations.

Several of the aquatic plant samples had measureable amounts of Sr-90 with two Columbia River l

samples (CR5, 03/27/81; and CR3, 09/02/81) having concentrations higher than measured in the previous three years. This Sr-90 is due to worldwide fallout (See Section 4.1.1).

Detectable concentrations of Mn-54, Co-57, Co-58, Co-60, Zr-95, Nb-95, Ru-103, Ru-106, Sb-125, Cs-134. Cs-137, Ce-141,

]

and Ce-144 were found in some of the Columbia River samples. It is pos-I sible that these radioactivities were a result of plant operations. How-ever, since the radioactivity levels at the upstream location (CRS) were I

essentially the same as at the outfall location (CR3), the radioactivity 4-5 l

s

1 was likely due to fallout. Except for Ce-144 and Ru-106, which are probablyLdue to fallout (See Section 4.1.1), the measured concentrations were less than the design objective values in the Trojan Environmental

-Technical Specifications for edible leafy vegetables such s.s lettuce.

Data are presented in Section 5.0 on Pages 5-32 and 5-33.

s 4.2.4 FISH i

Fish were collected twice during the year and when the sample was large enough, muscle, viscera, and bone were analyzed separately for gross beta j

concentration, Sr-89/90, and gamma emitters.

Small fish were analyzed l

whole. No radioactivity attributable to the Trojan Nuclear Plant was-i detected in any of the samples analyzed. The only non-naturally occurring I

i radionuclides detected was Sr-90 which is due to longterm worldwide fallout (See Section 4.1.1).

Data are presented in Section 5.0 on Pages 5-34 and 5-35.

t 4-6

5.0 COMMENTS ON, AND TERMS USED IN DATA TABLES Wet Weight A reporting unit used with organic tissue samples such as vegetation and 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 soil and sediment 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.

pC1/m3 A reporting unit used with air particulate and radioiodine 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 (GeLi) gamma or spectrometry. The resulting spectrum is analyzed by a Gamma Isotopic computer program which scans from 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.

NA, NS, NR Used in place of a concentration value when a sample was not available (NA), or when a sample was not analyzed for some specific measurement (NS), or when an analysis is not requ' red (NR).

Error Terms Figures following "1" 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 3o (99 percent confidence) level.

Sensitivity In general, all analyses meet the sensitivity requirements of the program as given in Table 3.1.

For Lne icw samples that do noc (because cf inadequate sample quantities, ana-lytical interference, etc.) the sensitivity actually ob-tained 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 presenting a whole page of "<" data.

If all but one or two data points are below the sensitivity limits, the previously mentioned ccmvention is followed and the finite data are given as footnotes.

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' PORTIAND GENERAL ELECTRIC J

.f

SUMMARY

- GROSS BETA in AIR SAMPLES pCi/m3 Average Maximum Minimum Trojan On-Site Stetions IF 0.104 0.347 0.008 1H 0.119 0.435 0.006 11 0.116 0.398 0.010 Oregon Stations 2

0.110 0.350 0.010 3

0.098 0.327 0.006 5-0.116 0.405 0.005 6B' O.132 0.530 0.011 19 0.117 0.422 0.008 Washington Stations 9B 0.111 0.379 0.008 10 0.105 0.313 0.004 11B 0.104 0.330 0.008 14 0.099 0.286 0.004 W

5-10 L

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PORTLAND GENERAL ELECTRIC i

GROSS ALPilA ANALYSIS OF AIR PARTICULATE

3 Average pCi/m Month _

Oross Alpha s

January

<0.002 February

<0.002 March

<0.002 April

<0.002 May

<0.002 June

<0.002 July

<0.002 August

<0.002 September

<0.002 October

<0.002 November

<0.002 December

<0.002

For date received, volume and an.ilysis date--see gross beta sheets.

