ML17320A459
| ML17320A459 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 03/31/1983 |
| From: | Chandrasekaran INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | |
| Shared Package | |
| ML17320A456 | List: |
| References | |
| NUDOCS 8304070126 | |
| Download: ML17320A459 (56) | |
Text
AV."RICAN FLECTRIC POVlER SERVIC'E CORPORATION DonaId C. Cook Nuclear Plant RADICLOGICAL ENVIRONMENT@'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 Preface SECTION 2 Sampling Program SECTION 3 Analysis Program 14 SECTION 4 Results and Discussion '23 SECTION 5 Data Tables 32 SECTION 6 Quality Assurance Data 47
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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 No. Station Collection Analysis Type T e Anal sis Remarks Air Particulate 6 4 Weekly Weekly Gross Beta lfonthly Gamma Isotopic By indicator and Composite, 2 background samples.
Samples Quarterly Sr-89, Sr-90 ~
Airborne 1-131 Weekly Weekly Gamma Isotopic Precipitation Monthly Monthly Gamma Isotopic By indicator and Composite, 2 background samples.
Samples Semi-annual Sr-89, Sr-90 By indicator and Composite, 2 background samples.
Samples Lake Water Monthly Monthly Gamma Isotopic By indicator and Composite, 2 background samples.
Samples Quarterly Tritium By indicator and Composite, 2 background samples.
Samples Well Water Every 18 wks. Every 18 wks. Gamma Isotopic Tritium Fish 2 per year 2 per year Gamma Isotopic Edible portion only.
Sr-89, Sr-90
TABLE 1 (Cont'd)
ENVIRONMENTAL MONITORING PROGRAM DONALD C. COOK NUCLEAR PLANT Sample No. Stations Collection Analysis Type T e Ind. Bk . Fre uenc Pre uenc Anal sis Remarks Aquatic Organisms 2 2 2 per year 2 per year Gamma Isotopic When available Sr-89, Sr-90 Milk Monthly Monthly Gamma Isotopic Sr-89, Sr-90 I-131 Sediment 2x per year 2x per year Gamma Isotopic Sr-89, Sr-90 TLD 9 14 Quarterly Quarterly Total Dose Pood Crops l l Annually Annually Gamma Isotopic
Table 2 LOWER LIMITS OF DETECTION (LLD')
LLD Samole Class Anal sis Units Air Particulates Gross Beta 0.01 pCi/ms Gamma Isotopic 0.01 pci/ms Sr-89 0.002 pCi/ms Sr-90 0.001 pCi/ms Airborne Iodine I-131 0.01 pCi/ms Milk I-131 0.05 pCi/l Gamma Isotopic 10 pCi/l Sr-89 5 pCi/l Sr-90 1 pCi/l Well Water LS Tritium 1000 pCi/1 Gamma Isotopic 10 pCi/1 Precipitation Gamma Isotopic 10 pCi/1 Sr-89 2 pCi/l Sr-90 1 pCi/1 Lake Water Gamma Isotopic 10 pCi/1 Enriched Tritium, 0.2 pCi/ml Aquatic Organisms Gamma Isotopic'r-89 1 pCi/g wet 0.05 pCi/g wet Sr-90 0.005 pCi/g wet Sediment Gamma Isotopic 1 pCi/g dry Sr-89 0.05 pCi/g dry Sr-90 0.005 pCi/g dry Fish Gamma Isotopic 1 pCi/g wet Sr-89 0.05 pCi/g wet Sr-90 0.005 pCi/g wet Food Cr'ops Gamma Isotopic pCi/g wet Background Gamma Dose mR/week Radiation (TLD) 10
TRUE PLANT NORTH NO RTH, METEOROLOGICAL TOWER Wl PROPERTY LINE ROADS T2 L3 W2~ R.R. TRACK TO8 L W5 545 KY YARD L
~E-W PLANT Q 765 KV W CHESAPEAKE SHORE LINE~ YARD N-S PLANT f 4A 6 OHIO R.R.
2,000 FOOT RADIUS T 6 INTERSTATE 94 SCALE PIGVRE I 1
LOCATI0 N S 0 l,000 2,000 3,000 4,000 FEET OF INDICATOR AIR SAMPLING STATIONS A 'ir, Precipitation T TLD Station W Well Water L Lake Water (taken at shoreline)
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- 0. C. COOK PLANT laire Berrl en Springs Niles Hex Buffalo f
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1Ã C Red Arrow Highway and vicinity of I-94 overpass.
- 2. Stevensvil le Sub Station.
s-r 3. Washington Avenue midway between Brentwood Drive and Kingman Drive.
Washington Avenue and Linco Road. FIGURE III Cleveland Avenue and Shawnee Road. TLD MONITOR LOCATIONS 6: Ho'iden Road and Snow Road. LOCATED ON THE FIVE MILE RADIUS FROM THE PLANT
- 7. Bridgman Sub Station.
'8. California Road between Browntown and Snow Roads.
- 9. Ruggles Road between Hinchman and Lemon Creek Roads.
- 10. At intersection of Hildebrant Road and Red Arrow Highway.
13
SECTION 3 ANALYSIS PROGRAM 14
ANALYTICAL PROCEDURES 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 ashed at high tem-perature ()700 c). The ash is dissolved and the solution treated from this point on in the same manner as are air 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 0 c). The ashed sample is then dissolved and processed 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 is spike, a blank, to be run routinely. Every tenth sample 0
and blanks a or a split sample.
