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Radiological Environ Monitoring Annual Rept,1982
	ML17320A459
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Site:	Cook
Issue date:	03/31/1983
From:	Chandrasekaran; INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
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AV."RICANFLECTRIC POVlER SERVIC'E CORPORATION DonaId C. Cook Nuclear Plant RADICLOGICALENVIRONMENT@'I"IONITORING Annual Report 1982

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ENVIROHMEiiTAL SAMPLING AND ANALYSIS PROGRAM FOR DONALD C.

COOK NUCLEAR PldDT AMERICAN ELECTRIC POWER SERVICE CORPORATION ANNUAL REPORT JANUARY DECEMBER 1982 Reported by EBERLINE LABORATORIES ALBUQUERQUE, NM Reviewed and Approved by:

Chandrasekaran, E.S.

Manager

"TABLE'OF CONTENTS

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SECTION 1 SECTION 2 SECTION 3 SECTION 4 SECTION 5 SECTION 6 Data Tables 32 Quality Assurance Data 47 Preface Sampling Program Analysis Program 14 Results and Discussion

'23

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SECTION 1

PREFACE

ABSTRACT This report presents the data obtained from the analyses of environmental samples collected for the American Electric Power Service Corporation Donald C.

Cook Nuclear Station Environmental Radiological Surveillance Program for the period Ol January 1982 through 31 December 1982.

The activity present above the detection limits in the routinely collected sample media was observed to be of natural and atomospheric origin.

In no case did radioactivity from the Cook Nuclear Plant exceed the design objectives of the Cook Radiological-Environmental Technical specifications.

INTRODUCTION The Donald C. Cook NucXear Station of American Electric Power Service Corporation consists of two Westinghouse PWR units (Unit 1

and Unit 2).

Each unit consists of a pressurized water reactor (PWR) which generates about 3250 megawatts (MW) of heat to generate about 1100 MW of electricity.

The station i's located in Benton Harbor, Mich-igan.

'he D.C.

Cook Plant utilizes a pressurized water reactor with a radwaste hold-up and treatment system that has been designed to keep radioactive releases to as low as is practible levels.

However', small quantities of noble gases and radioiodine may be released to Lake Mich-igan.

The quantities of radionuclides released to the environment are expected'o be miniscule and insignificant as a source of potential exposure to flora and fauna in the area.

However, direct radiation ex-posure to man and radionuclide accumulations in various components of food chains to man will be carefully monitored.

The environmental radiological monitoring program is intended to serve the following purposes:

a)

To yield average values of radiation levels and concentrations of radioactive material in various media of the environment.

b)

To identify sample locations and/or types of samples that deviate from the averages.

c)

To document seasonal variations that could be erroneously interpreted when the power station is operating.

d)

To indicate the range of values that should be considered "background" for various types of samples.

The basic approach for the Donald C. Cook Nuclear Plant is to con-trol the release of radioactive material at levels far below that which would be expected to cause detrimental impact on the environment.

The environmental radioactivity surveillance program will be closely coord-inated with conditions of. plant operation and sub]ect to periodic review.

Levels of environmental radioactivity are subject to change for reasons in no way related to the operation of the D.C. Cook Nuclear Plant.

Therefore, the radioactivity surveillance program has been de-signed to include reference or "background" stations as well as "indicator" stations.

The program is summarized in Table l.

This report contains a compilation of the results of analyses of various types of samples collected during the period January 1982 through December

.1982.'4

SECTION 2 SAMPLING PROGRAM

All samples are collected by Eberline personnel and shipped to the Eberline Laboratory-in West Chicago, Illinois.during the first half of I

the year.

The samples collected during the second half of the year were shipped to Eberline, Albuquerque Laboratory in New Mexico.

The sample collection procedures remained the same as those detailed in the semi-annual report for the period Ol January through 30 June 1973.

Upon receipt of the samples, the Laboratory staff enters the samples in a log book identifying them as to sample type, collection date, and sample code number of location, then verifies the specific analyses to be performed on each sample.

The samples are then stored, awaiting

analysis, on shelves expressly for this purpose to assure accountability through the Laboratory processes.

Table 1 lists the sample analysis program - sample type, frequency, and the type of analysis required.

Table 2 lists the LLD's (Lower Limits of Detection) for the analy-tical program.

These LLD's are based on the Regulatory Guide 4.8.

For analyses not listed in Regul'atory Guide 4.8, Federal EPA, former require-ments for similar programs or other appropriate guides are used.

The LLD's are calculated at the 3a (99X confidence) level.

The Guide specifically states that the LLD's are priori, not a posteriori (after the fact) limit for a particular measurement.

When

however, RG 4.8 or other LLD's have not been achieved, a footnote giving a brief explanation has been inserted.

Maps of sampling locations are shown on pages 11-13.

Figure I gives the air sampling locations, Figure II shows other sampling locations and TLD monitoring locations.

TABLE 1 ENVIRONMENTAL MONITORING PROGRAM DONALD C.

COOK NUCLEAR PLANT Sample T

e No. Station Collection Analysis Type Anal sis Remarks Air Particulate 6

4 Airborne 1-131 Precipitation Lake Water Weekly Weekly Monthly Monthly Weekly lfonthly Quarterly Weekly Monthly Semi-annual Monthly Gross Beta Gamma Isotopic Composite, 2

Samples Sr-89, Sr-90

~

Gamma Isotopic Gamma Isotopic Composite, 2

Samples Sr-89, Sr-90 Composite, 2

Samples Gamma Isotopic Composite, 2

Samples By indicator and background samples.

By indicator and background samples.

Quarterly Tritium Composite, 2

Samples By indicator and background samples.

Well Water Every 18 wks.

Every 18 wks.

Gamma Isotopic Tritium Fish 2 per year 2 per year Gamma Isotopic Sr-89, Sr-90 Edible portion only.

TABLE 1 (Cont'd)

ENVIRONMENTAL MONITORING PROGRAM DONALD C.

COOK NUCLEAR PLANT Sample T

e No. Stations Ind.

Bk Collection Fre uenc Analysis Pre uenc Type Anal sis Remarks Aquatic Organisms 2

2 Milk Sediment 2 per year Monthly 2x per year 2 per year Monthly 2x per year Gamma Isotopic When available Sr-89, Sr-90 Gamma Isotopic Sr-89, Sr-90 I-131 Gamma Isotopic Sr-89, Sr-90 TLD Pood Crops 9

14 Quarterly l

l Annually Quarterly Annually Total Dose Gamma Isotopic

Table 2

Samole Class LOWER LIMITS OF DETECTION (LLD')

LLD Anal sis Units Air Particulates Airborne Iodine Milk Well Water Precipitation Lake Water Aquatic Organisms Sediment Fish Food Cr'ops

Background

Radiation (TLD)

Gross Beta Gamma Isotopic Sr-89 Sr-90 I-131 I-131 Gamma Isotopic Sr-89 Sr-90 LS Tritium Gamma Isotopic Gamma Isotopic Sr-89 Sr-90 Gamma Isotopic Enriched Tritium, Gamma Isotopic'r-89 Sr-90 Gamma Isotopic Sr-89 Sr-90 Gamma Isotopic Sr-89 Sr-90 Gamma Isotopic Gamma Dose 0.01 0.01 0.002 0.001 0.01 0.05 10 5

1 1000 10 10 2

1 10 0.2 1

0.05 0.005 1

0.05 0.005 pCi/ms pci/ms pCi/ms pCi/ms pCi/ms pCi/l pCi/l pCi/l pCi/l pCi/1 pCi/1 pCi/1 pCi/l pCi/1 pCi/1 pCi/ml pCi/g wet pCi/g wet pCi/g wet pCi/g dry pCi/g dry pCi/g dry pCi/g wet pCi/g wet pCi/g wet pCi/g wet mR/week 10

RTH, Wl TRUE PLANT NORTH NO METEOROLOGICALTOWER PROPERTY LINE L

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TO8 ROADS R.R. TRACK 545 KY YARD

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YARD CHESAPEAKE 6 OHIO R.R.