5-12

j PORTLAND GENERAL ELEC1'RIC Sheet 1 of 3 RADI0 ACTIVITY IN ANIMAL TISSUE (Semiannual Collections)

Tissue pCi/g Wet Weight Andlyzed Gross Beta Sr-89 Sr-90 Gamma Emitters l

Beef Collected 03/11/81 at 3 Thyroid 2.920.4

<0.021(a) <0.023(a)

<0.05 Liver 2.2 0.3

<0.005

<0.05 Muscle 4.010.4

<0.008(b) <0.008(b)

<0.05 l

Bone 2.5!0.4

<0.009(b) 0.824t0.082

<0.05 Beef Collected 03/11/81 at 16 Thyroid 2.1 0.6

<0.009(b) <0.00t9(b)

<0.05 Liver 3.1!0.3

<0.009(b) <0.008(b)

<0.05 Muscle 2.420.3

<0.003(b) <0.003(b)

<0.05 Bone 0.810.5

<0.005 0.872i0.067

<0.05 Goat Collected 03/11/81 at 63 Thyroid 2.5 0.3

<0.037(s) <0.037(a)

<0.05 Liver 2.910.3

<0.005 0.113!0.011

<0.05 Muscle 3.610.4 (0.005

<0.005

<0.05 Bone 0.7 0.4

<0.005 0.46410.046 (0.05 I

Goat Collected 03/11/81 at 37A Thyroid 3.42u.a

<0.050(a) <0.060(a)

<0.05 Liver 3.2io.3

<0.005

<0.05 Muscle 1.0!0.2

<0.006(b) <0.007(b)

<0.05 Bone 3.3t0.5

<0.003(b) 0.318 0.032

<0.05 (a)

Insufficient sample for more sensitive analysis.

(b)

Lower sensitivity due to low chemical recovery.

(c) Cs-137 = 0.06 0.02.

5-13

.,e m

PORTLAND GENERAL ELECTRIC-Sheet 2 of 3 RADIO!.CTIVITY IN' ANIMAL TISSUE (Semiannual Collections)

Tissue DCi/a Wet weight

-Ahalyzed Gross Beta Sr-89 Sr-90 Gamma Emitters i

p Possum Collected 03/12/81 et 17, Thyroid 1.7 0.2

<0.042(s) <0,051(a)

<0.05 Liver 1.7t0.2

<0.010(a) <0.010(a)

(0.05 Muscle 2.310.4

<0.011(a) 0.08310.016

<0.05 Bone 3.0 0.4

<0.008(a) 0.28510.029

<0.05 Possum Collected 03/17/81 at 1A

. Thyroid 2.410.3

<0.728(a) <0.739(a)

<0.22(a)

Liver 2.1:t0. 3

<0,016(a) <0.016(a)

<0.05 Muscle 2.110.4

<0.017(a) <0.019(a)

<0.05 Bone 2.910.4

<0.009(a) 0.17010.017 (0.05 Beef Collected _04/13/81 at 5 Thyroid-3.210.3

<0.005 0.00610.005

<0.05 Liver 3.510.4

<0.005

<0.05 (c)

Muscle 2.510.3

<0.005

<0.05 Bone 7.5 0.8

<0.016(b)2.4610.25

<0.05 Rabbit Collect.ed 04/12/81 at 11B Thyroid 3.210.5

<0.097(a) <0.097(a)

<0.86(a)

Liver 1.0 0.1

<0.043(a) <0.043(a)

<0.05 (d)

Muscle 1.410.1

<0.016(a) 0.023!0.016

<0.05 (e)

Bone 2.510.3

<0.269(a) 0.33710.255

<0.10 (a, f )

Io.

(a) Insufficient sample for more sensitive analysis.

l (b) Lower sensitivity due to low chemical recovery and problem associated with chemistry of bone samples.

(c) Cs-137 = 0.07!0.01 (d) Cs-137 = 0.13!0.04 (e) Cs-137 = 0.0910.03 i

(f) Cs-137 = 0.1510.06

{

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i 5-14 i

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4 o

PORTLAND GENERAL ELECTRIC Sheet 3 Of 3 RADI0 ACTIVITY IN ANIMAL TISSUE l

(Semiannual Collections)

Tissue pCi/g Wet Weight Analyz,ed Oross Beta

,Sr-89 Br-90 casuna Emitters i

Goat Collected 09/23/81 at 17A 1

Thyroid 0.610.2

<0.076 (a) <0.076(a)

<0.05(b)

Liver 1.:810.2

<0.005

.0031.002

<0.05 Muscle 1.810.2

<0.005

.006.002

<0.05 Heart 0.910.2

<0. 012 (a)

.0282.010

<0.05

^

i i

Beef Collected 09/23/81 at 16 Thyroid 0.5 0.1

<0.005-

<0.005

<0.05 Liver 2.0!C.3

<0.016 fc)-.0441.015

<0.05

' Muscle

-4.910.5

<0.005

<0.05 -

Heart 1.6 0,2

<0.005

,007t.002

<0.05 (a)

Lower sensitivity due to insufficient sample.