Regular QC reports are prepared by a laboratory-manager on a monthly 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 Calibration Standard Gross Beta 'olution of Standard 137 Cs certified by NBS or Amersham Searle 3
Tritium Solution standard of H certified by NBS Gamma Solution standards of various gamma emitters Spectrometry certified by NBS or Amersham Searle. Standards are used to calibrate each counting geometry used.
90 certified Strontium-89 Solution standards of Sr by Amersham and 90 Searle or NBS 239 certified Gross Alpha Solution standards of Pu by NBS or Amersham Searle.
137 with Radiation Dose Cs gamma source cross-referenced 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 Michigan Reporting Period: January December 1982 County State Hedium or Pathway Type and Lower Limit All Indicator Location with Control Number of Sampled Total Number,. of Locations Hi hest Mean I.ocations Non-routine (Unit of of Analyses Detection Mean Hean- Heanl Reported Measurement) Performed (LLD) (Ran e) Name (Ran e) (Ran e) Heasurements (pCi/ms)
'ross Air Particulates g 0. Ol 0.03 (270/311) 0.01-0.08 On Sites 3, 5, and 6 0.04 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 0. 01 ALL LLD Not Applicable AI.I. LLD Ru-103 24 0.01 ALL LLD Not Applicable ALL LLD Other y 24 0.01 ALL'LD Not Applicable All LLD Sr-89 8 0.002 ALL LLD Not Applicable All LLD Sr-90 0.001 ALL LLD Not Applicable All LLD Airborne Iodine I-131 515 0. Ol ALL LLD Not Aoplicable All LLD
( Ci/m3)
Well Water Tritium 21 1000 1767 (3/12) On Sites 2100 All LLD (pCi/1) 1100-2100 4 and 5 (a) y Spec. 21 10 ALL LLD Not Applicable 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) Page 2 of 3 Facility: o a C .oo Medium or Pathway Type and Lower Limit All Indicator Location with Control Number of Sampled Total Number of Locations Hi hest Mean Locations Non-routine (Unit of of Analyses Detection Mean Mean Meanl Reported Measurement Performed LLD Ran e) Name (Ran e) (Ran e) Measurements Milk I-131 58 0.05 All LLD Not Applicable All LLD (pCi/1)
Sr-89 58 All LLD Not Applicable All LLD Sr-90 58 4.2 (35/35) Bridgman 4.2 (12/12) 4. 6 (23/23) 1-12 1 12 1-1 y Spec. 58 10 All LLD Not Applicable All LLD 0 Precipitation y Spec. 24 All LLD Not Applicable All LLD (pci/1)
Sr-89 4 10'0 All LLD. Not Apolicable All LI.D Sr-90 4 All LLD Not Applicable 4 (1/2),
4 Lake Mater y Spec. 20 All LLD Not Applicable All LLD (pCi/1)
Tritium 8 200 300 1/4 Not Applicable 2OO (1/4)
(a) (a)
Aquatic Organisms Ce-144 8 All LLD Not. Applicable . ALL LLD (pCi/g wet)
Nb-95 -8 All LLD Not Applicable ALL LLD Zr-95 8 All LLD Not Applicable AI.L LI.D a
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) Page 3 of 3 Facility: Donald C. Cook Nuclear Station Medium or Pathway Type and Lower'Limit All Indicator Location with Control Number of Sampled Tote'umber of Locations Hi hest Mean Locations Nc'n-routine (Unit of of Analyses Detection Meanl Mean Mean1 Reported Measurement Performed LLD (Ran e Name (Ran e) (Ran e) Measurements Aquatic Organisms Sr-89 8 0.05 All LLD Not Applicable All LLD (pCi/g wet)
Sr-90 8 0.005 ALL LL6 Not Applicable. ALL LLD Sediment y Spec. 12 All LLD Not Applicable All LLD (pCi/g dry)
Sr-89 12 0. 05 All LLD Not Apnlicable All LLD Sr-90 12 0.005 ALL LLD Not Applicable ALL LLD Food Crops y Spec. 4 All'LLD Not Applicable All LLD 0
( Ci/ wet)
Fish y Spec 8 All LLD Not Applicable All LLD (pCi/g wet)
Sr-89 8 0.05 All.LLD Not Applicable All LLD Sr-90 8 0.005 0.019 (2/4) On Site, 0.020 (1/2 0.022 (2/4) 0.017-0.020 South .'(a) .
0.016-0.027 Background y Dose 91 O.l 1.1 (35/35) . On-Site 1.3 (4/4) 1.2 (56/56)
Radiation (TLD) 0.6-1.7 1.1-1.7 0.8-1.8 (mR/week)
(a) Range is not reported as only are detectable measurement was available.
only. ractions indicated in parentheses.
~
and range based on detectable measurements
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/m3 , and was 0.03 pCi/m3 for the background stations.
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 Back round 3
pCi/m Preoperational 1973 0.04 0.04 1974 Operational 1975 0.08 0.09 1976 0.09 0.08 1977 0.22 0.22 27
Xndicator ~Back round 3
Ci/m Operational 1978 0.11 1979 0.04 0.04 1980'981 0.04 0.04
- 0. 12 0. 11 1982 0.03 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/m3 for all 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 3 for both indica-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/m2 ). Sr-89 and Sr-90 concentrations 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 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-peak of. any nuclides present in concentra-tions exceeding the sensitivity limits set fo'r "that particular experiment.
NA, NS, NR 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).
