Text

1997 Annual Radiological Environ Monitoring Rept
	ML20247G162
Person / Time
Site:	Prairie Island
Issue date:	12/31/1997
From:	Sorensen J; NORTHERN STATES POWER CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	NUDOCS 9805200154
	Download: ML20247G162 (88)
	v • d • e

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t Northem States Power Company 1717 Wakonade Drive East Welch, MN 55089 Telephone 612-388-1121 May 15,1998 PINGP Technical Specification 6.7.C.1 ISFSI Technical Specification 6.2 U S Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket Nos. 50-282 License Nos. DPR-42 50-306 DPR-60 ISFSI Docket No. 72-10 License No. SNM-2506 1997 Annual Radiological Environmental Monitoring Report in accordance with the Prairie Island Nuclear Generating Plant Technical Specifications, Apper dix A to Operating License DPR-42 and DPR-60, and in accordance with the Prairie Island Independent Spent Fuel Storage Installation Technical Specifications, Appendix A to Materials License DNM-2506, we are submitting one copy of the Annual Radiological Environmental Monitoring Report covering the period January 1,1997 through December 31,1997.

Please contact us if you have any questions related to the information we have provided.

Joel P Sorensen Plant Manager jf Prairie Island Nuclear Plant c: Regional Administrator- 111, NRC I l Region til n Attn: Dr. John House ,

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NRC Project Manager, NRC /

Director of NMSS Sr Resident inspector, NRC State of Minnesota Attn: Kris Sanda . [j {j C C 1 J Silberg l

Attachment:

Annual Report to the United States Nuclear Regulatoiy Commission, Radiation Environmental Monitoring Program, January 1,1997 through December 31,1997 9805200154 971231 PDR ADOCK 05000282 R PDR

W TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES MIDWEST LABORATORY u$ 'i ?El$i"*

NORTHERN STATES POWER COMPANY MINNEAPOLIS, MINNESOTA PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket No. 50-282 License No. DPR-42 50-306 DPR-60 ANNUAL REPORT to the UNITED STATES NUCLEAR REGULATORY COMMISSION Radiation Environmental Monitoring Program January 1 to December 31,1997 Project No. 8010 Prepared Under Contract by TELEDYNE BROWN ENGINEERING ENVIRONMENTAL SERVICES I MIDWEST LABORATORY Project No. 8010 0

Approved by: /Dh )l4 oniaprob, M.S.

echrkal Lead 16 April 1998

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PREFACE The staff of Teledyne Brown Engineering Environmental Services, Midwest Laboratory was responsible for the acquisition of data presented in this report. Samples were collected by members of the staff of the Prairie Island Nuclear Generating Plant, Northern States Power Company. The report was prepared by staff members of Teledyne Brown Engineering Environmental Services, Midwest Laboratory.

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s TABLE OF CONTENTS Section Page Preface........................................................................................... . . . . . . . . . . ii List of Tables . ....... ........................................................ .... . . . . . . . ..iv Lis t o f Fig u re s. .... .... .. . ... .. . . . .. .. .. . . . .. .... . .. . .. .. ...................................... . ..v

1. 0 I NTRO D UCTIO N . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 2 . 0 S UM M ARY . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. ................2

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3.0 RADIATION ENVIRONMENTAL MONITORING PROGRAM (REMP).... .. .......3 3.1 Program Design and Data Interpretation.. ... .. ...... ... . . . . . . . . . . ......3 i 3.2 Program Description.. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ....4 3.3 Program Execu tion.......... ... . ....... .. ... . . ... . .. . . . . . . . . .. . . . ....... ...5 3.4 Laboratory Procedures . . ... .. ..... ........... .... . ....... .. . .. .. . . . .. . . . . . .....6 3.5 Program Modifications... ... ........ .. . . ........... . . . . . .. . . . . . . . . . . . . . . .......6 3.6 Land Use Census...... ............ .. . . . . ...... . . . . . . . . . . . . . . . . ..........6 4.0 RESULTS AND DISCUSSION..... . ... ............. ....... . . . ..... . .... . . . . . . ..7 4.1 Atmospheric Nuclear Detonations and Nuclear Accidents.. .. ... .........7 4.2 Summary of Preoperational Data ..... . . ...... . .... .... . . .... .. . . . . . . . . .............7 4.3 Program Findings . . . . . .. . . . . . . . . . . . . .. . . . . . . . . . . . . .. . . . . . . .. . . . . . . . . . . . . . . . . ..............8 5.0 FIGURES AND TABLES.............. .. ... .......... .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ........12

6.0 REFERENCES

CITED... .......... ... ........ . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . ........25 APPENDICES A Interlaboratory Comparison Program Results..... . . . .. . . . . . . . . .. . . . . . . A-1 Attachment 1, Acceptance Criteria for " Spiked" Samples.. . . . . . . . . . . . A-2 B Data Reporting Conventions. ...... . . . . . . . . . . . . . . . . . .. . . . . . . . . . . .. . ..B-1 C Maximum Permissible Concentrations of Radioactivity in Air and Water Above Natural Background in Unrestricted Areas... . .... . . . . . . . . . . . . . . . . . . . . .C - 1 D Special Ground and Well Water Samples.. . ... . .... ..... ... .... . . ... . . . D-1 E Sampling Location Maps............ .. ... . ... ..... . . . . . . . . . . . . . . . . ..E-1 f

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i LIST OF TABLES No. Title Page 5.1 Sample Collection and Analysis Program,1997... . .. ... . . . . . . . . . . . . .. . . . . .13 5.2 Sampling Locations... .... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .... . . . . . .. .14 5.3 Missed Collections and Analyses,1997..... ... ... . . . . . . . . .. ...... . . . .. .17 5.4 Radiation Environmental Monitoring Program Summary . .. .. . . . . . . . . . . . . . 20 In addition, the follawing tables are in the Appendices:

Apt,endix A A-1 U.S. Environmental Protection Agency's Crosscheck Program results.. . .. ... A l - 1 A-2 Crosscheck Program Results; (TLDs).... . ..... . . . . . . . . . . . .. A2-1 A-3 In-house " Spiked" Samples... .. .. . ........ ... . . . . .. .. .. . . . . . . . . . . . . A3-1 A-4 In-house " Blank" Samples... .. ........ . . . . . . . . .. . . A4-1 A-5 In-house " Duplicate" Samples.. . . . . . . . . . . .. . . . . . . . . . .. . A5-1 A-6 Department of Energy _MAPEP comparison results.. . . . . . . .. . . . . . . . . A6-1 A-7 Environmental Measurements Laboratory Quality (EML) Assessment Program comparison results.... . ............ . . . . . . . . . . . . . . . . . . . . . . . . . . ... .. . A7-1 Appendix C C-1 Maximum Permissible Concentrations of Radioactivity in Air and Water Above Natural Background in Unrestricted Areas... . . . . . . . . ..C-2 Appendix D D-4.1 Sample collection and analysis program... . . . . . . . . . . . .. ..D-6 D-4.2 Sampling locations.. .. .... ... . . ....... ... .... . . . . . . . . . . .. . . . . ... D-7 D-4.3 REMP Summary.. .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. .D-8 D-4.4 REMP Complete Data Table..... ... .. .. . . . . . . . . . . . . . . . . . . . . . . .. . . . .D-9 iv

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LIST OF FIGURES' No. ' y

. 5.1 Offsite Ambient Radiation (TLDs), average ofinner and outer ring indicator

< loca tions versus con trol,1984-1997.. ..................... ....... ... . ........... . . ........... .. ... .... .... ... ... 18 5.2 - Airborne Particulate; analysis for gross beta, average mean of all indicator locations'(P-2,3,4,6) versus control location (P-1),1984-1997....................................... . .19 l

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1.0 INTRODUCTION

This report summarizes and interprets results of the Radiation Environmental Monitoring Program (REMP) conducted by Teledyne Brown Engineering Environmental Services, Midwest Laboratory at the Prairie Island Nuclear Generating Plant, Red Wing, Minnesota, during the period January - December,1997. This program monitors the levels of radioactivity in the air, terrestrial, and aquatic environments in order to assess the impact of the plant on its surroundings.

Tabulations of the individual analyses made during the year are not included in this report.

These data are included in a reference document (Teledyne Brown Engineering Environmental Services, Midwest Laboratory,1998b) available at Northern States Power Company, Prairie Island Nuclear Generating Plant.

Prairie Island Nuclear Generating Plant is located on the Mississi Minnesota, and operated by Northern States Power The Company.ppi plant has twoRiver 550 MWe in Goodhue Co pressurized water reactors. Unit 1 achieved initial criticality on 1 December 1973. Commercial operation at full power began on 16 December 1973. Unit 2 achieved initial criticality on 17 December 1974. Commercial operation at full power began on 21 December 1974. ;

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SUMMARY

l .The Radiation Environmental Monitoring Program (REMP) required by the U.S. Nuclear l

Regulatory Commission (NRC) Technical Specifications for the Prairie Island. Nuclear Generating Plant and the Inde 3endent Spent Fuel Storage Installation (ISFSI) is described.

Results for 1997 are summarizec. and discussed.

Program findings show background levels of radioactivity in the environmental samples -

j. collected in the vicinity of the Prairie Island Nuclear Generating Plant.

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3.0 RADIATION ENVIRONMENTAL MONITORING PROGRAM (RIM t 3.1 Procram Desien and Data Interpretation l

l The purpose of the Radiation Environmental Monitoring Program (REMP) at the Prairie Island Nuclear Generating Plant is to assess the impact of the plant on its environment.

For this purpose, samples are collected from the air, terrestrial, and aquatic environments and analyzed for radioactive content. In addition, ambient gamma radiation levels are monitored by thermoluminescent dosimeters (TLDs).

Sources of environmental radiation include the following:

(1) Natural background radiation arising from cosmic rays and primordial radionuclides; (2) Fallout from atmospheric nuclear detonations; (3) Releases from nuclear power plants; (4) Industrial and medical radioactive waste; and (5) Fallout from nuclear accidents.

In interpreting the data, effects due to the plant must be distinguished from those due to other sources.

A major interpretive aid in assessment of these effects is the design of the monitoring program at the Prairie Island Plant which is based on the indicator-control concept. Most types of samples are collected both at indicator locations (nearby, downwind, or downstream) and at control locations (distant, upwind, or upstream). A plant effect would be indicated if the radiation level at an indicator location was significantly larger than that at the control location. The difference would have to be greater than could be accounted for by typical fluctuations in radiation levels arising from other sources.

An additional interpretive technique involves analyses for specific radionuclides present in the environmental samples collected from the plant site. The plant's monitoring program includes analyses for tritium and iodine-131. Most samples are also analyzed for gamma-emitting isotopes with results for the following groups quantified: zirconium-95, cesium-137, cerium-144, beryllium-7, and potassium-40. 'Ihe first three gamma-emitting isotopes were selected as radiological impact indicators because of the different characteristic proportions in which they appear in the fission product mix produced by a nuclear reactor and that produced by a nuclear detonation. Each of the three isotopes is produced in roughly equivalent amounts by a reactor: each constitutes about 10% of the j total activity of fission products 10 days after reactor shutdown. On the other hand,10 1 days after a nuclear explosion, the contributions of zirconium-95, cerium-144, and cesium-137 to the activity of the resulting debris are in the approximate ratio 4:1:0.03 (Eisenbud, .

1963). Beryllium-7 is of cosmogenic origin and potassium-40 is a naturally-occurring isotope. They were chosen ai calibration monitors and should not be considered 3 radiological impact indicators. l The other group quantified consists of niobium-95, ruthenium-103 and -106, cesium-134, barium-lanthanum-140, and cerium-141. These isotopes are released in small quantities by nuclear power plants, but to date their major source of injection into the general environment has been atmospheric nuclear testing. Nuclides of the final group, manganese-54, iron-59, cobalt-58 and -60, and zinc-65, are activation products and !

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3.1 Procram Desien and Data Interpretation (continued) arise from activation of corrosion products. They are typical components of a nuclear power plant's effluents, but are not produced in significant quantities by nuclear detonations.

Other means of distinguishing sources of environmental radiation are employed in interpreting the data. Current radiation levels are compared with previous levels, including those measured before the Plant became operational. Results of the plant's monitoring program can be relate.1 to those obtained in other parts of the world. Finally, results can be related to events known to cause elevated levels of radiation in the environment, e.g., atmospheric nu clear detonations.

3.2 Procram Description The sampling and analysis schedule for the radiation environmental monitoring program at Prairie Island is summarized in Table 5.1 and briefly reviewed below. Table 5.2 defines the sampling location codes used in Table 5.1 and specifies for each location its type (indicator or control) and its distance, direction, and sector relative to the reactor site or ISFSI facility, as appropriate. To assure that sampling is carried out in a reproducible manner, detailed sampling procedures have been prescribed (Prairie Island Nuclear Generating Plant,1997). Maps of fixed sampling locations are included in Appendix E.

To monitor the air environm(nt, airborne particulate are collected on membrane filters by l continuous pumping at five locations. Also, airborne iodine is collected by continuous pumping through charcoal fdters at all of these locations. Filters are changed and counted ,

weekly. Particulate filters are analyzed for gross beta activity and charcoal filters for iodine-131. A quarterly composite of the particulate filters from each location is gamma-scanned on an HP Ge or Ge(Li) detector. One of the five locations is a control (P-1), and four are indicators (P-2, P-3, P-4, and P-6).

Offsite ambient gamma radiation is monitored at thirty-four locations, using CaSO4:Dy dosimeters with four sensitive areas at each location: ten in an inner ring in the general 1 area of the site boundary, fifteen in the outer ring within a 4-5 mile radius, eight at special interest locations, and one controllocation,11.1 miles distant from the plant. They are replaced and measured quarterly. Also, a complete emergency set of TLDs for the inner ring, outer ring arti specialinterest locations are placed in the field at the same time as regular sets. The emergency set is returned to TBEESML quarterly for annealing and repackaging.

Ambient gamma radiation is monitored at the Independent Spent Fuel Storage Installation (ISFSI) Facility by twenty CaSO4:Dy dosimeters. Twelve dosimeters are located inside of the earthen berm in direct line of sight from the storage casks and eight dosimeters are located outside of the earthen berm. They are replaced and measured quarterly.

Milk samples are collected monthly from five farms (four indicator and one control) and analyzed for iodine-131 and gamma-emitting isotopes. The milk is collected biweekly during the growing season (May - October), because the milk animals may be on pasture.

For additional monitoring of the terrestrial environment, green leafy vegetables (cabbage) are collected annually from the highest D/Q garden and a control location (P-38) and analyzed for iodine-131. Corn is collected annually only if fields are irrigated with river water and analyzed for gamma-emitting isotopes. Well water and ground water are collected quarterly from four locations near the plant and analyzed for tritium and gamma-emitting isotopes. River water is collected weekly at two locations, one upstream 1

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0 3.2 Procram Description (continued) of the plant (P-5) and one downstream (P-6, Lock and Dam No.3). Monthly composites are analyzed for gamma-emitting isotopes. Quarterly composites are analyzed for tritium.

Drinking water is collected weekly from the City of Red Wing well. Monthly composites are analyzed for gross beta, iodine-131, and gamma-emitting isotopes. Quarterly composites are analyzed for tritium.

The aquatic environment is also monitored by semi-annual upstream and downstream collections of fish, periphyton or invertebrates, and bottom sediments. Shoreline sediment is collected semi-annually from one location. All samples are analyzed for gamma-emitting isotopes.

Due to detectable levels of tritium in a well south of the plant in 1989, special tritium sampling has been implemented. A summary of the special tritium sampling of ground and well water is included in Appendix D.

3.3 Procram Execution The Program was executed as described in the preceding section with the following exceptions:

(1) Approximately 15 hours1.736111e-4 days 0.00417 hours 2.480159e-5 weeks 5.7075e-6 months of sampling time were lost from air particulate / air iodine sample location (P-6) for the week ending April 9,1997 due to a brief power outage.

(2) Only 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months of sampling time were logged from air particulate / air iodine sample location (P-3) for the week ending June 18,1997. The sampler cartridge had inadvertently tripped the power switch.

(3) No air iodine sampling data was available (P-1,P-2, P-3, P-4, P-6) for the week ending July 30,1997. The samples were received too late for analysis, due to the UPS strike.

(4) No iodine sampling data was available for milk samples (P-14, P-18, P-37, P-25) for the week ending July 30, 1997. The samples were received too late for analysis, due to the UPS strike.

(5) Approximately 74 hours8.564815e-4 days 0.0206 hours 1.223545e-4 weeks 2.8157e-5 months of sampling time were lost from air particulate / air iodine sample location (P-1) the week ending August 27,1997, due to an open l fuse.

(6) Approximately 10 hours1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months of sampling time were lost from air particulate / air l iodine sample location (P-3) the week ending September 14,1997, due to an open fuse.

Deviations from the program are summarized in Table 5.3.

I Laboratory Procedures 3.4 All iodine-131 analyses in mill and drinking water were made by using a sensitive radiochemical procedure which involves separation of the element by use of an ion-exchange resin and subsequent beta counting. All gamma-spectroscopic analyses were performed with an HP Ge or Ge(Li) detector. Levels of iodine-131 in cabbage were 5

3.4 Labratory Procedures (continued) determined by HPGe or Ge(Li) spectrometry. Levels of airborne iodine-131 in charcoal samples were measured by HPGe or Ge(Li) spectrometry.

Tritium levels were determined by liquid scintillation technique.

Analytical procedures used by the Teledyne Brown Engineering Environmental Services, Midwest Laboratory are on file and are available for inspection. Procedures are based on those prescribed by the National Center for Radiological Health of the U. S. Public Health Service (U. S. Public Health Service,1967) and by the Health and Safety Laboratory of the U. S. Atomic Energy Commission (U. S. Atomic Energy Commission,1972).

Teledyne Brown Engineering Environmental Services, Midwest Laboratory has a comprehensive quality control / quality assurance program designed to assure the reliability of data obtained. Details of TBEESML's Quality Assurance Program are presented elsewhere (Teledyne Isotopes Midwest Laboratory,1992). The TBEESML Quality Assurance Program includes participation in Interlaboratory Comparison (Crosscheck) Programs. Results obtained in crosscheck programs are presented in Appendix A.