(b) Cs-137 = 0.1710.04 (c) Lower sensitivity due to low chemical yield.

5-15 L______

's i' FORT 1AND GENERAL ELECTRIC TROJAN NUCLEAR FIANT l'

J RADI0 ACTIVITY in PRODUCE SAMPLES (Semiannual Collections)

PCi/a Wet Weight a

Sample Type Grcss 8 y Emitters

_ Sr-89 sr-90 Collected 06/24/81 at 1-7 Lettuce (a) 5.220.5

<0.05(b)

<0.002(c) 0.01110.005 Cabbage 2.610.3

<0.05 (0.006 (c).

0.023:0.008 Carrots (a) 4.100.4 (0.05

<0.003(c) 0.01810.004 Potatoes 0.120.1

<0.05

<0. 00? (d) 0.01410.002 Onions 5.5!0.6

<0.05

<0. 004 (c) 0.03420.004 Collected 08/11/81 at 1-1 Blackberries 1.2 0.1

<0.05

<0. 007 (c)

<0.008(c)

Lettuce 4.110.1

<0.05

<0.002 (c) 0.05020.005 Squash 1.710.2

<0.05

<0.003(c) 0.00410.002 Carrots 4.310.4

<0.05

<0.003(c) 0.01910.004 Onions 2.310.2

<0.05

<0.003(c) 0.01710.003 Collected 08/26-27/81 at 1-I Cucumber (a) 1.5 0.2

<0.05

<0.003 (c) 0.009!0.004 Lettuce (a) 2.810.3

<0.05

<0.002(c) 0.01120.002 Swiss Chard (a) 7.510.8

<0.05

<0.004(c)

<0.006(c)

Apples 0.910.1

<0.05

<0.001 0.00510.002 Collected 08/27/81 at 1-C Apples 1.110.1 (0.05

<0.005(e) 0.01610.005 (a) State Split sample.

(b) Cs-137 - 0.05 0.01, Ce-144 = 0.410.1.

(c)' Insufficient sample for more sensitive analysis.

(d)- Insufficient sample was used for analysis.

(c) Lower sensitivity due to low chemical yield.

5-16

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PORTLAND GENERAL ELECTRIC RADIOACTIVITY IN SOIL SAMPLE (Semiannual Collections}

' Collection DCi/g Dry Weight' Date

' Gross Beta Sr-89 Sr Cs-137 Other Gamma Location 1A 03/18/81 7.3 1.1

.<0.01 0.0910.02 0.610.1

<0.1 09/08/81 4.010.9

<0.01 0.14 0.01 2.510.3

<0.1' Location IF

'03/18/81 4.611.0

<0.01 0.03!0.01

<0.1

<0.3

'09/08/81 2.110.7

<0.01-0.02!0.01

<0.1

<0.1 (a)

Location II 03/18/81 3.310.9

<0.01 0.1820.02 0.410.1

<0.1 09/08/81 2.9 0.9

<0.01

'O.22t0.02 0.210.1

<0.1 Location 3 03/18/81

.2.210.8

<0.01 0.1210.01 0.810.1

<0.1 09/08/81 2.910.8

<0.01 0.2810.03 1.210.1

<0.1 Location 5 03/18/81 9.711.2

<0.01 0.5810.06 1.8 0.2

<0.1 09/08/81 2.310.8

<0.01 0.1810.02 0.510.1

<0.1 Location 8 03/18/81 6.611.1

<0.01 0.1610.02 1.8!0.2

<0.1 09/08/81 4.110.9

<0.01 0.2210.02 1.3 0.1

<0.1 Location 11B 03/18/81 3.410.9

<0.01 0.1610.02 0.610.1

<0.1 09/08/81 1.010.7

<0.01 0.0210.01

<0.1

<0.1 (a) Zr-95 = 0.410.1, Nb-95 = 0.3!0.1 5-22 A

PORTLAND GENERAL ELE NRIC GROSS BETA & TRITIUM CONCENTRATIONS IN PRECIPITATION SAMPLES (Monthly Collections)

DCi/1 Met Tower (1F)

Woodland (9B)