Error Terms 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 Expected Collection Sam le T e Location Date Reason AP/CC DOH~COL 01/09/82 Heather conditions AP/CC SBN,COL 01/23/82 Heather conditions-frozen locks Lake Hater All points 02/06/82 Lake frozen AP/CC ONS-1 08/31/82 No power to unit Milk SBN 09/04/82 Not available
'ilk ll/06/82 Not available 34
DONALD C. COOK AIRBORNE IODINE-131* and GROSS BETA in AIR PARTICULATE FILTERS (Meekly Collections)
Gross Beta 10"a Ci/ms ON-SITE 1 ON-SITE 2 ON-SITE 3 ON-SITE 4 ON-SITE 5 Collection Volume Volume Volume Volume Volume Date ~ms Gross ~ms Gross ~ms Gross Gross 8 Gross 8 Ol/04/82 340 <1 380 1+1 370 5+1 395 5+1 335 6~=1, 01/11-12/82 400 2+1 470 1+1 .385 4+1 '05 1+1 410 8+1 Ol/18/82 350 1+1 290 1+1 395 1+1 375 1+1 '390 1+1 01/26/82 390 <1 370 1+1 410 6+1 485 6+1 495 6+1 02/02/82 360 1+1 325 1+1 360 6+1 465 2+1 475 6+1 02/09/82 360 1+1 305 1+1 360 6+1 430 5+1 485 7+1 02/16/82 340 <1 445 1+1 355 7+1 435 6+1 485 4+1 02/23/82 390 <1 305 1+1 310 4+1 435 3+1 385 4+1 03/02/82 380 1+1 275 1+1 315 3+1 450 2+1 395 5+1 03/09/82 380 <1 250 <1 310 5+1 420 5+1 415 5+1 03/16/82 205 <1 360 <1 305 4+1 410 4+1 415 5+1 03/23/82 345 <1 505 <1 315 2+1 325 <1 335 1+1 03/30/82 370 <1 500 1+1 395 3+1 350 2+1 350 4+1 04/06/82 345 <1 495 1+1 390 3+1 330 3+1 360 3+1 04/13/82 340 <1 500 2+1 400 5+1 340 5+1 360 5+1 04/20/82 415 <1 375 1+1 410 3+1 335 2+1 390 4+1 04/27/82 495 <1 345 1+1 415 6+1 385 5+1 370 7+1 05/04/82 485 <1 350 <1 390 4+1 380 4+1 375 6+1 05/11/82 365 <1 380 <1 415 5+1 425 4+1 460 5+1 05/18/82 275 <1 375 1+1 415 4+1 435 4+1 370 5+1 05/25/82 335 <1 215 1+1 340 2+1 485 <1 365 3+1 06/01/82 325 <1 335 1+1 340 3+1 280 3+1 335 3+1 06/08/82 280 1+1 320 2+1 330 3+1 280 3+1 320 2+1 06/15/82 275 1+1 315 3+1 340 4+1 460 3+1 320 5+1 06/22/82 330 1+1 310. 2+1 340 3+1 455 2+1 340 3+1 06/29/82 355 1+1 285 2+1 350 4+1 440 3+4 330 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 Volume Volume Volume Volume Volume Date ~ms ~Gro s s ~ms Gross B ~ms Gross 8 +gi~s Gross B Gross 07/06/82 360 1+1 290 2+1 340 4+1 435 4+1 340 2+1 07/13/82 330 2+1 275 5+1 360 4+1 535 2+1 340 7+1 07/20/82 305 3+1 270 2+1 380 5+1 685 5+1 350 7+1 07/27/82 435 <1 290 1+1 385 5+1 565 <1 345 <1 08/03/82 430 1+1 320 . 3+1, 385 5+1 630 3+1 '80 5+1 08/10/82 375 1+1 360 2+1 390 4+1 600 3+1 365 5+1 08/17/82 365 1+1 345 2+1 385 3+1 485 2+1 375 3+1 08/24/82 400 1+1 340 1+1 410 2+1 310 2+1 350 2+1 08/31/82 (a) 335 1+1 420 4+1 310 5+1 335 4+1 09/07/82 385 {b) 4+1 335 3+1 405 3+1 275 4+1 345 4+1 09/14/82 295 1+1 380 3il 415 3+1 310 4+1 395 5+1 09/21/82 330 %1 280 2+1 315 2+1 310 2+1 375 2+1 09/28/82 370 1+1 295 4+1 345 3+1 335 3+1 375 4+1 10/05/82 385 1+1 315 2+1 345 5+] 315 3+1 405 5+1 10/12/82 380 <1 350 <1 350 3xl 315 2+1 390 4+1 10/19/82 360 <l. 290 221 335 2+1 300 1+1 380 2<Jl 10/26/82 345 1+1 270 3il 320 4+1 295 <1 440 4+1 ll/02/82 355 lkl 355 3+1 315 4+1- 260 4+1 360 4+1 11/09/82 340 <1 370 l 280 290 4+1 611 235 315 270 3+1
<1 511 325 380 385 3+1 3i1 ll/30/82 295 <1 335 4tl 295 5+1 235 2+1 395 4il 12/07/82 320 <1 365 3kl 350 321 265 3+l 375 2il .
12/14/82 305 <1 395 <1 345 4il 375 3il 355 5+1 12/21/82 300 2+1 280 2+1 340 5+1 305 4+1 300 6+1 12/28/82 295 1+1 315 1+1 345 3+1 325 3+1 245 2+1 Iodine cartidges are sampled weekly. Concentrations are <Os10 PCi/ms unless otherwise noted.
See Lisiing of Hissed Samnles page.