3.5 Procram Modifications There were no changes to the program for 1997.

3.6 Land Use Census In accordance with the Prairie Island Nuclear Generating Plant Offsite Dose Calculation Manual, H4, (ODCM) a land use census is conducted in order to identify ?.he location of the nearest milk animal, the nearest residence, and the nearest garden of greater than 507 ft2 producing fresh leafy vegetables in each of the 16 meteorological sectors within a distance of 5 miles. This census is conducted at least once per 12 months between the dates of May 1 and October 31. If new locations yield a calculated dose or dose equivalent (via the same exposure pathway) twenty percent greater than the required locations per the ODCM, then the new locations are added to the radiation environmental monitoring arogram within 30 days, and sampling locations having lower calculated doses or a lower c ose commitrnent may be deleted from this monitoring program after October 31 of the year in which the land use census was conducted.

This land use census insures thS updating of the radiation environmental monitoring program should sampling locations change within the 5 mile radius from the plant.

The 1997 Land Use Census was completed in September,1997. There were no changer in any of the highest D/Q locations for dairy, nearest residence, or garden sites in 1997.

The critical receptor location did not change in 1997 due to the requirements of the land use census.

No downstream irrigation of corn was dis,. overed within 5 miles of the Prairie Island Plant. Therefore, no corn samples were collected for analysis.

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4.0 RESULTS AND DISCUSSION All of the scheduled collections and analyses were made except those listed in Table 5.3.

All results are summarized in Table 5.4 in a format recommended by the Nuclear Regulatory Commission in Regulatory Guide 4.8. For each type of analysis of each sampled medium, this table lists the mean and range for all indicator locations and for all control locations. The locations with the highest mean and range are also shown.

4.1 Atmospheric Nuclear Detonations and Nuclear Accidents There were no reported atmospheric nuclear tests in 1997. The last reported test was conducted on October 16,1980 by the People's Republic of China. The reported yield was in the 200 kiloton to 1 megaton range.

There were no reported accidents at nuclear reactor facilities in 1997.

4.2 Summary of Preonerational Data The following constitutes a summary of preoperational studies conducted at the Prairie Island Nuclear Power Plant during the years 1970 to 1973, to determine background levels expected in the environment, and provided, where applicable, as a means for comparison j with present day levels. Strict comparisons, however, are difficult, since background ;

levels of radiation were much higher in these years due to radioactive fallout from the atmosphere. Gross beta measurements in fallout declined yearly from a level of 12,167 pCi/m2 to 1,020 pCi/m 2, and these declining values are reflected throughout the various media tested.

In the air environment, ambient gamma radiation (TLDs) averaged 9.4 mR/4 weeks during preoperational studies. Gross beta in air particulate declined from levels of 0.38 to 0.037 3

pCi/m Average present day levels have stabilized at arourd 0.025 pCi/m3. Airborne radiciodine remained below detection levels.

In the terrestrial environment of 1970 to 1973, milk, agricultural crops, and soil were monitored. In milk samples, low levels of Cs-137,1-131, and Sr-90 were detected. Cs-137 levels declined from 16.5 to 8.6 pCi/L. Present day measurements for both Cs-137 and l-131 are below detection levels. Agricultural crop measurements averaged 57.7 pCi/g for ,

gross beta and 0.47 pCi/g for Cs-137. Gross beta measured in soil averaged 52 pCi/g .

The aqueous environment was monitored by testing of river , well and bke waters, bottom sediments, fish , aquatic vegetation and periphyton. Specific location comparison of drinking, river and well water concentrations for tritium and gross beta are not possible.

However, tritium background levels, measured at eight separate locations, declined steadily from an average concentration of 1020 pCi/L to 490 pCi/L. Present day environmental levels of tritium are below detection levels, with the exception of the special tritium sampling described in Appendix D. Values for gross beta, measured from 1970 to 1973, averaged 9.9 pCi/L in downstream Mississippi River water,8.2 pCi/L for well waters, and 11.0 pCi/L for lake waters. Gamma emitters were below the lower limit of detection (LLD). In bottom sediments, gross beta background levels were determined at 51.0 pCi/g. Cs-137 activity during preoperational studies in 1973 measured 0.25 pCi/g upstream and 0.21 pCi/g downstream. The lower levels occasionally observed today can still be attributed to residual activity from atmospheric fallout. Gross beta in fish, measured in both flesh and skeletal samples, averaged 7.3 and 11.7 i pCi/g,respectively Gross beta 1 ackground levels in aquatic vegetation, algae and periphyton samples measured 76.0 pCi/g ,46.0 pCi/g, and 13.6 pCi/g, respectively.

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l 4.3 Procram Findines Results obtained show background levels of radioactivity in the environmental samples collected in the vicinity of the Prairie Island Nuclear Generating Plant in 1997.

Offsite Ambient Radiation (TLDs)

Ambient radiation was measured in the general area of the site boundary, at the outer ring 4 - 5 mi distant from the Plant, at special interest areas and at one control location. The means ranged from 14.2 mR/91 days at inner ring locations to 15.7 mR/91 days at outer ring locations. The mean at special locations was 14.5 mR/91 days and 16.0 mR/91 days at the control location. The dose rates measured at the inner and outer ring and the control locations were similar to those observed from 1984 through 1996. The results are tabulated below.No plant effect on ambient gam,ta radiation was indicated (Figure 5-1).

Averagt Year and Outer kines) Control Dose rate (mR/91 days) 1984 15.0 15.4 1985 14.0 15.3 1986 17.1 17.3 1987 16.9 17.0 1988 15.4 16.0 1989 16.5 16.7 1990 15.9 16.3 1991 14.9 14.5 1992 16.3 14.8 1993 15.9 15.4 1994 15.2 16.0 1995 15.6 16.6 1996 14.8 16.4 Ambient gamma radiation as measured by thermoluminescent dosimetry.

Average quarterly dose rates.

ISFSI Facility Ooerations Monitorine Ambient radiation was measured inside the ISFSI earth berm, outside the ISFSI earth berm and at two special locations between the plant ISFSI and the Prairie Island Indian Community. The mean dose rates measured 48.1 mR/91 days inside the ISFSI earth berm and 17.0 mR/91 days outside the ISFSI earth berm. Two additional casks, loaded with spent nuclear fuel, were placed on the ISFSI pad during 1997, on the dates of January 12 and January 24, bringing the total number of loaded casks to seven by the end of 1997.

The higher levels inside the earth berm are expected due to the loaded spent fuel casks being in direct line-of-sight from the TLDs. The ambient radiation levels measured outside the earth berm show a slight increase as compared to other offsite dose rates around the plant. If the dose rates outside the earth berm are an indication of gamma skyshine from the casks, they are consistent with predictions given in the ISFSI Safety Analysis Report, Table 7A-7, " Total Skyshine Dose Rate". The cumulative average of the two special Prairie Island Indian Community TLDs measured 14.6 and 14.1 mR/91 days. No spent fuel storage effect on offsite ambient gamma radiation was indicated.

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Airborne Particulate i

The average annual gross beta concentration in airborne particulate was identical at both indicator and control locations (0.021 pCi/m3), and was similar to or slightly lower than the average means observed from 1984 through 1996. The results are tabulated below.

The data for 1986 does not include the results from May 19 to June 9,1986, which were influenced by the accident at Chernobyl. (Figure 5-2).

l Average of Year Indicators Control Concentration (pCi/m3) 1984 0.025 0.027 1985 0.025 0.025 4 1986 0.024 0.029 I 1987 0.024 0.023 1988 0.030 0.030 1989 0.028 0.027 1990 0.024 0.023 i 1991 0.025 0.025 l

1992 0.023 0.021 1993 0.022 0.019 j 1994 0.022 0.022 1995 0.022 0.022 1996 0.023 0.020 l Average annual gross beta concentrations in airborne particulate.

A spring peak in beta activity had been observed almost annually for many years (Wilson d al.,1969). It had been attributed to fallout of nuclides from the stratosphere (Gold d al.,1964). It was pronounced in 1981, occurred to a lesser degree in 1982, and has not occured since 1983. In 1986, a spring peak could not be identified because it was j overshadowed by releases of radioactivity from Chernobyl. The highest averages for gross beta were seen in the months of January and December. The increase of beta activity during the winter months was also observed in 1983 through 1997.

Two pieces of evidence indicate conclusively that the elevated activity observed during the winter months was not attributable to the Plant operation. In the first place, elevated activity of similar size occurred simultaneously at both indicator and control locations. j Secondly, an identical pattern was observed at the Monticello Nuclear Generating Plant, !

about 100 miles distant from the Prairie Island Nuclear Generating Plant (Northern States Power Company,1998a).

Gamma spectroscopic analysis of quarterly composites of air particulate filters yielded l similar results for indicator and control locations. Beryllium-7, which is produced I continuously in the upper atmosphere by cosmic radiation (Arnold and Al-Salih,1955),

was detected in all samples. All other gamma-emitting isotopes were below their respective LLD limits.

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Weekly levels of airborne iodine-131 were below the lower limit of detection (LLD) of 0.07 pCi/m3 ni all sampics. There was no indication of a plant effect.

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Milk Iodine-131 results were below the detection limit of 1.0 pCi/L in all samples. Cs-137 results were below the LLD level of 15 pCi/L in all samples. No other gamma-emitting isotopes, except naturally-occurring potassium-40, were detected in any milk samples.

This is consistent with the findings of the National Center for Radiological Health that most radiocontaminants in feed do not find their way into milk due to the selective metabolism of the cow. The common exceptions are radioisotopes of potassium, cesium, strontium, barium, and iodine (National Center for Radiological Health,1968).

In summary, the milk data for 1997 show no radiological effects of the plant operation.

Drinkine Water In drinking water from the City of Red Wing well, tritium activity was below the LLD level of 175 pCi/L in all samples. As with the other well water samples, all analyses for gamma-emitting isotopes yielded results below detection limits. Gross beta averaged 5.1 pCi/L and was similar to levels observed from 1984 through 1996. In summary, drinking water data for 1997 show no effects of plant operation.

Gross Beta (pCi/L) 1984 7.9 1985 7.1 1986 6.8 1987 7.9 1988 8.0 1989 7.0 1990 7.0 1991 8.0 1992 7.6 1993 7.5 1994 5.8 1995 3.9 1996 6.3 Average annual concentrations; Gross beta in drinking water.

l River Water i At both the upstream and downstream collection sites, quarterly composite tritium levels were below the LLD level of 175 pCi/L . Gamma-emitti.g isotopes were beloiv detection limits in all samples. There was no indication of a plant effect. l Well Water At the control well P-25, Rohl Farm and three indicator wells (P-8, Community Center, P-6, Lock and Dam No. 3, and P-9, Plant Well No. 2 ) no tritium was detected above the LLD level of 179 pCi/L in all samples. Gamma-emitting isotopes were i,elow detection limits in all samples.

In summary, well water data for 1997 show no radiological effects of the plant operation.

Crops 10

4 Two samples of cabbage were collected in August and analyzed for I-131. The I-131 level was below 0.017 pCi/g wet weight in both samples. There was no indication of a plant effect.

The field sampling personnel conducted an annual land use survey and found that there was no river water taken fer irrigation into fields within 5 miles downstream from the Prairie Island Plant. Therefore,it was not necessary to collect and analyze corn samples.

Eish Fish samples were collected in May and September,1997 and analyzed for gamma emitting isotopes. Only naturally-occurring potassiu_m-40 was detected, and there was no significant diflerence between upstream and downstream results. There was no indication of a plant effect.

Aquatic Insects or Periphyton Aquatic insects (invertebrates) or periphyton were collected in May and October,1997.

The samples were analyzed for gamma-emitting isotopes.

All gamma-emitting isotopes were below their respective detection limits. There was no indication of any plant effect.

l Bottom and Shoreline Sediments Sediment collections were made in May and October,1997 and analyzed for gamma-emitting isotopes. Cesium-137 was detected in one downstream sample and measured 0.047 pCi/g dry, indicating the influence of fallout deposition. All other gamma-emitting

- isotopes, except naturally-occurring potassium-40, were below their respective LLDs. No plant effect was indicated.

i l

l-I l

11

p---n------ - - , - -- , . - - -.------------- -- --------- -- ,. , -- _ --,-- -- - , - . - - , - - - - - - - - - - - - , - - - - - - , . - - - - _ . , - . - - - - - - - - -

I 1

l 5.0 FIGURES AND TABLES i

4 4

I i

i 12

1 i

1 Table 5.1. Sample collection and analysis program, Prairie Island Nuclear Generating Plant,1997.

j Locations Collection Analysis Codes Type and Type and Medium Number (and Type)a Frequencyb Frequency <

Ambient radiation 54 P-01 A - P-10A C/Q Ambient garmna (TLD's) P-01B - P-15B P-01S - P-08S l P-011A - P-08IA l P-011B - P-OblB P-011X - P-04IX P-01C Airborne particulate 5 P-1(C), P-2, C/W GB, GS (QC of P-3,P-4,P-6 each location)

Airborne Iodine 5 P-1(C), P-2, P-3, C/W I-131 P-4, P-6 Milk 4 P-14, P-18, G/Md j.131, GS P-25(C), P-37 1 P-39 G/M I-131, GS River water 2 P-5(C), P-6 G/W GS(MC), H-3(QC)

Drinking water 1 P-11 G/W GB(MC),1-131(MC)

GS(MC), H-3(QC)

Well Water 4 P-25(C), P-6, G/Q H-3, GS P-8, P-9 Edible cultivateci crops - 2 P-38(C), P-24 G/A I-131 leafy green vegetables Fish (one species, edible portion) 2 P-19(C), P-13 G/SA GS Periphyton or invertebrates 2 P-40(C), P-6 G/SA GS Bottom Sediment 2 P-20(C), P-6 G/SA GS Shoreline sediment 1 P-12 G/SA GS a Location codes are defined in Table D-2. Control stations are indicated by (C). All other stations are indicators.

b Collection type is coded as follows: C/ = continuous, G/ = grab. Collection frequency is coded as follows:

W= weekly, M = monthly, Q = quarterly, SA = semiannually, A = anaually, c Analysis type is coded as follows: GB = gross beta, GS = gamma spectroscopy, H-3 = tritium,1-131 =

iodine 131. Analysis frequency is coded as follows: MC = monthly composite, QC = quarterly composite.

d Milk is collected biweekly during the grazing season (May - October).

13

Table 5.2. Sampling locations, Prairie Island Nuclear Generating Plant,1997.

Distance and Type of Direction from Code Type a Collection Site ,

Sampleb Reactor P-1 C Air Station P-1 AP,Al 11.8 mi @ 316 /NNW P-2 Air Station P-2 AP,Al 0.5 mi @ 294 /WNW P-3 Air Station P-3 AP,AI 0.8 mi @ 313 /NW P-4 Air Station P-4 AP,Al 0.4 mi @ 359 /N P-5 C Upstream of Plant RW 1.8 mi @ 11 /N P-6 Lock & Dam #3 & Air AP, AI, RW, Station P-6 WW, BS,BOC 1.6 mi @ 129 /SE P-8 Community Center WW 1.0 mi @ 321 /WNW P-9 Plant Well #2 WW 0.3 mi @ 306 /NW P-11 Red Wing Service Center DW 3.3 mi @ 158 /SSE P .12 Downstream of Plant SS 3.0 mi @ 116 /ESE P-13 Downstream of Plant FC 3.5 mi @ 113 /ESE P-14 Gustafson Farm M 2.3 mi @ 173 /S P-18 Christiansen Farm M 3.8 mi @ 88 /E P-19 C Upstream of Plant FC 1.3 mi @ 0 /N P-20 C Upstream of Plant BS 0.9 mi @ 45 /NE P-24 Suter Residence VE 0.6 mi @ 158 /SSE P-25 C Rohl Farm M, WW 12.9 mi @ 352 /N P-37 Welsch Farm M 4.1 mi @ 87 /E P-38 C Cain Residence VE 14.2 mi @ 359 /N P-39 Born Farm M 2.8 mi @ 239 /WSW P-40 C Upstream M Plant BOc 0.4 mi @ 0 /N General Area of the Site Boundary P-01 A Property Line TLD 0.4 mi @ 359 /N P-02A Property Line TLD 0.3 mi G 10 /N P-03A Property Line TLD 0.5 mi @ 183 /S P-04A Property Line TLD 0.4 mi @ 204 /SSW P-05A Property Line TLD 0.4 mi O 225 /SW P-06A Property Line TLD 0.4 mi @ 249'/WSW P-07A Property Line TLD 0.4 mi @ 268 /W P-08A Property Line TLD 0.4 mi @ 291 /WNW P-09A Property Line TLD 0.7 mi @ 317 /NW P-10A Property Line TLD 0.5 mi @ 333 /NNW t

I j

l l

14 L____________ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - . - . - - -

l i

Table 5.2. Sampling locations, Prairie Island Nuclear Generating Plant,1997 (continued).

