ML17319B255

Radiological Environ Monitoring Annual Rept 1981.

ML17319B255
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Site:	Cook
Issue date:	12/31/1981
From:	KOHL K A, LIU C K INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
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AMERICAN ELECTR lC PGN/ER SERYICE CORPORATlGN

, Donald C.Cook, Nuclear Plant RADIOLOGICAL'NVIRONMENTAL MONITORING Annual Report 1981'ubmitted by EBERLINE INSTRUMENT CORPORATION Midwest Faciiity West Chicago, Illinois 8204020390 820323 PDR ADOCK 05000315 R PDR gg 2G' (P/~&>>V-~.'I*I I*P 4 5 I 1'I k C i$I 4 k eI C I 1 C%1lt(7,%%1K I aMtA.tat~~

DONALD C.COOK NUCLEAR PLANT OPERATIONAL ENVIRONMENTAL RADIOLOGICAL SURVEILLANCE PROGRAM Annual Report JANUARY 1-DECEMBER 31, 1981 Prepared for AMERICAN ELECTRIC POWER SERVICE CORPORATION By EBERLINE INSTRUMENT CORPORATION NUCLEAR SERVICES DIVISION-MIDWEST FACILITIES 245 WEST ROOSEVELT ROAD BLDG.2, SUITE 9 WEST CHICAGO, IL 60185 as a contractor to AMERICAN ELECTRIC POWER SERVICE CORPORATION Compiled by: Ka hryn A.hl, Admin strator Written, A db l 7C Chung-King Liu, P , Manager Final Date: 03/10/82

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SECTlON 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 01 January 198 1 through 31 December 1981.The activity present above the detection limits in the routinely collected sample media was observed to be of natural and atmospheric origin.The results show that the radiation dose to a member of the general population did not exceed the technical specifications of 1X of the 10 CFR 20 limit during 1981.

INTRODUCTION The Donald C.Cook Nuclear 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 MM of electricity.

The station is located in Benton Harbor, Mich-igan.The D.C.Cook Plant utilizes a pressurized water reactor with a radwaste hold-up and treatment system that has been designed to keep cd radioactive releases to as low as is pract ble 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 to 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 radiologicaLmanitoring 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 level's 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 subject 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 sunznarired in Table I.This report contains a compilation of the results of analyses of various types of samples collected during the period January 1981 through December 1981.~'"'

SUMMARY

Environmental monitoring results showed that the radiation dose to a member of the general population did not exceed Tehcnical Specifications of 1X of the 10CFR20 limit during during 1981.The activity present above the detection limits in the routinely collected sample media was observed to be of natural and atmospheric fallout origin.Table 3 summarizes the range and average concentrations for measurements at the indicator and control locations, and the location with the highest annual mean.Complete information is given in the Sample Data Tables (Section 5).),4 I+~O 0, 9 t,low,~W 0+,I 9%1 g'>0't'"(>>'t,.'g1'%'v,,~', s~~""',~~p le C, se g>>s 1~'"r<<,(dye SECTION 2 SPZPLING PROGRAM All samples'are collected by Eberline personnel and shipped to the Eberline laboratory in West Chicago, Illinois.The sample collection procedures remained the same as those detailed in the semi-annual report for the period 01 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 sampling locations and frequencies.

Figures I, II, and III show the locations of the various sampling environs.

I ea t~w 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 analytical program.These LLD's are based on the Regulatory Guide 4.8.For analyses not listed in Regulatory Guide 4.8, Federal EPA, former requirements for similar programs or other appropriate guides are used.The LLD's are calculated at the 3o (99/confidence) level.The Guide specifically states that the LDL'are a priori, not a fosterlori (after'he 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.

~4~4~P I (All tI 64 I I dL PC~ei Ce@g TABLE 1 ENVIRONMENTAL MONITORING PROGRAM DONALD C.COOK NUCLEAR PLANT LC p~Sample T e No.Station.Ind.-Bk.Collection Fre uenc Analysis Fre uenc Type Anal sis Remarks J C J'C p p'I Air Particulate 6 4 Airborne I-131 Precipitation Lake Water Weekly Weekly Monthly Monthly Weekly Monthly Quarterly Weekly Monthly Semi-annual Monthly Gross Beta Gamma Isotopic Composite, 2 Samples Sr-89, Sr-90 Gamma Isotopic Gaama 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.By indicator and background samples.By indicator and background samples.P.L Well Water Quarterly Every 18 wks.Every 18 wks.Tritium Composite, 2 Samples Ganma Isotopic Tritium By indicator and background samples.jP QP j r J Fish 2 per year 2 per year Gamma Isotopic Sr-89, Sr-90 Edible portion only.

DONALD C.COOK NUCLEAR PLANT Sample T e No.Stations Ind.-Bk Type Anal sis Aquatic Organisms 2 2 2 per year When available Milk Monthly Sediment 2x per year Quarterly Total Dose TLD Food Crops Annually Gamma Isotopic~~~TABLE l (Cont'd)ENVIRONMENTAL MONITORING PROGRAM Collection Analysis Remarks l'-" 2 per year Gamma Isotopic Sr-89, Sr-90 3 2 Mon thly Gamma Isotopic Sr-89, Sr-90 I-131 2 2 2x per year Gamma Isotopic'4ÃSr-89, Sr-90 9 14 Quarterly f".",.'c'5-l I Annually g-.'c'~'46 ljg g f;g(7j 4:~';gKt'~t4'~

2I Samole Class Table 2 LOWER LIMITS OF DETECTION (LLD's)LED Anal sis Units Air Particulates Airborne Iodine Milk Well Water Precipitation Lake Water Aquatic Organisms Gross B'eta 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 Sr-89 Sr-90 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 pci/ms pCi/ms pCi/ms pCi/ms pci/ms pCi/l pCi/l pCi/1 pC1/1 pCi/1.pCi/1 pCi/1 pCi/l pCi/1 pCi/l pCi/ml pCi/g wet pCi/g wet pCi/g wet j Sediment Fish Food Crops Background Radiation (TLD)Gamma Isotopic Sr-89 Sr-90 Gamma Isotopic Sr-89 Sr-90 Gamma Isotopic Gamma Dose 1 0.05 0.005 1 0.05 0.005 pCi/g dry pCi/g dry pCi/g dry pCi/g wet pCi/g wet pci/g wet pCi/g wet mR/week TRUE PLANT NORTH NORTH Wl METEOROLOGICAL TOWER PROPERTY LINE L3 TO7 T2 ROADS W2-e R.R.TRACK Ll L T 08 545 KV YARD SHORE LINE~E-W PLANT Q TO9 4 A TQ>765 KV M YARD CHESAPEAKE 6 OHIO R.R.T 6 W7 2,000 FOOT RADIUS INTERSTATE 94 SCALE 0 l,000 2,000 3,000 4,000 FEET FIGURE I LOCATIONS OF INDICATOR AIR SAMPLING STATIONS A'ir, Precipitation T TLD Station W Well Mater L Lake Water (taken at shoreline)

A-AIr, Preclpitatlon, TLD Stations L-Lake Mater Sample Stations H NIlk Sanyle Stations 2D MILES~1196 Mate I94 BEHTOH HARBOR L ST~JOSEPH M51 Stevensvk I~Do C.COOK PLAHT BR dna 3 Eau Ialre berrl en Springs M51 Hew Buffalo HICHIGAH CITT I94 MICHIGAN 176KQiA Neo Carl Isle%Iles UFO 8 Scale of HIles 10 2O l'IGURE IT.OFF SITS LOCATIOXS OF SAIC.IXG STATIONS 13 4 4 Io VI ,<varv44~)lz SCO~0/Iw I~aarv3~ar C ao 4LCll 40 90.LE io 149 I ,4q~~L E l5 45 C 4 44 ll LUCV, a:~I)44 a.l~aaccJ LU III.I~'Calvaav LUCra~4 o o a aro~l5 S 0 D 20'a la I rI~~I~~I~I 3 8 9 2 OL~~.YtOQD V a 99/20 9~mr 444 I-.'4/4 r-~-3l 3 aaoc rara 242 N C"., 34 4444 rrVV<<Va 2 3 5~I N:~ala r 3 o R'0 Y 3I 2 9 A L 32 LI 449 28 27 4~, I'Qc(N 0 N33 AHOY I 5 r?"'33 LI6 44 C'4 JKRI 0~\~\'I\~4 ra rl)59 9 I 0 I~9 o I 2~V~\o 559 IL+HINCHIciAN 9 jj I 0 II41V I 16 4 jf BAROOA is rlaaaLL Cvav CP 3 I.~Ig L Ql LCVCUI I~455 l3" IS 1194/I lr 0 R"0 N i0 K:" l7 l6 g l5 o 444 943 v V tt 444 a)Irav 330 2 I~22 I 23 j 2 435'aaaa VL~2 I~i9 el V 20!i 2I l 22)5~zg9,)1vc44'4 2'8 6 SNO'W I R"O f 52~0 A.30 CVOV d V 27 I (3 r I~44 225 3L Ia v II ta car v 33 225 36~I V X 3I/Paallmra IL 3i 38 34~~I o-i.<<z-'~I CULVO 4 831'il 2.3." 5.6;7.'8.9.10.TLD MONITOR LOCATIONS LOCATED ON THE FIVE MILE RADIUS FROM THE PLANT Red Arrow Highway and vicinity'of I-94 overpass.Stevensville Sub Station.Washington Avenue midway between Brentwood Drive and Kingman Drive.Washington Avenue and Linco Road.FIGURE III Cleveland Avenue.and Shawnee Road.Holden'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.14 IIC+9<v~/4 rl 4 4 1~.~4 LL44 4 w/II'~, ro I rr vr 44 rar r v 44 I 44~%4 r.,~4 4 4 SECTION 3 ANALYSIS PROGRAM 15 Samples received at the laboratory are analyzed for the various radio-equal to, and in most cases, identical with, those of the U.S.D.O.E.

or Brief descriptions of analytical procedures are available in the Lab-radioanalytical contractor's laboratory.