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2,000 FOOT RADIUS INTERSTATE 94 SCALE 0

l,000 2,000 3,000 1

4,000 FEET PIGVRE I LOCATI0 NS OF INDICATOR AIR SAMPLING STATIONS A 'ir, Precipitation T

TLD Station W

Well Water L

Lake Water (taken at shoreline)

A Air, Precipitation, TLO Stations

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Hilt Supple Stations 20 MILES~

1196 Nate BOITON HARBOR L ST, JOSEPH Stevensvil e

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COOK PLANT Eaulaire Berrl en Springs Hid Hex Buffalo f

MICHIGAN CITY HICNIGAN INOIXNA Nnr Carl isle Niles OS20 Scale of Hiles 10'0 FIGURE" IX OFF SITE LOCATIONS OF SAMPLING STATIONS 12

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Red Arrow Highway and vicinity of I-94 overpass.

Stevensvil le Sub Station.

Washington Avenue midway between Brentwood Drive and Kingman Drive.

Washington Avenue and Linco Road.

FIGURE III Cleveland Avenue and Shawnee Road.

Ho'iden Road and Snow Road.

Bridgman Sub Station.

California Road between Browntown and Snow Roads.

Ruggles Road between Hinchman and Lemon Creek Roads.

At intersection of Hildebrant Road and Red Arrow Highway.

TLD MONITOR LOCATIONS LOCATED ON THE FIVE MILE RADIUS FROM THE PLANT 13

SECTION 3 ANALYSIS PROGRAM 14

ANALYTICALPROCEDURES Samples received at the laboratory are analyzed for tHe"various radio-'ctive components by standard radiochemical methods.

These methods are equal to, and in most cases, identical with, those of the U.S.D.O.E.1 or those of the Federal E.P.A.

Brief descriptions of analytical procedures are available in the Lab-oratory Procedures Manual available at the Cook Nuclear Plant and the radioanalytical contractor's laboratory.

AIR PARTICULATE FILTERS Gross Beta Exposed air particulate filters are counted in low back-ground Geiger or proportional flow beta counters using anti-coincidence background suppression after the short-lived naturally occurring radon and thoron daughters have decayed.

Filters are counted long enough to ensure that the required sensitivity (LLD) is met.

Gamma Isotopic Monthly composites of air particulate filters grouped by indicator and background stations into two samples are counted in high resolution (GeLi) gamma spectrometers for periods of time long enough to ensure that the required program sensitivity (LLD) is met.

Strontium-89 and Strontium-90 After carrier strontium is added to semiannual composite samples of air particulate filters, the strontium is then separated and purified by either ion exchange chromatography (EPA method) or straight wet chemistry (HASL method).

The chemical HASL Procedures Manual, edited by John H. Harley, Health and Safety Laboratory, US Atomic Energy Commission, 1972 edition, revised annually.

National Environmental Research

Center, Environmental, Protection Agency; Handbook of Radiochemical Analytical Methods.

Program Element 1HA 325.

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

15

yield for strontium is determined by atomic absorbtion spectrometry or gravimetric methods.

After a suitable period (usually 14 days) to allow for ingrowth of Y-90, the sample is count'ed in a low background beta counter (equilibrium or total Sr count).

The strontium is next put into solution, carrier yttrium added, and the strontium and yttrium fractions separated.

The yttrium is counted and from the Y-:90 (Sr-90 daughter)

count, the Sr-90 concentration can be determined.

0 The difference between the total strontium concentration as determined by the equilibrium count and the Sr-90 concentration as determined from the Y-90 count is the Sr-89 concentration.

Equations are avail-able to'ermit calculation of Sr-89 and Sr-90 by counting the purified strontium fraction at two points during ingrowth of the Sr-90 daughter Y-90.

While either method is acceptable, we find the former method provides more consistent, results:

WATER SAMPLES (Includes Lake, Well;,Precipitation) small controlled volume and counted in a standard geometry in a high resolution (GeLi) gamma spectrometer long enough to ensure meeting

=

the sensitivity requirements of the program.

See also the Intro-duction to Data Tables.

Strontium-89 and Strontium-90 Stable strontium carrier is added to a measured. aliquot of, sample.

The strontium is then treated from this point on in the same manner as are air particulate samples.

Tritium Tritium as tritiated water is analyzed by liquid scintil-lation'ounting after distillation. If high sensitivity is not required (ie.

LLD -500 pCi/1) the sample is distilled, mixed with the appropriate counting phosphors and counted with no further 16

treatment.

If higher sensitivity is required (ie. ("300 pCi/1) the sample is isotopically enriched in tritium concentration prior to liquid scintillation counting.

Isotopic enrichment is done by the classical method of Ostlund which involves alkaline electrolysis of a purified aliquot of sample under controlled conditions of temper-ature'nd electrode current density.

MILK SAMPLES 1-131 - lfeasured amounts of tarrier iodide are added to a known volume of milk and the iodine extracted on anion exchange resin.

The iodine is recovered and purified by classical iodine chemistry methods which are similar to those given in former Regulatory Guide 4.3.

The yield or recovery of iodine is measured gravimetrically and the precipitated sample is mounted and counted in a low level beta detector for a long enough period to ensure that the "required LLD is met.

dried to a standard volume and counted in a fixed geometry in a high resolution (GeLi) gamma spectrometer for a long enough period to ensure that the required LLDs are reached (see also Introduction to Data Tables).

Strontium-89 and Strontium-90 Stable strontium carrier is added to an aliquot of the sample which is then dried and perature

()700 c).

The ash is dissolved and the from this point on in the same manner as are air ashed at high tem-solution treated particulate samples.

ORGANIC SKPLES (Aquatic Organisms, Food Crops, Fish) as appropriate, placed in a controlled geometry and counted in a high 1'7

resolution (GeLi) gamma spectrometer for a period long enough to en-sure that the LLDs of the program will be set (see also Introduction to Data Tables).

Strontium-89 and Strontium-90 -,Stable strontium carrier is added to a weighed aliquot of the sample and the sample is ashed at high tem-perature

(>700 c).

The ashed sample is then dissolved and processed 0

in the same manner as are air particulate samples.

SEDIMENT SAMPLES then sieved to remove pieces of stone and/or other large pieces of I

material.

An appropriate

sized, weighed aliquot of the sample is then transferred into a standard geometry container and counted for a period long enough. to ensure, that. the LLDs of the"program will be met".

(See also Introduction to Data Tables.)

Strontium-89 and Strontium-90. A sample is ashed until free of carbon.

The ash, with carriers added, is dissolved in hydrochloric

acid, then processed in the same manner as are air particulate samples.

THERMOLUPZNISCENT DOS IMETERS Environmental radiation doses are measured using badges comprizing five chips sealed in plastic protective holders having a density of 50 mg/cm The TLD chips are 1/8" x 1/8" x 1/32 Lip (thallium activated) known commercially as Harshaw-100..

The chips are all selected to pro-vide uniform response to within five percent of the mean for the batch.

Prior to installation, the chips are annealed, by a standard. cycle.of 60 minutes at 400 c and immegiate cooling'o ambient temperature by plac-ing the tray containing the annealed chips on an aluminum block 18

12" x 12" x 1".

After exposure the chips are read on an Eberline instrument Corporation ifodel TLR-6 reader.

The system employs a preheat cycle which removes low temperature peaks and integrates and digitizes only the light output in a selected temperature range.

The dose is calculated from the average light output for the five chips and the statistical uncertainty is the standard deviation of the five readings.

Control badges are used to detect any unusual exposu're to the badge which might occur during shipment.

19

QUALITY ASSURANCE PROGRAM A. Design of 6'lan Quality of product or service has always been a primary key to in-crease is sales, customer satisfaction, and profit.

The management of Eberline Instrument Corporation recognizes the ever increasing demand for higher quality and reliability for services related to protection of workers and the environment.

It is our firm belief that in order to judge the worth of a support service, one must know the philosophy behind it.

Eberline will provide only those services for which it is qualified and these will be provided in a manner that is reliable, with a quality assurance program that maintains a high degree of client confidence.

This quality assurance program has been prepared cosistent with the following specifica-tions, per the Technical and Quality Assurance;Requirements for Special Purposes.

ANSI-N45.2, American National Standard Institute NRC Branch Technical Position of November 1979 NRC Regulatory Guide 4.15, Revision 1 of February 1979.

B. Intercomparison Program Results of Eberline's Midwestern Facility (1st half of 1982) and Albuquerque Laboratory (2nd half of 1982) participation in the USEPA's Crosscheck Program are included in the monthly and annual reports provided to the client.