1 Distance and Type of Direction from Code Type a Collection Site Sampleb Reactor Anoroximatelv 4 to 5 miles Distant from the Plant P-01 B Thomas Killian Residence TLD 4.7 mi @ 355 /N P-02P Roy Kinneman Farm TLD 4.8 mi @ 17 /NNE P-03B Wayne Anderson Farm TLD 4.9 mi @ 46 /NE P-04 B Nelson Drive (Road) TLD 4.2 mi @ 61 /ENE P-05B County Road E and Coulee TLD 4.1 mi @ 102 /ESE P-06B William Hauschbilt Residence TLD 4.4 mi G 112 /ESE P-07B Red Wing Public Works TLD 4.7 mi @ 140 /SE P-08B David Wnuk Residence TLD 4.1 mi @ 165 /SSE P-09B Highway 19 South TLD 4.2 mi G 187 /S P-10B Cannondale Farm TLD 4.9 mi @ 200 /SSW P-11B Wallace Weberg Farm TLD 4.5 mi G 221 /SW P-12B Ray Gergen Farm TLD 4.6 mi @ 251 /WSW

. P-13B Thomas O'Rourke Farm TLD 4.4 mi @ 270'/W l P-14B David J. Anderson Farm TLD 4.9 mi @ 306 /NW I

P-15B Holst Farms TLD 3.8 mi @ 345 /NNW Special Interest Locations P-01S Federal Lock & Dam #3 TLD 1.6 mi @ 129 /SE i P-02S Charles Suter Residence TLD 0.5 mi @ 155 /SSE P-03S Carl Gustafson Farm TLD 2.2 mi @ 173 /S P-04S Richard Burt Residence TLD 2.0 mi @ 202 /SSW P-05S Kinney Store TLD 2.0 mi @ 270 /W P-06S Earl Flynn Farm TLD 2.5 mi @ 299 /WNW P-07S Indian Community TLD 0.7 mi @ 271 /W P-08S Indian Community TLD 0.7 mi @ 287 /NWW P-01C C Robert Kinneman Farm TLD 11.1 mi @ 331 /NNW l

l l

15 l

I Table 5.2. Sampling k) cations, Prairie Island Nuclear Generating Plant,1997 (continued).

Distance and Type of Direction from Code Type a Collection Site Sampleb ISFSI Center i I

ISFSI Area inside Earth Berm f

P-011A ISFSI Nuisance Fence TLD 190' O 45 /NE I P-02IA ISFSI Nuisance Fence TLD 360' @ 82 /E l P-031A ISFSI Nuisance Fence TLD 370' @ 100 /E P-041A ISFSINuisance Fence TLD 200' @ 134 /SE l! P-051A - ISFSINuisance Fence TLD 180' @ 219 /SW

! P-061A ISFSI Nuisance Fence TLD 320' @ 258 /WSW l P-071A ISFSINuisance Fence TLD 320' @ 281'/WNW P-08IA ISFSINuisance Fence TLD 190' @ 318 /NW )

P-011X ISFSINuisance Fence TLD 140' @ 180 /S P-02IX ISFSINuisance Fence TLD 310' @ 270 /W P-031X ISFSINuisance Fence TLD 140 @ 0 /N P-04D; ISFSINuisance Fence TLD 360' @ 90 /E

- ISFSI Area Outside Earth Berm P-011B ISFSI Berm Area TLD 340' @ 3 /N P-021B ISFSI Berm Area TLD 380' @ 28 /NNE P-03IB ISFSI Berm Area TLD 560' @ 85 /E P-04IB ISFSI Berm Area TLD 590' @ 165 /SSE

.P-OSIB ISFSI Berm Area TLD 690' @ 186 /S P-061B ISFSI Berm Area TLD 720' @ 201 /SSW P-071B ISFSI Berm Area TLD 610' @ 271 /W P-081B ISFSI Berm Area TLD 360' @ 332 /NNW a "C" denotes control location. All other locations are indicators.

b Sample Codes:

AP = Airborne particulate WW = Weil water AI = Airborne Iodine BS = Bottom (river) sediments M = Milk SS = Shoreline Sediments VE = Vegetation / vegetables BO = Bottom organisms (periphyton or DW = Drinking water macroinvertebrates)

RW = River water F = Fish c Distance and direction data for fish and bottom organisms are approximate because availability of sample specimen may vary at any one location.

16

l l

l Table 5.3. Missed collections and analyses,1997. Prairie Island Nuclear Generating Plant.

l All required samples were collected and analyzed as scheduled except the following:

t Sample Collection Reason for not conducting Plans for Preventing Recurrence l

Type Analysis Location Date or REMP as required Period l

AP/AI Gross P-6 04-09-97 No power,15.2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months Power loss due to flood Beta / downtime. conditions at substation. No I131 action deemed necessary.

AP/AI Gross P-3 06-18-97 Air sampler failure; The sampler cartridge fell Beta, only 5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months run-time. against the power switch and I-131 Power inadvertently shut the power off. The switched off. cartridge elbow was modified to prevent recurrance.

Al I-131 P-1,2,3, 07-30-97 Samples received too FedEx was used for the P-4, 6 late for 1-131 analysis, remainder of the strike period.

due to UPS strike.

MI i-131 P-14,18, 7-30-97 Samples received too FedEx was used for the P-25,37 late for I-131 analysis, remainder of the strike period.

due to UPS strike.

AP/AI Gross P-1 08-27-97 Sampler operated Replaced fuse.

Beta, approximately 94 hrs.

1-131 Open fuse possibly due to lightning strike in area.

AP/Al Gross P-3 09-14-97 Approximately 10 hrs. Returned sampler to vendor for Beta, downtime. Open fuse on repair. Under warranty.

I-131 new sampier.

17 l

Figura 5-1. Offsita Ambi:nt Radiation (TLDs); avsrage of inner and outer ring indicator locations versus control location.

-e- Indicator 20 19 18 17 E 16 A g 15 ' " 1H

14

'm ,

E 13 12 11 10 19841985198619871988198919901991199219931994199519961997 I

i

Control (P-01C) I 20 ,

19 18 17 I E 16 '

)

15 5 V r 14

'c l i

E 13 12 l 11 10 19841985198619871988198919901991199219931994199519961997 1

l 18 N__________---__ .

Figura 5-2. Airborno Particulat::s; analysis for gross bsta, average mean of all indicator locations versus control location.

-e- Indicators (P-2,3,4,6) 0.035 0.033 0.031 n 0.029 b s

E 0.027 [ \(

Ua 0025 m

0.023 vN, x j 0.021 0.019 ;

0.017 0.015 19841985198619871988198919901991199219931994199519961997

Control (P-1) 0.035 0.033 0.031 0.029 b U 0027 0'025 -

0.023 V N/\ l 0.021

mq Sg 0.019 0.017 0.015 19841985198619871988198919901991199219931994199519961997 19

Table 5.4. Radiation Envis onmental Monitoring Program Summary.

- Nameof Facility - Prairie Island Nuclear Power Station Docket No. 50-282, 50-306 l location of Facility Goodhue, Minnesota Reporting Period January - December 1W7 (County, State) l Indicator Location with Highest Control Number Sample Type and . Locations Annual Mean Locations Non-Type Number of LLob Mean (F)C Routine Mean (F)C Mean (F)c (Units) Analysesa Rangec Locationd. Rangec Range Results' l

TLD (mR/91 Camma 40 3.0 14.2 (40/40) P-09A, 15.1 (4/4) (See Control 0 days) (Inner (10.6-163) 0.7 mi @ 317* /NW (13.2-16.4) below.)

Ring, Area at Site Boundary)

TLD(mR/91 Gamma 60 3.0 15.7 (60/60) P-03B, Anderson Farm, 17.6 (4/41 (See Control 0 days)(Outer (9.2-20.0) 4.9 mi @ 46*/NE (14.0-19.1) below.)

Ring,4 5 miles distant)

TLD (mR/91 Gamma 32 3.0 14.5 (32/32) P-04S, Burt Residence, 16.6 (4/4) (See Control 0 days)(Special (9.5-18.8) 2.0 mi @ 202*/SSW (12.4-18.8) below.)

Interest Areas)

TLD (mR/91 Camma 4 3.0 None P-01C, R. Kinneman Farm, 16.0 (4/4) 16.0 (4/4) 0 days)(Control) 11.1 mi @ 331*/.NNW (12.8-17.4) (12.8-17.4)

Airborne GB 258 0.002 0.021 (206/206) P-4, AirStation 0.022 (52/52) 0.021 (52/52) 0 Particulate (0.008-0.054) 0.4 mi @ 359" /N (0.008-0.054) (0.008-0.067)

(pCi/m3)

CS 20 Be-7 0.022 0.076 (16/16) P-4, AirStation 0.077 (4/4) 0.071 (4 /4) 0 (0.043-0.11) 0.4 mi @ 359' /N (0.043-0.10) (0.057-0.093)

Mn-54 0.0008 <LLD - - <LLD 0 Co-58 0.0009 <LLD - -

<LLD 0 Co-60 0.0011 <LLD - - (LLD 0 Zn-65 0.0021 <LLD - -

<LLD 0 Zr-Nb-95 0.0018 <LLD - - <LLD 0 Ru-103 0.0009 <LLD - -

<LLD 0 l Ru-106 0.0084 <LLD - - (LLD 0 Cs-134 0.0010 (LLD - -

<LLD 0 Cs-137 0.0008 <LLD - -

<LLD 0 Ba-La-140 0.0019 <LLD - -

<LLD 0 l Ce-141 0.0017 <tLD - -

cLLD 0 Ce-144 0.0049 <LLD - - (LLD 0 Airborne 1131 253 0.07 <LLD - -

<LLD 0 lodine (pCi/m3) 20

Tab!c 5.4. Radiation Environmental Monitoring Program Summary.

l Name of Facility PrairieIsland Nuclear PowerStation Docket No. 50-2H2, 50-3(M Location of Facility Goodhue, Minnemta Reporting Period January - December 1W7 (County, State)

Indicator Location with Highest Control Numter Sample Type and locations Annual Mean Locations Non- i j- Type Number of LLDb Mean (F)C Routine Mean (F)C Mean (F)c (Units) Analyma Rangec Locationd Rangec Range Results" Milk, 1131 78 1.0 <LLD - - <LLD 0 (pCi/L)

O 82 K-40 200 1540 (64/64) P-39, Born Farm 1790 (10/10) 1410 (18/18) 0 (1320-2210) 2.8 mi @ 239*/WSW (1460-2210) (1260-1520) l Cs-134 15 <LLD - (LLD 0 Cs-137 15 <LLD - <LLD 0 Other 15 <LLD - <LLD 0 gammas River Water H-3 8 175 (LLD - -

<LLD 0 (pCi/L)

CS 24 Mn-54 15 <LLD - -

<LLD 0 Fe-59 30 - <LLD - -

<LLD 0 Co-58 15 <LLD - - <LLD 0-Co-60 15 <LLD - -

<LLD 0 Zn-65 30 <LLD - - <LLD 0 ,

Zr-Nb-95 15 <LLD - - <LLD 0 Cs 134 15 <LLD - - <LLD 0 Cs-137 18 <LLD - -

<LLD 0 i Ba-La-140 15 <LLD - -

<LLD 0 1 Ce-144 69 <LLD - - <LLD 0 21

.Tabie14. Radiation Environmental Monitoring Pmgram Summary.

Name of Facility l PrairicIsland Nuclear Power Station Docket No.- 50-282, 50-306 Location of Facility Goodhue, Minnesota Reporting Period January - December 1997 (County, State) l .

Indicator Location with linghest Control Number Sample Type and locations . Annual Mean Locations Non.

Type Number of LLob Mean (F)C Routine Mean (F)C Mean (F)c (Units) Analywsa RangeC' Locationd' Rangec Range Result #

Drinking GB 12 2.1 5.1 (11/12) P 11, Red Wing 5.1 (11/12) None 0 Water (pCi/L) (2.3-7.6) Service Center 3.3 (2.3-7.6) mi@ 158*/SSE I-131 12 - 1.0 (LLD - - None o l1-3 4 175 (LLD - - None o GS 12 Mn-54 15 <LLD - -

None 0 Fe-59 30 <LLD - -

None O Co-58 15 <LLD - -

None O Co-60 15 <LLD - -

None 0 Zn-65 30 <LLD - -

None P Zr-Nb-95 15 <LLD - -

None O Cs-134 10 <LLD - -

None 0

. Cs-137 10 <LLD - -

None 0 Ba-La 140 15 <LLD - -

None 0.

Ce-144 67 <LLD - -

None 0 Well Water H-3 16 179 <LLD - <LLD 0 (pCi/L)

CS 16 Mn-54 15 <LLD - - <LLD 0

' Fe-59 30 <LLD - -

<LLD .O Co-58 15 <LLD - - <LLD 0 Co-60 15 <LLD - - <LLD 0 L 'Zn-65 30 <LLD- - - <LLD 0 l Zr-Nb-95 15 <LLD - -

<LLD 0 Cs 134 15 (LLD - -

<LLD 0 l-Cr,-137 18 <LLD - -

<LLD 0

! Da-La-140 15 <LLD - -

<LLD 0 Ce-144 ' 57 <LLD - -

<LLD 0 l

- Crops - I131 2 0.017 <LLD - -

(LLD 0 Cabbage (pCi/g wet) 22

Table 5 4. Radiation Environmental Monitoring Program Summary.

. Nameof Facility PrairieIsland Nuclear PowerStation Docket No. 50-282, 50-306

. Location of facihty Goodhue, Minnesota Reporting Period January - December 1997 (County, State)

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLob Mean (F)C Mean (F)C Routine Mean (F)c (Units) Analyses a Rangec locationd Range c Range Results' Fish-Flesh CS 4 (pCi/g wet)

K-40 0.1 2.75 (2/2) P-19, Upstream, 2.78 (2/2) 2.78 (2/2) 0 (2.63-2.86) 1.3 mi @ 0*/N (2.39-3.17) (2.39-3.17)

Mn-54 0.014 <LLD - <LLD 0 Fe-59 0.047 <LLD - <LLD 0 Co-58 0.025 <LLD - <LLD 0 Co-60 0.017 (LLD -

<LLD 0 Zn-65 0.027 <LLD -

<LLD 0 Zr-Nb-95 0.037 <LLD -

<LLD 0 Cs-134 0.017 <LLD -

<LLD 'O Cs-137 0.017 (LLD -

<LLD 0 Ba-La-140 0.19 <LLD - <LLD 0 invertebrates GS 4 (pCi/g wet)

Be-7 1.85- <LLD - - <LLD 0 K-40 3.89 <LLD - -

<LLD 0 Mn-54 0.13 <LLD - - <LLD 0 Co-58 0.12 <LLD - -

<LLD 0

Co-60 0.13 <LLD - - <LLD 0-f Zn-65 0.50 <LLD - - <LLD 0 Zr-Nb-95 0.30 <LLD - - (LLD 0 Ru-103 0.22 <LLD - - <LLD 0 l'

l Ru-106 1.18 <LLD - - <LLD 0 l

Cs-134 0.16 <LLD - - <LLD 0 Cs-137 0.17 <LLD - - <LLD 0 i Ba-La 140 0.36 LLD - -

<LLD 0 l.

Ce141 0.31 <LLD - -

<LLD 0 Ce-144 0.91 <LLD - - <LLD 0 23

I Table 5.4. Radiation Environmental Monitoring Program Samtmary.

Name of Facility Prairie Island Nuclear Power Station Docket No. 50-282, 50-3w, location of Facihty Goodhue, Minnesota Reporting Period January - Decemtier IW7 (County, State)

Indicator Location with Highest Control Number Sample Type and locations Annual Mean Locanons Non-Type Number of LLDb Mean (F)C Routine Mean (F)' Mean (F)c (Units) Analyses a Range c Locationd Rangec Range Results" Bottom and GS 6 Shoreline Sediments Be-7 0.24 <LLD P-20, Upstream, 0 66 (1/2) 0 66 (1/2) 0 (pCi/g dry) 0.9 mi. 045*/NE K-40 0.5 7.57 (4/4) P-20, Upstream, 10.22 (2/2) 0 10.22 (2/2)

(6.65 8.86) 0.9 mi. @45*/NE (9.56-10.88) (9.56-10.88)

Mn-54 0.015 <LLD - -

<LLD 0 Co-58 0.026 <LLD - -

<LLD 0 Co-60 0.017 <LLD - -

<LLD 0 Zn-65 0.11 <LLD - -

(LLD 0 Zr-Nb-95 0.031 <LLD - -

<LLD 0 Ru-103 0.035 <LLD - -

<LLD 0 Ru-106 0.21 <LLD - -

(LLD 0 Cs-134 0.035 <LLD - -

<LLD 0 Cs-137 0.027 0.047 (1/4) P-6, Lock 0.047 (1/4) <tLD 0 and Dam #3 1.6 mi @ 129 /SE Ba La-140 0.12 <LLD - -

(LLD 0 Ce-141 0.053 <LLD - -

<LLD 0 Ce 144 0.11 <LLD - -

<LLD 0 d

GB = Gross beta; GS = gamma scan.

b LLD = Nominal lower limit of detection based on 4 66 sigma error for background sample.

C Mean and range are based on detectable measurements only. Fraction of detectable measurements at specified hications is indicated in parentheses (F).

d locations are specified: (1) by name, and code (Table 2) and (2) by distance, direction and sector relative to reactor site.

Non-routine results are those which exceed ten times the control station value. If no control station value is available, the result is considemd non-routine if it exceeds ten times the typical pre-operational value for the medium or k> cation.

24

l l

6.0 REFERENCES

CITED Arnold, J. R. and H. A. Al-Salih.1955. Beryllium-7 Produced by Cosmic Rays. Science 121:

451-453.

Eisenbud, M.1963. Environmental Radioactivity, McGraw-Hill, New York, New York, pp.

213,275 and 276.

Gold, S., H. W. Barkhau, B. Shlein, and B. Kahn,1964. Measurement of Naturally Occurring Radionuclides in Air, in the Natural Environtn-t, University of Chicago Press, Chicago, Illinois, 369-382.

Hazleton Environmental Sciences Corporation. 1979a to 1983a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1978 through 1982.

Hazleton Environmental Sciences Corporation. 1979b to 1983b. Radiation Environmental I Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1978 through 1982.

Hohenemser, C. M. Deicher, A. Ernst, H. Hofsass, G. Lindner, E. Racknagel. 1986.

"Chernobyl," Chemtech. October 1986, pp. 596-605.

National Center for Radiological Health,1968. Radiological Health and Data Reports, Vol. 9, Number 12, 730-746.

Northern States Power Company. 1972. Prairie Island Nuclear Generating Plant, Environmental Monitoring and Ecological Studies Program, January 1,1971 to December 31,1971. Minneapolis, Minnesota.

1973. Prairie Island Nuclear Generating Plant, Environmental Monitoring and Ecological Studies Program, January 1,1972 to December 31, 1972. Minneapolis, Minnesota.

1974. Prairie Island Nuclear Generating Plant, Environmental Monitoring and Ecological Studies Program, Volume 1, January 1,1973 to December 31, 1973.