Gross Beta-Exposed air particulate filters are counted'in low back-background suppression after the short-lived naturally occurring radon and thoron daughters have decayed.Filters are counted long enough to-'"~m c4(>'5 p',1~ANALYTICAL PROCEDURES i j C active components by standard radiochemical methods.These methods are'1+those of the Federal E.P.A.oratory Procedures Manual available at the Cook Nuclear Plant and the&AIR PARTICULATE FILTERS'ground Geiger or proportional flow beta counters using anti-coincidence e'jj fl 1 tg if 1~'nsure that the required sensitivity (LLD)is met.Gamma Isoto ic-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"l\il I~is then separated and purified by either ion exchange chromatography (EPA method)or straight wet chemistry (HASL method).The chemical 1HASL Procedures Manual, edited by John H.Harley, Health and Safety Laboratory, US Atomic Energy Commission, 1972 edition, revised annually.'5"5 2National Environmental Research Center, Environmental Protection Agency;Handbook of Radiochemical Analytical Methods.Program Element 1HA 325.Office of Research and Development, Las Vegas, Nevada 89114.16~>>\5(III'5 5 I Pt~'I'lI, 9$59~P\51%h h I~~\I~5t~%5~I 11 w~e~WI.1II~5,~'~~l w yield for strontium is determined.

by'atomic, absorbtfan'pectrometry or gravimetric methods.After a suitable period (usually 14 days)to allow for ingrowth of Y-90, the sample i's counted 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.

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 permit 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)

Gamma Isoto ic-A measured aliquot of the sample is evaporated to a 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-Tri.tium as tritiated water is analyzed by liquid scintil-lation counting 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 17 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 and electrode current density.MILX SAMPLES I-131-Measured amounts of carrier 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.Gamma Isoto ic-A measured aliquot of sample is evaporated and oven-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 0 from this point on in the same manner as are air particulate samples.ORGANIC SPZPLES (Aquatic Organisms, Food Crops, Fish)as appropriate, placed in a controlled geometry and counted in a high 18 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 SAtiPLES then sieved to remove pieces of stone and/or other large pieces of 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'anner as are air particulate samples.THERMOLUMINISCENT DOSIMETERS 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 LiE (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.j Prior to installation, the chips are annealed by a standard cycle of 60 minutes at 400 c and immediate cooling to ambient temperature by plac-0 ing the tray containing the annealed chips on an aluminum block 19 st t I ($%tP I\ll~4 T'I lt~~Fv~~r t l 12" x 12" x 1".After exposure the chips are read on an Eberline instrument Corporation Model 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 exposure to the badge which might occur during shipment.20 QUAL'ITY ASSURANCE'ROGRAM A.Design of Plan 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.Eber-line 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 consistent with the following specifications, per the Technical and Quality Assurance Requirements for Special Purposes.ANSI-N4S.2, American National Standards 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 participation in the USEPA's Crosscheck Program will be included in the monthly 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 Quality Control Service US National Bureau of Standards Eberline's Albuquerque Laboratory.

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 the laborary manager on a monthly 21 schedule and forwarded to each client.Each report'outinely 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.C.Quality Assurance Plan The Quality Assurance Program follows the requirments of Company and Division Manuals.The discussion belo~outlines Quality Assurance Programs as conducted in the laboratory and as required in our QA Manual.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 (EML)are used unless thorough testing has demonstrated that an alternate procedure is equal to or better than the EPA or EHL 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 quhlitative 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:

22 Measurement Gross Beta Tritium Calibration Standard Solution 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 on an energy calibration of the gamma spectrometer and the gamma energy and abundance information provided in Table of Zsotopes, Sixth Edition by Leds'er, Hollander, and Perlman.The results of the Quality Control Programs are summarized in Section 6.23 SECTION 4 RESULTS AND DISCUSSION 24 444IAM ii E~i~iJ Nm I 4<iliii&hCSS Ta 3 Page 1 of 3 Environmental Radiolo ical Monitorin 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 1981 Medium or Pathway Sampled (Unit of Measurement)

Air Particulates (pCi/m3)Type and Total Number of Analyses Performed Gross 8 509 C8-144 24 Zr-95 24 Nb-95 24 Ce-141 24 RU-103 24 Other y 24 Sr-89 8 Sr-90 Lower Limit of Detection (LLD)0.01 0.01 0.01 0.01 0.01 0.Ol 0.01 0.002 0.001 All Indicator Locations Meanl (Ran e)0.12 (291/301)0.01-0.96 0.06 (9/12)0.01-0.12 0.03 (7/12)0.01-0.06 0.04 (7/12)0.01-0.13 0.02 (4/12)0.01-0.03 0.02 (5/12)0.01-0.02 All LLD 0.002 (1/4)0.002 All LLD Location with Hi hest Mean Name Mean (Ran e)Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable Not Applicable On-Site 6 0.16 (52/52)0.02-0.96 Not Applicable Control Locations Meanl (Ran e)0.11 (205/208)Oi01-0.49 0.06 (8/12)0.01-0.11 0.02 (6/12)0.01-0.04 0.03 (8/12)0.01-0.11 0.03 (3/12)0.02-0i04 0.02 (3/12)0.01-0.03 All LLD All LLD All LLD Number of Non-routine Reported Measurements 0 0 0 0 0 0 0 Airborne Iodine (Ci/m')Well Water (pCi/1)I-131 508 Tritium 21 y Spec.21 0 F 01 1000 10 All LLD 1120 (9/12)600-1500 All LLD Not Applicable On-Site 5 1300 (3/3)1200-1500 Not Applicable All LLD 933 (3/9)800-1200 All LLD 0 Mean and range based on detectable measurements only.Frac'ons indicated in parentheses.

Table 3 (continued)

Facility: Dn aI 0 Page 2 of 3 1 6 Medium or Pathway Sampled (Unit of Measurement Milk (pCi/l)Precipitation (pCi/l)Lake Water (pCi/l)Aquatic Organisms (pCi/g wet)Type and Total Number of Analyses Performed I-131 57 Sr-89 57 Sr-90 57 y Spec.57 y Spec.24 Sr-89 4 Sr-90 4 y Spec.20 Tritium 8 Ce-144 8 Nb-95 8 Zr-95 8 Cr-51 8 Ce-141 8 Other y 8 Lower Limit of Detection LLD 0.05 10 10'0 200 All Indicator Locations Meanl Ran e)All LLD All LLD 3.1 (34/35)1.0-8.0 All LLD All LLD All LLD All LLD All LLD 367 (3/4)200-500 1 (1/4)1 1 (1/4)1 (1/4)1 2 (1/4)2 All LLD All LLD Location with Hi hest Mean Name Mean Ran e Not Applicable L Not Applicable Galien 3.3 (11/11)1.0-7.0 Not Applicable P Not Applicable Not Apolicable Not Applicable Not Applicable Not Applicable South 2 On-Site 2 (1/4)Not Applicable Not Applicable South 1 (1/2)On-Site 1 South 1 (1/2)On-Site 1 South 1 (1/2)On-Site 1 Control Locations Meanl (Ran e All LLD All LID 5.2 (22/22)2.0-14.0 All LLD All LLD All LLD 4 (1/2)4 All LLD 273 (3/4)200-320 2 (1/4)2 2 (1/4)2 1.5 (2/4)1.0-2.0 All LLD (1/4)1 All I.I.D Number of Non-routine Reported Measurements 0 0 0 0 0 0 0 0 0 0 0 0 0 jg Qg)1 Mean and range based on detectable measurements only.Fractions indicated in parentheses.