No power. Data based-on an estimated average e for the week.
s
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 Volume Gross Collection Volume Gross Gross Volume Gross Volume Gross Date (m3) Beta Date (m3) Beta (m3) Beta (uP) Beta (m3) Beta 01/04/82 345 5+1 01/02/82 380 7il 335 5+1 370 6+1 335 7+1 01/12/82 395 S+1 01/09/82 365 6+1 310 5+1 (a) (a) 01/10/82 350 3+1 01/17/02 450 5+1 335 10+1 720 3+1 670 2+1 01/26/82 400 5+1 01/23/82 330 6+1 (a) 370 4+1 (a) 02/02/82 375 6+1 01/30/82 390 4+1 600 2+1 385 1+1 660 5+1 02/09/82 390 7+1 02/06/82 380 4+1 1'olume 365 4+1 385 1+1 350 3+1 02/16/82 385 2+1 02/13/82 410 5+1 375 7+1 395 <1 345 1+1 02/23/82 380 5+] 02/20/82 360 3+1 365 3+1 405 5+1 295 2+1 03/02/82 380 5+1 02/27/82 385 3+1 385 4+1 470 3+1 345 3+1 03/09/82 385 4+1 03/06/82 370 3+1 345 2+1 440 1+1 345 2+1 03/16/82 375 4+1 03/13/82 345 5+1 300 5+1 335 4+1 315 3+1 03/23/02 360 1+1 03/20/82 330 1+1 325 1+1 300 1+1 385 1+1 03/30/82 365 4+1 03/27/82 375 2+1 365 3+1 315 2+1 425 <1 04/06/82 360 3+1 04/03/82 360 1+1 340 2+1 325 3+1 370 1+1 04/13/82 375 5+1 04/10/82 445 5+1 375 5+1 325 6+1 440 4+1 04/20/82 340 3+1 04/17/82 355 2+1 360 3+1 340 2+1 405 3+]
04/27/82 330 6+1 04/24/82 390 6+1 320 6+1 320 5+1 495 4+]
05/04/02 335 5+1 05/01/82 355 4+1 330 <1 345 3+1 470 2+1 05/11/02 335 4+1 05/00/02 345 3+1 330 3+1 330 5+1 515 1+1 05/10/02 345 5+1 05/15/02 350 5+1 335 1+1 365 4+1 580 2+1 05/25/82 370 2~1 05/21/82 340 2+1 335 1+1 325 2+1 360 2+1 06/01/82 345 3+1 05/29/82 365 2+1 - 330 1+1 325 2+1 415 1+1 06/08/82 315 3+1 06/05/82 310 3+1 360 3+1 320 3+1 420 3+1 06/15/82 300 4+1 06/12/82 325 3+1 355 3+1 365 3+1 405 3+1 06/22/82 310 2+1 06/19/82 340 3+1 340 4+1 360 3+1 340 3+1 06/29/82 310 4+1 06/26/82 340 3+ 315 3+1 395 1+1 3qO 2+1
" Iodine cartridges are sampled weekly. Concentrations are <Oe10 pCi/m3 unless otherwise noted.
(a) See Listing of Hissed samples page.
DONALD C. COOK AIRBORNE IODINE-131* and GROSS BETA in AIR PARTICULATE FILTERS (Weekly Collections)
-2 3 Gross Beta 10 Ci m ON-SITE 6 NEW BUFFALO SOUTH BEND DOWAGIAC COLOMA Collection Volume Gross Collection Volume Gross Voltage Gross Volume Gross Volume Gross Date ~{m3 Beta Date (m3) Beta ~m3) Beta ~m>) Beta 07/06/82 320 4+1 07/03/82 335'40 4+1 405 5+1 410 4+1 420 5+1 07/13/82 325 5+1 07/10/82 4+1 375 5+1 415 4+1 44$ 6+1 07/20/82 330 4+1 07/17/82 355 4+1 385 4+1 405 4+1 625 3+1 07/27/82 335 5+1 07/24/82 400 2+1 380 3+1 405 2+1 625 2+1 08/03/82 360 4+1 07/31/82 375 4+1 310 4+1 430 3+1 640 3+1 08/10/82 365 4+1 08/07/82 385 4+1 400 5+1 435 4+1 690 3+1 08/17/82 555 1+1 08/14/82 385 1+1 465 <1 415 2+1 640 2+1 08/24/82 605 2+1 08/21/82 395 3+1 570 221 505 2+1 455 3+1 08/31/82 620 3+1 08/28/82 370 2+1 590 3+1 475 4+1 265 3+1 09/07/82 565 2+1 09/07/82 420 1+1 510 1+1 415 3+1 320 4+1 09/14/82 610 1+1 09/11/82 440 4+1 600 3+1 455 5+1 360 4+1 09/21/82 235 1+1 09/18/82 305 2+1 300 1+1 295 2+1 350 1+1 09/28/82 230 5+1 90/25/82 300 2+1 285 <1 255 <1 280 <1 10/05/82 240 3+1 10/02/82 295 (a ) <l. 315 3+1 310 5+1 265 2+1 10/12/82 240 2+1 10/09/82 400 2il 335 2+1 340 4+1 310 <1 10/19/82 280 2+1 10/16/82 630 <1 335 <1 360 <1 300 1+1 10/26/82 265 2+1 10/23/82 475 2+1 325 2+1 375 1+1 340 <1 11/09/82 345 (a) <1 11/06/82 480 2+1 330 1+1 345 2+1 340 3+1 11/12/82 275 4+1 10/30/82 510 2il 330 3+1 390 310 3+1 11/16/82 360 4+1 11/13/82 415 5+1 290 3+1 320 5+1 380 4+1 11/23/82 405 5+1 11/20/82 400 <1 250 1+1 345 3+1 320 5+1 11/30/82 445 1+1 11/27/82 355 5+1 350(a) 2+1 360 2+1 450 <1 12/07/82 410 2+1 12/04/82 325 3+1 310 5+1 340 1+1 360 3+1 12/14/82 375 4+1 12/11/82 340 3+1 375 3+1 345 <1 355 2+1 12/21/82 390 4+1 12/18/82 350 2+1 485 1+1 360 1+1 210 3+1'+1 12/28/82 425 2+1 12/25/82 335 4+1 410 3+1 350 <1 320
- Iodine cartridges are 3 sampled weekly. Concentrations are <0.10 pCi/m unless otherwise noted.