Minneapolis, Minnesota.

Northern States Power Company.1979 to 1983. Prairie Island Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31,1978 through 1982 (prepared by Hazleton EnvironmentalSciences). Minneapolis, Minnesota.

Northern States Power Company.1984 to 1998. Prairie Island Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31,1983 through 1997 (prepared by Teledyne Brown Engineering Environmental Services, Midwest Laboratory). Minneapolis, Minnesota.

25

Teledyne Brown Engineering Environmental Services, Midwest Laboratory.1984a to 1998a.

Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January - December 1983 through 1997.

l Teledyne Brown Engineering Environmental Services, Midwest Laboratory.1984b to 1998b.

Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, j Complete Analysis Data Tables, January - December 1983 through 1997.

Northern States Power Company.1997. Radiological Environmental Monitoring for Prairie Island Nuclear Generating Plant, Radiation Protection Implementing Procedures 4700.

l Teledyne Brown Engineering Environmental Services, Midwest Laboratory.1995. Quality Control Program, Revision 0.

20 July 1995.

l

l. 1994. Quality Control Procedures Manual, Revision 18,27 September 1994 j 1992. Quality' Assurance Program Manual, Revision 1,20 August 1992.

[ U.S. Atomic Energy Commission. 1972. HASL Procedures Manual, Health and Safety Laboratory, New York, NY.,10014.

)

U.S. Public Health Service.1967. Radioassay Procedures for Environmental Samples, National Center for Radiological Health, Rockville, Maryland (Public Health Service Publication

). No. 999-RH-27).

l Wilson, D. W., G. M. Ward and J. E. Johnson. 1969. In Environmental Contamination by Radioactive Materials, International Atomic Energy Agency. p.125.

1 i

f 26

1 l

APPENDIX A INTERLABORATORY COMPARISON PROGRAM RESULTS l

l NOTE: Teledyne's Midwest Laboratory participates in intercomparison studies administered by U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada. The results are reported in ;

Appendix A. Also reported are results of InternationalIntercomparison and Teledyne testing of i TLD's, as well as, in-house spikes, blanks, duplicates and mixed analyte performance evaluation j-program results. Appendix A is updated four times a year; the complete Appendix is included in March, June, September and December monthly progress reports only.

January,1997 through December,1997

Apoendix A Interlaboratory Comparison Program Results Teledyne Brown Engineering Environmental Services Midwest Laboratory (formerly Hazleton Environmental Sciences) has participated in interlaboratory comparison (crosscheck) programs since the formulation of it's quality control program in December 1971. These programs are operated by agencies which supply environmental type samples (e.g., milk or water) containing concentrations of radionuclides known to the issuing agency but not to participant laboratories. The purpose of such a program is to provide an independent check on the laboratory's analytical procedures and to alert it to any possible problems.

Participant laboratories measure the concentration of specified radionuclides and report them to the issuing agency. Several months later, the agency reports the known values to the participant laboratories and specifies control limits. Results consistently higher or lower than the known values or outside the controllimits indicate a need to check the instruments or procedures used.

The results in Table A-1 were obtained thmugh participation in the environmental sample crosscheck program for milk, water and air filters during the past twelve months. Data for previous years is available upon request.

This program is conducted by the U.S. Environmental Protection Agency Office of Research and Development National Exposure Research Laboratory Characterization Research Division-Las Vegas, Nevada.

The results in Table A-2 were obtained for Thermoluminescent Dosimeters (TLDs), via various

-International Intercomparisons of Environmental Dosimeters under the sponsorships listed in Table A-2.

Also Teledyne testing results are listed.

Table A-3 lists results of the analyses on in-house " spiked" samples for the past twelve months. All samples are prepared using NIST traceable sources. Data for previous years available upon request.

Table A-4 lists results of the analyses on in-house " blank" samples for the past twelve months. Data for previous years available upon request.

Table A-5 list results of the in-house " duplicate" program for the past twelve months. Acceptance is based on the difference of the results being less than the sum of the errors. Data for previous years available upon request.

The results in Table A-6 were obtained through participation in the mixed analyte performance evaluation program.

The results in Table A-7 were obtained through participation in the Environmental Measurement Laboratory Quality Assessment Program.

Attachment A lists acceptance criteria for " spiked" samples.

Out-of-limit results are explained directly below the result.

Al o__ _ _-___ _ . _ _ .__ _ __ l

12-31-97 ATTACHMENT A ACCEPTANCE CRITERIA FOR " SPIKED" SAMPLES .

LABORATORY PRECISION: ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSES'

' One Standard Deviation Analysis Level ' for single determinations Gamma Emitters 5 to 100 pCi/ liter or kg 5.0 pCi/ liter

>100 pCi/ liter or kg 5% of known value 6

Strontium-89 5 to 50 pCi/ liter or kg 5.0 pCi/ liter

>50 pCi/ liter or kg 10% of known value Strontium-90 6

2 to 30 pCi/ liter or kg 5.0 pCi/ liter

>30 pCi/ liter or kg 10% of known valui Potassium-40 >0.1 g/ liter or kg 5% of known value Gross alpha s20 pCi/ liter 5.0 pCi/ liter

>20 pCi/ liter 25% of known value Gross beta s100 pCi/ liter 5.0 pCi/ liter

>100 pCi/ liter 5% of known value Tritium s4,000 pCi/ liter is = (pCi/ liter) =

169.85 x (known) ""

>4,000 p Ci/ liter 10% of known value Radium-226,-228 <0.1 pCi/ liter 15% of known value Plutonium 0.1 pCi/ liter, gram, or sample 10% of known value i

Iodine-131, s55 pCi/ liter 6.0 pCi/ liter Iodine-129 6 >55 pC1/ liter 10% of known value Uranium-238, s35 pCi/ liter 6.0 pCi/ liter Nickel-63 6 >35 pCi/ liter 15% of known value 6

Technetium-99

. 50 to 100 pCi/ liter 10 pCi/ liter Ir n-55

. >100 pCi/ liter 10% of known value Others" -

20% of known value

From EPA publication, " Environmental Radioactivity Laboratory Intercomparison Studies Program, Fiscal Year,1981-1982, EPA-600/4-81-004.

Teledyne limit.

A2

Table .'.1. U.S. Environmental Protection Agency's crosscheck program, comparison of EPA and Teledyne's Midwest Laboratory results'.

Concentration in pCi/L' Lab Sample Date Teledyne Results EPA Result' Control Code Type Collected Analysis 12 Sigma' 1s, N=1 Limits STW-782 WATER Jan,1997 Sr-89 9.7i 0.6 12.0 i 5.0 3.3 - 20.7 STW-782 WATER Jan,1997 Sr-90 24.0 1.0 25.0 5.0 16.3 - 33.7 STW-783 WATER Jan,1997 Gr. Alpha 10.0 1.4 5.2 5.0 0.0 - 13.9 STW-783 WATER Jan,1997 Gr. Beta 15.8 2.0 14.7 5.0 6.0 - 23.4 STW-784 WATER Feb,1997 I-131 86.0 2.0 86.0 9.0 70.4 - 101.6 STW-784 WATER Feb,1997 I-131 79.3 i 2.0 86.0 9.0 70.4 - 101.6 STWW-786 WATER Feb,1997 Ra-226 6.710.2 5.9i0.9 4.3 - 7.5 STWW-706 WATER Feb,1997 Ra-228 8.4il.1 8.2 2.1 4.6 - 11.8 STWW-786 WATER Feb,1997 Uranium 26.511.3 27.0 3.0 21.8 - 32.3 STW-787 WATER Mar,1997 H-3 ,

7,594.0 279.7 7,900.0 i 790.0 6,529.4 - 9,270.6 STW-794 WATER Apr,1997 Gr. Alpha 44.3 1.6 48.0112.0 27.2 - 68.8 STW-794 WATER Apr,1997 Ra-226 10.7i 0.9 13.0 2.0 9.5 - 16.5 STW-794 WATER Apr,1997 Ra-228 4.710.4 3.1 0.8 1.7 - 4.5 All raw data and calculations were reviewed for arrors. The analysis was repeated with the technician observed by the lab supervisor; the result of the reanalysis 3.110.5 pCi/L. The suspected cause of the higher result was the lower than expected recovery of barium tracer. No further action is planned at this time.

STW-794 WATER Apr,1997 Uranium 26.8 0.3 24.0 3.0 18.8 - 29.2 STW-795 WATER Apr,1997 Co-60 21.7 i 0.6 21.0 5.0 12.3 - 29.7 STW-795 WATER Apr,1997 Cs-134 27.3 i 1.2 31.015.0 22.3 - 39.7 STW-795 WATER Apr,1997 Cs-137 21.7i l.5 22.015.0 13.3 - 30.7 STW-795 WATER Apr,1997 Gr. Beta 98.2 2.1 102.1 1 15.3 75.6 - 128.6 STW-795 WATER Apr,1997 Sr-89 21.3 i 1.2 24.0 i 5.0 15.3 - 32.7 STW-795 WATER Apr,1997 Sr-90 12.7 i 0.6 13.0 i 5.0 4.3 - 21.7 STW-796 WATER Jun,1997 Ba-133 24.711.2 25.0 5.0 16.3 - 33.7 STW-796 WATER Jun,1997 Co-60 18.7 0.6 18.0i5.0 9.3 - 26.7 STW-796 WATER Jun,1997 Cs-134 19.7 i 0.6 22.0 5.0 13.3 - 30.7 STW-796 WATER Jun,1997 Cs-137 52.0 i 2.0 49.0 5.0 40.3 - 57.7 STW-796 WATER Jun,1997 Zn-65 101.012.0 100.0 t 10.0 82.7 - 117.3 STW-797 WATER Jun,1997 Ra-226 2.7 0.1 3.0 i 0.5 2.1 - 3.9 STW-797 WATER Jun,1997 Ra-228 2.3i0.3 3.110.8 1.7 - 4.5 STW-797 WATER Jun,1997 Uranium 38.111.0 40.3 i 4.0 33.4 - 47.2 STW-799 WATER Jul,1997 Sr-89 37.7 i 3.2 44.0 5.0 35.3 - 52.7 l STW-799 WATER Jul,1997 St-90 16.011.0 i6.0 5.0 7.3 - 24.7 STW-802 WATER Jul,1997 1-131 10.7 i 1.2 10.0 6.0 0.0 - 20.4 STW-800 WATER Jul,1997 Gr. Alpha 3.1 i 0.3 3.1 5.0 0.0 - 11.8 STW-800 WATER Jul,1997 Gr. Beta 13.910.2 15.1 5.0 6.4 - 23.8 STW-801 WATER Aug,1997 H-3 11,348.7 i 241.4 11,010.0 i l,101.0 9,099.8 - 12,920.2 STW-803 WATER Sep,1997 Ra-226 20.0i0.8 20.0 3.0 14.8 - 25.2 l I Al-1 l

Table A-1. U.S. Environmental Protection Agency's crosscheck program, comparison of EPA and Teledyne's Midwest Laboratory results'.

Concentration in pCi/L6 Lab Sample Date Teledyne Results EPA Resuld Control Code Type Collected Analyeis i2 Sigma

1s, N=1 Limits STW C03 WATER Sep,1997 Ra-228 7.0 i 0.1 8.012.0 4.5 - 11.5 )

STW-803 WATER Sep,1997 Uranium 5.0 0.1 5.1i3.0 0.0 - la3 STW-811 WATER Nov,1997 Ba-133 97.315.0 99.0 10.0 81.7 - 116.3 1 STW-811 WATER Nov,1997 Co-60 28.3i l.7 27.0 5.0 18.3 - 35.7 STW-811 WATER Nov,199'/ Cs-134 9.7i 1.0 10.0 5.0 1.3 - 18.7

- STW-811 WATER Nov,1997 Cs-137 78.0 i 3.5 .74.015.0 65.3 - 82.7 STW-811 WATER Nov,1997 Zn-65 76.7 i 2.1 75.0 i 8.0 61.1 - 88.9

Results obtained by Teledyne Drown Engineering Environmental Services Midwest Laboratory as a participant in the environmental sample crosscheck program operated by the Intercomparison and Calibration Section, Quality Assurance Branch, Environmental Monitoring and Support Laboratory, U.S.

Environmental Protection Agency (EPA), Las Vegas, Nevada.

6 All results are in pCi/L, except for elemental potassium (K) data in milk, which are in mg/L; air filter samples, which are in pCi/ Filter.

Unless otherwise indicated, the TBEESML results are given as the mean 12 standard deviations for three determinations.

d ' USEPA results are presented as the known values and expected laboratory precision (1s,1 determination) and control limits as defined by the EPA.

I' I

1 1

I l

A1-2

)

. 1 i

Table A-2. Crosscheck program results;Thermoluminescent Dosimeters. (TLDs).

)

mR Lab Teledyne Results Known Average 2 Sigma Code TLD Type Date Measurement t 2 Sigma Value 2 Sigma (All Participants) 2nd International Intercomoarison 115-2 CaF : Mn Bulb Apr,1976 Field 17.0i l.9 17.1 16.417.7 115-2 CaF2 : Mn Bulb Apr,1976 Lab 20 4 4.1 21.3 18.8 7.6 Second International Intercomparison of Environmental Dosimeters conducted in April of 1976 by the Health and Safety Laboratory (HASL), New York, new York, and the School of Public Health of the University of Texas, Houston, Texas.

3rd International Intercomoarison 115-3 CaF2 : Mn Bulb Jun,197' Field 30.7 i 3.2 34.9 4.8 31.5 i 3.0 115-3 CaF2 : Mn Bulb Jun,1977 Lab 89.616.4 91.7 14.6 86.2 t 24.0 Third IntemationalIntercomparison of Environmental Dosimeters conducted in the summer of 1977 by Oak Ridge National Laboratory and the School of Public Health of the University of Texas, Houston, Texas.

4th International Intercomoarison 115-4 CaF2 : Mn Bulb Jun,1979 Fie1d 14.1 i 1.1 14.111.4 16.0 9.0 115-4 CaF : Mn Bulb Jun,1979 Lab, High 40.411.4 45.8 9.2 43.9 13.2 115-4 CaF2 : Mn Bulb Jun,1979 Lab, Low 9.8 i l.3 12.2 2.4 12.0 i 7.4 Fourth InternationalIntercomparison of Environmental Dosimeters conducted in the summ'er of 1979 by the School of Public Health of the University of Texas, Houston, Texas. s 5th International Intercomparison 115-5A CaF2 : Mn Bulb Oct,1980 Field 31.4 i 1.8 30.016.0 30.2 i 14.6 115 5A CaF2 : Mn Bulb Oct,1980 Lab,End 96.6 5.8 88.4 8.8 90.7 31.2 115-5A CaF2 : Mn Bulb Oct,1980 Lab, Start 77.4 i 5.8 75.2 t 7.6 75.8 i 40.4 Fifth International Intercomparison of Environmental Dosimeters conductoi in the fall of 1980 at Idaho Falls, Idaho and sponsored by the School of Public Health of the University of Texas, Houston, Texas and the Environmental Measurements Laboratory, New York, New York, U.S. Department of Energy.

5th International Intercomoarison 115-5B LiF-100 Chips Oct,1980 Field 30.3 4.8 30.0 t 6.0 30.2114.6 115-5B LiF-100 Chips Oct,1980 Lab,End 85.4 i 11.7 83.4 i 8.8 90.7 31.2 115-5B LiF-100 Chips Oct,1980 Lab, Start 81.l i 7.4 75.2 i 7.6 75.8 40.4 t Fifth International Intercomparison of Environmental Dosimeters conducted in the fall of 1980 at Idaho Falls, 1

Idaho and sponsored by the School of Public Health of the University of Texas, Houston, Texas and the Environmental Measurements Laboratory, New York, New York, U.S. Department of Energy.

6th International Intercomparison l- 115-6 Teledyne did not participate in the Sixth International Intercomparison of Environmental Dosimeters.

7th International Intercomoarison 115-7A LiF-100 Chips Jun,1984 Field 75.4 2.6 75.816.0 75.l i 29.8 115-7A LiF-100 Chips Jun,1984 Lab, Co-60 80.013.5 79.914.0 77.9 27.6 115-7A LiF-100 Chips Jun,1984 Lab, Cs-137 66.6 i 2.5 75.0 3.8 73.0 i 22.2 l b' 1

l A2-1

l .

l l

Table A-2. Crosscheck program results; Thermoluminescent Dosimeters. (TLDs).

Lab Teledyne Results Known Average 2 Sigma Code TLD Type Date Measurement i 2 Sigma Value 2 Sigma (All Participants)

Seventh 1 international Intercomparison of Environmental Dosimeters cenducted in the spring and summer of 1984 at Las Vegas, Nevada, and sponsored by the U.S. Department of Energy, The Nuclear Regulatory Commission, and the U.S. Environmental Protection Agency.

7th International Intercomoarison 115-7B LiF-100 Chips Jun,19M Field 71.5 2.6 75.8 6.0 75.1 29.8 115-7B LiF-100 Chips Jun,1984 Lab, Co-60 84.8 i 6.4 79.9 4.0 77.9 27.6 115-7B LiF-100 Chips Jun,1984 Lab, Cs-137 78.8 1.6 75.0 i 3.8 73.0 i 22.2 Seventh InternationalIntercomparison of Environmental Dosimeters conducted in the spring and summer of 1984 at Las Vegas, Nevada, and sponsored by the U.S. Department of Energy, The Nuclear Regulatory Commission, and the U.S. Environmental Protection Agency.

7th International Intercomoarison 115-7C CaSO4 : Dy Jun,1984 Field 76.8 i 2.7 75.8 6.0 75.1 29.8 Cards 115-7C CaSO4 : Dy Jun,19M Lab, Co-60 82.5 3.7 79.9 4.0 77.9 27.6 Cards 115 7C CaSO4 : Dy Jun,19M Lab, Cs-137 '79.013.2 75.0 i 3.8 73.0122.2 Cards Seventh International 1ntercomparison of Environmental Dosimeters conducted in the spring and summer of 1984 at Las Vegas, Nevada, and sponsored by the U.S. Department of Energy, The Nuclear Regulatory Commission, and the U.S. Environmental Protection Agency.