Other intercomparisons in which, we routinely participate include:

Environmental Protection Agency Environmental Measurement Lab DOE Quality Assessment Program Battelle Northwest Laboratories IAEA Analytical Qu'ality Control Service US National Bureau of Standards Each'of the laboratory managers is responsible for preparing spikes and blanks to be run routinely.

Every tenth sample is a spike, a blank, or a split sample.

Regular QC reports are prepared by a laboratory-manager on a monthly 0

20

schedule and forwarded to each client.

Each report routinely includes:

results from EIC interlaboratory comparison, results from EPA Crosscheck

program, and results from other intercomparison programs.

Results are reviewed by the laboratory manager.

If a problem is in-dicated by the data, the nature of the problem is investigated and corrective steps taken immediately.

A copy of each report is also provided to the Quality Assurance Manager of the Nuclear Services Division.

0 C.

Quality Assurance Plan The Quality Assurance Program follows the requirments of Company and Division Manuals.

The'discussion below outlines Quality Assurance Programs as conducted in the laboratory and as required in our QA Manual.

P Procedure A

royal Each procedure goes through a vigorous evaluation and review process before it is incorporated. into, the EIC Procedures Manual.

Established pro-cedures of the Environmental Protection Agency (EPA) or the Environmental Measurements Laboratory of the US Department of Energy (EMK') are used unless thorough testing has demonstrated that an alternate procedure is equal to or better than the EPA or EML procedure.

Uniform procedures are used at both laboratories to the fullest extent possible, except when deviations are necessary to meet the specific requirements of the client.

The manager of each laboratory and the quality assurance manager review and approve signif-icant procedural changes before they are implemented.

E ui ment Calibration and Maintenance Equipment used for qualitative or quantitative measurements is care-fully calibrated and maintained with records of each calibration or main-tenance action kept in appropriate logbooks.

To the extent possible, certified standards are used for all primary calibrations.

The following standards are used for the application indicated:

21

Measurement Gross Beta Tritium Calibration Standard

'olution of Standard Cs certified by NBS or 137 Amersham Searle Solution standard of H certified by NBS 3

Gamma Spectrometry Strontium-89 and 90 Gross Alpha Radiation Dose Solution standards of various gamma emitters certified by NBS or Amersham Searle.

Standards are used to calibrate each counting geometry used.

Solution standards of Sr certified by Amersham 90 Searle or NBS Solution standards of Pu certified by NBS or 239 Amersham Searle.

137 Cs gamma source cross-referenced with NBS using R-meters.

Ra is used for some special, application.

When suitable standards are not available for a specific gamma emitter, quantitative gamma isotopic analysis is based onan 'energy calibration of the gamma spectrometer and the gamma energy and..

abundance information provided -in Table of Esotopes, Sixth Edition.

by Ledrer, Hollander, and Perlman.

The results of the Quality Control Programs are summarized in Section 6.

22

SECTION 4 RESULTS A%) DISCUSSION 23

Table 3

Page 1 of 3 Environmental Radiolo ical Honitorin Pro ram Name of Facility:

Donald C.

Cook Nuclear Station Docket Number:

50-315 and 50-316 Location of Facility:

Berrien County Michigan State Reporting Period:

January December 1982 Hedium or Pathway Sampled (Unit of Measurement)

Type and Lower Limit Total Number,.

of of Analyses Detection Performed (LLD)

All Indicator Locations Mean (Ran e)

Name Hean-(Ran e)

Location with Hi hest Mean Control I.ocations Heanl (Ran e)

Number of Non-routine Reported Heasurements Air Particulates (pCi/ms) 'ross g

0. Ol 0.03 (270/311)

On Sites 0.04 0.01-0.08 3, 5, and 6

0.01-0;08 0.03 (186/204) 0.01-0.10 Ce-144 24 0.01 ALL LLD Not Applicable ALL LLD Zr-95 24 0.01 ALL LLD Not Applicable ALL LLD Nb-95 24

0. 01 ALL LLD Not Applicable ALL LLD Ce-141 24 Ru-103 24

0. 01 0.01 ALL LLD ALL LLD Not Applicable Not Applicable AI.I. LLD ALL LLD Other y 24 Sr-89 8

0.01 0.002 ALL'LD ALL LLD Not Applicable Not Applicable All LLD All LLD Airborne Iodine

( Ci/m3)

Well Water (pCi/1)

Sr-90 I-131 515 Tritium 21 y Spec.

21 0.001

0. Ol 1000 10 ALL LLD ALL LLD 1767 (3/12) 1100-2100 ALL LLD Not Applicable Not Aoplicable On Sites 2100 4 and 5

(a)

Not Applicable All LLD All LLD All LLD All LLD H

nd range based on detectable measurements only.

ctions indicated in parentheses.

(a) e is not reported as eely are detectable measure was available

0 Table 3

(continued)

Facility:

o a C

.oo Page 2 of 3 Medium or Pathway Type and Sampled Total Number (Unit of of Analyses Measurement Performed Lower Limit of Detection LLD All Indicator Locations Mean Ran e)

Name Mean (Ran e)

Location with Hi hest Mean Control Locations Meanl (Ran e)

Number of Non-routine Reported Measurements Milk (pCi/1)

Precipitation (pci/1)

Lake Mater (pCi/1)

Aquatic Organisms (pCi/g wet)

I-131 58 Sr-89 58 Sr-90 58 y Spec.

58 y Spec.

24 Sr-89 4

Sr-90 4

y Spec.

20 Tritium 8

Ce-144 8

Nb-95

-8 0.05 10 10'0 200 All LLD All LLD 4.2 (35/35) 1-12 All LLD All LLD All LLD.

All LLD All LLD 300 1/4 (a)

All LLD All LLD Not Applicable Not Applicable Bridgman 4.2 (12/12) 1 12 Not Applicable Not Applicable Not Apolicable Not Applicable Not Applicable Not Applicable Not. Applicable.

Not Applicable All LLD All LLD

4. 6 (23/23) 1-1 All LLD All LLD All LI.D 4

(1/2),

4 All LLD 2OO (1/4)

(a)

ALL LLD ALL LLD 0

Zr-95 8

All LLD a

Not Applicable AI.L LI.D Cr-51 8

All LLD Not applicable All LI.D Ce-141 8

All LLD Not Applicable ALL LLD Other y 8

All LLD Not Applicable All LLD 1 Mean and range based on detectable measurements only.

Fractions indicated in parentheses.

(a)

Range is not reported as only one detectable measurement was available

Table 3

(continued)

Facility:

Donald C. Cook Nuclear Station Page 3 of 3 Medium or Pathway Sampled (Unit of Measurement Type and Tote'umber of Analyses Performed Lower'Limit of Detection LLD All Indicator Locations Meanl (Ran e Name Mean (Ran e)

Location with Hi hest Mean Control Locations Mean1 (Ran e)

Number of Nc'n-routine Reported Measurements Aquatic Organisms Sr-89 8

(pCi/g wet)

Sr-90 8

0.05 0.005 All LLD ALL LL6 Not Applicable Not Applicable.

All LLD ALL LLD Sediment (pCi/g dry) y Spec.

12 Sr-89 12 Sr-90 12

0. 05 0.005 All LLD All LLD ALL LLD Not Applicable Not Apnlicable Not Applicable All LLD All LLD ALL LLD Food Crops

( Ci/

wet)

Fish (pCi/g wet)

Background

Radiation (TLD)

(mR/week) y Spec.

4 y Spec 8

Sr-89 8

Sr-90 8

y Dose 91 0.05 0.005 O.l All'LLD All LLD All.LLD 0.019 (2/4) 0.017-0.020 1.1 (35/35).

0.6-1.7 Not Applicable Not Applicable Not Applicable On Site, South 0.020 (1/2

.'(a).

On-Site 1.3 (4/4) 1.1-1.7 All LLD All LLD All LLD 0.022 (2/4) 0.016-0.027 1.2 (56/56) 0.8-1.8 0

(a)

Range is not reported as only are detectable measurement was available.

and range based on detectable measurements only.

ractions indicated in parentheses.

. ~

Results of all the analyses for January through December 1982 are presented in full in section 5, Data Tables pages 32 thxough 46.

Table 3 summarizes the range and average concentrations for meas-urements at the indicator and control locations with the highest annual mean.