Table 3 (continued)

Facility: Donald C.Cook Nuclear Station Page 3 of 3Medium or Pathway Sampled (Unit of Measurement Aquatic Organisms (pCi/g wet)Type and Total Number of Analyses Performed Sr-89 8 Lower Limit of Detection LLD)0.05 All Indicator Locations Meanl Ran e All LLD Location with Hi hest Mean Name Mean (Ran e)Not Applicable Control Locations Meanl (Ran e)All LLD Number of Non-routine Reported Measurements 0 0.021 (2/4)0.017-0.024 Sr-90 8 0'23 (2.4)0.013-0.033 North 0.033 (1/2)On-Site 0.033 0.005 0 Not Applicable All LLD 0.05 All LLD Not Applicable South 0.013 (1/2)On-Site 0.013 Sr-90 8 All LLD y Spec.4 Food Crops (Ci/wet)0 All LLD Not Applicable 7r Sediment y Spec.8 1 All LLD (pCi/g dry)Sr-89 8 All LLD 0 0.005 0.013 (1/4)0.048 (1/4)0 0.013 0.048 1 Fish (pCi/g wet)Background Radiation (TLD)(mR/week)y Spec 8 Sr-89 8 Sr-90 8 y Dose 82 0.05 0.005 All LLD All LLD 0.031 (4/4)0.018-0.043 l.1 (35/35)0.7-1.8 Not Applicable Not Applicable North 0.037 (2/2)On-Site 0.031-0.043 On-Site 7 1.2 (4/4)0.9-1.8 All LLD All LLD 0.045 (4/4)0.030-0.053 1.1 (47/47)0.7-1.9 0 0 0 1 Mean and range based on detectable measurements only.Fra tions indicated in parentheses.

7 l JW d6

~r>>>>t>>~'>>,J>>>>>>Results of all the analyses for January through December 1981 are presented in full in Section 5, Data Tables pages 38 through 49.Table 3 summarizes the range and average concentrations for meas-urements at the indicator and control locations with the highest annual>>>>'!)>>r mean.Environmental monitoring results showed that the radiation dose to a member of the general population did not exceed Technical Specifi-cations of 1 percent of the 10CFR20 limit during 1981.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 after the short-lived naturally-occurring radon and thoron daughters have decayed.The gross beta particulate data obtained during the first six-month 1 t>>A period of 1981 are higher than the data obtained during the latter half.According to P.K.Kuroda et al1, concentrations of Sr-89 and Sr-90 in rain and snow at Payetteville, Arkansas, showed a spectacular increase during the spring months of 1981 due to the 25th Chinese nuclear test explosion of October 1980.It is therefore suggested that these higher P.K.Kuroda,"Recent Atmospheric ln)ections of Nuclear Debris: Pallout from the 16 October 1980 Nuclear Explosion", unpublished manuscript, 1981.28 P>>>>'Y~>>~~8<<'>>>>>>)>>>>>>1>>>>>>>>>>h Vlf\I VWW V~>>~f>>>>-~8>>Y>>V>>'w>>">>>>tl~>>>>'-~'>>%*

levels are attributable to the stratospheric fallout from this test.The average gross beta concentration for the year for all indicator stations was 0.12 pCi/m , and was 0.11 pCi/m for the background stations.Data for analyses of individual filters are given on pages 38 through 41 in.Section 5.The following table summarizes the average gross beta concentrations for both indicator and background stations for each year from 1973 through 1981.The preoperational data were collected in 1973 and 1974;operational data were collected from 1975 through the present.Indicator~Back round Ci/m3+2cr Preoperational 1973 1974 Operational 1975 1976 1977 1978 1979 1980 1981 0.04+0.04 0.16+0.24 0.08+0.18 0.09+0.22 0.22+0.63 0.12+0.40 0.04+0.16 0.04+0.16 0.12+0.40 0.04+0.04 0.16+0.29 0.09+0.17 0.08+0.19 0.22+0.53 0.11+0.30 0.04+0.16 0.04+0.16 0.11+0.30 The elevated levels of gross beta activity at both indicator and background locations during preoperational and operational phases from 1974 through 1981 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 See Annual Environmental..Monitoring Reports for, D..C.Cook Plant from previous years for details.29 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 program.The activity detected are not attributable to the operation of the Cook plant.Airborne I-131 concentration was less than 0.1 pCi/m for all samples received.The gamma spectrometry data for monthly composites of air particulate files begins on page 42.Traces of Ce-144, Zr-95, Cs-137, Ru-103, Ru-106," Nb-95, and Ce-141 were detected at both indicator and background stations during the first six-month period of 1981 and are attributable to the stratospheric fallout from the 25th Chinese nuclear test.Be-7, a natu-rally occurring nuclide formed by the cosmic ray interaction with nuclei in the upper atmosphere, was also detected in the composites.

These were generally in the range to be expected from measurement of this nuclide in this medium.Quarterly composites of air particulate filters were analyzed for Sr-89 and Sr-90.Sr-89 concentrations were at or below the detection limit of 0.002 pCi/m, and Sr-90 were also at or below the detection limit of 0.001 pCi/m for both indicator and background locations.

These were generally in the range to be expected from measurements of these nuclides in this medium.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/l 30+qr,.7~1~/4etit;':er'g i~'~P;h<<7,5r".Sar.,,,re

..Cs<EC Pf..7.0>:V, 5.9'" J~.'V e*0~'.W'~

in all samples collected during"the year.: Si-90.:concentrations continued to display considerable variation, which is typical for this type of sam-pie.This nuclide is attributable to worldwide fallout from both recent and older nuclear test programs.Data are given on page 43.I-131 concentrations were below the detection limits of, the program.Date.are presented on page 43.Gamma emitters other than those which occur in nature were not de-tected in most samples at a measurement sensitivity of 10 pCi/1.Trace Cs-137 was detected in one sample from Dowagiac and was due to worldwide fallout from recent nuclear tests.Data are given on page 44.PRECIPITATION SAMPLES Gamma isotopic analyses of monthly precipitation samples from indica-tor and background locations indicate the presence of no gamma emitters in concentrations exceeding 10 pCi/1 (<3000 pCi/m2),.Sr-89 concentrations were less than the detection limit of 2 pCi/l.Traces of Sr-90 were de-tected in one background sample and are attributable to the recent Chinese bomb test.Data are presented on page 45.WELL WATER SAMPLES Mell water is collected from seven locations at 18-week intervals during the year and.analyzed for.tr5.tium.and.-gamma emitters..

Low-concen-trations of tritium were detected in samples from both indicator stations and background stations throughout 1981.It is possible that the tritium found is these samples is a result of plant operations.

Gamma emitters were below the detection limit in all samples analyzed.Data are present-4 ed on page 46.31 Samples of water from Lake Michigan are composited by indicator and background 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 500 pCi/l for in indicator locations and 200 to 320 pCi/l for the background locations.

These concentrations are in the range to be expected from measurements of this nuclide in this medium.A VATIC ORGANISM S~LES Aquatic organisms were collected twice during the year from 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.Traces of Ce-144, Nb-95, Ce-141, and Zr-95 were present in several samples.Long and short term worldwide fallout deposits are probably the reason for these activities.

Sr-89 was not detected in any of the samples;the detection limit of 0.05 pCi/g (wet)was achieved.Sr-90 were detected at trace level (0.03 pCi/g wet)in four samples and were attributable to recent fallout.Data are presented on page 47.SEDIMENT SAMPLES Sediment samples were collected twice during the year from 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.The gamma emitters were below the detection limit of 1 pCi/g (dry)32

~'n a11 the samples;, Sr.-89 wasialso below.the detection.

lirait-, 0;.05-pCi/g (dry).Trace Sr-90 was evident in two samples and is due to recent stratospheric fallout.Date are given on page 48, 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 1 pCi/g (wet), and Sr-89 was below the detection limit of 0.05 pCi/g (wet).Sr-90 ranged in concentration from 0.018 to 0.053 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 48.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-and off-site locations.

Data are given on page 48.G~fA-DOSE Gamma radiation dose was measured with Thermoluminiscent Dosimeters (TLDs)on a quarterly schedule.A total of 20 field locations (9 indicator and 11 background) were monitored during the first, second, and third quarters of the year.Three additional background locations were added in the fourth quarter.Throughout the year, there was no statistically significant dif-33 ference 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 49.34 SECTION 5 DATA TABLES 35 INTRODUCTION TO THE DATA TABLES The following information will be helpful in understanding the presentation of the data in the tables in this section.Wet Weight a reporting unit used with organic tissue samples such as vegetation and animal samples in which the amount of sample is taken to be the weight as received from the field with no moisture removed.Dry Weight a reporting unit used for soil and sediment in which the amount of sample is taken to be the weight of the sample after removal of moisture by drying in an oven at about 110 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 for 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), or when an analysis is not required (NR).Error Terms figures following"i" 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 3a (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.Commen t 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.