8th International Intercomoarison 115-8A LiF-100 Chips Jan,1986 Field, Site 1 29.5 t l.4 29.7 1.5 28.9 12.4 115-8A LiF-100 Chips Jan,1986 Field, Site 2 11.3 0.8 10.4 0.5 10.1 9.1 115-SA LiF-100 Chips Jan,1986 Lab, Cs-137 13.7 i 0.9 17.2 i 0.9 16.216.8 Eighth International Intercomparison of Environmental Dosimeters conducted in the fall and winter of 1985-1986 at New York, New York, and sponsored by the U.S. Department of Energy, 8th International Intercomparison 115-8B LiF-100 Chips Jan,1986 Field, Site 1 32.3i l.2 29.7i l.5 28.9 12.4 115-8B LiF-100 Chips Jan,1986 Field, Site 2 9.0 i l.0 10.4 i 0.5 10.1 9.0 115-8B LiF-100 Chips Jan,1986 Lab, Cs-137 15.810.9 17.2 0.9 16.2 6.8 Eighth International Intercomparison of Environmental Dosimeters conducted in the fall and winter of 1985-1986 at New York, New York, and sponsored by the U.S. Department of Energy.

8th International Intercomnarison 1 115-8C CaSO4 : Dy Jan,1986 Field, Site 1 32.2 0.7 29.7 1.5 28.9 12.4 Cards 115-SC CaSO4 : Dy Jan,1986 Field Site 2 10.6 i 0.6 10.4 i 0.5 10.1 9.0 <

Cards 115-8C CaSO4 : Dy Jan,1986 Lab, Cs-137 18.lio.8 17.2 0.9 16.2 6.8 Cards A2-2

_ __________________j

l Table A-2. Crosscheck program results;Thermoluminescent Dosimeters. (TLDs).

mR Lab Tcledyne Results Known Average i2 Sigma Code TLD Type Date Measurement 2 Sigma Value 2 Sigma (All Participants)

Eighth International Intercomparison of Environmental Dosimeters conducted in the fall and winter of 1985-1986 at New York, New York, and sponsored by the U.S. Department of Energy.

9th International Intercomoarison 115-9 The Ninth International Intercomparison of Environmental Dosimeters was not available to Teledyne's Midwest Laboratory.

10th InternationalJptercomparic.on 115-10A LiF-100 Chips Aug,1993 Field 25.7 t l.4 27.0 1.6 26.4110.2 115-10A LiF-100 Chips Aug,1993 Lab,1 22.7i l.6 25.911.3 25.019.4 115-10A LiF-100 Chips Aug,1993 Lab,2 62.7 i 2.6 72.7 1.9 69.8120.3 The Tenth International Intercomparison of Environmental Dosimeters conducted in 1993 at Idaho State University and sponsored by the U.S. Department of Energy and the Idaho State University.

10th International Intercomparison 115-10B CaSO.: Dy Aug,1993 Field 26.012.3 27.011.6 26.4110.2 Cards 115-10B CaSO.: Dy Aug,1993 Lab,1 24.111,7 25.911.3 25.0194 Cards 115-10B CaSO.: Dy Aug,1993 Lab,2 69.2 i 3.0 72.7 1.9 69.8 20.3 Cards The Tenth International Intercomparison of Environmental Dosimeters conducted in 1993 at Idaho State University and sponsored by the U.S. Department of Energy and the Idaho State University.

lith International Intercomoarison 115-11 Apr,1997 The Eleventh International Intercomparison of Environmental Dosimeters was conducted in 1997 cond was organized by the Department of Energy's Environmental Measurements Laboratory in collaboration with Brookhaven National Laboratory and the National Institute of Standards and Technology.

Results for the Eleventh International Intercomparison were originally reported in error; The results are being re-evaluated and will be reported in a later update.

Teledvne Testing 89-1 LiF-100 Chips Sep,1989 Lab 21.010.4 22.4 ND ND = No Data; Teledyne Testing was only performed by Teledyne.

Chips were irradiated by Teledyne isotopes, Inc., Westwood, New Jersey, in September,1989.

Tcledyne Testing 89-2 CaSO.: Dy Nov,1989 Lab 20.9 i 1.0 20.3 ND i Cards ND = No Data; Teledyne Testing was only performed by Teledyne.

Cards were irradiated by Teledyne Isotopes, Inc., Westwood, New Jersey, in June,1990.

A2-3 l

l

Table A-2. Crosscheck program results; Thermoluminescent Dwimeters. (TLDs).

mR Lab Teledyne Results Known Average 2 Sigma Code TLD Type Date Measurement i 2 Sigma Value 2 Sigma (All Participants)

Teledvne Testing 90-1 CaSO,: Dy Jun,1990 1.ab 20.6 L4 19.6 ND Cards ND = No Data; Teledyne Testing was only performed by Teledyne.

Cards were irradiated by Teledyne Isotopes, Inc., Westwood, New Jersey, in June,1990.

Teledvne Testing 90-2 CaSO.: Dy Jun,1990 Lab 100.8 4.3 100.0 ND Cards ND = No Data; Teledyne Testing was only performed by Teledyne.

Cards were irradiated by Dosimetry Asssociates, Inc., Northville, MI, in October,1990.

Teledyne Testing 91-1 CaSO.: Dy Oct,1990 Lab,1 33.4 i 2.0 32.0 ND Cards 91-1 CaSO4 : Dy Oct,1990 Lab,2 55.214.7 58.8 ND Cards 91 1 CaSO4 : Dy Oct,1990 Lab,3 87.8 6.2 85.5 ND Cards ND = No Data; Teledyne Testing was only performed by Teledyne.

Cards were irradiated by Teledyne Isotopes, Inc., Westwood, New Jersey, in October,1991.

Teledyne Testing 92-1 LIF-100 Chips Feb,1992 Lab,1 11.110.2 ND

( 10.7 l 92-1 UF-100 Chips Feb,1992 Lab,2 25.6 i 0.5 25.4 ND l 92-1 LiF-100 Chips Feb,1992 Lab,3 46.410.5 46.3 ND ND = No Data; Teledyne Testing was only performed by Teledyne.

Chips were irradiated by Teledyne Isotopes, Inc., Westwood, New Jersey, in February,1992.

Teledyne Testing

! 92-2 CaSO : Dy Apr,1992 Reader 1, #1 20.110.1 20.1 ND l Cards l 92-2 CaSO4 : Dy Apr,1992 Reader 1, #2 40.610.1 40.0 ND

t Cards

( 92-2 CaSO : Dy Apr,1992 Reader 1, #3 60.0 i l.3 60.3 ND l Cards 92-2 CaSO,: Dy Apr,1992 Reader 2, #1 20.310.3 20.1 ND i- Cards 92-2 CaSO4 : Dy Apr,1992 Reader 2, #2 39.2 i 0.3 40.0 ND Cards 92-2 CaSO.: Dy Apt,1992 Reader 2, #3 60.710.4 60.3 ND Cards A2-4

i Table A-2. Crosscheck program results;Thermoluminescent Dosimeters. (TLDs).

mR Lab f Teledyne Results Known_ Average 12 Sigma '

Code TLD Type Date Measurement - i 2 Sigma Value 2 Sigma (All Participants)

ND = No Data; Teledyne Testing was only performed by Teledyne.

Cards were irradiated by Teledyne Isotopes, Inc., Westwood, New Jersey, in April,1992.

Teledyne Testing

' 93-1 . Teledyne Mar,1993 Lab,1 10.011.0 10.2 ND LiF-100 Chips 93-1 Teledyne Mar,1993 Lab,2 25.212.2 25.5 ND LiF-100 Chips 93-1. Teledyne Mas,1993 Lab,3' 42.7i 5.7 45.9 ND LiF-100 Chips ND = No Data; Teledyne Testing was only performed by Teledyne.

Chips were irradiated by Teledyne isotopes, Inc., Westwood, New Jersey, in March,1993. Due to a potential error of 10-12% when cards where irradiated, results of the testing on the cards will not be published. Data is available upon request.

Teledyne Testing 94-1 Teledyne Nov,1994 Lab,1 15.610.4 14.9 ND <

LiF-100 Chips {

94 1 Teledyne Nov,1994 Lab,2 30.2 i 0.4 29.8 ND LiF-100 Chips 94-1 Teledyne Nov,1994 Lab,3 59.2 i 0.3 59.7 ND LiF-100 Chips 94-1 CaSO4 : Dy Nov,1994 Reader 1, #1 14.9 i 0.1 14.9 ND Cards 94-1 CaSO,: Dy Nov,1994 Reader 1, #2 30.8 i 0.1 29.8 ND I Cards 94-1 CaSO4 : Dy Nov,1994 Reader 1, #3 58.9 i 0.3 59.7 ND Cards 94-1 - CaSO,: Dy Nov,1994 Reader 2, #1 15.4 i 0.2 14.9 ND Cards 94-1 CaSO : Dy Nov,1994 Reader 2, #2 31.4 i 0.2 29.8 ND Cards 94-1 CaSO i Dy Nov,1994 Reader 2, #3 60.1 i 0.3 59.7 ND Cards

ND = No Data;Teledyne Testing was only performed by Teledyne.

Cards were irradiated by Teledyne Isotopes, Inc., Westwood, New Jersey, in November,1994.

Teledyne Testing 95-1 LiF-100 Chips Mar,1995 Lab,1 16.110.2 15.7 95-1 LiF-100 Chips Mar,1995 Lab,2 31.710.1 32.3 95-1 LiF-100 Chips Mar,1995 Lab.-3 59.710.6 60.8 95 1 CaSO.: Dy Mar,1995 Reader 1, #1 16.4 i 0.1 15.7 ND Cards A2-5 l l

l

Table A-2. Crosscheck program results;Thermoluminescent Dosimeters. (TLDs).

mR Lab Teledyne Results Known Average 2 Sigma Code TLD Type Date Measurement i 2 Sigma Value i 2 Sigma (All Participants) 95-1 CaSO : Dy Mar,1995 Reader 1, #2 34.9 i 0.1 32.3 ND Cards 95-1 CaSO.: Dy Mar,1995 Reader 1, #3 64.4 i 1.5 60.8 ND Cards ND = No Data; Teledyne Testing was only performed by Teledyne.

Cards and Chips were irradiated by Teledyne Isotopes, Inc., Westwood, New Jersey, in March,1995.

Teledvne Testing 95-2 CaSO.: Dy Mar,1995 Reader 2, #1 16.4 i 0.2 15.7 ND Cards 95-2 CaSO : Dy Mar,1995 Reader 2, #2 33.9 i 0.4 32.3 ND Cards 95-2 CaSO : Dy Mar,1995 Reader 2, #3 60.510.3 60.8 ND Cards ND = No Data; Teledyne Testing was only performed by Teledyne.

Cards and Chips were irradiated by Teledyne Isotopes, Inc., Westwood, New Jersey, in March,1995.

Teledyne Testing 96-1 LiF-100 Chips Mar,1996 Lab,1 15.9 i 0.3 15.4 96-1 LiF-100 Chips Mar,1996 Lab,2 29.4 i 0.3 30.8 96-1 LiF-100 Chips Mar,1996 Lab,3 62.5 i 1.3 62.5 96-1 CaSO : Dy Mar,1996 Reader 1, #1 14.410.1 15.4 ND Cards 96-1 CaSO : Dy Mar,1996 Reader 1, #2 31.8 i 0.1 30.8 ND Cards 96-1 CaSO.: Dy Mar,1996 Reader 1, #3 64.7 i 0.4 62.5 ND Cards Teledvne Testing 96-2 CaSO : Dy Mar,1996 Reader 2, #1 14.3 0.4 15.4 ND Cards 96-2 CaSO.: Dy Mar,1996 Reader 2, #2 31.810.1 30.8 ND Cards 96-2 CaSO.: Dy Mar,1996 Reader 2, #3 68.6 i 0.1 62.5 ND Cards ND = No Data; Teledyne Testing was only performed by Teledyne.

Chips and Cards were irradiated by Teledyne Isotopes, Inc., Westwood, New Jersey, in March,1996.

Teledyne Testing 97-1 LiF-100 Chips Mar,1997 Lab,1 13.4 i 1.4 15.0 j 97-1 LiF-100 Chips Mar,1997 Lab,2 29.8 0.6 30.1 l

97-1 LiF-100 Chips Mar,1997 Lab,3 63.4 i 0.9 60.2 {

l l

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l.

Table A-2. Crosscheck program results; Thermoluminescent Dosimeters. (TLDs).

mR Lab' .

. Teledyne Results Known Average 12 Sigma Code TLD Type Date Measurement i 2 Sigma Value 2 Sigma (All Participants) 97-1 CaSO4 : Dy. Mar,1997 Reader 1, #1 15.5 i 0.1 15.0 ND Cards 97-1 CaSO4 : Dy Mar,1997. Reader 1, #2 34.0 0.1 30.1 ND Cards 97-1 CaSO8 Dy Mar,1997 Reader 1, #3 68.3 i 2.1 60.2 ND Cards l

Teledvne Testing l

97-2 CaSO8 Dy . Mar,1997 Reader 2, #1 16.8103 15.0 ND Cards 97-2 ' CaSO4 : Dy Mar,1997 Reader 2, #2 - 36.210.2 30.1 ND Cards 97-2 CaSO4 Dy Mar,1997 . Reader 2, #3 69.610.2 60.2 ND Cards ND = No Data;Teledyne Testing was only performed by Teledyne.

Chips and Cards were irradiated by Teledyne isotopes, Inc., Westwood, New Jersey, in March,1997.

l L

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A2-7 l

Table A-S. In-liouse " spike" samples.

Concentration in pCi/L'

. Lab Sample Date Teledyne Results Known Control' Code Type Collected Analysis 2s, n=1 6 Activity Limits SPW-844 WATER Jan,1997 Th-230 3.120 i 0.104 3.070 1.842 - 4.298 SPW-844 WATER Jan,1997 Th-232 3.355 1 0.108 3.070 1.842 - 4.298 SPW 548 WATER Feb,1997 Gr. Beta 43.881 1.305 41.860 31.860 - 51.860 SPMI-534 MILK Feb,1997 Cs-134 48.649 i 4.940 56.400 46.400 66.400 SPMI-534 MILK Feb,1997 Cs-137 54.700 i 8.450 52.300 42.300 - 62.300 SPMI-535 MILK Feb,1997 Sr-89 49.849 1 7.940 40.030 30.030 - 50.030 SPMI-535 MILK Feb,1997 Sr-90 48.856 i 1.740 50.300 40.240 - 60.360 SPW 536 WATER Feb,1997 H3 27229.744 1 452.056 28234.000 22587.200 - 33880.800 SPW-547 WATER Feb,1997 Co-60 65.219 i 8.790 62.950 52.950 - 72.950 SPW 547 WATER Feb,1997 Cs-134 52.996 t 8.000 56.430 46.430 - 66.430 SPW 547 WATER Feb,1997 Cs-137 60.419 1 12.900 52.320 42.320 - 62.320 SPW-600 WATER Feb,1997 l-131 72.182 1 1.009 66.300 53.040 - 79.560 SPW-600 WATER Feb,1997 1-131(g) 68.816 i 14.800 66.300 39.780 - 76.300 SPCH-701 CH AL Feb,1997 I-131(g) 1.171 1 0.023 1.080 0.648 - 1.512 ER SPAP-704 AIR FILTER Feb,1997 Gr. Beta 6.302 i 0.041 5.740 0.000 - 15.740 SPW-838 WATER Feb,1997 Ra-226 19.770 i 0.189 17.300 12.110 - 22.490 SPW-838 WATER 'Feb,1997 Ra 228 36.784 2.571 31.300 21.910 - 40.690 SPW-840 WATER Feb,1997 - Sr 90 35.822 1 2.020 33.520 26.816 - 40.224 SPW-841 WATER Feb,1997 I-129 15.525 0.854 14.942 2.942 - 26.942 SPW-843 WATER Feb,1997 Fe-55 1.418 i 0.530 1.535 0.000 - 21.535 SPAP-2730 AIR FILTER Mar,1997 Cs-137 2.151 1 0.025 1.900 1.140 - 2.660 SPMI-1670 MILK Apr,1997 Cs-134 50.282 1 8.920 53.600 43.600 - 63.600 SPMI-1670 MILK Apr,1997 Cs-137 56.090 i 14.900 52.100 42.100 - 62.100 SPW-2073 WATER Apr,1997 Co-60 54.077 4.280 51.300 41.300 - 61.300 SPW-2073 WATER Apr,1997 Cs-134 47.636 i 4.150 53.200 43.200 - 63.200 SPW-2073 WATER Apr,1997 Cs-137 60.688 1 5.760 52.100 42.100 - 62.100 SPW 2075 - WATER Apr,1997 Gr. Alpha 34.554 2.677 41.300 20.650 - 61.950 SPW-2075 WATER Apr,1997 Gr. Beta 38.729 i l.658 41.700 31.700 - 51.700 SPW-2546 WATER Apr,1997 H-3 25445.478 1 428.384 26257.000 21005.600 - 31508.400 SPF-3434 ' FISH May,1997 Cs-134 0.199 i 0.020 0.222 0.133 - 0.311 SPF-3434 FISH May,1997 Cs-137 0.234 i 0.037 0.227 0.136 - 0.318 SPW-3750 WATER Jun,1997 l-131' 76.174 1 0.776 71.800 57.440 - 86.160 SPW-3750 WATER Jun,1997 . 1-131(g) 66.587 1 8.750 71.800 43.080 - 81.800 l SPMI-3752 MILK Jun,1997 1-131 79.851 i 0.833 71.800 57.440 - 86.160

. SPMI-3752 - MILK Jun,1997 I-131(g) 78.887 i 7.750 71.800 43.080 - 81.800 SPCH-3754 CA AL Jun,1997 I-131(g) 81.869 i 0.317 76.600 45.960 - 86.600 R

SPMI-4216 MILK Jul,1997 Cs 134 38.265 1 5.450 39.500 29.500 - 49.500 SPMI-4216 MILK Jul,1997 Cs-137 46.472 10.600 41.500 31.500 51.500 SPMl-4216 MILK Jul,1997 I131 75.247 1 0.831 83.230 66.584 - 99.876 SPMI-4216 MILK Jul,1997 1131(g) 84.872 1 7.010 83.230 49.938 - 93.230 A3-1

4 Table A-3. In-house " spike" samples.

Concentration in pCi/L' Lab Sample Date Teledyne Results Known Control' Code Type Collected Analysis 2s, n=1" Advity Limits SPMI-4216 hilLK Jul,1997 Sr-90 33.610 1 1.430 33.210 26.568 - 39.852 SPW-4420 WATER Jul,1997 Co-60 26.270 4.360 24.900 14.900 - 34.900 SPW-4420 WATER Jul,1997 Cs-134 36.591 5.040 39.540 29.540 - 49.540 SPW-4420 WATER Jul,1997 Cs-137 45.552 i 7.770 41.480 31.480 - 51.480 SFW-4420 WA1 ER Jul,1997 I-131(g) 85.221 9.660 83.230 49.938 - 93.230 SPW-4420 WATER Jul,1997 Sr-90 36.285 1 1.629 33.210 26.568 - 39.852 SPMl-4916 hiILK Jul,1997 1-131(g) 84.870 i 7.010 83.230 49.938 - 93.230 SPW-5470 WATER Jul,1997 Fe-55 4.548 i 0.640 5.477 0.000 - 25.477 SPW-5472 WATER Jul,1997 H-3 41026.000 1 329.000 41578.000 33262.400 - 49893.600 SPW-5474 WATER Jul,1997 Gr. Alpha 49.266 1 2.081 41.305 20.653 - 61.958 SPW-5474 WATER Jul,1997 Gr. Beta 44.450 1.334 41.406 31.406 - 51.406 SPF-5476 Fisii Jul,1997 Cs-134 0.641 1 0.030 0.700 0.420 - 0.980 SPF-5476 FISti Jul,1997 Cs-137 0.632 1 0.042 0.527 0.316 - 0.73S SPW-7500 WATER Oct,1997 Co-60 30.424 1 7.530 33.642 23.642 - 43.642 SPW-7500 WATER Oct,1997 Cs-134 37.410 1 6.690 36.086 26.086 - 46.086 SPW-7500 WATER Oct,1997 Cs-137 52.845 i 11.300 41.221 31.221 - 51.221 The Cs-137 spike is suspect. No errors were found in the spectroscopy program and the Cs-134 and Co-60 test results on the same sample were very good. Sample results prepared with a new standard are acceptable.