(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 Back round Stations Ci/ms Ci/ms Month Be-7 ~other Bc-7 O~ther January 0.06+0.01 <0.01 0.09+0.01 <Oe 01
- ebruarv 0.07+0.01 <0.01 0.12+0.01 <0.01 March 0.09+0.01 <0.01 0.'07+0.01 <0.01 April 0.09+0.01 <0.01 0.18+0.02 <0.01 May 0.10+0.01 <0.01 0.13+0.02 <0.01 June 0.19+0.10 <0.01 0.20+0.12 <0.01 July 0.21+0.11 <0.01 0.14+0.09 <0.01 August 0.09+0.05 <0.01 0.14+0.09 <0.01 September <0.07 <0.01 0.11+0.04 <0.01 October <0.1 <0.01 <0.2 <0.01 November <O.l <0.01 <0.2 <0.01 December 0.03+0.01 <0.01 0.07+0.02 <0.01 STRONTIUM 89 AND STRONTIUM 90 ANALYSIS OF QUARTERLY AIR PARTICULATE COMPOSITES Indicator Stations Back round Stations Collection Ci/ms Ci/ms Period Sr-89 Sr-90 Sr-89 Sr-90 1st Ouarter <Oe 002 <0.001 <0.002 <0.001 2nd Quarter <0.002 <0.001 <0.002 <0.001 3rd Quarter <0.002 <0.001 <0.002 <0.001 4th Quarter <0.002 <0.001 <0.002 <0.001 39
DONALD C. COOK Sr-89*/90 and I-131 CONCENTRATIONS in MILK SAMPLES (Monthly Collection)
Indicator Stations Back round Stations Collection Site: r man tevensv e a ien Dowa iac K South Bend Kl Collection Date I-131 Ci/1 01/09/82 <0. 5 <0.5 <0. 5 <0.5 <0.5 02/06/82 <0. 5 <0.5 <0. 5 <0.5 <0. 5 03/06/82 <0.5 <0.5 <0.5 <0.5 <0. 5 04/17/82 <0.6(a) <0.7(a) <0.7(a) <0.7(a) <0. 7(a) 05/08/82 <0.5 <0.5 <0.5 <0.5 <0.5 06/12/82 <0.9(a) <0.9(a) <0.9(a) <0.9(a) <0.9(a) 07/10/82 <0.5 <0.5 <0.5 <0.5 <0.5 08/07/82 <0.5 <0.5 <0. 5 <0. 5 <0.5
~0.5 <0.5 <0.5 (0 (b')
09/04/82 5'0.
10/09/82 <0.5 ~0. 5 <g.5 5 <0. 5
<0.5 <0. 5 (i) <0. 5 (0. 5 11/06/82 12/04/82 <0.5 <0. 5 <0.5 <0.5 <0.5 Sr-90 Ci/1 01/09/82 2+1 1+1 1+1 2+1 3+1 02/06/82 2+1 2+1 2+1 5+1 2+1 03/06/82 3+2 4+1 3+2 6+1 2+1 04/17/82 2+1 2+1 4+1 5+1 2+1 05/08/82 2+1 2+1 3+1 7+1 3+1 3+1 2+1 2+1 2-+1 3+1 06/12/82 07/10/82 l2+1 721 &+1 lal 1+1 08/07/82 l+l 3+1 2+1 2+1 l+l 09/04/82 3+1 4+1 4+1 4+1 (b) 10/09/82 9+1 9+1 6+1 ll+1 10+1 11/06/82 5+1 12+1 (b) 11+1 7+1 12/04/82 6+1 8+1 7+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 Cs-137 Ci/l 01/09/82 <10 <10 <10 16+3 <10 02/06/82 <10 <10 <10 <10 <10 03/06/82 <10 <10 <10 <10 <10 04/17/82 <10 <10 <10 <10 <10 05/08/82 <10 <10 <10 <10 <10 06/12/82 <10 <10 <10 <10 <10 07/10/82 <10 <10 <10 <10 - <10 08/07/82 <10 <10 <10 <10 <10 09/04/82 <10 <10 <10 <10 (a) 10/09/82 <10 <10 <10 <10 <10 11/06/82 <10 <10 (a) <10 <10 12/04/82 <10 <10 <10 <10 <10 Other Gamma Emitters Ci l 01/09/82 <10 <10 <10 <10 <10 02/06/82 <10 <10 <10 <10 <10 03/06/82 <10 <10 <10 <10 <10 04/07/82 <10 <10 <10 <10 <10 05/08/82 <10 <10 <10 <10 <10 06/12/82 <10 <10 <10 <10 <10 07/10/82 <10 <10 <10 <10 <10 OS/07/S2 <10 <10 <10 <10 <10 0 0/04/82 <lo <10 <10 <10 (a) 10/09/82 <10 <10 <10 <10 <10 11/06/82 <10 <10 <10 <10 <10 12/04/82 <10 <10 <10 <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: Indicator Back round Collection Period 80i/i nCi/m* nCi/1 nCi/mn January <10 <0.3 <10 <0. 4 February <10 <Q.3 <10 <0.5 March <10 <0.3 <10 <0.3 April <10 <0. 3 <10 <0. 2 May <10 <0. 3 <10 <0.2 June <10 <0. 3 <10 <0.2 July <10 <0.2 <10 <Q.2 August <10 <0.3 <10 <0.3 September <10 <0.2 <10 <0.2 October <10 (0.2 <10 <0.2 November <10 <0.2 <10 <0.2 December <10 <0.2 <10 <0.2 RADIOSTRONTIUM CONCENTRATIONS IN PRECIPITATION SAMPLES (Semiannual Analysis on Composites of Monthlys)