Specific finding for the various environmental media are discussed below.

AIR PARTICULATE SAMPLES Atmospheric particulate matter at a field location is accumulated for a one-week on a glass fiber filter using a low-volume air sampler at a collection rate of one cubic foot per minute.

This particulate matter contained on the filter is counted for beta activity in a low background counting system aftex the short-lived naturally-occuxxing radon and thoron daughters have decayed.

, The average gross beta concentration for the year for all indicator stations was 0.03 pCi/m, and was 0.03 pCi/m for the background stations.

3 3

Data for anayses of individual filters are given on page 35 through 38 in Section 5.

The following Cable summarizes the average gross beta concentx'ations for both indicator and background stations for each year from 1973 through 1982.

The preoperational data were collected in 1973 and 1974; opexational data were collected from 1975 through the present.

TABLE 3 Indicator pCi/m3 Back round Preoperational 1973 1974 Operational 1975 1976 1977 0.04 0.08 0.09 0.22 0.04 0.09 0.08 0.22 27

Xndicator

~Back round Ci/m3 Operational 1978 1979 1980'981 1982 0.04 0.04

0. 12 0.03 0.11 0.04 0.04

0. 11 0.03 The elevated levels of gross beta activity at both indicator and background locations during preoperational and operational phases from 1974 through 1982 were mainly the result of nuclear test explosions in the atmosphere by the people's republic of China.

Such tests took place on 27 June

1973, 17 June

1974, 23 January

1976, 26 September

1976, 17 November

1976, 17 September

1977, 13 March 1978, 14 December 1978 and October 1980.

The data indicate that there is significantly no difference between the levels of gross beta activity measured at the, indicator and back-ground locations for the operational and preoperational phases of the programl

. The activity detected are not attributable to the operation of the Cook Plant.

Airborne T.-131 concentration was less than 0.1 pCi/m for all 3

samples received.

The gamma spectrometry data for monthly composites of air particulate files begins on page 39

~

Be-7, a naturally occurring nuclide formed by the cosmic ray interaction with nuclei in the upper atmosphere, was detected in the composites.

These were generally in the range to be expected from measurement of this nuclide in this medium.

No other gamma emitters were detected.

1 See Annual Environmental Monitoring Reports for D.C.Cook Plant from previous years for details.

28

Quarterly composites of air particulate filters were analyzed for Sr-89 and Sr-90.

Sr-89 concentrations were below the detection limit of 0.002 pCi/m,

3 and Sr-90 were also below the detection limit of 0.001 pCi/m for both indica-3 tor and background locations., Data are presented on page 39.

MILK SAMPLES Milk samples were collected monthly and were analyzed for I-131, Sr-89, Sr-90, and gamma emitters.

Sr-89 concentrations measured below the detection limit of 5 pCi/1 in all samples collected during the year..

Sr-90 concentrations continued to display considerable variation, which is typical for this type of sample.

This nuclide is attributable to worldwide fallout from both recent and older nuclear test programs.

Data are given on page 40.

I-131 concentrations were below the detection limits of the program.

Data are presented on page 40.

Gamma emitters other than those which occur in nature were not detected in all samples at a measurement sensitivity of 10 pCi/1.

Data are given on page 41.

PRECIPITATION SAMPLES Gamma isotopic analyses of monthly precipitation samples from'indicator and background locations indicate the presence of no gamma emitters in concen-trations exceed'ing 10 pCi/1 (<3000 pCi/m ).

Sr-89 and Sr-90 concentrations 2

were below the detection limits 'of the program.

Data are presented on page 42.

WELL WATER SAMPLES Well water is collected from seven locations at 18 week intervals during the year and analyzed for tritium and gamma emitters.

Low concentrations of tritium were detected in samples from three indicator stations during January-February 1982. It is possible that the tritium found in these samples is a re-sult of plant operations.

Gamma emitters were below the detection limit in all 29

samples analyzed.

D'ata are presented on page 43.

LAKE WATER 'AMPLES Samples of water from Lake Michigan are composited by indicator and back-ground locations and analyzed for gamma emitters on a monthly basis.

Quarterly composites of the monthly composites are analyzed for tritium.

The gamma emitters in the monthly composites were measured to be less than the detection limit of 10 pCi/1 per nuclide for all samples.

The tritium concentrations in the quarterly composites were in the range of <200 to 300 pCi/1 for in indicator locations and <200 to 200 pCi/1 for the background locations.

These concentrations are in the range to be expected from measurements of this nuclide in this medium.

Data is presented on page 44.

AQUATIC ORGANISM SAMPLES Aquatic organisms were collected twice.during the year fiom areas north and south of the plant, at on-site and off-site locations.

The samples, were analyzed for gamma,emitters,

.Sr-89, and Sr-90.

Data is presented on page 44.

No gamma emitters were detected in 'all samples collected during the year below the detection limit.1 pCi/g.

Sr-89 and Sr-90 were not detected in any of the samples above the detection limit of 0.05 pCi/g (wet) for Sr-89 and 0.005 pCi/g (wet) for Sr-90.

SEDIMENT SAMPLES Sediment samples were collected twice during the year from areas north, and south of the plant, at the on-site and off-site locations.

The samples were analyzed for gamma emitters, Sr-89, and Sr-90.

The gamma emitters were below the detection limit of 1 pCi/g (dry) in all samples.

Sr-89 and Sr-90 were also below the detection limit, 0.05 pCi/g (dry) for Sr-89 and 0.005 pCi/g (dry) for Sr-90.

Data are given on page 45.

30

FISH SAMPLES Fish samples collected from areas north and south of the plant, both on-site and off-site locations, were analyzed for gamma emitters, Sr-89 and Sr-90.

For all samples, gamma emitters were below the detection limit of 1 pCi/g (wet), and Sr-89 was below the detection limit of 0.05 pCi/g (wet).

Sr-90 ranged in concentration from 0.016 to 0.027 pCi/g (wet).

The concentrations observed were attributable to worldwide fallout and were generally in the range to be expected from measurements of this nuclide in this medium.

Data are given on page 45.

FOOD CROP SAMPLES Grapes and grape leaves were collected during the fall harvest period from on-site and off-site locations and were analyzed for gamma emitters.

They were found to be below'the detection 'limit of 1 pCi/g (wet) at both on-site and off-site locations.

Data are given on page 45.

Gd29fA DOSE Gamma radiation dose was measured with Thermoluminiscent Dosimeters (TLDS) on a quarterly schedule.

A total of 23 field locations(9 indicator and 14 back-ground) were monitored during the year.

I Throughout the year, there was no statistically significant difference in dose rates between indicator and background locations, nor do they differ significantly from dose rates measured in previous years.

Data are presented on page 46.

31

SECTION 5 DATA TABLES 32

INTRODUCTION TO THE DATA TABLES The following information will be helpful in understanding..the presentation of the data in the tables in this section.

Met Lleight 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 Meight 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 for about 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br />.

pCi/ms a reporting unit used with air particulate and radioiodine data which refers to the radioactivity content expressed in picocuries 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 or Gamma Isotopic samples were analyzed by high resolution (GeLi) gamma spectrometry.

The resulting spectrum is analyzed by a computer program which. scans from about 50 to 2000 kev and lists the energy-peak of. any nuclides present in concentra-tions exceeding the sensitivity limits set fo'r "that particular experiment.

NA, NS, NR Error Terms used in place of a concentration when a sample was not available (NS), or when a sample was not analyzed for some specific measurement (NA), ot'hen an analysis is no) required (NR).

figures following "+" are error terms based on counting uncertainties at the 2a (95Z confidence) level.

Values pre-ceded by the "<" symbol were below the stated concentration at the 3e (99Z confidence) level.

Exponents Exponents necessary to prevent data tables from being cumbersome are handled in the conventional manner of including them in the column headings.

Sensitivity In general, all analyses meet the sensitivity requirements of the program as given in Table 3.

For the few samples that do not (because of inadequate sample quantities, analytical interferences, 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 presenting a whole page of "<" data.

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

33

COOK LISTING OF MISSED S&PLES 1982 Sam le T e

AP/CC AP/CC Lake Hater AP/CC Milk

'ilk Location DOH~COL SBN,COL All points ONS-1 SBN Expected Collection Date 01/09/82 01/23/82 02/06/82 08/31/82 09/04/82 ll/06/82 Reason Heather conditions Heather conditions-frozen locks Lake frozen No power to unit Not available Not available 34

DONALD C.