SPW-7500 WATER Oct,1997 I-131 78.126 1.201 78.302 62.642 - 93.962 SPM1-7505 hilLK Oct,1997 Cs-134 15 '66 i 3.250 18.043 8.043 - 28.043 SPMI-7505 hilLK Oct,1997 Cs-137 91.110 8.370 82.440 72.440 - 92.440 SPMI-7505 hilLK Oct,1997 I-131 73.529 1.253 78.302 62.642 - 93.962 SPMI-7505 hilLK Oct,1997 I-131(g) 74.613 8.810 78.302 46.981 - 88.302 SPMI-7506 hi!LK Oct,1997 Sr-89 31.281 i 4.601 39.490 29.490 - 49.490 SPCH-7727 CliARCOAL Oct,1997 1-131(g)

CANISTER 0.450 i 0.050 0.440 0.264 - 0.616 SPAP-7730 AIR FILTER Oct,1997 Gr. Beta 3.080 i 0.030 3.040 1.824 - 4.256 (ss)

SPF-8485 FISti Nov,1997 Cs-134 0.306 0.025 0.318 0.191 - 0.445 SPF-8485 FISti Nov,1997 Cs-137 0.738 1 0.049 0.649 0.389 - 0.909 SPW-9315 WATER Nov,1997 Gr. Alpha 51.420 i 6.385 41.280 20.640 - 61.920 SPW-9315 WATER Nov,1997 Gr. Beta 48.938 i 3.735 43.164 33.164 - 53.164 SPW-9706 WATER Dec,1997 Gr. Alpha 40.4801 4.598 41.280 20.640 - 61.920 SPW-9853 WATER Dec,1997 Co-60 44.900 1 8.290 42.080 32.080 - 52.0S0 SPW-9853 WATER Dec,1997 Cs-134 40.010 7.010 37.850 27.850 - 47.850

All results are in pCi/L, except for elemental potassium (K) in milk, which are in mg/L., air filter samples, which are in pCi/ Filter; and food products, which are in mg/kg.

" All samples are the results of single determinations.

Control limits are based on Attachment A, page A2 of this report.

!40TE: For fish, Jello is used for the spike matrix. For vegetation, Sawdust is used for the spike matrix.

A3-2

Table A-4. In-house " blank" samples.

Concentration pCi/L*.

Teledyne Results Acceptance Lab Sample Sample (4.66 Sigma) Criteria Code Type Date Analysis LLD Activit y (4.66 Sigma)

SPW-845 WATER Jan 1997 Th-228 <0.9 -0.263 1 0.560 <1.000 SFW-845 WATER Jan 1997 Th 230 <0.2 0.191 0.236 <1.000 SPW-845 WATER Jan 1997 Th-232 <0.2 -0.018 0.145 <1.000 SPMl-533 M1LK Feb 1997 Cs-134 <2.7 -0.531 0.647 < 10.000 SPMl-533 MILK Feb 1997 Cs-137 <5.5 0.526 i 3.380 < 10.000 SPW-2 WATER Feb 1997 Ra-226 <0.1 0.000 1 0.034 <1.000 SPMI-533 MILK Feb l997 1-131 <0.5 -0.031 1 0.316 <0.500 SPMI-533 MILK Feb l997 Sr-89 <0.7 -0.994 i 0.952 < 5.000 SPMl-533 M1LK Feb 1997. Sr-90 N/A 1.695 t 0.439 <1.000 Low level of Sr-90 concentration in milk (1-5 pCi/L) is not unusual.

SPW-537 WATER - Feb 1997 Co-60 <3.1 0.065 0.179 < 10.000 SPW 537 WATER Feb l997 Cs-134 <3.5 0.905 1.100 < 10.000 SPW-537 WATER Feb l997 Cs-137 < 1.7 -1.430 1.800 < 10.000 SPW-537 WATER Feb l997 Gr. Alpha <0.4 -0.109 0.218 <1.000 SPW 537 WATER Feb l997 Gr. Beta <0.9 -0.155 i 0.596 < 3.200 SPW-537 WATER Feb 1997 I-131 <0.4 -0.275 i 0.235 < 0.500 SPW-537 WATER Feb l997 Sr-89 <0.8 -0.167 1 0.557 < 5.000 SPW-537 WATER Feb 1997 St-90 <0.5 0.099 0.239 <1.000 SPW-842 WATER Feb 1997 Fe-55 <0.7 -0.403 0.374 < 1000.000 SPW-842 WATER Feb l997 I-129 <0.9 -0.129 1 0.442 <1.500 SPW-842 WATER Feb l997 Ra-226 <0.04 0.013 0.026 <1.000 SPAP-2731 AIR FILTER Mar 1997 Co-60 <2.5 0.000 i 0.000 < 10.000 SPAP-2731 AIR FILTER Mar 1997 Cs-134 <2. 6 -0.000 1 0.000 < 10.000 SPAP-2731 AIR FILTER Mar 1997 Cs-137 <2.9 0.000 0.001 < 10.000 SPMI-1669 MILK Apr1997 Cs-134 <5.5 0.069 i 0.118 < 10.000 SPMI 1669 MILK Apr1997 Cs-137 <3.8 0.717 2.480 < 10.000 SPW-2074 WATER Apr1997 Co-60 <3.6 0.857 1 8.380 < 10.000 SPW-2074 WATER Apr1997 Cs-134 <4.7 1.610 1 10.200 < 10.000 J SPW-2074 WATER Apr1997 Cs-137 <5.0 1.800 1 3.200 < 10.000 SPW 2074 WATER Apr1997 Gr. Alpha <0.5 0.119 0.307 <1.000 j SPW-2074 WATER Apr 1997 Gr. Beta < 1.3 0.464 1 0.720 < 3.200 i SPW-2547 WATER Apr1997 H 3 < 150 12.822 75.126 < 200.000 SPW-5 WATER May 1997 Ra-226 <0.03 -0.053 0.025 <1.000 ,

SPF-3435 FISH May 1997 Cs-134 <0.015 -0.014 2 0.002 < 10.000 l

SPF-3435 FlSH May1997 Cs-137 <0.016 0.001 0.011 < 10.000 SPW-6 WATER Jun1997 Ra-226 <0.04 -0.044 0.027 <1.000 A4-1 j

i i

Table A-4. In-house " blank" samples.

Concentration pCi/L".

, Teledyne Results Acceptance i Lab Sample Sample (4.66 Sigma) Criteria Code Type Date Analysis LLD Activity" (4.66 Sigma) l SPW-3751 WATER Jun1997 I131 <0.3 -0.127 0.145 <0.500 SPMI-3753 MILK Jun1997 1-131 <0.3 0.089 0.167 <0.500 SPCH-3755 CHARCOAL Jun1997 I-131(g) <0.017 0.010 0.009 < 9.600 CANISTER SPMI-4217 MILK Jul1997 Co-60 <4.8 -0.392 1.230 < 10.000 SPMI-4217 MILK Jul1997 Cs-134 <3.0 -0.874 1.700 < 10.000 SPMI-4217 MILK Jul1997 Cs-137 <5.9 1.600 3.43n < 10.000 SPMI-4217 MILK Jul1997 1-131 <0.3 -0.049 0.171 < 0. iOO SPW-4421 WATER Jul1997 Co-60 < 1.9 -4.660 4.750 < 10.000 SPW-4421 WATER Jul1997 Cs-134 <4.7 -1.450 3.090 < 10.000 SPW-4421 WATER Jul1997 Cs-137 <6.7 0.739 t 4.550 < 10.000 SPMI-4217 MILK Jul1997 Sr-89 < 1.5 -0.165 1.901 <5.000 SPMI-4217 MILK Jul1997 Sr-90 N/A 1.677 0.418 <1.000 Low level of Sr-90 concentration in milk (1-5 pCi/L) is not unusual.

SPW-4421 WATER Jul1997 Sr-89 < 1.7 0.917 1.547 < 5.000 SPW-4421 WATER Jul1997 Sr-90 <0.6 0.341 0.332 <1.000 SPW-5471 WATER Jul1997 Fe 55 <733 48.157' 44S.317 < 1000.000 SPW-5473 WATER Jul1997 H-3 <161 22.700 5S.200 < 200.000 SPW-5475 WATER Jul1997 Gr. Alpha <0,6 0.170 0.425 <1.000 SPW-5475 WATER Jul1997 Gr. Beta <0.5 0.173 0.473 < 3.200 SPF-5477 FISH Jul1997 Co-60 <0.011 -0.001 0.002 < 10.000 SPF-5477 FISH Jul1997 Cs-134 <0.015 0.005 0.008 < 10.000 SPF-5477 FISH Jul1997 Cs-137 <0.018 0.006 2 0.010 < 10.000 SPW-7501 WATER Oct 1997 1-131 <0.4 0.010 0.009 < 0.500 SPW-7504 WATER Oct 1997 Sr-89 <1.1 -0.650 1 0.800 < 5.000 SPW-7504 WATER Oct 1997 Sr-90 <0.4 0.150 0.210 <1.000 SPMI-7507 MILK Oct 1997 Co-60 <6.2 -1.190 1.620 < 10.000 SPMI-7507 MILK Oct 1997 Cs-134 <4.9 1.710 1.950 < 10.000 SPMl-7507 MILK Oct 1997 Cs-137 <6.5 -0.232 3.740 < 10.000 SPMI-7507 MILK Oct 1997 1-131 <0.3 -0.022 0.157 < 0.500 SPMI-7507 MILK Oct 1997 Sr-89 < 1.0 0.862 1.107 <5.000 )

SPMI 7507 MILK Oct 1997 Sr-90 N/A 1.031 0.319 <1.000 Low level of Sr-90 concentration in milk (1-5 pCi/L) is not unusual.

RA-W-11 WATER Dec1997 Ra-228 <0.7 0.134 0.318 <1.000 SPW-9852 WATER Dec1997 Co-60 <2.4 -1.600 9.460 < 10.000 i SPW 9852 WATER Dec1997 Cs-134 <5.7 -0.450 2.340 < 10.000 A4-2

Table A 4. In-house " blank" samples.

Concentration pCi/ L'.

Teledyne Results Acceptance Lab Sample Sample (4.66 Sigma) Criteria l- Code Type Date Analysis LLD Activity" (4.66 Sigma) _

SPW-9852 WATER Dec1997 Cs-137 <6.0 2.190 1 3.550 < 10.000

' Liquid sample results are reported in pCi/ Liter, air filter sample results are in pCi/ filter, charcoal sample results are in pCi/ charcoal, and solid sample results are in pCi/ kilogram.

l ~

The activity reported is the net activity result.

l l

l A4-3

Table A-5. In-house " duplicate" samples.

Concentration in pCi/L' Lab Sample First Second Averaged Cocies* Date Analysis Result Result Result SW - 42,43 Jan,1997 Gr. Beta 3.0753 1 0.9097 2.5036 0.8819 2.7894 i 0.6335 MI 63,64 Jan,1997 Co-60 0.8960 1 2.5500 0.8290 1.4300 0.8625 1.4618 MI- 63,64 Jan,1997 Cs 137 0.4480 i 2.0600 0.7240 1.3800 0.5S60 1.2398

~

MI - 19,20 Jan,1997 Co-60 2.7900 i 2.6200 1.4300 2.4700 2.1100 1.8004 MI- 19,20 Jan,1997 Cs-137 -0.8750 i 2.7600 2.3900 1 1.9100 0.7575 1.6782 MI - 92,93 Jan,1997 I-131 0.0455 i 0.2124 0.1031 0.2405 0.0743 0.1604 MI - 92,93 Jan,1997 K-40 1,466.8000 i 129.0000 1,417.3000 163.0000 1,442.0500 i 103.9351 WW - 116,117 Jan,1997 I-131 0.1299 i 0.2579 -0.0824 0.2359 0.0237 0.1747 LW - 146,147 Jan,1997 Co-60 -0.1850 1 0.4500 1.9100 16.9000 0.8625 8.4530 LW - 146,147 Jan,1997 Cs-137 -0.8360 1 2.1600 0.2350 i 3.4500 -0.3005 i 2.0352 LW - 146,147 Jan,1997 Gr. Beta 6.9782 1.4082 7.8900 1.5599 7.4341 1.0507 LW - 224,225 Jan,1997 Co-60 1.8300 i 4.2500 -1.2200 0.9290 0.3050 2.1752 LW - 224,225 Jan,1997 Cs-137 -0.9650 i 3.4000 1.4500 i 1.7100 0.2425 i 1.9029 LW - 224,225 Jan,1997 Gr. Beta 6.2889 1.3951 7.3610 1.5370 6.8250 i 1.0379 WW - 322,323 Jan,1997 H-3 -5.4270 1 80.6586 -14.4721 i 80.2518 -9.94v6 i 56.8906

- CW - 355,356 Jan,1997 Gr. Beta 3.1262 1 1.4281 2.0589 1.4561 2.5926 1.0198 CW - 355,356 Jan,1997 Gr. Beta -0.3849 1 1.2993 0.4440 1.3725 0.0296 0.9450 CW - 299,300 Jan,1997 Gr. Beta 2.4965 i 1.0877 2.7913 i 1.4707 2.6439 i 0.9146 CW - 299,300 Jan,1997 Gr. Beta 0.2070 i 1.3507 0.7394 i 1.3967 0.4732 0.9715 SW - 441,442 Jan,1997 Co-60 -0.2460 i 1.3100 0.3250 1 0.3190 0.0395 1 0.6741 SW - 441,442 Jan,1997 Cs-137 0.0619 1 2.3900 3.0200 2.8400 1.5410 i l.8559 SWU 389,390 Jan,1997 Gr. Beta 2.7555 i 0.5392 2.6585 i 0.5182 2.7070 0.3739 SWU - 389,390 Jan,1997 H-3 158.6398 i 94.8968 125.0455 i 93.5661 141.8427 66.6333 MI - 377,378 Jan,1997 I-131 0.1482 i 0.2260 0.0950 i 0.2541 0.1216 i 0.1700 MI- 377,378 Jan,1997 K-40 1,379.5000 i 122.0000 1,304.8000 1 113.0000 1,342.1500 83.1460 MI- 377,378 Jan,1997 Sr-89 -0.4172 i 0.8436 -0.2671 i 0.7827 -0.3421 i 0.5754 MI- 377,378 Jan,1997 Sr-90 0.9881 i 0.3785 1.0431 i 0.3340 1.0156 0.2524 CW - 416,417 Jan,1997 Gr. Beta 3.7493 i 1.2558 4.5363 1.1489 4.1428 i 0.8510 CW - 416,417 Jan,1997 Gr. Beta 0.1479 i 1.3455 0.6807 1.3926 0.4143 i 0.9682 PW - 607,608 Jan,1997 Co-60 -0.4870 t 0.6140 0.8310 2.4300 0.1720 i 1.2532 60 , an Gr ea 5.73 i 78 6 5.6550 3 CW - 846,847 Jan,1997 Gr. Alpha 0.0484 i 0.4520 0.6758 0.4786 0.3621 0.3292 CW - 846,847 Jan,1997 Gr. Beta 1.3287 1 0.5381 2.1250 1 0.5415 1.7268 1 0.3817 CW - 846,847 Jan,1997 H-3 1,518.5023 131.0155 1,631.7608 134.0877 1,575.1316 i 93.7344 CW - 846,847 Jan,1997 Sr-89 0.3800 i 0.5210 0.7406 0.8976 0.5603 0.5189 CW - 846,847 Jan,1997 Sr-90 0.1424 i 0.2458 0.7292 1 0.3717 0.4358 i 0.2228 l

A5-1 L

Table A-5. In-house " duplicate" samples.