36 L'ISTING OF MISSED SAMPLES 1981 Sam le ne Location Expected Collection Da te Reason Lake Water All January February Lake frozen at all points.Air Particulates ONS 2 01/05-27 Exposed part of filter missing due to apparent vandalism.

Milk Galien Air Particulates ONS 4 Air Particulates ONS 4 January 02/10 05/19 06/19-30 07/07 No milk left.Road closed due to snow.Area flooded.Milk SBN 09/12 10/10 No milk available.

Iodine Cartridge COL Air Particulates ONS 2 09/26 12/14 Lost in processing.

No power to unit.37 Collection Date 01/05/81 01/12/81 01/19/81 01/27/81 02/03/81 02/10/81 02/17/81 02/24/81 03/03/81~03/10/81 03/17/Sl 03/24/81 03/31/81 04/07/81 04/14/81 04/21/81 04/28/81 05/05/81 05/12/81 05/19/81 05/26/81 06/02/81 06/09/81 06/16/81 06/23/81 06/30/81 AIRBORNE IODINE-131*

and GROSS BETA in AIR PARTICULATE FILTERS (Meekly Collections)

ON-SITE 1 ON-SITE 3 ON-SITE 4 Volume~ms Volume Gross Gross Gross tt 9+1 12+1 14+1 20+2 13+1 ll+1 18+2 10+1 ll+1 12+1 26+3 17+2 43+1 66+7 18+1 26+3 34+2 31+2 23+2 41+4 34+3 17+2 35+3 18+2 18+2 21+2 5+1 3+1 8+1 7+1 3+1 2+1 6+1 3+1 3+1 6+1 4+1 5+1 8+1 13+1 6+1 10+1 5+1 1+1 ll+1 15+2 12+1 6+1 12+1 2+1 3+1 4+1 335 335 330 360 390 (a)710 375 380 380 385 385 395 355 340 355 380 375 510 lnoo 420 (a)(a)(a)(a)10+1 ll+1 14+1 18+2 12+1 12+1 16+2 9+1 ll+1 13+1 30+3 19+2 37+4 42+4 12+1 29+3 23+2 29+2 21+2 38+4 37+4 16+2 19+2 16+2 19+2 20+2 395 390 395 365 420 370 365 355 190 280 95(b)190 405 335 330 355 350 360 350 345 235 280 265 270 250 250 DONALD C.COOK Gross B~ta 10 a Ci/m"-ON-SITE 2 ON"SITE 5 Volume Volume Volume j~ra~~Gross Gross B~m>8 355 (a)425 8+1 465 360 2+1 435 14+1 460 350 400 16+2 460 395 (a)470 46+5 380 375 8+1 460 37-+3 355 355 3+1 450 330 345 6+1 450 15+2 335 355 1+1 435 10+1 365 355 5il 410 10+1 275 355 6+1 400 13+1 330 360 16+3 415 29+3 325 350 4+1 410 15+2 325 320 11+1 410 40+4 315 345 16+2 395 37+4 110(c)g>-~~g+335 10+1.405 22+1 60(d)330 10+1 395 28+3 320 290 16+2 60(e)37+2 320 350 12+1 245 23+1 355 485 7+1 285 21+2 345 295 26+3 350 350 340 22i2 360 33+3 300 380 8+1 385 ll+1 315 335 42+4 415 295~,A$-.355 6+1 390 280 340 8+1 360 320 365 16+2 395 315 w, gP*Iodine cartidges are sampled weekly.Concentrations are<OslO pCi/m unless otherwise noted.(a)See Listing of Missing Samples page.(b)Low volume due to broken meter.'(c)No powor-(d)Low volume due to power offage.(e)Low volume: calculation based on average volume.-0

)<<4~~)m<<mm)seedwmauwwme

'ssmo, s e f'v DONALD C.COOK AIRBORNE IODINE-131>>

and GROSS BETA in AIR PARTICULATE FILTERS (Weekly Collections)

Gross Beta 10 Ci/m')S,=ON-SITE 1 ON-SITE 2 ON-SITE 3 ON-SITE 4 ON-SITE 5 Collection Date Volume~ms~Gross Volume Volume~ms Gross 0~ms Gross Volume~ms Gross 8 Volume Gross 8 07/07/Sl 07/14/81 07/21/81 07/28/81 08/04/81 08/10/81 08/17/81 08/24/81 08/31/81 09(07/81 09/14/81 09/21/81 09/28/81 10/05/81 10/12/81 10/19/81 10/26/81 11/02/81 11/09/81 11/16/81 11/23/81 ll/30/81 12/07/81 12/14/81 12/21/81 12/28/81 325 305.360 335 265 330 235 380 365 425 375 375 375 405 415 415 385 250 430 435 330 350 340 215 215 345 5+1 4+1 3+1 10+1 2+1<1 1+1 1+1 2+1<1 1+1<1<1 1+1<1<1 1+1 1+1 1+1 1+1 1+1 1+1 1+1 5+1 1+1 1+1 265 255 300 320 290 305 350 390 400 350 350 340 320 425 430 445 365 195 375 420 395 390 330 (a)225 290 4+1 6+1 4+1 3+1 6+1 6+1 2+1 4+1 5+1 1+1 3+1 1+1<1 3+1<1 2+1 1+1 2+1 1+1 2+1 1+1 1+1 1+1 1+1<1 355 410 430 465 365 370 415 390 445 400 340 340 345 335 355 365 360 360 370 365 380 380 395 360 350 350 17+2 16+2 ll+1 10+1 10+1 6+1 7+1 8+1 7+1 4+1 7+1 3+1 4+1 3+1 1+1 5+1 3+1 8+1 5+1 6+1 5+1 4+1 6+1 3+1 5+1 7+1 1140 305 210 265 270 305 335 385 320 300 295 305 300 290 285 320 325 350 420 450 410 430 405 355 360 (a)13+1 10+1 14+1 ll+1 6+1 6+1 8+1 6+1 3+1 6+1 2+1 3+1 6+1 2+1 4+1 3+1 7+1 5+1 5+1<1 5+1 5+1 4+1 4+1 6+1 325 315 320 340 305 320 340 365 390 290 285 350 355 370 370 375 365 360 405 385 400 430 360 380 355 365 16+2 16+2 12+1 10+1 12+1 6+1 8+1 10+1 7+1 3+1 7+1 3+1 4+1 3+1 2+1 6+1" 3+1 8+1 2+1 7+1 5+1 5+1 6+1 7+1 6+1 8+1 l)e e e",.*Iodine cartidges are sampled weekly.Concentrations are<0.10 (a)See Listing of Missing Samples page.pCi/ms unless otherwise noted.

er mm m q~im'sl>w~~~Ia<~w m~.t~~qC V't~.1 ,'I gm m I i (AIRBORNE IODINE-131" and GROSS BETA in AIR PARTICULATE FILTERS (Weekly Collections) nci/m3 Nr.vl BUFFALO DOWAGIAC Collection Date Volume (m3)Volume (m~)Volume (m3)Gross Beta Volume (m')'Ol/05/81 01/12/81 01/19/81 01/27/81 02/03/81 02/10/81 02/17/81 02/24/81 03/03/81 03/10/81 03/17/81 03/24/81 03/31/81 04/07/81 04/14/81 04/21/81 04/28/81 05/05/81 05/12/81 05/19/81 05/26/81 06/02/81 06/09/81 06/16/81 06/23/81 06/30/81 355 370 355 410 445 400 420 470 425 410 430 430 465 155(a).85 (b)385 360 405 415 440 440 420 430 435 425 405 410 405 405 405 395 395 375 395 365 345 350 395 425 435 445 370 425 400 440 375 400 415 415 395 400 425 460 415 350 330 325 350 340 350 305 300 270 270 265 310 315 415 415 405 395 415 415 435 420 445 375 375 365 405 380 375 380 375 365 355 310 310 310 320 345 330 330 430 435 390 405 400 395 415 390 380 375 375 365 410 350 355 355 355 370 355 310 300 305 305 340 325 310 510 460 470 520 515 380 (a)No power.(b)Low volume due to power offage." Iodine cartridges are sampled weekly;Concentrations are<Om10 DONALD C.COOK lk;<Gross Beta 10 2 ON-STTE 6 SOUTH BEND COLCMA Gross Collection Gross Volume Gross Gross Beta Date Beta (m3)Beta Beta 12+1 01/03/&1 7+1 6+1 12+1 5+1 9+1 01/10/81 15+1 ll+1 13+1 2+1 17+2 01/17/81 10+1 8+1 8+1 8+1 24+2 Ol/24/81 18+2 2+1 19+2 ll+1 8+1 01/31/81 5+1 13+1 14+1 ll+1 15+2 02/07/81 7+1.1+1 12+1 12+1 21+2 02/14/81 10+1 (1 10+1 4+1 6+1 02/21/81 18+2 13+1 13+1 18+2 12+1 02/28/81 1+1 8+1 5+1 7+1 25+3 03/07/81 14+1 5+1 14+1 4+1 2&i3 03/14/81 18+2 30+3 19+2 18+2 17+2 03/21/81 19+2 5+1 18+2-17+2 42+4 03/28/81 17+2 20+2 23+2 9+1 96+10 04/04/81 45+5 42+4 49+5 22+2 22+1 04/11/81 24+1 2&+2 25+1 14+1 485 28+3 04/18/81 27+3 27+3 24+2 9+1 39+1 04/25/81 22+1 7+1 7+1 14+1 33+1 05/02/81 30+2 8+1 35+2 9+1 25+3 05/09/81 23+2 ll+1 26~3 6+1 485 43+4 05/16/81 32+3 ll+1 33+3 21+2 33+3 05/23/81 33+3 7+1 40+4 33+3 13+1 05/30/81 24+2 8+1 23+2 17+2 19+2 06/06/Sl'2+1 29+2 14+1 6+1 395 16+2 06/13/81 24+2 8+1 14+1 12+1 360 17+2 06/20/81 10+1 7+1 14+1 12+1 375 19+2 06/27/81 15+1 9+1 12+1 12+1 pCi/m unless otherwise noted.3~~