Rainier (2)_

s Gross 8 Tritium Gross 8 Tritium Gross 8 Tritium January 6.0i0.9

<1000 7.511.0

<1000 6.710.9

<1000 February 13.8!1.4

<1000 16.811.7 1000!400 14.1 1.4

<1000 March 1.510.8

<1000 16.311.3

<1000 20.012.0 700!400 April 11.0!1.0 (1000 13.011.0

<1000 10.011.0

<1000 May 15.311.5

<1000 14.011.4 (1000 13.511.4

<1000 June 13.511.3

<1000 13.611.3

<1000 11.211.2 (1000 July (a)

<1000 (a)

<1000 August (b)

(b)

September 6.3!1.0

<1000 8.421.1

<1000 8.611.1

<1000 October 4.610.9

<1000 3.910.8

<1000 2.4!0.7

<1000 November 1.810.7

<1000 2.210.8

<1000 0.810.7

<1000 December 0.9 0.7

<1000 1.lt0.7

<1000 1.1!0.5

<1000 GAMMA ISOTOPIC ANALYSIG OF PRECIPITATION SAMPLES H. WING GROSS I !lTA CONCENTRATION IN EXCLES JF 10 pCi/1 Gamma Emitters pCi/1/nuclide honth Met Tower (1F)

Woodland (9B)

Rainier (2[

Tebruary

<25

<25 March

<25

<25 April

<?S

<25

<25 May

<25 (25

<25 June

<25

<25 Exclusive of naturally occurring radionuclides.

(a) Gross beta analysis not performed due to low volume.

(b) Due to hot weather, no precipitation collected in August.

l l

5-23 l

L______-_________--_.-_-----------

Mq Shest 1 ef 3 PORTLAND GENERAL ELECTRIC j

. AMBIENT CAMMA RADIATION LEVELS - 1981 1

.mR/ Day (Mean Daily Exposure 12e Error)

First Second Third Fc,urth site Quarter Quarter Quarter Quarter Annual

~'

1A 0,1010.03-0.0910.01 0.0910.01 0.1110.02 0.1110.02 1B 0.1210.03 0.1010.01 0.0910.01 0.1210.03 0.1010.01 1C 0.1310.03 0.1010.01 0.1310.03 IE 0.1110.03 0.0910.01 0.0810.01 0.1110.02 0.0910.01 IF 0.1510.04 0.1210.01 0.1110.02 0.1410.03 0.1110.02

~

1H 0.1510.04 0.1710.01 0.1610.03 0.1810.04 0.1410.02 11 0.1010.02 0.0910.01 0.0910.01 0.1110.02 0.0910.01 IJ 0.1110.03 0.0910.01 0.0910.01 0.1110.02 0.0910.01 2

0.1610.05 0.1210.01 0.1210.02 0.1610.04 0.1410.03 3

0.16t0.04 0.1410.01 0.1310.02 0.1810.04 0.14+0.02 4C 0.1110.03 0.1210.01 0.1110.02 0.14+0.03

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6B 0.1310.03 0.1210.01 0.1110.02 0.1 6 03 0.1310.02 7

0.1310.04 0.1310.01 0.1110.02 0.1310.03 0.1210.02 8

0.1610.04 0.1410.01 0.1310.02 0.1610.04 0.14+0.02 9B 0.1110.03 0.1210.01 0.1010.02 0.1410.03 0.1210.02 10 0.1510.04 0.13t0.01 0.1110.02 0.1510.03 0.1210.02 11A 0.1110.03 0.1110.01 0.1010.02 0.1310.02 11B 0.1310.04 0.1210.01 0.1010.02 0.1310.03 0.1110.02 12 0.13_+0.04 0.11_+0.01 0.10.+_0. 02 0.12_+0.03 0.12+0.02 13 0.1510.04 0.1510.01 0.1310.02 0.1510.03 0.1610.02 14 0.13+0.03 0.13+0.01 0.12+0.02 0.14+0.03 0.13+0.02

Dosimeter vandalized during field exposure.

4 1

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5-24

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-PORTLAND GENERAL ELECTRIC-AMBIENT GA)ttA RADIATION LEVELS - 1981 mR/ Day (Mean Daily Exposure 120. Error)

~

First Second IIsird.

Fourth Site Quarter-Quarter Quarter Quarter 20 0.1110.02 0.10t0.01:

0.05to.01 0.1310.03 21 0.08t0.01:

-0.08t0.01 0.07; p.01.