Indicator Back round Ci/1 Ci/1 Collection Period 8r-89 Sr-90 8r-89 8r-90 1st semi annual 82 <2 <1 <2 <1 2nd semi annual 82 <2 ( 3* <2 (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: ONS 1 ONS 2 ONS 3 ONS 4 ONS 5 ONS 6 ONS 7 Collection Date Gamma Emitters pCi/1 01/28,02/04/82 <10 <10 <10 <10 <10 <10 <10 06/03/82 <10 <10 <10 <10 <10 <10 <10 10/14/82 <10 <10 <10 <10 <10 <10 <10 Tritium Ci/1 01/28$ 02/04/82 <1000 <1000 <1000 2100+400 2100+400 1100+400 <1000 06/03/82 <1000 <1000 . <1000 <1000 <1000 <1000 <1000 10/14/82 <1000 <1000 <1000 <1000 <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 Indicator Com osite Back round Com osite January <10 <10 tear ch (10 (10 April (10 (10 May (10 (10 June <10 (10 July (10 <10 August <10 <10 September <lo <10 October <10 <10 November <10 <10 December <10 <10 TRITIUM IN LAKE WATER SAMPLES (Quarterly Composites of Monthly Samples)
Tritium Ci/'1
uarter Indicator Stations Back round Stations "
1st 300+100 200+100 2nd <200 (200 3rd <200 <200 4th <200 <200 RADIONUCLIDES IN AQUATIC ORGANISMS (Semiannual Collections when Available)
Collection Ci/ wet Location Date Sr-89 Sr-90 Ce-144 ~Other North - on>>site 05/25/82 <0. 05 <0.005 <l <1 North - off-site 05/25/82 <0.05 <0.005 <l <1
,South on-site, 05/25/82 <0.05 <0.005 <1 <l South - off-site 05/25/82 <0.05 <0.005 <l North on site 10/22/82 <0.05 <0.005 <1 <T North off site 10/22/82 <0.05 <0.005 <1. <1 South on site 10/26/82 <0.05 <0.005 <1 <1 South off site 10/26/82 <0.05 <0.005 <1 <1
DONALD C. COOK RADIONUCLIDES IN SEDLNENT SAMPLES (Semiannual Collections)
Collection Collection oCi/ (dr )
Site Date Gamma Emitters Sr-89 Sr-90 N ONS 04/27/82 <1 <0. 05 <0. 005 S ONS 04/27/82 <1 '<0. 05 <0.005 N OFS 04/27/82 <1 <0. 05 <0.005 S OFS 04/27/82 <1 <0.05 <0.005 S OFS 05/25/82 <1 <0.05 <0.005 S ONS 05/25/82 <1 <0. 05 <0.005 N OFS 05/25/82 <1 <0. 05 <0.005 N ONS 05/25/82 <1 <0.05 <0.005 N ONS 10/12/82 <l <0. 05 <0.005 S ONS 10/l2/82 <1 <0. 05 <0.005 N OFS 10/12/82 <l <0. 05 <0.005 S OFS 10/12I82 <l <0. 05 <0.005 RADIONUCLIDES IN FISH SAMPLES (Semiannual Collections)
Collection Collection Ci/ wet)
Site Date Gamma Emitters Sr-89 Sr 90-N ONS 04/14/82 <1 <0. 05 0;017+0.012 S ONS 04/14/82 <1 <0. 05 0.020+0.007 N OFS 04/14/82 <1 <0. 05 0.016+0.013 S OFS 04/14/82 <1 <0. 05 0.027~0.016 N ONS 10/25/82 <1 <0.05 <0.005 S ONS 10/25/82 <1 <0.05 <0.005 N OFS 10/25/82 <1 <0.05 <0.005 S OFS 10/25/82 <1 <0.05 <0.005 RADXONUCLIDES IN FOOD CROPS (Annual Fall Harvest Collection)
Collection Site: ON Site OFF Site Collection Sample Ci/ (wet)
Date Gamma Emitters 09/82 Grapes 09/82 Leaves 09/82 Grapes 09/82 Leaves 45
DONALD C, COOK GAM1A RADIATION (Quarterly)
(Measured using Thermoluminiscent Dosimeters)
Date Annealed: 12/16/81 03/17/82 06/16/82 09/15/82 Date Read: 04/06-08/82 07/01-02/82 10/07/82 01/07/83 1st 2nd Otr. 3rd Otr. 4th Otr.