.~eP te e'rett e e DONALD C.COOK AIRBORNE IODINE-13l" and GROSS BETA in AIR PARTICULATE FILTERS (Weekly Collections) ah~a~~), Gross Beta lO 2 Ci/m~ON-SITE 6 NEW BUFFALO SOUTH BEND DOWAGIAC COLOMA e'I.";I~\4 e~)Collection Date 07/07/81 07/14/81 07/21/81 07/28/81 08/04/81 08/10/81 08/17/81 08/24/81 08/31/81 09/07/81 09/14/81 09/21/81 09/28/81 10/05/&1 10/12/81 10/19/81 10/26/81 11/02/81 11/09/81 11/16/81 11/23/81 11/30/81 12/07/81 12/14/81 12/21/81 12/28/81 Volume (m~)350 340 365 385 320 325 355 340 365 315 295 285 290 300 295 290 320 325 315 320 300 320 310 375 355 355 Gross Beta 15+2 16+2 11+1 11+1 12+1 6+1 7+1 10+1 7+1 4+1 7+1 4+1 4+1 6+1 2+1 5+1 4+1 7+1 7+1 7+1 8+1 6+1 5+1 5+1 5+1 7+1 Collection Date 07/04/&l 07/11/81 07/18/81 07/25/81 08/01/81 08/08/81 08/15/81 0&/22/81 08/29/81 09/05/81 09/12/81 09/19/81 09/26/81 10/03/81 10/10/81 10/17/81 10/24/81 10/31/81 11/07/81 11/14/81 11/21/81 11/28/81 12/05/81 12/12/81 12/19/81 12/26/81 Volume (me)475 425 360 400 345 350 395 410 320 290 305 335 315 335 325 340 365 340 340 360 385 360 355 370 375 365 Gross Beta 17+2 15+2 13+1 13+1 7+1 7+1 8+1 8+1 7+1 5+1 6+1 3+1 4+1 4+1 3+1 4+1 3+1 8+1 5+1'+1 2+1 4+1 5+1 5+1 4+1 4+1 Volume (m~)355 270 315 380 330 315 350 370'20 305 335 320 370 375 345 325 320 355 365 380 380 365 355 340 350 330 Gross Beta 8+1, 4+1 3+1 8+1 5+1 2+1 6+1 1+1 5+1 2+1 1+1<1 2+1 3+1<1 2+1 3+1 1+1 3+1 4+1 4+1 2+1 4+1 4+1 3+1 3+1 Volume (n?~)330 360 350 425 350 425 425 415 325 285 300 295 280 395 310 310 325 335 325 335 330 320 355 360 370 350 Gross Beta 21+2 11+1 11+1 12+1 7+1 7+1 8+1 , 6+1 7+1 5+1 4+1 4+1 4+1 3+1 3+1 4+1 5+1 8+1 5+1 6+1 5+1 4+1 5+1 4+1 3+1 4+1 Volume (me)325 335 325 350 305 340 370 430 400 430 425 390 320(a)275 295 305 295 295 290 295 285 305 330 330 325 335 Gross Beta 19+2 ll+1 5+1 13+1 4~1 7+1 1+1 6+1 7+1 4+1 4+1 3+1 4+1 4+1 2+1 5+1 2+1 6+1 4+1 2+1 5+1 6+1 4+1 4~1 4+1 3 1~'"'1 (a)See Listing of Hissed Sainples page." Iodine cartridges are sainpled sleekly.Concentrations are<Oe10 pCi/m unless otherwise noted.

e t f O r f e h t R R DONALD C.COOK" GAMP%ISOTOPIC ANALYSIS of MONTHLY AIR PARTICULATE COMPOSITES Month Ce-144 or r oCi.m Zr-95 Ce-Re-0~Other January February~Rfarch April May June July August September October November December<0.01 0.03~0.01 0.05+0.02 0.04+0.02 0.11+0.01 0.05+0.01 0.10+0.02 0.10+0.01 0.06+0.01 0.07+0.01 0.06+0.01 0.09+0.01 0.01+0.01 0.0l+0.01 0.07+0.01 0.10+0.01 0.12+0.01 0.07+0.01 0.06 0.01 0.05+0.01 0.05+0.01<0.01<0,01<0.01 0.03~0.01 0.01+0.01 0.03+0 F 01 0.06+0.01 0.04+0.01 0.01+0.01 0.01+0.01<0.01<0.01<0.01<0.01<0.01 0.01 0.01 0.01~0.01 0'4+0.01 0.06 0.01 0.13+0.01 0.02 0.01 0.02+0.01<0.01<0.01<0.01<0.01<0.01 0.01+0.01<0.01 0.03+0.01 0.02+0.01 0.03+0.01<0.01<0.01<0.01<0.01<0.01<0.01<0.01<O.01<0.01 0.02+0.01 0.02+0.01 0.02+0.01 0.01+0.01 0.01+0.01<0, 01<0.01<0.01<0.01<0.01<0.01<0.01<0.01<0.01(a)<0.01<0.01<0.Ol<0.01<0.01<0.01<0.01<0.01 3 Jt t4 Month January February March April May June July August September October November December Be-7 0.06+0.01 0.02 0.01 0.04+0.02 0.14+0.02 0.12+0.03 0.08+0.01 0.08+0.02 0.09+0.01 O.ll+0.02 0.08+0.01 0.13+0.02 0.06+0.01 Ce-144<0.01 0.01+0.01 0.02+0.01 0.11+0.02 0.11+0.02 0.05+0.01 0.09+0.01 0.02 0.01 0.04+0.02<0.02<0.01<0.01<0.01 0.01+0.01 0.02+0.01 0.04+0.01 0.04+0.01 0.01+0.01 0.02+0.01<0.01<0.01<0.01<0.01<0.01<0.01 0.01+0.01 0.02+0.01 0.07+0.01 0.11+0 01 0.02 0.01 0.01 0.01 0.01 0.01 0.01+0.01<0.01<0.01<0.01<0.01<0.01 0.04~0.01 0.04 0,01 0.02+0.01<0.01<0.01<0.01<0.01<0.01<0.01<0.01 Back round Stations Ci/ms Zr-95 Nb-95 Ce-141 RU-103<0.01<0.01 0.02+0.01 0.02 0.01 0.03+0.01<0.01<0.01<0.01<0.01<0.01<0.01<0.01 Other Y<0.01<0.01<0.01<0.01<0.01<0.01 (b)<0.01<0.01<0.01<0.01<0.01<0.01 STRONTIUM-89/90 hNALYSIS of QUhRTERLY hIR PARTICULATE COMPOSITES Indicator Stations Back round Stations Collection Period Sr-89 Ci/ms Sr<<90 Sr-89 oCi/ms Sr-90~~1st quarter 2nd quarter 3rd quarter 4th quarter<0.002 0.002+0.001