COOK AIRBORNE IODINE-131* and GROSS BETA in AIR PARTICULATE FILTERS (Meekly Collections)

ON-SITE 1

ON-SITE 2 Gross Beta 10"a ON-SITE 3 Ci/ms ON-SITE 4 ON-SITE 5 Collection Date Volume

~ms Gross Volume

~ms Gross Volume Gross 8

Volume Gross 8

Ol/04/82 01/11-12/82 Ol/18/82 01/26/82 02/02/82 02/09/82 02/16/82 02/23/82 03/02/82 03/09/82 03/16/82 03/23/82 03/30/82 04/06/82 04/13/82 04/20/82 04/27/82 05/04/82 05/11/82 05/18/82 05/25/82 06/01/82 06/08/82 06/15/82 06/22/82 06/29/82 340 400 350 390 360 360 340 390 380 380 205 345 370 345 340 415 495 485 365 275 335 325 280 275 330 355

<1 2+1 1+1

<1 1+1 1+1

<1

<1 1+1

<1

<1 1+1 1+1 1+1 1+1 380 470 290 370 325 305 445 305 275 250 360 505 500 495 500 375 345 350 380 375 215 335 320 315 310.

285 1+1 1+1 1+1 1+1 1+1 1+1 1+1 1+1 1+1

<1

<1 1+1 1+1 2+1 1+1 1+1

<1

<1 1+1 1+1 1+1 2+1 3+1 2+1 2+1 370 5+1

.385 4+1 395 1+1 410 6+1 360 6+1 360 6+1 355 7+1 310 4+1 315 3+1 310 5+1 305 4+1 315 2+1 395 3+1 390 3+1 400 5+1 410 3+1 415 6+1 390 4+1 415 5+1 415 4+1 340 2+1 340 3+1 330 3+1 340 4+1 340 3+1 350 4+1 395

'05 375 485 465 430 435 435 450 420 410 325 350 330 340 335 385 380 425 435 485 280 280 460 455 440 5+1 1+1 1+1 6+1 2+1 5+1 6+1 3+1 2+1 5+1 4+1

<1 2+1 3+1 5+1 2+1 5+1 4+1 4+1 4+1

<1 3+1 3+1 3+1 2+1 3+4 335 410

'390 495 475 485 485 385 395 415 415 335 350 360 360 390 370 375 460 370 365 335 320 320 340 330 6~=1, 8+1 1+1 6+1 6+1 7+1 4+1 4+1 5+1 5+1 5+1 1+1 4+1 3+1 5+1 4+1 7+1 6+1 5+1 5+1 3+1 3+1 2+1 5+1 3+1 5+1

Iodine cartidges are sampled weekly.

Concentrations are <0.10 pCi/m unless otherwise noted.

DONALD C.

COOK AIRBORNE IODINE-131* and GROSS BETA in AIR PARTICULATE FILTERS (Weekly Collections)

Gross Beta 10"a Ci/m ON-SITE 1

ON"SITE 2 ON-SITE 3 ON-SITE 4 ON-SITE 5

'Collection Date Volume

~ms

~Gro s s Volume

~ms Gross B

Volume

~ms Gross 8

Volume Volume

+gi~s Gross B

Gross 07/06/82 07/13/82 07/20/82 07/27/82 08/03/82 08/10/82 08/17/82 08/24/82 08/31/82 09/07/82 09/14/82 09/21/82 09/28/82 10/05/82 10/12/82 10/19/82 10/26/82 ll/02/82 11/09/82 11/16/82 ll/23/82 ll/30/82 12/07/82 12/14/82 12/21/82 12/28/82 360 330 305 435 430 375 365 400 (a) 385 {b) 295 330 370 385 380 360 345 355 340 385 280 295 320 305 300 295 1+1 2+1 3+1

<1 1+1 1+1 1+1 1+1 4+1 1+1

%1 1+1 1+1

<1

<l.

1+1 lkl

<1 1+1 4tl

<1

<1 2+1 1+1 290 275 270 290 320 360 345 340 335 335 380 280 295 315 350 290 270 355 370 365 360 335 365 395 280 315 2+1 5+1 2+1 1+1

. 3+1, 2+1 2+1 1+1 1+1 3+1 3il 2+1 4+1 2+1

<1 221 3il 3+1

<Ilil 2>l 4tl 3kl

<1 2+1 1+1 340 360 380 385 385 390 385 410 420 405 415 315 345 345 350 335 320 315 315 280 290 295 350 345 340 345 4+1 4+1 5+1 5+1 5+1 4+1 3+1 2+1 4+1 3+1 3+1 2+1 3+1 5+]

3xl 2+1 4+1 4+1-3+1 4+1 611 5+1 321 4il 5+1 3+1 435 535 685 565 630 600 485 310 310 275 310 310 335 315 315 300 295 260 235 315 270 235 265 375 305 325 4+1 2+1 5+1

<1 3+1 3+1 2+1 2+1 5+1 4+1 4+1 2+1 3+1 3+1 2+1 1+1

<1 4+1 3+1

<1 511 2+1 3+l 3il 4+1 3+1 340 340 350 345

'80 365 375 350 335 345 395 375 375 405 390 380 440 360 325 380 385 395 375 355 300 245 2+1 7+1 7+1

<1 5+1 5+1 3+1 2+1 4+1 4+1 5+1 2+1 4+1 5+1 4+1 2<Jl 4+1 4+1 3+1 3i1 4il 2il 5+1 6+1 2+1 Concentrations are

<Os10 PCi/ms unless Iodine cartidges are sampled weekly.

See Lisiing of Hissed Samnles page.

No power.

Data based-on an estimated average e for the week.

s otherwise noted.

0 DONALD C.

COOK AIRBORNE IODINE-131+ and GROSS BETA in AIR PARTICULATE FILTERS (Weekly Collections)

Gross Beta 10"2 Ci/m3 ON-SITE 6 NEW BUFFALO SOUTH BEND DOMAGIAC COLOMA Collection Date 01/04/82 01/12/82 01/10/82 01/26/82 02/02/82 02/09/82 02/16/82 02/23/82 03/02/82 03/09/82 03/16/82 03/23/02 03/30/82 04/06/82 04/13/82 04/20/82 04/27/82 05/04/02 05/11/02 05/10/02 05/25/82 06/01/82 06/08/82 06/15/82 06/22/82 06/29/82 Volume (m3) 345 395 350 400 375 390 385 380 380 385 375 360 365 360 375 340 330 335 335 345 370 345 315 300 310 310 Gross Beta 5+1 S+1 3+1 5+1 6+1 7+1 2+1 5+]

5+1 4+1 4+1 1+1 4+1 3+1 5+1 3+1 6+1 5+1 4+1 5+1 2~1 3+1 3+1 4+1 2+1 4+1 Collection Date 01/02/82 01/09/82 01/17/02 01/23/82 01/30/82 02/06/82 02/13/82 02/20/82 02/27/82 03/06/82 03/13/82 03/20/82 03/27/82 04/03/82 04/10/82 04/17/82 04/24/82 05/01/82 05/00/02 05/15/02 05/21/82 05/29/82 06/05/82 06/12/82 06/19/82 06/26/82 Volume (m3) 380 365 450 330 390 380 410 360 385 370 345 330 375 360 445 355 390 355 345 350 340 365 310 325 340 340 Gross Beta 7il 6+1 5+1 6+1 4+1 4+1 5+1 3+1 3+1 3+1 5+1 1+1 2+1 1+1 5+1 2+1 6+1 4+1 3+1 5+1 2+1 2+1 3+1 3+1 3+1 3+

1'olume (m3) 335 310 335 (a) 600 365 375 365 385 345 300 325 365 340 375 360 320 330 330 335 335

- 330 360 355 340 315 Gross Beta 5+1 5+1 10+1 2+1 4+1 7+1 3+1 4+1 2+1 5+1 1+1 3+1 2+1 5+1 3+1 6+1

<1 3+1 1+1 1+1 1+1 3+1 3+1 4+1 3+1 Volume (uP) 370 (a) 720 370 385 385 395 405 470 440 335 300 315 325 325 340 320 345 330 365 325 325 320 365 360 395 Gross Beta 6+1 3+1 4+1 1+1 1+1

<1 5+1 3+1 1+1 4+1 1+1 2+1 3+1 6+1 2+1 5+1 3+1 5+1 4+1 2+1 2+1 3+1 3+1 3+1 1+1 Volume (m3) 335 (a) 670 (a) 660 350 345 295 345 345 315 385 425 370 440 405 495 470 515 580 360 415 420 405 340 3qO Gross Beta 7+1 2+1 5+1 3+1 1+1 2+1 3+1 2+1 3+1 1+1

<1 1+1 4+1 3+]

4+]

2+1 1+1 2+1 2+1 1+1 3+1 3+1 3+1 2+1

" Iodine cartridges are sampled weekly.