Main Backup Hain Backup Hain Backup Main Backup TLD TLD TLD TLD TLD TLD TLD TLD Location Measured mR/week Indicator Stations On-Site 1 l. 2+0. 1 1. 5+P. 2 1.1+0.2 1. 2+0. 2 1.0+0.3 0.8i0.2 l. 110. 2 l.pi0.3 On-Site 2 1.5+0.4 l. 3+0. 2 1.3+0.1 1.1+0.2 0.9+0.1 0.9+O.l 0.8+0.2 1. 1+0. 3 1.1+0.'2 1.0+0.2 On-Site 3 1.4+0.4 1. 5+0. 3 1.3+0.3 1.1+0.2 0.8+0.1 1.010.1 On-Site 4 1.3+0.4 1. 2+0. 3 1.0+0.1 1.0+0.2 0.8+0.1 0.6+0.2 0.910.2 0.9+0.1 On-Site 5 1.3+0.4 1. 3+0. 1 1.2+O.l 1.2+0.3 0. 9+0. 1 0.9+0.1 1.0+0.1 1.0+0.1 On-Site 6 1.2+0.3 1. 4+0. 5 1.3+0.2 missing 0.9+0.1 0.8+O.l 1.110.2 1.0+O.l On-Site 7 1.6+0.9 1.4+0.4 missing missing 0.9+0.2 0.9+0.2 1.0+0.2 l. 1+0. 1 On-Site 8 1.3+0.3 1.2+0.2 1.0+O.l 1.1+0.2 0.9+O.l 0.8+0.1 1.1+O.l 1.0+0.1 On-Site 9 1.7+0.5 1.4+0.5 1.2+0.3 1.0+0.2 1.2+0.1 l.lip.l 1.1+O.l 1.0+0.2 Background Stations Coloma 1. 6+0. 9 1. 4+0. 1 l. 0+0. 1 1. 0+0. 4 0.9+0.2 0.8+O.l l.pip.l 0.910.1 Dowagiac 1.5+0.5 1. 7+0. 7 1.3+0.4 1.1+0.2 0.9+0.1 0.8+O.l 1.0+0.2 0.9+0.1 New Buffalo 1.7+1.0 1. 3+0. 2 1.0+0.2 1.0+0.2 0.9+O.l 0.8i0.1 1.1+0.1 1.0+O.l South Bend 1.8+0.9 1.2+0.2 1.0+0.1 1.0+P.2 0.9+O.l l.pi0.2 1.0+0.1 l.lip.l Off-Site- 1 1.5+0.5 1.6+1.5 1.1+0.3 1.1+0.2 p.8+0.2 0.8+0.2 1.1+O.l 1.0+0.2 Off-Site- 2 1.1+0.4 1.3+0.2 1.0+0.2 1.1+0.3 p.9+O.l 0.8+0.1 l.pip.l 1.1+O.l Off-Site- 3 1.5+0.2 1.5+0 1.2+0.5 1.0+0.3 0.9+0.1 0.8+0.1 1.1+O.l 1.0+0.2 Off-Site- 4 1.6+0.5 1.5+0.4 1.1+O.l 1.2+O.l 1.1+0.1 0.910.2 1.0+0.1 1.1+0.3 Off-Site- 5 1.4+0.4 1.4+0.5 1.0+0.3 1.2+0.2 0,9+0.1 0.9+0.2 1.1+0.1 1.1+0.2 Off-Site- 6 1.6+0.8 1.4+0.2 1.2+0.2 1.1+0.2 1.0+0.1 0.9+0.2 1.1+0.2 1.0+0.2 Off-Site- 7 1.7+0.5 1. 4+0. 4 1.1+0.2 1.1+0.2 1.0+0.1 0.9+0.1 1.310.1 1.1+0.2 Off-Site- 8 1.3+0.3 1.4+0.1 1.2+0.2 1.1+0.2 1.0+0.2 1.020.2 1.310.1 1.210.1 Off-Site- 9 1.3+0.3 1.4+0.3 1.1+0.2 1.2+0.1 1.0+0.2 1.0+0.2 1.2+0.3 1.2+0.2 Off-Site-10 1.4+0.4 1.4+0.5 1.0+0.1 1.0+0.2 0.8+0.2 0.9+0.2 1.0+0.1 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 9.0+3.3 30 29+4 30 26.5i4.2 11 11.5+3.8 30 28+4 43 39.2+9.4 .
'7 24.7+3.2 51 49+12 62 -,59.5i9.3,, 27 25.3+3".8 '. 51 46i7 75 72.6+4.4 42 40. 7+4. 8 73 68d.16 75 70.0+9.5 . 42 42.6+5.0 73 64+l4 80 81.1+18.2 73 69+8 90+9 80 77.0+13.1 73 72+8 91 88+13 100 94.5~13e1 89 80+9 100 95+22 100 115.8+10.4 89 80+9 100 96+14
Pi ~
TABLE 3.2 1982 USEPA - EBERLTNE INTERCOMPARISON PROGRAM Sam le T e ~Anal sis Value (EPA) Value (EXC) Units Air Filter Alpha 25+11 27+2 pCi/Filter Air Filter Beta 52+8.7 58+2 pCi/Filter Air Filter Sr-90 16+2.6 24+3 pCi/Pilter Air Filter Cs-137 19+8.7 32+7 pCi/Filter Air Pilter Alpha 32+8, 24+19 pCi/Sample Air Filter Beta 67+5 77+10 pCi/Sample Air Filter Sr-90 20+1.5 17+4 pCi/Sample Air Filter Cs-137 27+5 27~9 pCi/Sample Pood Sr-89 38~5 15+4 pCi/kg Pood Sr 23+1.5 21+2 pCi/kg
'Food Co-60 30+5 46+16 pCi/kg Food Cs-137 33+5 54i14 pCi/kg Food K 2730i3.32 2870+290 pCi/kg Pood Ba-1.40 0 <114 pCi/kg Mater Alpha 21+9.1 20+3 pCi/1 Water Beta 23+8.2 15+2 pCi/1 Water Alpha 24+10 22+2 pCi/1 Water 'Beta 32+8.7 30+2 pCi/1 Water Cr-51 34+8.7 44+25 pci/1 Mater Co-60 22+8.7 24+3 pCi/1 Water Zn-65 24i8.7 23+4 pCi/1 Water Ru-106 0 <26 pci/1 Water Cs-134 21+8.7 20+2 pCi/1 Water Cs-137 32~8.7 36+3 pci/1 Water Alpha 80+35 73~7 pCi/1 Water Beta llL+8.7 107+6 pCi/1 Water Co-60 0 <1 pCi/1 Water Sr-89 21~8.7 25+4 pci/l.