<0.002<0.002<0.001 0.001+0.001

<0.001<0.001<0.002<0.002<0.002<0.002<0.001<0.001<0.001<0.001 (a)Cs-137.0.01+0.01 (b).Ru-106~0.01+0.01 42

~~~~~~I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I I~~~~e~

ilC'FF h>PV+PP ataiiFFF Collection'Site:

Collection Date Ol/10/81 02/07/81 03/07/81 04/04/81 05/02/81 06/06/81 07/04/81 08/01/81 09/12/81 10/10/81 ll/07/81 12/05/81 DONALD C.COOK RADIONUCLIDES in MILK SAMPLES (Monthly Collections)

Indicator Stations Galien Cs-137 Ci/l<10<10<10<10<10<10<10<10<10<10<10<10<10<10<10<10<10<10<10<10<10<10<10<10 (.)<10<10<10<10<10<10<10<10<10<10<10 Brid man K2 Stevensville K1<10<10<10<10<10<10<10<10<10 10+3<10<10<10<10<10<10<10<10<10<10 (a)(a)<10<10 Back round Stations DoMa iac Kl South Bend Kl i:~>-'V';FF'FVV F.'p4.PW CZcl i: F'ei%5 tF.,~~(<,+5-hh.5,,/FFF't., P ii YF Q~k.Other Gamma Emitters Ci l<10<10<10<10<10<10<10<10<10<10<10<10<10<lo<lo<10<10<10<10<10<10<10<10<10 (a)<10<10<10<10<10<10<10<10<10<10<10<10<10<10<10<10<10<10<10<10<10<10<10<10<10<10<10<lO<10<10<10 (a)(a)<10<ln (a)See Listing oE Missing Samples.page.Q<'k 5+.j DONALD'".C

.COOK'AMMA ISOTOPIC ANALYSIS OF PRECIPITATTON SAMPLES (Monthly Collections)

Collection Sites: Collection Period Indicator~Ci/1 r0 1/m*Back round rCi/1.rCS/r*January February March April May.~June July August September October November December<10<10<10<10<10<10<10<10<10<10<10<10<0.4<0.2<0.3<0.4<0.4<0.3<0.3<0.4<0.5<0.5<0.3<0.2<10<10<10<10<10<10<10<10<10<10<10<10<0.4<0.2(a)<0.3<0.3<0.3<0.2<0.2<0.3<0.3<0.3<0.5<0.2 RADIOSTRONTIUM CONCENTRATIONS IN PRECIPITATION SAMPLES (Semiannual Analysis on Composites of Monthlys)Indicator Ci/1 Back round Ci/l Collection Period Sr-89 Sr-90 Sr-89 Sr-90 January-June July-December

<2<2<1<1<2<2 4+2<1 (a)Ru-103=0.4+0.1 nCi/ma.45 ee~e~e ej I I 1 Cg ej iAA')~Ic i)Collection Site: Collection Date 01/23/81 05/06/81 09/11/81 DONALD C.COOK RADIONUCLIDES IN WELL WATER SPPPLES (18-week Interval Collections)

Back round Stations ONS 1 ONS 2 ONS 3 ONS 4 ONS 7 Tritium Ci/ml<1 0.8+0.4 0 8+0.4<1<1<1 l.2+0.4<1<1<1 0'+0.4 0.6+0.4 1.5+0.4 1.2+0.4 1.2+0.4 Gamma Emitters Ci/1<10<10<10<10<10<10<10<10<10<10<10<10<10<10<10'e~','4'Indicator Stations ONS 5 ONS 6 peg'.1+0.4 1.1+0.4 1.0+0.4<1 1.4+0.4 1.2+0.4>,i.e eel V,vs(j<10<10<10<10<10<10'"Q,~;f~ffe-[4,'

DONALD C.COOK GAMMA EMITTERS IN LAKE WATER SAMPLES (Monthly Composites of Indicator and Background Stations)Gamma Emitters Ci/1/nuclide Month Indicator Com osite Back round Com osite January February March April?fay June July August September October November December (a)(a)<10<10<10<10'<10<10<10<10<10<10 (a)(a)<10<10<10<10<10<10<10<10<10<10 i4 I uarter 1st 2nd 3rd 4th Indicator Stations 200+100 400+110<200 500+100 Back round Stations 200+100'20+200

<200 300+200 TRITIUM IN LAKE WATER SAMPLES (Quarterly Composites of Monthly Samples)Tritium Ci/1 RADIONUCLIDES IN AQUATIC ORGANISMS (Semiannual Collections when Available)

Location Collection Date Sr-89 Ci/wet')Sr-90 Zr-95 Other y ONS S ONS N OFS S OFS N ONS S ONS N OFS S OFS N 07/23/81 07/23/81 07/23/81 07/23/81 09/15/81 09/15/81 09/15/81 09/15/81<0.05<0.05<0.05<0.05<0.05<0.05<0.05<0.05 0.013+0.005 0.033+0.028 0.024+0.019 0.017+0.013

<0.005<0.005<0.005<0,005 1+1<1 1+1 2il<1<1<1<1<1 (b)<1<1<1 (c)<1<1<1<1 (a)See Listing of Hissing Samples page.(b)Ce-144, Nb-95=lil;Cr-51 2~1.(c)Ce-144, Nb-95 2+1;Ce-141 1+1.47 l'il+l 9'I 0.P an%Ig s qq I~P gl l'I~,~'algal".I

''r'I">P l'0 P~III ll QR>l it s u PI@*v)*,II h~i%i, lI PO e 9<>g DONALD C.COOK e 9:>>')Collection Site Collection Date Ci/dr)Gamma Emitters Sr-89 S>>-90 ONS N ONS S OFS Vi OFS S 05/19/81 05/19/81 05/19/81 05/19/81<l<1<l<l<0.05<0.05<0.05<0.05<0.005 0.013+0.004

<0.005 0.048+0.009 f"-,'i~>>'>>e>>r ONS Vi ONS S OFS N OFS S 09/21/81 09/21/81 09/21/81 09/21/81<1<1<1<1 RADIONUCLIDES IN FISH SAMPLES (Semiannual Collections)

<0.05<0.05<0.05<0.05<0.006(a)<0.005<0.005<0.005 Collection Site Collection Date Ci/wet)Se-89 Gamma Emitters Se-90 ONS iV ONS S OFS N OFS S ONS N ONS S OFS N OFS S 05/12/81 OS/l2/8l 05/12/81 05/12/81 09/23/81 09/23/81 09/23/81 09/23/81<1<l<l<l<1<1<1<1<0, 05<0.05<0.05<0.05<0.05<0.05<a.as<0~05 0.031+0.005 0.032+0.008 0.053+0,012 0.045+0.007 0.043+0.008 0.018+0.009 0.030+0.015 0.051~0.017 RADIONUCLIDES IN FOOD CROPS (Annual Fall Harvest Collection)

Collection Site: Collection Sample Date~e 09/30/81 Grapes 09/30/81 Leaves ON Site OFF Site Ci/(wet)Gamma Emitters (a)Lower sensitivity due to low chemical yield.4 48 DONALD C.COOK GANfA RADIATION (Quarterly3 (Measured Using Thermoluminiscent Dosimeters3 Date Annealed: Date Read: 12116/80 04/07/81 1st 0tr.)iain'ackup TLD TLD 03/18/81 07/08/81 2nd Otr.Main Backup TLD TLD 06/18/81 10/06/81 3rd Otr.Hain Backup TLD TLD 09/17/81 12/30/81 4th Otr.Main Backup TLD TLD'I ,'l~<Location Indicator Stations On-Site l On-Site 2 On-Site 3 On-Site 4 On-Site 5 On-Site 6 On-Site 7 On-Site 8 On-Site 9 0.9+0.2 missing 0.8+0.1 0.9+O.l 0.8+0.2 0.7+0.1 0.9+O.l 0.8+0.2 0.8+O.l 0.7+0.1 missing 0.8+0.2 0.8+O.l 0.7+0.1 0.7+0.1 0.7+O.l 0.9+0.1 0.7+0.1 0.7+O.l 0.8+O.l 0.7+0.1 0.9+0.1 1.0+0.2 missing 0.9+O.l 0.8+0.1 0.8+O.l 0.9+O.l 0.9+0.1 0.8+0.2 0.9+O.l 0.9+O.l 1.0+0.1 0.8+0.1 0.7+0~2 1.0+O.l 1.3+0.2 1.4+0.1 1.2+O.l 1.0+0.l 1.2+O.l 1.2+0.1 1.3+0.1 1.3+0.1 1.2 0.2 Measured mR/week 1.2+0.1 1.0+0.1 1.2+0.1 missing 1.3+0.2 1.2+0.1 1.2+0.2 1.1+0.1 1.1+O.l 1..5+0.2 1.6+0.2 1.5+0.4 1.4+0.4 1.8+0.5'.6+0.1 1.8+0.4 1.5+0.2 1.5+0.2 1.5+0.6 1.7+0.1 1.6+0.3 1.4+0.4 1.8+0.8 1.5+0.5 2.1+1.5 1.6+O.E)2.0+0.3 Background Stations New South Bend Dowagiac Coloma 0.9+0.2 1.0+O.l 0.7+0.1 0.7+0.1 0.8+O.l 0.9+0.2 0.8+O.l 0.8+0.2 0.8+0.1 0.7+0.2 0.8+O.l 0.7+O.l 0.9+O.l 1.0+O.l 0.9+0.2 0.9+O.l 1.1+0.1 1.0+O.l 1.0+0.1 1.0+O.l 1.2+0.1 1-3+0.1 0.9+0.1 0.9+0.1 1.5+0.1 l.7+0.4 1.5+0.3 1.5+0.2 1.6+O.l 1.7+0.3 1.7+0.4 1.8+0.6 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 0.8+O.l 0.8+O.l 0.8+O.l 0.7+O.l 0.8+0.1 0.7+O.l 0.9+0.2 0.9+O.l 0.9+O.l 0.9+0.2 0.9+O.l 0.8+O.l 0.8+0.3, 0.7+O.l Effective 4th Quarter 0.9+0.2 0.8+0.2 0.7+0.1 0.8+0.1 0.9+0.2 1.0+0.2 0.9+O.l 0.9+0.1 0.9+0.1 0.8+0.1 0.9+0:1 0.9+O.l 0.8+O.l 0.8+0.1 1.1+0.1 1.0+0.1 1.8+O.l 1.3+0.1 1.1+0.1 1.1+O.l 1.0+0.2 l.0+0.1 1.0+O.l 1.1+0.2 1.0+0.1 0'+0.2 0.9+0.1 1.0+O.l 1.5+0.2 1.4+0.1 1.6+0.5 1.5~0.2 1.7+0.4 1.9+0.3 1.5+0.4 1.5+0.3 1.7~0.3 1.4+0.1 1.5+0.4 1.5+0.5 1.8+0.7 1.8+0.7 1.8+0.4 2.1~1.2 1.6+0.6 1.5+0,4 1.7+0.2 1.5+0.4 SECTION 6 QUALITY ASSK4QICE DATA 50 ENVIRONMENTAL QUALITY CONTROL ANALYSES