0.0910.02 22' O.11+0.02 0.1010.01 0.0910.02 0.1110.02

~

23-0.1010.02' O.0910.01 0.0810.01 0.10t0.02 24 0.1510.03:

'O.1510.01 0.1410.02 0.1610.04 25

'O.07+0.01 0.06t0.01 0.06t0.01 26i 0.1510.03 0.1510.01 0.1410.03 0.1610.03 27 0.1610.04 0.1610.01l 0.1610.03 0.1710.04 28 0.1510.03 0.1510.01 0.1510.03 0.1610.04 29 0.1710.04 0.1610.01-0.1610.03-0.1710.04 30 0.1410.03 0.1510.01 0.1510.03 31~

0.1210.02 0.1210.01 0.1110.02 0.1210.02

-32 0.1210.03 0.1210.01 0.1210.02

+

33 0.1410.03 0.1410.01 0.1110.02 0.1210.03 34 0.1410.03 0.14_+0.01 0.1310.02.

0.1310.03 35 0.1210.03 0.1210.01 0.1110.02-0.1110.02 L

36 0.1410.03

'O.1310.01 0.1110.02 0.1310.03 37 0.14+0.03 0.13+0.01 0.12+0.02-0.12M.03

-38 0.12%.03 0'.11+0. 01 0.10+0.02 0.11+0.02 39 0.1610.03 0.1610.01-0.1510.03 0.1610.03 40 0.12f0.01 0.11f0.02 0.1110.02 41 0.1410.03 0.1510.03 0.1510.03 j

Dosimeter vandalized during field exposure.

l-li k

5-25 e

p,,

Shtst 3 cf 3 PORTLAND GENERAL ELECTRIC AMBIENT GAMMA RADIATION LEVELS - 1981 mR/ Day (Mean Daily Exposure 120 Error)

First Second Third Fourth Site Quarter Quarter

' Quarter Quarter

~

42 0.1510.04 0.1510.01 0.1410.02 0.1410.03 43 0.1310.03 0.1210.01 0.1110.02 0.1210.03 44 0.1410.03 0.1510.01 0.1310.02 0.1410.03 45 0.1310.03 0.1410.01 0.1210.02 46 0.12_+0.01 0.12.+0.02 0.12+0.03 47_

0.1310.03 0.1210.01 0.1110.02 0.1110.02 48 0.1210.03 0.1210.01 0.1110.02 0.1110.02 49 0,1110.02 0.1310.01 0.1210.02 0.1310.03 50 0.1010.02 0.1010.01 0.0910.02 P.1010.02 51 0.1210.02 0.1210.01' O.1110.02 0.1310.03 52 0.1110.02 0.1110.D1 b.0910.02 0.1010.02 53 0.1010.02 0.1110.01 0.0910.02 54 0.1610.04 0.1610.01 0.1610.03 0.1610.03

. 55 0.1110.02 0.1110.01 0.1010.02 0.11+0.02 56 0.1410.03 0.1410.01 0.0510.01 0.0510.01 57 0.1310.03 0.1410.01 0.1210.01 0.1410.03 0.1210.02 0.1310.03 I

58 0.1410.03 59 0.1110.02 0.1110.01 0.1110.02 60 0.11,+0.02 0.1110.01 0.1110.02

0. Q ).02 61 0.1410.03 0.1410.01 0.1410.02 0.1510.03 62 0.0710.01 0.0610.01 0.0610.01 64 0.11_H).02 0.1010.01 0.1110.02 0.1210.02

Dosimeter vandalized during field exposure.

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,n PORTLAND GENERAL ELECTRIC J

j RADIOACTIVITY IN SHORELINE SOIL' SAMPLES I

(Semiannual ~ Collections)

I pCi/m Dry weight' I

CR1 CR3 CR5 I

Gross Gamma Cross Gamma Gross Gamma Collection Beta Emitters Beta Emitters Beta-Emitters

]

1:

'03/26-27/81 1.720.8

<0.1 4.611.1

<0.1 1.520.8

<0.1 1

09/02/81 1.6t0.7

<0.1 1.510.8

<0.1

<0.5-

<0.1 j

~~

RADI0 ACTIVITY IN SEDIMENT SAMPLES I

(Semiannual Collections) i j

1 pCi/g Dry weight 1

Igcation

_ Gross 6

_Cs-137 Other y Collection Date: March 1981 j

IA 9.0!].2

<0.1

<0.1 IB 7.5 1.1

<0.1

.lD 6.4!1.1

<0.1 (0.1 j

CR2 2.0 0.8

<0.1 (0.1 i

CR3 1.0i0.7

<0.1

<0.1 CR4 1.720.8

<0.1

<0.1 1

I Collection Date: September IA 3.0!0.4 0.210.1

<0.1

{'