Concentrations are (a)

See Listing of Hissed samples page.

<Oe10 pCi/m3 unless otherwise noted.

DONALD C.

COOK AIRBORNE IODINE-131* and GROSS BETA in AIR PARTICULATE FILTERS (Weekly Collections)

-2 3

Gross Beta 10 Ci m Collection Date Volume

~{m3 Gross Beta ON-SITE 6 Collection Date NEW BUFFALO Volume Gross (m3)

Beta SOUTH BEND Voltage Gross DOWAGIAC Volume Gross

~m3)

Beta COLOMA Volume Gross

~m>)

Beta 07/06/82 07/13/82 07/20/82 07/27/82 08/03/82 08/10/82 08/17/82 08/24/82 08/31/82 09/07/82 09/14/82 09/21/82 09/28/82 10/05/82 10/12/82 10/19/82 10/26/82 11/09/82 11/12/82 11/16/82 11/23/82 11/30/82 12/07/82 12/14/82 12/21/82 12/28/82 320 325 330 335 360 365 555 605 620 565 610 235 230 240 240 280 265 345 275 360 405 445 410 375 390 425 (a) 4+1 5+1 4+1 5+1 4+1 4+1 1+1 2+1 3+1 2+1 1+1 1+1 5+1 3+1 2+1 2+1 2+1

<1 4+1 4+1 5+1 1+1 2+1 4+1 4+1 2+1 07/03/82 07/10/82 07/17/82 07/24/82 07/31/82 08/07/82 08/14/82 08/21/82 08/28/82 09/07/82 09/11/82 09/18/82 90/25/82 10/02/82 10/09/82 10/16/82 10/23/82 11/06/82 10/30/82 11/13/82 11/20/82 11/27/82 12/04/82 12/11/82 12/18/82 12/25/82 335'40 355 400 375 385 385 395 370 420 440 305 300 295 (a 400 630 475 480 510 415 400 355 325 340 350 335 4+1 4+1 4+1 2+1 4+1 4+1 1+1 3+1 2+1 1+1 4+1 2+1 2+1

)

<l.

2il

<1 2+1 2+1 2il 5+1

<1 5+1 3+1 3+1 2+1 4+1 405 375 385 380 310 400 465 570 590 510 600 300 285 315 335 335 325 330 330 290 250 350(a) 310 375 485 410 5+1 5+1 4+1 3+1 4+1 5+1

<1 221 3+1 1+1 3+1 1+1

<1 3+1 2+1

<1 2+1 1+1 3+1 3+1 1+1 2+1 5+1 3+1 1+1 3+1 410 415 405 405 430 435 415 505 475 415 455 295 255 310 340 360 375 345 390 320 345 360 340 345 360 350 4+1 4+1 4+1 2+1 3+1 4+1 2+1 2+1 4+1 3+1 5+1 2+1

<1 5+1 4+1

<1 1+1 2+1 5+1 3+1 2+1 1+1

<1 1+1

<1 420 44$

625 625 640 690 640 455 265 320 360 350 280 265 310 300 340 340 310 380 320 450 360 355 210 320 5+1 6+1 3+1 2+1 3+1 3+1 2+1 3+1 3+1 4+1 4+1 1+1

<1 2+1

<1 1+1

<1 3+1 3+1 4+1 5+1

<1 3+1 2+1 3+1'+1 Iodine cartridges are sampled weekly.

Concentrations are <0.10 pCi/m unless otherwise noted.

3 (a) Power failure.

Date based on an estimated average weekly volume.

.~

1982 DONALD C.

COOK GAMMA ISOTOPIC ANALYSIS OF MONTHLY AIR PARTICULATE COMPOS1TES Indicator Stations Ci/ms Back round Stations Ci/ms Month January

ebruarv March April May June July August September October November December Be-7 0.06+0.01 0.07+0.01 0.09+0.01 0.09+0.01 0.10+0.01 0.19+0.10 0.21+0.11 0.09+0.05

<0.07

<0.1

<O.l 0.03+0.01

~other

<0.01

<0.01 Bc-7 0.09+0.01 0.12+0.01 0.'07+0.01 0.18+0.02 0.13+0.02 0.20+0.12 0.14+0.09 0.14+0.09 0.11+0.04

<0.2

<0.2 0.07+0.02 O~ther

<Oe 01

<0.01

<0.01 STRONTIUM 89 AND STRONTIUM 90 ANALYSIS OF QUARTERLY AIR PARTICULATE COMPOSITES Indicator Stations Back round Stations Collection Period Sr-89 Ci/ms Sr-90 Sr-89 Ci/ms Sr-90 1st Ouarter 2nd Quarter 3rd Quarter 4th Quarter

<Oe 002

<0.002

<0.001

<0.002

<0.001

<0.001 39

DONALD C.

COOK Sr-89*/90 and I-131 CONCENTRATIONS in MILK SAMPLES (Monthly Collection)

Indicator Stations Back round Stations Collection Collection Site:

Date r

man tevensv e

a ien I-131 Ci/1 Dowa iac K South Bend Kl 01/09/82 02/06/82 03/06/82 04/17/82 05/08/82 06/12/82 07/10/82 08/07/82 09/04/82 10/09/82 11/06/82 12/04/82

<0. 5

<0.5

<0.6(a)

<0.5

<0.9(a)

<0.5

~0.5

<0.5

<0.7(a)

<0.5

<0.9(a)

<0.5

~0. 5

<0. 5

<0.5

<0.7(a)

<0.5

<0.9(a)

<0.5

<0. 5

<0.5

<g.5 (i)

<0.5

<0.7(a)

<0.5

<0.9(a)

<0.5

<0. 5 (0

5'0.

5

<0. 5

<0.5

<0. 5

<0. 7(a)

<0.5

<0.9(a)

<0.5

<0.5 (b')

<0. 5 (0. 5

<0.5 01/09/82 02/06/82 03/06/82 04/17/82 05/08/82 06/12/82 07/10/82 08/07/82 09/04/82 10/09/82 11/06/82 12/04/82 2+1 2+1 3+2 2+1 2+1 3+1 l2+1 l+l 3+1 9+1 5+1 6+1 1+1 2+1 4+1 2+1 2+1 2+1 721 3+1 4+1 9+1 12+1 8+1 Sr-90 Ci/1 1+1 2+1 3+2 4+1 3+1 2+1

&+1 2+1 4+1 6+1 (b) 7+1 2+1 5+1 6+1 5+1 7+1 2-+1 lal 2+1 4+1 ll+1 11+1 7+1 3+1 2+1 2+1 2+1 3+1 3+1 1+1 l+l (b) 10+1 7+1 8+1

Sr-89 was determined on each sample and was

<5 pCi/1 unless otherwise noted.

(a) Too much decay for lower sensitivity requirement between collection date and receipt of samples at lab.

(b) Sample not available see listing of missed.

DONALD C.

COOK RADIONUCLIDES in MILK SAMPLES (Monthly Collections)

Indicator Stations Back round Stations Collection Site:.

Brid man K2 Stevensville Kl Galien Collection Date 01/09/82 02/06/82 03/06/82 04/17/82 05/08/82 06/12/82 07/10/82 08/07/82 09/04/82 10/09/82 11/06/82 12/04/82

<10

<10 Cs-137

<10

<10 (a)

<10 Ci/l 16+3

<10

- <10

<10 (a)

<10

<10 Other Gamma Emitters Ci l 01/09/82 02/06/82 03/06/82 04/07/82 05/08/82 06/12/82 07/10/82 OS/07/S2 0 0/04/82 10/09/82 11/06/82 12/04/82

<10

<lo

<10

<10 (a)

<10

<10 (a)Sample was not available.