SUMMARY

1981'Ihe tables below summarize results of samples run for process quality control purposes during thc subject month.These listings are in add-ition to such m<<asuremcnts ns dutcctor backgrounds, check source values, radiometric-gravimetric comparisons, system calibrations, etc.Detailed listings of each measurement are maintained at the laboratory and are available for inspection if required.'BLANK SAMPLES.Nuclide Anal zed Numbursof.

Determinations Numbur of analyses exceeding the LLD for that anal sis Gross beta Gross alpha Strontium-89 Strontium-90 Tritium Gamma emitter Iodine-131 Calcium-45 46 47 95 95 61 64 191 3 1*0 0 0]*0 0 0 SPLIT SAMPLES Nuclide Annlvz<<.d Gross beta Gross alpha Gamma emitters Iodine-131 Strontium-89 Strontium-90 Tritium Calcium-45 Uranium Number of Det'ns 142 39 126-146 38 44 89 8 71 No.agreeing with'I.n 2a 138 38 122 146 38 42 89 8 71 SPIKED SAMPLES No.agreeing within 3a 4 1 4 0 0 2 0 0 0 No.differing bv>3a 0 0 0 0 0 0 0 0 0 Nuclide Anal zed'ross beta Gamma emitters Iodine-131 Strontium-89 Strontium-90 Tritium No.of Des'es 55 44 ll 18 94 45 Within 2a of'nown 53 43 11 18 93 44 Within 3a of known 1 1 0 0 1 1 differing from known b>3a 1*0 0 0 0 0*Corrective actions were taken to eliminate the problem.51 EPA INTERCOMPARISON 1981~~~I~h u~~~~~~I1~1~I~I~I~~~2~~~~~!i RESULTS page 1 of 3'onth/Yea r December 1980 D<<cember 1980 December 1980 December 1980 Decembex'980 D<<cumber 1980 ,1anuary 1981 January 1981 January 1981 January 1981 January 1981 January 1981 January 1981 January 1981 January 1981 January 1981 1'<<b run ry 1981 F<<bruary 1981 Februax'y 1981 February 1981 1:obruary 1981 February 1981 February 1981 Mare h 1981 M;i x'c1<1981 March 1981 March 1981'larch 1981 March 1981 April 1981 April 1981 April 1981 April 1981 April 1981 April 1981 April 1981 Apx'il 1981 Hay 1981 May 1981 May 1981 Yiay 198 l May 1981 i~1Q y 1981 Sample T e 1 ater Water Air Filter Aiz Filter Air Filter Air F11 c<<t Water Water Hater Water Milk Milk Milk Milk Milk N.lk Water Water Water Wa tez Wacer Water Water Hater Water Air Filter Air Filter Air Filter Air Filter Water Water Water Water Water Water Water Water Water Water Water Water Water'Hater Anal sis Iodine-131 TH.tium Gross Alpha Gross Beta Strontium-90 C<<siuu<-137 Gross Alpha Gross Beta Strontium-89 Strontium-90 Strontium-89 Strontium-90 Iodine-131 Cesium-137 Barium-140 Potassium Tritium Chromium-51 Cob alt<<60 Zinc-65 Ruthenium-106 Cesium-134 Cesium-137 Gross Beta Gross Alpha Gross Alpha Gross Seta Strontium-90 Cesium-137 Tritium Cesium-134 Cesium-137 S tr ontium-89 Strontium-90 Radium-226 Radium-228 Uranium Strontium-89 Strontium-90 Strontium-89 Strontium-90 Iodine-131 Cesium-137 Agency Va luu 22 2240 21 19 0 19 9 44 16 34 0 20.2 25.8 43.5 0 1551 1760 0 25 85 0 36 4 25 25 30 50 18 14 2710 10 15 38 28 15.0 12.0 12 36 22 Control Limits Q3n n 3)6 604 9;1 8.7 0 8.7 8.7 8.7 8.7 2.9 0 2.6 10.4 8.7 0 134 590 0 8.7 8.7 0 8.7 8.7 8.7 10.4 13 8.7 2.6 8.7 615 8.7 8.7 8.7 2.6 4.0 3.1 10 8.7 2.6 MWF Measured x2o error*17+2 2600+300 21 2 28~3 LT 1 19+2 10~1 43+4 LT 5 35+4 LT 2 14+1 29+3 47~5 LT 25 1350+140 1680 170 LT 100 29+5 92+9 LT 100 29+5 9 3 27+3 20+2 30+3 66+7 17+4 15+2 3000+300 7+2 13 1 35+7 24 3 13.2~1.3 10+2 6+2 29+3 26+3 Unics pCi/liter pCi/liter pCi/filter pCi/filter pCi/filter oCi/Cilc<<r pCi/litez pCi/liter pCi/liter pCi/liter pCi/liter pCi/liter pCi/liter pCi/liter pCi/liter pCi/liter pCi/li ter pCi/liter pCi/liter pCi/liter pCi/liter pCi/liter pCi/liter'Ci/liter pCi/lit<<r pCi/filter pCi/filter pCi/filtex pCi/filter pCi/liter pCi/liter pCi/liter pCi/liter pCi/liter pCi/liter pCi/liter pCi/liter pCi/liter pCi/liter*When analyses of a particular type result in concentrations below the detection limits, the term"LT" is used to indicate"Less Than" values for that measurement.

based on 3a (99.5%)confidence level.~~~~" i e i q qp e~-EPA INTERCOMPARXSON RESULTS 1981 Page 2" of 3.>>.5 Month/Year 1981 1981 1981 1981 1981 1981 198.1 1981 1981 1981 1981 1981 1981 1981 1981 1981 1981 1981 1981 1981 1981 1981 1981 1981 1981 1981 1981 1981 1981 1981 1981 May aMay June June June June June June June June June June June June June July July July July July ly ly uly July July July July August hu>>ust Augus t September September September September September September'eptember September September September September~1981 1981 1981 1981 1981 1981 1981 1981 1981 1981 Sample T e Mater Water Water Mater Water Water Water'ater Water Water Mater Air filter Air filter Air filter Air filter Food Food Food Food Food Pood Milk Milk Milk Milk Milk Milk Water Water Water Mater Water Urine Mater Water.Water Water Air filter Air filter Air filter Air filter Anal sis Barium-140 Potassium Chromium-51 Cobalt-60 Zinc-65 Ruthenium-106 Cesium-134 Cesium-137 Tritium Radium-226 Radium-228 Gross alpha Gross beta Strontium-90 Cesium-137 Strontium-89 Strontium'-90 