IB 3.610.9

<0.1

<0.1 ID 4.710.9

<0.1

<0.1 CR2 1.010.7 0.120.1

<0.1 CR3 1.210.7 0.lt0.1 (0.1 CR4 1.110.7

<0.1

<0.1 q

l

)

5-31 I

_ v __ r -~r

.. ; *. a.w, _

PORTLAND GENERAL ELECTRIC Shut 1 of 2 RADIOACTIVITY IN SAMPLES OF AQUATIC PLANTS (Semiannual Collections)

Collection Date:

03/18/81 03/19/81 Collection Site:

1A 1D pCi/a wet

~

Er-95 0.1 0.1

<0.1 Nb-95 0.2 0.1

<0.1 l

Other y

<0.1

<0.1 l

Gross B 0.910.1 1.0 0.1 1.

Sr-89

<0.003(a)

<0.006(a)

Sr-90

<0.003(a) 0.04100.007 Collection Date:

03/26/81 03/26/81 03/27/81 Cc11ection Site:

CR1 CR3 CR5 pCi/a wet Ce-144

<0.20 1.47 0.57 1.40i0.24 L

Be-7 0.3210.16

<0.60 0.6010.30 Cs-137

<0.10 0.09!0.05

<0.10 Zr-95 0.1320.04 0.45 0.16 0.34!0.05 Nb-95 0.14!0.C3 1.15!0.12 0.50!0.05' co-58

<0.10 0.49 0.06 0.27:0.03-Mn-54

<0.10 0.28 0.05 0.09 0.03 Co-60

<0.10 0.6410.10 0.42!0.04 Ce-141 0.7910.22 0.8420.22 1.31 0.31 Ru-103

<0.10 0.27:0.07 0.27!O.03 Other Y

<0.10

<0.10 Gross 8 1.E20,20 2.710.30 3.5!O.40 Sr-89

<0.005 (0.011(a)

<0.007 (a)

Sr-90 0.01810.004 0.065!0.011 0.52320.052 (a)' Insufficient sample for more sensitive analysis.

1 i

l 5-32

PORTLAND GDIERAL ELECTRIC Sh::st 2 cf 2 RADIOACTIVITY IN SAMPLES OF AQUATIC PLANTS (Semiannual Collections) i Collection Date:

09/14/81 09/11/81-Collection Site:

1A 1D

~

PCi/R wet y enitters (0.1

<0.1 Cross beta 1.510.2 0.410.3 Sr-89

<0.006(b)

<0.014(a,b)

Sr-90 0.06910.007 0.03110.020-Collection Date:

09 /02fjl__,,

04/02/91 npfn?/n1 Collection Site:

CR1 CR3 CR5 pCi/R wet Ce-144 0.410.1 1.010.4 2.110.2 Be-7' O.410.1 1.4!0.4 1.410.1 Cs-137 0.110.1 0.410.1 0.310.1-Zr-95 0.210.1

<0.1 0.4t0.1 Nb-95 0.2!0.1 0.410.1 0.6 0.1 Co-58

<0.1 0.4 0.1

<0.1 Mn-54

<0.1 0.1 0.1

<0.1 Co-60

<0.1 1.8 0.2 0.li0.1 Co-57

<0.1 0.1 0.1 0.1 0.1 Sb-125

<0.1 0.3 0.1 0.110.1 Ce-141

<0.1

<0.1 0.110.1 Ru-106

<0.1

<0.1 0.4 0.1 Cs-134

<0.1 0.1 0.1 0.110.1 Other gamma

<0.1

<0.1 Gross beta 2.0!0.3 7.911.8 7.8t0.8 Sr-89

<0.002(a)

<0.018(a)

(0.009(a)

Sr-90 0.013 0.002 0.259 0.035 0.01510.013 (a) Insufficient sample for more sensitive analysis.

(b) Lower sensitivity due to low chemical yield.

5-33 i

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ML20247E412

Contents

Text

1.0 INTRODUCTION

3.1 INTRODUCTION

SUMMARY

SUMMARY

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ML20247E412

Text

1.0 INTRODUCTION

3.1 INTRODUCTION

SUMMARY

SUMMARY

Navigation menu

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