See listing of missed samples.

1982 DONALD C.

COOK GAMMA ISOTOPIC ANALYSIS OF PRECIPITATION SAMPLES (Monthly Collections)

Collection Sites:

Collection Period Indicator 80i/i nCi/m*

Back round nCi/1 nCi/mn January February March April May June July August September October November December

<10

<0.3

<Q.3

<0.3

<0. 3

<0.2

<0.3

<0.2 (0.2

<0.2

<10

<0. 4

<0.5

<0.3

<0. 2

<0.2

<Q.2

<0.3

<0.2

<0.2 RADIOSTRONTIUM CONCENTRATIONS IN PRECIPITATION SAMPLES (Semiannual Analysis on Composites of Monthlys)

Indicator Ci/1 Back round Ci/1 Collection Period 1st semi annual 82 2nd semi annual 82 8r-89

<2

<2 Sr-90

<1(3*

8r-89

<2

<2 8r-90

<1 (2*

lower sensitivity due to low chemical recovery 42

DONALD C.

COOK RADIONVCLIDES IN MELL WATER SAMPLES (18-week Interval Collections)

Back round Stations Indicator Stations Collection Site:

Collection Date ONS 1

ONS 2

ONS 3 Gamma Emitters pCi/1 ONS 4 ONS 5 ONS 6 ONS 7

01/28,02/04/82 06/03/82 10/14/82

<10

<10 Tritium Ci/1 01/28$

02/04/82 06/03/82 10/14/82

<1000

<1000 2100+400 2100+400 1100+400

<1000

. <1000

<1000

1982 DONALD C.

COOK GAMMA EMITTERS IN LAKE WATER SAMPLES (Monthly Composites of Indicator and Background Stations)

Ganja Emitters Ci/l/nuclide Month January tear ch April May June July August September October November December Indicator Com osite

<10 (10 (10 (10

<10 (10

<10

<lo

<10

<10 Back round Com osite

<10 (10 (10 (10 (10

<10

<10 TRITIUM IN LAKE WATER SAMPLES (Quarterly Composites of Monthly Samples)

Tritium Ci/'1

uarter Indicator Stations Back round Stations 1st 2nd 3rd 4th 300+100

<200

<200 200+100 (200

<200

<200 RADIONUCLIDES IN AQUATIC ORGANISMS (Semiannual Collections when Available)

Location Collection Date Sr-89 Ci/

wet Sr-90 Ce-144

~Other North - on>>site North - off-site

,South on-site, South - off-site North on site North off site South on site South off site 05/25/82 05/25/82 05/25/82 05/25/82 10/22/82 10/22/82 10/26/82 10/26/82

<0. 05

<0.05

<0.005

<l

<1<l

<1

<1.

<1

<1<l

<T

<1

DONALD C.

COOK RADIONUCLIDES IN SEDLNENT SAMPLES (Semiannual Collections)

Collection Site Collection Date oCi/

(dr )

Sr-89 Gamma Emitters Sr-90 N ONS S

ONS N OFS S

OFS S

ONS N OFS N ONS N ONS S

ONS N OFS S

OFS 04/27/82 04/27/82 04/27/82 04/27/82 05/25/82 05/25/82 05/25/82 05/25/82 10/12/82 10/l2/82 10/12/82 10/12I82

<1

<1<l

<1

<l

<0. 05

'<0. 05

<0. 05

<0.05

<0. 05

<0.05

<0. 05

<0. 005

<0.005

<0.005 RADIONUCLIDES IN FISH SAMPLES (Semiannual Collections)

Collection Site Collection Date Ci/

wet)

Gamma Emitters Sr-89 Sr 90-N ONS S

ONS N OFS S

OFS N ONS S

ONS N OFS

" S OFS 04/14/82 04/14/82 04/14/82 04/14/82 10/25/82 10/25/82 10/25/82 10/25/82

<1

<0. 05

<0.05

<0.05 0;017+0.012 0.020+0.007 0.016+0.013 0.027~0.016

<0.005

<0.005 RADXONUCLIDES IN FOOD CROPS (Annual Fall Harvest Collection)

Collection Site:

Collection Sample Date ON Site OFF Site Ci/

(wet)

Gamma Emitters 09/82 09/82 09/82 09/82 Grapes Leaves Grapes Leaves 45

DONALD C, COOK GAM1A RADIATION (Quarterly)

(Measured using Thermoluminiscent Dosimeters)

Date Annealed:

Date Read:

1st Main TLD Backup TLD 12/16/81 04/06-08/82 03/17/82 07/01-02/82 2nd Otr.

Hain Backup TLD TLD 06/16/82 10/07/82 3rd Otr.

Hain Backup TLD TLD 09/15/82 01/07/83 4th Otr.

Main Backup TLD TLD Location Indicator Stations Measured mR/week On-Site 1

On-Site 2

On-Site 3

On-Site 4

On-Site 5

On-Site 6

On-Site 7

On-Site 8

On-Site 9

Background Stations Coloma Dowagiac New Buffalo South Bend Off-Site-1 Off-Site-2 Off-Site-3 Off-Site-4 Off-Site-5 Off-Site-6 Off-Site-7 Off-Site-8 Off-Site-9 Off-Site-10

l. 2+0. 1 1.5+0.4 1.4+0.4 1.3+0.4 1.3+0.4 1.2+0.3 1.6+0.9 1.3+0.3 1.7+0.5

1. 6+0. 9 1.5+0.5 1.7+1.0 1.8+0.9 1.5+0.5 1.1+0.4 1.5+0.2 1.6+0.5 1.4+0.4 1.6+0.8 1.7+0.5 1.3+0.3 1.3+0.3 1.4+0.4

1. 5+P. 2

l. 3+0. 2

1. 5+0. 3

1. 2+0. 3

1. 3+0. 1

1. 4+0. 5 1.4+0.4 1.2+0.2 1.4+0.5

1. 4+0. 1

1. 7+0. 7

1. 3+0. 2 1.2+0.2 1.6+1.5 1.3+0.2 1.5+0 1.5+0.4 1.4+0.5 1.4+0.2

1. 4+0. 4 1.4+0.1 1.4+0.3 1.4+0.5 1.1+0.2 1.3+0.1 1.3+0.3 1.0+0.1 1.2+O.l 1.3+0.2 missing 1.0+O.l 1.2+0.3

l. 0+0. 1 1.3+0.4 1.0+0.2 1.0+0.1 1.1+0.3 1.0+0.2 1.2+0.5 1.1+O.l 1.0+0.3 1.2+0.2 1.1+0.2 1.2+0.2 1.1+0.2 1.0+0.1

1. 2+0. 2 1.1+0.2 1.1+0.2 1.0+0.2 1.2+0.3 missing missing 1.1+0.2 1.0+0.2

1. 0+0. 4 1.1+0.2 1.0+0.2 1.0+P.2 1.1+0.2 1.1+0.3 1.0+0.3 1.2+O.l 1.2+0.2 1.1+0.2 1.1+0.2 1.1+0.2 1.2+0.1 1.0+0.2 1.0+0.3 0.9+0.1 0.9+O.l 0.8+0.1

0. 9+0. 1 0.9+0.1 0.9+0.2 0.9+O.l 1.2+0.1 0.9+0.2 0.9+0.1 0.9+O.l 0.9+O.l p.8+0.2 p.9+O.l 0.9+0.1 1.1+0.1 0,9+0.1 1.0+0.1 1.0+0.1 1.0+0.2 1.0+0.2 0.8+0.2 0.8i0.2 0.8+0.2 0.8+0.1 0.6+0.2 0.9+0.1 0.8+O.l 0.9+0.2 0.8+0.1 l.lip.l 0.8+O.l 0.8+O.l 0.8i0.1 l.pi0.2 0.8+0.2 0.8+0.1 0.8+0.1 0.910.2 0.9+0.2 0.9+0.2 0.9+0.1 1.020.2 1.0+0.2 0.9+0.2

l. 110. 2

1. 1+0. 3 1.010.1 0.910.2 1.0+0.1 1.110.2 1.0+0.2 1.1+O.l 1.1+O.l l.pip.l 1.0+0.2 1.1+0.1 1.0+0.1 1.1+O.l l.pip.l 1.1+O.l 1.0+0.1 1.1+0.1 1.1+0.2 1.310.1 1.310.1 1.2+0.3 1.0+0.1 l.pi0.3 1.1+0.'2 1.0+0.2 0.9+0.1 1.0+0.1 1.0+O.l l.1+0. 1 1.0+0.1 1.0+0.2 0.910.1 0.9+0.1 1.0+O.l l.lip.l 1.0+0.2 1.1+O.l 1.0+0.2 1.1+0.3 1.1+0.2 1.0+0.2 1.1+0.2 1.210.1 1.2+0.2 1.1+0;2