Iodine-131 Cesium-137 Barium-140 Potassium Strontium-89 Strontium-90 Iodine-131 Cesium-137 Barium-140 Potassium Iodine-131 Tritium Uranium Strontium-89 Strontium-90 Tritium Radium-226 Radium-228 Gross alpha Gross beta Gross alpha Gross beta Strontium-90 Cesium-137 Agency Value 0 1559 0 17 0 15 21 31 1950 6.7 8.0 28 54 19 16 44 31 82 45 0 2640 25 17 0 31 0 1600 23 2630 23 23 ll 2050 8.3 11.7 33 28 25 52 16 19 Control Limits~3eu)0 135 0 8.7 0 8.7 8.7 8.7 596 1.7 2.1 12 8.7 2.6 8.'7 8.7 2.8 14 8.7 0 229 8.7 2.6 0 8.7 0 139 13 613 10 8.7 2.6 599 2.2 3.0 4 8.7 11 8.7 2.6 8.7 MWF Measured~7o error LT 20)400+140 LT 20 16+2 LT 20 13+4 13+2 25+3 2300+200 5.9~0.4 10.6i).6 31 6 74+8 21+5 15+2 38+4 28+3 75+8 40~4<25 2267i227 13+3 16+3<5 35+12<16 1463+305 53+11 2973 878 14+2 18+5 14+2 2166+624 8.4+0.8 4..6+3a7'" 32+14 30+6 25+6 71+7 18+2 20+2 Units pCi/liter mg/liter pCi/liter pCi/liter~pCi/liter-.pCi/liter pCi/liter pCi/liter pCi/liter pCi/liter pCi/liter pCi/filter pCi/filter pCi/filter pCi/filter pCi/kilogram pCi/kilogram pCi/kilogram pCi/kilogra~

p Ci/kilogram mg/kilogram p Ci/li.ter pCi/liter p Ci/li ter pCi/liter pCi/liter mg/liter pCi/liter pCi/liter pCi/liter pCi/liter pCi/liter pCi/liter pCi/liter pCi/~ter pCi/liter pCi/liter pCi/filter PCi/filter PCi/filter pCi/filter

53 ps~~~~g<e<<~v<<,was>>q,.-r>>a<>>e<aaea>>'<<a e<.<<<<We<et<'ee'<<e<V.e EPA INTERCOMPAPiXSON RESULTS 198 1 Month/Year Sample T e Anal sis Agency Value Control Limits~3eu)MWF Measured+7o error Units October October October October October October October October October October October October October October October October November November November November November November December 1981 1981 1981 1931 1981 1981 1931 1981 1981 1981 1981 1981 1981 1981 1981 ,1981 1981 1981 1981 1981 1981 1981 1981 Water Water Water Water Water Water'Water Water Water Water liilk Milk Milk Hi,lk Milk Milk Food Food Food Food Food Pood Water Gross alpha Gross beta.Cobalt-60 Strontium-89 Strontium-90 Cesium-134 Cesium-137 Radium-226 Radium-228 Cross Uranium Strontium-89 Strontium-90 Iodine-131 Cesium-137 Barium-140 Potassium Strontium-89 Strontium-90 Cobalt-60 Cesium-137 Barium-140 Potassium Tritium 80 96 0 21 14.4 12 15 12.7 9.2 15 23 18 52 25 0 1530 38 23 30 33 0 2730 2700 35 8.7 0 8.7 2.6 2.6 8.7 3.3 2.4 10 8.7 2.6 10 8.7 0 133 8.7 2.6 8.7 8.7 0 236 615 91+26 112 11 LT 5 13+6 14.6+2.0 14+2 20+14 11.8~3.5 8.3+5.1 9+2 24+8 14+5 58 ll.29+9 LT 16 1700+240 41+6 21+5 35+8 32+8 LT 31 2700+270 2950+127 pCi/liter pCi/li,ter pCi/liter pCi/liter pCi/liter pCi/liter pCi/liter pCi/liter pCi/liter pCi/liter p Ci/liter oCi/liter pCi/liter pCi/liter pCi/liter mg/liter pCi/kilogram pCi/kilogram pCi/kilogram pCi/kilogram pCi/kilogram mg/kilogram pCi/liter 54 EPA INTZRCOMPARLSON RESULTS p$<X<j 1981 (Lab Performance Evaluation Study-EHSL-LV)

Sample Agency Control Limits~(3a n]MMP Measured 2e error Units g~: Water Water Water Water Water Water, Water Mater Water Water Water Gross alpha 39 Gross beta 60 Cobalt-60 12 Cesium-134 12 Cesium-137 20 Ruthenium-106 0 Zinc-65 0 Strontium-89 6 Strontium-90 0 Radium-226 12.8 Uranium 5 10 1.8 39+4 70+7 LT20 11+2 20+2 LT100 LT20 LT 1 12.6+1.3 4+2 pCi/liter pCi/liter., pCi/liter pCi/liter pCi/liter pCi/liter pCi/liter pCi/liter pCi/liter pCi/1'[ter pCi/liter55 1981 Sample T e ,Air (81-04)Air (81-04)Air (81-04)Air (81-04)Air (81-04)Air (81-04)Air (81-04)Air (81-04)0.244 E+04 0.117 E+03 0.450 E+02 0.630 E+01 0.122 E+03 0.139 E+04 0.190 E+04 0.223 E+Ol 0.247 0.015 E+04 0.093 0.006 E+03 0.515 0:087 E+02 (0.100 E+02 0.828 0.048.E+02 0.133 0.006 E+04 0.133+0.007 EM4 0.750+0.053 E+01 Be-7 Mn-54 Sr-89 Sr.-90 Zr-95 Sb-125 Cs-134 U r.~I, I'~~r~r.r~USDOE UALITY ASSESSMENT PROGRAM Measured Nuclide Known~2a error"l Uni ts pCi/filter pci/filter pCi/filter pCi/filter pCi/filt'er pCi/filter pci/filter pCi/filter P;'I'tr Soil (81-04)Soil (81-04)Soil (81-04)Tissue (81-04)Tissue (81-04)Tissue (81-04)Tissue (81-04)K-40 Sr-90 Ra-226 U 0.158 E+01 0.240 E+Ol 0.450 E+00 0.290 E-OL K-40 0.213 E+02 Cs<<137 0.200 E+00 Ra-226 0.770 E+00 0,290+0,017 K+02 0.250+0.070 E+00 0.668+0.057 E+00 0.433+0.058 E+Ol 0.188+0.016 E+01 0.433+0.058 E+00 0.850+0.333 E-01 pci/g pci/g pCi/g pci/g pci/g pCi/g pCi/g~'I~i~I Vegetation (81-04)Vegetation (81-04)Vegetation (81-04)Vegetation (81-04)Water (81-04)Water (81-04)Water (81-04)Water (81-04)Water (81-04)Water (81-04)Water (81-04)Water (81-04)K-40 Sr-90 Cs-137 U H-3 Co-57 Co-60 Sr-90 Cs-137 Ce-141 U U 0,224 E+03 0.560 E+01 0.230 E+00 0.310 E+00 0.246 E+02 0.118 E+01 0.129 E+01 0.440 E-01 0.137 E+01 0.527 E+01 0.145 E-01 0.102 E-01 0.277+0.018 E+03 0.258+0.016 E+Ol 0.200+0.058 E+00 0.133+0.058 E+00 0.197+0,012 E+02 0.243+0.018 E+Ol 0.133+0.006 E+01 0.405i0.063 E-01 0.150+0.012 E+01 0.193~0.012 E+01 0.200+0.026 E-Ol 0.?50+0.140 E-02 pci/g pci/g PCi/g pCi/g pCi/ml pCi/ml pCi/ml pci/ml pCi/ml pCi/ml ug/ml pCi/ml TLD Intezcomparison Badges Irradi.ated by Battelle Northwest'.

Labs Total mR less trans ortation control 1st tr 2nd tr 3rd tr 4th tr Measured IH.O 18.5 4.1 26.0 29.1+2'2<).I+6.I 18.0 17.8 5aO 24.0 24.5+5.5 38.0 34.1+9.0 57.0 42.1 6.0 59.0 61.4i6.5 69.0 77.6 12.5 69.0 71.2 19.0 47.0 46.8 5'44.0 43.2+6.0 20.0 25.5 4.8 90.0 86.2-15.5 28.0 31.4~2.5 51.0 53.6 5.3 16.0 17.9+2.7 100.0 93.4~10.1 32.0 36.5+3.5 42.0 41.9~19.7 40.0 41.2 4.0 18.0 20.1+3.4 53.0 55.4~15.2 29.0 32.0-3.0 76.0 65.6 6.6 73.0 74.1~21.6 69.0 75.1~13.2 34.0 32.0~3.0 88.0 88.6+12.6 79.0 80,8+17.3 82,0 80.4+10.7 82.0 79.0+8.0 I 00.0 I 00.0 I 02+I 0 99+10 79.0 79.9+18.2 99.0 100.2i25.4 93.0 100.0 86.1+15.5 34.0 38.7~9.3 100.4~15.3 74.0 69.2~8.8 57

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