Water Sr-90 14.4+2.6 16~2 pCi/1 Water Cs-134 12+8.7 10+2 pCi/1 Water Cs-137 15+8.7 15+2 pCi/1 Water Ra-226 12.7~3.3 11.7+3.5 pCi/1 Water Ra-228 9.2+2.4 12.9 1.6 pci/1 Water Gross U 15+10 15+1 pCi/1 Mater Cr-51 0 <58 pCi/1 Mater Co-60 20+9 20+3 pCi/1 Water Zn-65 15+9 16+4 pCi/1 Mater RQ-106 20+9 <25 pCi/1 Mater Cs-134 22+9 22+2 pci/1 Water Cs-137 23+9 27+2 .pci/1 Water I-131 8.4i1.5 <75 pCi/1 Water Uranium 35+6 26+6 pCi/1 Water H-3 1820i590 1990+690 pci/1 Water Ra-226 10+2 11+3 pCi/1 Water Ra-228 9~1 13'2 pci/1 49
Samole T e ~Anal sts Value (EPA) Value (EXC) Units s
Water Pu-239 6.7+1.2 5.8+0.2 pCi/1 Water Sr<<89 21+8.7 17+4 pCi/1 Water Sr-90 12+2.6 10+2 pci/1 Water H-3 2860+620 1890+600 pCi/1 Water ALpha 16+5 16+3 pCi/1 Water Beta 23+5 16+7 pCi/1 Water H-3 1830+340 1760+510 Qci/1 Water H-3 2890+380 2830+820 pCi/1 Water Ra-226 13.4+2.0 13.6~4.0 pCI/1 Water Ra-228 8.7~1.3 9.4+3.6 pci/1 Water I-131 4.4+0.7 5.561.8 pci/1 Water T.-131 87+8.7 67+14 pci/1 Water Cr-51 23+5 . <59 pCi/1 Water Co-60 29~5 31+3 pci/1 Water Zn-65 26+5 29+10 pCi/1 Water Ru-106 0 <25 pci/1 Water Cs-134 35+5 36+3 ~
pCi/1 Water Cs-137 25+5 28+3 pci/1 Water Ra-226 10.5+1.6 8.4+2.5 pCi/1 Water Ra-228 11.0+1.7 17.7+14.7 pCi/1 Water Uranium 3o+6 24+4 pci/1 Water Pu-239 6.9+0.7 7.2+0.4 pci/1 Water Alpha 19+8.7 8+4 pCi/1 Water Beta 24+8.7 24+5 . pci/1 Water Alpha 55+24 ~- 27+13 pCi/1 Water Beta 81+8.7 64+6 pci/1 Water Cs-134 1.8+8.7 <10 pci/1 Water Cs-137 20+8.7 16+7 pCi/1 Water R -226 12.5+3.2 11.8+3.5 pci/1 Water Ra-228 3.6+0.9 3.4+1.9 pci/1 Water Gross Uranium 16+10 9+1 pCi/1 Milk Sr-89 25+5 12+7 pCi/1 Milk Sr-90 16+1.5 13+3 pci/1 Milk Co-60 30+5 51+9 pCi/1 Milk Cs-137 28+5 39+19 pci/1 Milk Ba-14O 0 <489 pCi/1'g/1 Milk K 1500+ 75 1310+120 Milk I-131 5.4+0.8 6.7+3.1 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 Number of Number of Analyses Exceeding Anal zed Determinations the LLD for that Anal sis Gross Alpha 47 Gross Beta 37 Tritium 75 Sr-89-90 26 I-131 Am-241 12 0 Pb-210 27 0 Po-210 2 0 Pu-239 37 0 Ra-226 0 Fe-55 3 0 Isotopic Uranium 38 0 Isotopic Thorium 17 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 Number of. Within 2a Within 3a Differing from
~Anal zed Det'ns of known of known known b > 3a.
Gross Alpha 47 47 Gross Beta 37 37 Tiitium 75 75 Sr-89-90 26 26 Am-261 12 12 Pb-210 27 27 Po-210 2 2 PU-239 37 37 Ra-226 44 44 Fe-55 3 3 Isotopic Uranium 38 38 Isotopic Thorium 17 17 S lit Sam les Nuclide Number of . No. Agreeing ; -No.; Agreeing No. Differing.
~Anal zed Det'ns" Within 2a Within 3a Gross Alpha 17 17 Gross Beta 20 20 Tritium 20 20 Sr-89-90 7 7 I-131 2 2 Gamma Emitters 14 14 Pb-210 4 4 Po-210 .2 2 Pu-239 3 3 Am-241 .2 2 Isotopic Thorium 3 3 Isotopic Uranium 16 16 Ra-226 13 13 52