SECTION 6 QUALITY ASSURANCE DATA

TLD Intercomparison Badges Irradiated by Battelle Northwest Labs 1982 Total mR less trans ortation control 1st tr 2nd tr 3rd and 4th Otr

~Bad e Known Measured Known Measured Known Measured 22 19.9+7.5 30 26.5i4.2 9.0+3.3 11 11.5+3.8 30 30 29+4 28+4 43 39.2+9.4

. '7 24.7+3.2 51 75 72.6+4.4 42

40. 7+4. 8 73 75 70.0+9.5 42 42.6+5.0 73 62 -,59.5i9.3,,

27 25.3+3".8 '.

51 49+12 46i7 68d.16 64+l4 80 81.1+18.2 80 77.0+13.1 100 94.5~13e1 100 115.8+10.4 73 73 89 89 69+8 72+8 80+9 80+9 91 100 100 90+9 88+13 95+22 96+14

Pi ~

TABLE 3.2 1982 USEPA - EBERLTNE INTERCOMPARISON PROGRAM Sam le T e

~Anal sis Value (EPA)

Value (EXC)

Units Air Filter Air Filter Air Filter Air Filter Air Pilter Air Filter Air Filter Air Filter Pood Pood

'Food Food Food Pood Mater Water Water Water Water Mater Water Water Water Water Water Water Water Water Water Water Water Water Water Water Mater Mater Water Mater Mater Water Water Water Water Water Water Alpha Beta Sr-90 Cs-137 Alpha Beta Sr-90 Cs-137 Sr-89 Sr Co-60 Cs-137 K

Ba-1.40 Alpha Beta Alpha

'Beta Cr-51 Co-60 Zn-65 Ru-106 Cs-134 Cs-137 Alpha Beta Co-60 Sr-89 Sr-90 Cs-134 Cs-137 Ra-226 Ra-228 Gross U

Cr-51 Co-60 Zn-65 RQ-106 Cs-134 Cs-137 I-131 Uranium H-3 Ra-226 Ra-228 25+11 52+8.7 16+2.6 19+8.7 32+8, 67+5 20+1.5 27+5 38~5 23+1.5 30+5 33+5 2730i3.32 0

21+9.1 23+8.2 24+10 32+8.7 34+8.7 22+8.7 24i8.7 0

21+8.7 32~8.7 80+35 llL+8.7 0

21~8.7 14.4+2.6 12+8.7 15+8.7 12.7~3.3 9.2+2.4 15+10 0

20+9 15+9 20+9 22+9 23+9 8.4i1.5 35+6 1820i590 10+2 9~1 27+2 58+2 24+3 32+7 24+19 77+10 17+4 27~9 15+4 21+2 46+16 54i14 2870+290

<114 20+3 15+2 22+2 30+2 44+25 24+3 23+4

<26 20+2 36+3 73~7 107+6

<1 25+4 16~2 10+2 15+2 11.7+3.5 12.9 1.6 15+1

<58 20+3 16+4

<25 22+2 27+2

<75 26+6 1990+690 11+3 13'2 pCi/Filter pCi/Filter pCi/Pilter pCi/Filter pCi/Sample pCi/Sample pCi/Sample pCi/Sample pCi/kg pCi/kg pCi/kg pCi/kg pCi/kg pCi/kg pCi/1 pCi/1 pCi/1 pCi/1 pci/1 pCi/1 pCi/1 pci/1 pCi/1 pci/1 pCi/1 pCi/1 pCi/1 pci/l.

pCi/1 pCi/1 pCi/1 pCi/1 pci/1 pCi/1 pCi/1 pCi/1 pCi/1 pCi/1 pci/1

.pci/1 pCi/1 pCi/1 pci/1 pCi/1 pci/1 49

Samole T

e Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Water Milk Milk Milk Milk Milk Milk Milk

~Anal sts Pu-239 Sr<<89 Sr-90 H-3 ALpha Beta H-3 H-3 Ra-226 Ra-228 I-131 T.-131 Cr-51 Co-60 Zn-65 Ru-106 Cs-134 Cs-137 Ra-226 Ra-228 Uranium Pu-239 Alpha Beta Alpha Beta Cs-134 Cs-137 R -226 Ra-228 Gross Uranium Sr-89 Sr-90 Co-60 Cs-137 Ba-14O K

I-131 Value (EPA) 6.7+1.2 21+8.7 12+2.6 2860+620 16+5 23+5 1830+340 2890+380 13.4+2.0 8.7~1.3 4.4+0.7 87+8.7 23+5 29~5 26+5 0

35+5 25+5 10.5+1.6 11.0+1.7 3o+6 6.9+0.7 19+8.7 24+8.7 55+24

~-

81+8.7 1.8+8.7 20+8.7 12.5+3.2 3.6+0.9 16+10 25+5 16+1.5 30+5 28+5 0

1500+ 75 5.4+0.8 Value (EXC) 5.8+0.2 17+4 10+2 1890+600 16+3 16+7 1760+510 2830+820 13.6~4.0 9.4+3.6 5.561.8 67+14

<59 31+3 29+10

<25 36+3

~

28+3 8.4+2.5 17.7+14.7 24+4 7.2+0.4 8+4 24+5 27+13 64+6

<10 16+7 11.8+3.5 3.4+1.9 9+1 12+7 13+3 51+9 39+19

<489 1310+120 6.7+3.1 Units s

pCi/1 pCi/1 pci/1 pCi/1 pCi/1 pCi/1 Qci/1 pCi/1 pCI/1 pci/1 pci/1 pci/1 pCi/1 pci/1 pCi/1 pci/1 pCi/1 pci/1 pCi/1 pCi/1 pci/1 pci/1 pCi/1 pci/1 pCi/1 pci/1 pci/1 pCi/1 pci/1 pci/1 pCi/1 pCi/1 pci/1 pCi/1 pci/1 pCi/1'g/1 pCi/1 50

TABLE 3.4 1982 Quality Control Analyses Summary The tables below summarize results of samples run for process quality control purposes duxing the subject year.

These listings are in addition to such measurements as detector backgrounds, check source values, radiometric-gravi-metric comparisons, system calibrations etc.

Detailed listings of each measure-ment are maintained at the laboratory and are available for inspection if re-quired.

Blank Sa les Nuclide Anal zed Number of Determinations Number of Analyses Exceeding the LLD for that Anal sis Gross Alpha Gross Beta Tritium Sr-89-90 I-131 Am-241 Pb-210 Po-210 Pu-239 Ra-226 Fe-55 Isotopic Uranium Isotopic Thorium 47 37 75 26 12 27 2

37 3

38 17 0

0 0

0

Blank I-131 analyses axe pexformed with each batch of samples processed.

All blank data were below the detection limit.

51

S iked Sam les Nuclide

~Anal zed Gross Alpha Gross Beta Tiitium Sr-89-90 Number of.

Det'ns 47 37 75 26 Within 2a of known 47 37 75 26 Within 3a of known Differing from known b

> 3a.

Am-261 Pb-210 Po-210 PU-239 Ra-226 Fe-55 Isotopic Uranium Isotopic Thorium 12 27 2

37 44 3

38 17 12 27 2

37 44 3

38 17 S lit Sam les Nuclide

~Anal zed Number of Det'ns"

. No. Agreeing

-No.; Agreeing Within 2a Within 3a No. Differing.

Gross Alpha 17 Gross Beta 20 Tritium 20 Sr-89-90 7

I-131 2

Gamma Emitters 14 Pb-210 4

Po-210

.2 Pu-239 3

Am-241

.2 Isotopic Thorium 3

Isotopic Uranium 16 Ra-226 13 17 20 20 7

2 14 4

2 3

16 13 52

ML17320A459

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