Concentration in pCi/L' Lab Sample First Second Averaged Codes

Date Analysis Result Result Result WW - 576,577 Feb,1997 H-3 150.9770 i 84.0813 241.2023 87.8687 196.0897 60.8083 MI - 486,487 Feb,1997 I-131 -0.0797 1 0.1694 -0.1161 0.1703 -0.0979 0.1201 MI - 486,4S7 Feb,1997 K-40 1,278.2000 167.0000 1,316.5000 141.0000 1,297.3500 109.2817 MI- 486,487 Feb,1997 Cr-89 -0.8027 1 0.9962 -0.4554 0.9484 -0.6290 0.6877 MI - 486,487 Feb,1997 Sr-90 1.8013 0.4825 1.4892 0.4537 1.6453 0.3312 MI - 510,511 Feb,1997 Co-60 0.6890 i 1.0200 -2.2000 4.1400 -0.7555 2.1319 MI - 510,511 Feb,1997 Cs-137 0.7830 1 2.6300 2.2400 3.2800 1.5115 2.1021 M! - 510,511 Feb,1997 I-131 0.0764 i 0.2227 0.0373 0.2345 0.0568 1 0.1617 MI 531,532 Feb,1997 I-131 0.0368 0.1942 0.0045 i 0.2095 0.0161 0.1429 MI - 531,532 Feb,1997 K-40 1,300.3000 i 178.0000 1,48S.5000 156.0000 1,394.4000 118.3427 CW - 554,555 Feb,1997 Gr. Beta 3.6552 i 1.5170 2.7825 1.4922 3.2189 1 1.0639 i CW - 554,555 Feb,1997 Gr. Beta 0.5033 i 1.0364 0.2368 0.9931 0.1332 0.7177 MI - 632,633 Feb,1997 I-131 -0.2709 1 0.2349 0.1024 0.1676 -0.1867 0.1443 MI- 632,633 Feb,1997 K-40 1,408.0000 165.0000 1,243.1000 145.0000 1,325.5500 109.8294 MI- 723,724 Feb,1997 I-131 -0.0581 0.2376 0.2433 0.2658 0.0926 i 0.1783 M1 - 723,724 Feb,1997 K-40 1,574.6000 i 218.0000 1,396.8000 162.0000 1,485.8000 135.8013 LW - 757,758 Feb,1997 Gr. Beta 3.7439 1 0.9482 4.0547 0.9711 3.8993 0.6786 CW - 883,884 Feb,1997 Gr. Beta 1.2996 1.2901 2.335S 1.3877 1.8177 0.9474 DW - 1030,1031 Feb,1997 Gr. Beta 2.0791 0.4817 2.0596 i 0.5098 2.0694 0.3507 DW - 1030,1031 Feb,1997 I-131 -0.1816 i 0.3127 -0.1217 i 0.3071 -0.1517 i 0.2192 SWU - 929,930 Feb,1997 Gr. Beta 2.4729 i 0.6238 2.9908 0.6691 2.7319 0.4574 SWU - 929,930 Feb,1997 H3 170.1477 i 84.5878 202.2735 85.9328 186.2106 60.2900 WW - 979, 980 Feb,1997 H-3 102.1168 1 92.0531 12.4533 i 8S.3392 57.2850 63.7918 SW - 1370,1371 Feb,1997 H-3 50.6979 i 78.8916 -8.0656 76.2734 21.3161 i 54.8669 LW - 953,954 Mar,1997 Co-60 0.7490 i 1.7500 -1.3300 3.8800 -0.2905 i 2.1282 LW - 953,954 Mar,1997 Cs-137 -0.3220 i 2.2800 1.5500 2.7200 0.6140 1.7746 LW - 953,954 Mar,1997 Gr. Beta 3.7343 i l.0079 4.6558 0.9898 4.1951 0.7063 SW - 1036,1037 Mar,1997 Gr. Beta 1.7736 i 0.7279 2.1268 0.7453 1.9502 0.5209 SW - 1576,1577 Mar,1997 H3 219.6612 i 84.0956 250.7943 i 85.3666 235.2277 59.9156 SW - 1576,1577 Mar,1997 Sr-89 -0.5258 i l.1183 -0.6149 0.9822 -0.5704 0.7442 SW - 1576,1577 Mar,1997 Sr-90 0.6723 i 0.3462 0.7181 0.3074 0.6952 0.2315 MI- 1055,1056 Mar,1997 1-131 0.1081 i 0.1729 0.0400 1 0.1677 0.0741 i 0.1204 MI- 1055,1056 Mar,1997 K-40 1,452.9000 i 126.0000 1,530.3000 124.0000 1,491.6000 88.3912 LW - 1120,1121 Mar,1997 Gr. Beta 2.5963 1 0.6078 1.8604 i 0.6077 2.2283 0.4298 MI- 1158,1159 Mar,1997 I-131 0.0239 i 0.2040 0.0708 0.2015 0.0473 i 0.1434 M1 - 1158,1159 Mar,1997 K 40 1,523.5000 i 152.0000 1,418.5000 i 157.0000 1,471.0000 109.2623 CW - 1187,1188 Mar,1997 Gr. Beta 4.8369 i 1.9131 3.4999 i 1 8196 4.1684 i 1.3201 AS-2

Table A-5. In-house " duplicate" samples.

Concentration in pCi/ L' Lab Sample First Second Averaged Codes

Date Analysis Result Result Result CW - 1187,1186 Mar,1997 Gr. Beta 0.1481 i l.5087 -0.0888 1.4896 0.0296 1.0601 LW - 1145,1146 Mar,1997 Co-60 1.5000 1 3.3300 3.6600 6.9500 2.5800 3.8533 LW - 1145,1146 Mar,1997 Cs-137 1.6200 i 3.2500 -0.9330 4.1100 0.3435 2.6199 LW - 1145.1146 Mar,1997 Gr. Beta 4.2278 1 1.2135 3.5675 1.2356 3.8976 1 0.8659 MI - 1275,1276 Mar,1997 I131 -0.0683 1 0.2309 0.3734 0.4565 0.1525 0.255S MI- 1275,1276 Mar,1997 K-40 1,491.1000 i 193.0000 1,754.0000 177.0000 1,622.5500 130.9370 WW - 1309,1310 Mar,1997 H-3 4,282.8089 188.1304 4,034.4635 183.5207 4,158.6362 131.40S6 SWT - 1519,1520 Mar,1997 Gr. Beta 2.5242 t 0.6065 2.0921 0.5846 2.3082 0.4212 WW - 1539,1540 Mar,1997 Gr. Beta 1.2878 i 0.6803 1.8468 0.7043 1.5673 0.4896 WW - 1539,1540 Mar,1997 H-3 -34.4755 72.6445 41.3706 76.1590 3.4476 i 52.6246 DW - 1688,1689 Mar,1997 Gr. Beta 4.5141 1.3660 4.68S6 i 1.2681 4.6013 0.9319 DW - 1688,1689 Mar,1997 I131 -0.1688 0.3758 0.3183 0.3363 0.074S i 0.2522 SW - 2204,2205 Mar,1997 H-3 62.0000 i 152.0000 112.0000 152.0000 87.0000 i 107.4802 CW - 1909,1910 Mar,1997 H-3 435 8375 i 96.4774 430.4271 96.2750 433.1323 i 68.1483 LW - 1931,1932 Mar,1997 H-3 168.9801 i 83.1073 137.7304 81.7913 153.3552 58.3023 CW - 1599,1600 Mar,1997 Gr. Beta 3.4372 i l.5949 3.4464 1 1.5289 3.4418 1.1047 CW - 1599,1600 Mar,1997 Gr. Beta 1.0978 i 0.9656 1.0340 0.9528 1.0659 i 0.6783 AP - 2572,2573 Mar,1997 Co-60 -0.0006 0.0102 -0.0002 0.0002 -0.0004 0.0051 AP - 2572,2573 Mar,1997 Cs-137 0.0008 0.0007 0.0000 0.0005 0.0004 0.0004 SWU - 2045,2046 Mar,1997 St-89 -0.0237 0.7179 0.1072 1 0.6305 0.0417 0.4777 SWU - 2045,2046 Mar,1997 Sr-90 0.3676 i 0.3471 0.1910 0.2933 0.2793 0.2272 MI - 1641,1642 Apr,1997 1131 -0.6675 i 0.3099 -0.5511 0.3244 -0.6093 i 0.2243 MI - 1641,1642 Apr,1997 K-40 1,556.3000 t 111.0000 1,393.1000 160.0000 1,474.7000 97.3666 LW - 1763,1764 Apr,1997 Gr. Beta 2.3656 i 0.8258 2.1732 1 0.8478 2.2694 1 0.5917 LW - 1763,1764 Apt,1997 H-3 97.1488 i 79.2640 160.3540 82.0162 128.7514 57.0295 AP - 1974,1975 Apr,1997 Sr-89 -0.0001 0.0006 -0.0005 i 0.0015 -0.0003 0.000S AP - 1974,1975 Apr,1997 St-90 0.0001 i 0.0002 0.0001 0.0004 0.0001 1 0.0002 AP - 1994,1995 Apr,1997 Co-60 -0.0003 1 0.0013 0.0002 0.0007 -0.0000 0.0007 AP - 1994,1995 Apr,1997 Cs-134 -0.0001 1 0.0006 -0.0001 0.0016 -0.0001 0.0008 AP *994,1.995 Apr,1997 Cs-137 -0.0002 i 0.0005 -0.0001 0.0005 -0.0002 0.0004 AP - 1994,1995 Apr,1997 I-131(g) -0.0001 1 0.0002 0.0001 0.0002 0.0000 0.0001 AP - 1994,1995 Apr,1997 K-40 0.0306 1 0.0192 0.0114 0.0180 0.0210 0.0132 WW - 1665,1666 Apr,1997 I-131 -0.4430 i 0.2674 -0.0311 0.2626 -0.2370 0.1874 WW - 1708,1709 Apr,1997 Gr. Beta 1.2245 i 0.6161 1.2858 i 0.6134 1.2551 0.4347 l WW - 1785,1786 .Apr,1997 Gr. Beta 2.9118 i 2.0703 0.3820 1 2.1095 1.6469 1.4779 WW - 1785,1786 Apr,1997 H-3 -19.0365 i 73.7753 -74.4153 i 71.1298 -46.7259 51.2402 WW - 1785,1786 Apr,1997 Sr-89 0.6539 i 0.6546 -0.4951 0.5197 0.0794 0.4179 AS-3

Table A-5. In-house " duplicate" samples.

Concentration in pCi/L' Lab Sample First Second Averaged Codes

Date Analysis Result Result Result WW - 1785,1786 Apr,1997 Sr-90 -0.0023 i 0.2013 0.2468 0.2347 0.1223 0.1546 WW - 1737,1738 Apr.1997 Gr. Beta 15.0355 i 1.5075 15.6924 i 1.6231 15.3640 i 1.1076 WW - 1737,1738 Apr,1997 H-3 13.8405 i 75.2790 -5.1902 i 74.3991 4.3251 i 52.9201 LW - 2848,2849 Apr,1997 Gr. Beta 2.4095 1 0.6377 1.7316 0.5601 2.0706 0.4244 Mi- 1845,1846 Apr,1997 Co-60 0.0309 i 0.0778 -1.8500 22.4000 -0.9096 11.2001 MI- 1845,1846 Apr,1997 Cs-134 0.1600 1 0.1350 0.5860 1 2.2600 0.3730 1.1320 M1 - 1845,1846 Apr,1997 Cs-137 0.7580 i 1.1500 0.6290 2.6700 0.6935 i 1.4536 MI - 1845,1846 Apr,1997 1-131 -0.2586 i 0.2297 -0.0829 i 0.2149 -0.1708 0.1573 MI - 1845,1846 Apr,1997 1-131(g) -0.0707 i 0.2970 -0.7200 i 3.2700 -0.3954 1 1.6417 MI - 1845,1846 Apr,1997 K-40 1,592.5000 1 52.5000 1,559.3000 1 127.0000 1,575.9000 68.7118 MI- 1845,1846 Apr,1997 Sr-89 0.2592 1.3259 -0.3095 i 0.8315 -0.0252 0.7825 MI - 1845,1846 Apr,1997 Sr-90 1.3583 i 0.3573 0.8755 i 0.2294 1.1169 i 0.2123 F - 2175,2176 Apr,1997 Gr. Alpha 0.0245 i 0.0359 0.0672 0.0377 0.0458 0.0260 F - 2175,2176 Apr,1997 Gr. Beta 2.3387 i 0.2713 1.7003 1 0.3684 2.0195 0.2288 F - 2175,2176 Apr,1997 K-40 2.5383 i 0.3610 2.5345 t 0.3640 2.5364 i 0.2563 F - 2175,2176 Apr,1997 Sr-89 0.0003 1 0.0053 0.0021 i 0.0048 0.0012 1 0.0036 F - 2175,2176 Apr,1997 Sr-90 -0.0002 i 0.0018 -0.0003 0.0016 -0.0002 1 0.0012 SWU - 2091, 2092- Apr,1997 Gr. Beta 3 3295 i 0.6698 2.7374 1 0.6670 3.0334 0.4726 SWU - 2091,2092 Apr,1997 H-3 42.6019 i 76.2782 46.1034 1 76.43S8 44.3526 i 53.9936 SWU - 2636,2637 Apr,1997 H-3 17.9011 1 75.4236 92.3927 i 78.7712 55.1469 54.5290 SL - 2432,2433 Apr,1997 K-40 1.8447 1 0 4400 1.6811 1 0.5400 1.7629 0.3483 W W -2462,2463 Apr,1997 Co-60 -0.5320 i 0.7550 0.4650 1 0.7810 -0.0335 0.5431 WW - 2462, 2463 Apr,1997 Cs-137 0.6250 i 3.6500 -1.4600 3.4400 -0.4175 1 2.5078 WW - 2462, 2463 Apr,1997 H-3 19.6154 i 75.4335 -21.9230 73.5027 -1.1538 52.6613 F - 2412,2413 Apr,1997 K-40 3.0009 i 0.1660 3.0594 i 0.1470 3.0302 i 0.1109 LW - 2550,2551 Apr,1997 Gr. Beta 2.0074 i 0.8317 3.6936 i 0.8973 2.8505 0.6117 LW - 2550,2551 Apr,1997 K-40 102.7800 1 55.6000 96.6520 1 54.9000 99.7160 39.0684 SP - 2806,2807 Apt,1997 Gr. Alpha 0.0245 i 0.3861 0.1365 1 0.3720 0.0805 0.2681 l SP - 2806,2807 Apr,1997 Sr-89 -1.4194 i 6.8147 -5.6447i 8.6109 -3.5321 5.4906 SP - 2806,2807 Apr,1997 Sr-90 2.6542 1 2.3158 7.1752 i 2.9780 4.9147 1.8862 PW - 2736,2737 Apr,1997 Co-60 0.1300 1 4.6800 -0.6250 i 9.8400 -0.2475 5.4481 l PW - 2/36,2737 Apr,1997 Cs-137 -0.2740 i 4.2100 1.7400 3.3400 0.7330 1 2.6870 I PW - 2736,2737 Apr,1997 Gr. Beta 2.8037t 1.5036 2.6658 t l.4461 2.7348 i 1.0431 WW - 2712,2713 Apr,1997 H-3 1,482.0205 1 125.6515 1,596.1107 i 128.7524 1,539.0656 1 89.9520 SW - 2657, 2658 May,1997 Gr, Beta 13.2739 1 1.3358 13.1663 1.2719 13.2201 1 0.9222 S O - 2677,2678 May,1997 Cs-137 0.1078 1 0.1000 0.2315 0.0507 0.1697 1 0.0561 S O - 2677, 2678 May,1997 Gr. Alpha 5.5187 i 3.4094 8.3190 1 4.0540 6.9189 i 2.6486 i

A5-4 O____________________._- . _ . - _ _ _ _ _ _

j

Table A-5. In-house " duplicate" samples.

Concentration in pCi/L' l

l Lab Sample First Second Averaged Codes

Date Analysis Result Result Result S O - 2677, 2678 May,1997 Gr. Beta 21.9926 i 2.7808 21.8461 i 3.0806 21.9193 2.0750 S O - 2677, 2678 May,1997 Sr-89 0.0075 i 0.0954 -0.0008 0.0008 0.0034 0.0625 S O - 2677, 2678 May,1997 Sr-90 0.0713 0.0197 0.0642 0.0164 0.0677 0.0128 MI - 2764,2765 May,1997 Co-60 0.0636 i 0.0966 -1.5300 7.2300 -0.7332 3.6153 MI- 2764,2765 May,1997 Cs-137 5.5000 i 5.2800 1.7700 4.9900 3.6350 3.6324 MI - 2764,2765 May,1997 I-131 -0.1635 0.1612 -0.0766 i 0.1452 -0.1201 0.1085 MI - 2828,2829 May,1997 I-131 -0.0153 i 0.2503 -0.0855 1 0.2257 -0.0504 1 0.1685 MI - 2828,2829 May,1997 K-40 1,786.4000 i 126.0000 1,897.0000 1 192.0000 1,841.7000 i 114.8260 G - 2879,2880 May,1997 Co-60 0.0044 1 0.1100 -0.0207 0.2030 -0.0081 i 0.1154 G - 2879,2880 May,1997 Cs-134 0.0081 1 0.0305 -0.0030 0.0133 0.0025 1 0.0166 G - 2879,2880 May,1997 Cs-137 0.0006 i 0.0234 0.0013 1 0.0166 0.0010 0.0143 G - 2879,2880 May,1997 Gr. Deta 6.4712 i 0.2029 6.6206 i 0.1927 6.5459 i 0.1399 G - 2879,2880 May,1997 I-131(g) 0.0093 1 0.0456 0.0220 1 0.6620 0.0157 1 0.3318 G - 2879,2880 May,1997 K-40 6.2539 i 0.8340 5.7979 i 0.7160 6.0259 0.5496 S O - 2904, 2905 May,1997 Co-60 -0.0097 i 0.0201 -0.0021 i 0.0224 -0.0059 0.0150 S O - 2904, 2905 May,1997 Cs-134 0.0348 i 0.0682 0.0208 i 0.1500 0.0278 1 0.0824 S O - 2904, 2905 May,1997 Cs-137 0.2709 i 0.0541 0.2768 i 0.0463 0.2738 0.0356 S O - 2904,2905 May,1997 Gr. Deta 24.4695 2.3915 26.5459 1 2.5962 25.5077 1.7649 S O - 2904, 2905 May,1997 K-40 18.8100 1 1.0100 19.1610 i 0.8920 18.9855 1 0.6738 F - 2926,2927 May,1997 Co-60 0 0071 1 0.0082 -0.0010 1 0.0015 0.0031 i 0.0042 F - 2926,2927 May,1997 Cs-137 -0.0047 i 0.0122 -0.0029 i 0.0088 -0.0038 0.0075 SW - 3008,3009 May,1997 H-3 101.2957 91.5729 123.2634 i 92.4471 112.2795 65.0616 MI- 3050,3051 May,1997 Sr-89 -0.1527 i 0.9022 0.0234 0.8795 -0.0646 0.6300 MI- 3050,3051 May,1997 Sr-90 0.9779 1 0.3707 0.94271 0.3596 0.9603 i 0.2583 F - 3070,3071 May,1997 Co-60 -0.0093 i 0.0979 0.0094 i 0.0303 0.0000 1 0.0512 F - 3070,3071 May,1997 Cs-137 0.0 % 4 i 0.0113 -0.0003 1 0.0078 0.0030 1 0.0069 G - 3090,3091 May,1997 K-40 5.0649 i 0.2170 4.9752 i 0.2830 5.0201 0.1783 MI- 3116,3117 May,1997 I-131 -0.1346 1 0.1762 -0.0964 0.1650 -0.1155 0.1207 F - 3277,3278 May,1997 Gr. Beta 2.9487i 0.1093 3.0022 1 0.1035 2.9755 t 0.0753 F - 3277,3278 May,1997 K-40 2.8485 1 0.2780 2.4647 1 0.3130 2.6566 0.2093 MI - 3232,3233 May,1997 1-131 -0.1723 i 0.2021 -0.2680 1 0.2044 -0.2202 0.1437 MI - 3232,3233 May,1997 K-40 1,550.6000 i 121.0000 1,517.9000 141.0000 1,534.2500 92.9005 BS - 3311,3312 May,1997 Co-60 -0.0035 1 0.0348 -0.0044 0.0031 -0.0039 1 0.0175 BS - 3311, 3312 May,1997 Cs-137 0.0676 1 0.0334 0.0677 0.0297 0.0676 0.0223 F - 3484,3485 May,1997 K-40 2.4582 1 0.3320 1.8380 1 0.2990 2.1481 0.2234 SW - 3533,3534 May,1997 H-3 -95.4129 i 90.4309 -117.7172 1 89.5093 -106.5650 63.6193 WW - 3395, 3396 May,1997 I-131 -0.1507 i 0.1841 -0.0473 1 0.2108 -0.0990 0.1399 A5-5

Table A-5. In-house " duplicate" samples.

Concentration in pCi/L' Lab Sample First Second Averaged Codes

Date Analysis Result Result Result F - 3720,3721 May,1997 K-40 2.6063 1 0.4030 2.6623 i 0.3390 2.6343 1 0.2633

- LW - 3464,3465 May,1997 Co-60 -0.2860 i 1.2700 -0.0583 i 0.0489 -0.1722 1 0.6355 LW - 3464,3465 May,1997 Cs-137 2.4600 i 2.8100 1.5000 i 3.2400 1.9800 i 2.1444 LW - 3464,3465 May,1997 Gr. Beta 3.3532 i 0.9801 3.7723 1 0.9839 3.5628 i 0.6944 SW - 3883,3884 May,1997 H-3 -20.5031 i 87.7694 124.8827 i 93.7412 52.1898 i 64.2084 MI- 3513,3514 Jun,1997 I131 -0.1592 i 0.1592 -0.1028 1 0.1714 -0.1310 1 0.1170 MI- 3513,3514 Jun,1997 K-40 1,560.3000 i 129.0000 1,521.9000 1 179.0000 1,541.1000 1 110.3200 P - 3794,3795 Jun,1997 H-3 109.9207 i 93.1034 24.2198 89.6079 67.0702 i 64.6100 F - 4049,4050 Jun,1997 K-40 2.8350 i 0.3980 3.0237 i 0.2420 2.9294 0.2329 MI- 3903,3904 Jun,1997 I-131 0.1550 i 0.1840 -0.1290 0.1587 0.0130 i o.1215 MI- 3903,3904 Jun,1997 K-40 2,020.1000 i 142.0000 1,822.5000 i 188.0000 1,921.3000 117.8007 VE - 3839,3840 Jun,1997 Gr. Alpha 0.2489 i 0.0857 0.1876 0.0698 0.2183 i o.0553 VE - 3839,3840 Jun,1997 Gr. Beta 4.4859 i 0.4451 4.1281 1 0.4123 4.3070 1 0.3034 VE - 3839,3840 Jun,1997 K-40 5.4016 i 0.3360 4.6783 i 0.4282 5.0400 0.2721 F - 3928,3929 Jun,1997 Co -0.0025 i 0.0121 0.0045 i 0.0034 0.0010 1 0.0063 F - 3928,3929 Jun,1997 Cs-134 0.0050 i 0.0115 -0.0030 i 0.0114 0.0010 1 0.0081 F - 3928,3929 Jun,1997 Cs-137 0.0841 i 0.0225 0.0796 i 0.0286 0.0818 0.0182 F - 3928,3929 Jun,1997 Gr. Beta 2.7146 1 0.0950 2.6357 i 0.0977 2.6752 0.0681 F - 3928,3929 Jun,1997 I-131(g) 0.0206 i 0.0449 0.0158 1 0.0458 0.0182 1 0.0321 F - 3928,3929 Jun,1997 K-40 1.8883 i 0.3970 1.4854 i 0.3780 1.6869 0.2741 SWU - 3980,3981 Jun,1997 Gr. Beta 2.1443 t 0.62% 2.3149 i 0.6407 2.2296 i 0.4460 SWU - 3980,3981 Jun,1997 H 221.0233 i 89.9165 105.6271 i 85.0852 163.3252 i 61.8960 CW - 3948,3949 Jun,1997 Gr. Beta -0.4402 i 1.0747 -0.3764 t 1.1259 -0.4083 i 0.7782 SW - 4150,4151 Jun,1997 H-3 30.4430 i 77.1886 56.0152 i 78.3895 43.2291 55.0 % 8 MI - 4091,4092 Jun,1997 I-131 -0.0475 1 0.1439 -0.0071 1 0.1516 -0.0273 1 0.1045 SWT - 4240,4241 Jun,1997 Gr. Beta 2.1204 1 0.6338 2.8553 1 0.6330 2.4879 i 0.4479 )

SW - 5186,5187 Jun,1997 H-3 190.3311 i 89.7491 192.1730 i S9.8246 191.2521 1 63.4889 DW - 4280,4281 Jun,1997 Gr. Alpha -0.4934 1 0.7635 -0.4930 1 0.7640 -0.4932 i 0.5401 DW - 4280,4281 ' Jun,1997 Gr. Beta 2.0633 i 0.8600 2.0630 1 0.8700 2.0631 1 0.6117 WW - 4811,4812 Jun,1997 H-3 48.4888 i 83.6998 50.3302 i 83.7808 49.4095 59.2133 CW - 5207,5208 Jun,1997 H-3 151.5810 i 88.1060 135.0114 i 87.4113 143.2962 i 62.0552 SW - 4364,4365 - Jun,1997 H-3 83.4415 i 83.9269 94.4046 i 84.4029 88.9230 59.5138 AP - 4983,4984 Jun,1997 Co-60 0.0002 i 0.0009 0.0001 i 0.0007 -0.0000 i 0.0006

- AP - 4983,4984 Jun,1997 Cs-137 0.0003 i 0.0004 -0.0001 1 0.0 07 0.0001 1 0.0004 AP - S004,5005 Jun,1997 Co-60 0.0002 1 0.0002 0.0003 i 0.0003 0.0002 1 0.0004 AP- 5004,5005 Jun,1997 Cs-137 -0.0002 1 0.0004 0.0002 0.0006 -0.0000 1 0.0004 DW - 4484,4485 Jun,1997 Gr. Beta 2.0708 1 0.6272 1.9172 0.5805 1.9940 1 0.4273 I

A5-6 L

Table A-5. In-house " duplicate" samples.

Concentration in pCi/L' Lab Sample First Second Averaged Codes

Date Analysis R< sult Result Result DW - 4484,4485 Jun,1997 H-3 39.2579 i 83.2425 66.8612 84.4541 53.0596 1 59.2913 SW - 4460,4461 Jul,1997 Gr. Beta 1.8471 0.7685 2.2801 0.7788 2.0636 0.5471 DW - 4510,4511 Jul,1997 H-3 1.2216 i 80.7150 21.3772 81.6249 11.2994 57.3967 AP - 4917,4918 Jut,1997 Co-60 0.0002 i 0.0003 0.0002 i 0.0006 0.0002 1 0.0003 AP - 4917,4918 Jul,1997 Cs-134 0.0002 i 0.0003 0.0002 i 0.0052 0.0002 0.0026 AP - 4917,4918 Jul,1997 Cs-137 0.0005 i 0.0004 0.0002 i 0.0004 0.0003 0.0003 AP - 4917,4918 Jul,1997 I-131(g) -0.0009 i 0.0017 0.0022 1 0.0762 0.0006 i 0.0381 AP - 4917,4918 Jul,1997 K-40 0.0239 i 0.0081 0.0305 i 0.0086 0.0272 0.0059 SP - 5024,5025 Jul,1997 Gr. Alpha 0.4224 1 0.9602 1.7836 i 1.2429 1.1030 i 0.7853 SP - 5024,5025 Jul,1997 Sr-90 65.8931 i 7.2660 61.7118 i 6.1959 63.8024 i 4.7745 BS - 4573,4574 Jul,1997 K-40 11.9570 i 0.5550 12.0610 0.5170 12.0090 i 0.3792 WW - 4535, 4536 Jul,1997 Co-60 -0.0955 i 0.4620 1.0800 i 1.5100 0.4923 i 0.7895 WW - 4535,4536 Jul,1997 Cs-137 -0.7200 t 2.3500 0.1650 1 3.3100 -0.2775 1 2.0297 WW - 4535,4536 Jul,1997 H-3 565.2121 1 103.8753 524.7523 102.4326 544.9822 i 72.9426 G - 4745,4746 Jul,1997 Co-60 -0.0147 1 0.1270 -0.0016 i 0.0036 -0.0082 1 0.0635 G - 4745,4746 Jul,1997 Cs-134 0.0055 1 0.0386 -0.0118 1 0.0963 -0.0032 0.0519 G - 4745,474o Jul,1997 Cs-137 0.0057 1 0.0186 0.0132 1 0.0180 0.0095 1 0.0129 G - 4745,4746 Jul,1997 Gr. Deta 5.0148 i 0.1659 4.7792 1 0.1700 4.8970 0.1188 G - 4745,4746 Jul,1997 I-131(g) 0.00 0 i 0.0078 0.0104 1 0.0269 0.0072 1 0.0140 G - 4745,4746 Jul,1997 K-40 4.FI9610.5840 4.1530 0.6150 4.3563 1 0.4241 SWU - 4832,4833 Jul,1997 Gr. Beta 1.7683 i 0.6756 3.4254 0.6591 3.0968 i 0.4719 LW - 4782,4783 Jul,1997 Co-60 2.8200 i 20.3000 -1.9900 i 6.6500 0.4150 10.6807 LW - 4782,4783 Jul,1997 Cs-137 0.6730 i 3.2000 -0.6030 i 2.2500 0.0350 i 1.9559 LW - 4782,4783 Jul,1997 Gr. Beta 4.0046 i 1.0458 3.5274 1 0.9990 3.7660 t 0.7232 MI- 4897,4898 Jul,1997 I-131 -0.0412 1 0.2182 0.0463 1 0.2335 0.0026 i 0.1598 MI - 4897,4898 Jul,1997 K-O 1,531.3000 1 123.0000 1,270.5000 1 152.0000 1,400.9000 1 97.7663 CW - 5150,5151 Jul,1997 Gr. Beta 4.7218 1 1.5818 4.2648 i 1.6666 4.4933 i 1.1488 CW - 5150,5151 Jul,1997 Gr. Beta -0.2253 i 1.0995 0.5464 1.2464 0.1605 0.8310 G - 5296,5297 Jul,1997 K-40 6.8000 1 0.6000 8.2000 1 0.8000 7.5000 i 0.5000 WW - 5369, 5370 Jul,1997 H-3 18,013.8557 i 373.4409 18,133.8988 i 374.6263 18,073.8773 i 264.4820 CW - 5321,5322 Jul,1997 Gr. Beta 1.5612 i 1.4170 1.3507 1 1.2764 1.4560 0.9535 CW - 5321,5322 Jul,1997 Gr. Beta -0.6334 i 1.0849 0.5162 1.2191 -0.0586 i 0.8160 WW - 5348,5349 Jul,1997 H-3 1,763.0308 i 139.9964 1,813.1908 i 141.3214 1,788.1108 99.4620 MI - 5464,5465 Jul,1997 I-131 -0.2555 1 0.2878 -0.3511 1 0.2946 -0.3033 0.2059 MI - 5464,5465 Jul,1997 K-40 1,282.9000 i 143.0000 1,380.0000 1 124.0000 1,331.4500 94.6375 VE - 5506,5507 Jul,1997 Cr. Beta 7.2756 i 0.2197 7.0057 1 0.2090 7.1407 1 0.1516 VE - 5506,5507 Jul,1997 K-40 8.1566 i 0.3970 8.1817 1 0.4360 8.1692 0.2948 l

l A5-7 L__.________-___________________._____________

i

i Table A-5. In-house " duplicate" samples.

1 Concentration in pCi/L' Lab Sample First Second Averaged Code.? Date Analysis Result Result Result WW - 5848,5849 Jul,1997 H3 51.6431i B3.4870 40.4434 82.9847 46.0433 1 58.8569 WW - 552,9, 5530 Aug,1997 Gr. Beta 5.1545 1 2.1632 4.3564 i 1.9691 4.7555 i 1.4626 WW - 5529,5530 Aug,1997 H-3 235.5502 i 91.5917 372.4741 97.6610 304.0122 66.9453 MI- 5606,5607 Aug,1997 I-131 -0.0759 i 0.3043 -0.1020 1 0.3423 -0.0889 i 0.2290 SL - 5563,5564 Aug,1997 Cr. Beta 1.9301 i 0.2206 2.0961 i 0.2125 2.0131 0.1531 SL - 5563,5564 Aug,1997 K-40 1.1254 i 0.3530 1.3185 0.4050 1.2220 1 0.2686 SL - 5563,5564 Aug,1997 Sr-89 -0.0078 0.0216 0.0096 0.0196 0.0009 0.0146 SL - 5563,5564 Aug,1997 Sr-90 0.0097 0.0059 0.0031 1 0.0048 0.0064 0.0038 SW - 5584,5585 Aug,1997 Gr. Deta 2.9875 1 0.7744 2.0205 i 1.0326 2.5040 0.6454 LW - 5678,5679 Aug,1997 Co-60 0.4180 i 1.2900 0.7270 1 1.4500 0.5725 0.9704 LW - 5678,5679 Aug,1997 Cs-134 0.8140 1 0.6510 0.83401 0.4840 0.8240 0.4056 LW - 5678,5679 Aug,1997 Cs-137 1.1400 i 1.1800 0.7750 i 1.1900 0.9575 0.8379 LW - 5678,5679 Aug,1997 Gr. Beta 2.6926 i 0.6727 2.4242 0.6023 2.5584 1 0.4515 LW - 5678,5679 Aug,1997 I-131 -0.1036 1 0.3234 -0.0921 1 0.3371 -0.0979 1 0.2336 LW - 5678,5679 Aug,1997 I-131(g) -10.1000 11.1000 -3.6000 1 5.8200 -6.8500 6.2666 LW - 5678,5679 Aug,1997 K-40 137.0000 i 16.5000 124.0000 17.3000 130.5000 1 11.9535 G - 5653,5654 Aug,1997 K-40 6.0419 i 0.5940 5.5554 1 0.5870 5.7987 1 0.4176 CW - 5759,5760 Aug,1997 Gr. Beta 4.3051 i 1.5501 2.0048 i 1.4570 3.1550 1.0637 CW - 5759,5760 Aug,1997 Gr. Beta -0.5860 1 1.1030 -0.0177 i l.1407 -0.3018 1 0.7934 CW - 5708,5709 Aug,1997 Gr. Beta 1.7190 i 1.4125 1.8843 1 1.4139 1.8017 1 0.9993 MI - 5891,5892 Aug,1997 I-131 0.0000 0.2400 0.1928 1 0.2253 0.0964 1 0.1646 MI - 5891,5892 Aug,1997 K-40 1,438.6000 1 131.0000 1,218.6000 1 175.0000 1,328.6000 i 109.3000 M1 - 5926,5927 Aug,1997 I-131 -0.0311 1 0.1690 -0.1446 1 0.1748 -0.0879 0.1216 MI - 5926,5927 Aug,1997 K-40 1,577.8000 i 216.0000 1,429.9000 i 178.0000 1,503.8500 i 139.9464 SWU - 5972,5973 Aug,1997 H-3 274.7574 i 93.6817 157.2707 i 88.8812 216.0140 i 64.5681 CW - 6013,6014 Aug,1997 Gr. Beta 4.9801 1 1.3048 4.5882 i l.6114 4.7841 i l.0367 CW - 6013,6014 Aug,1997 Gr. Beta -0.5668 i l.0528 -0.6145 1 1.1307 -0.5907 0.7725 SL - 6034,6035 Aug,1997 Co-60 0.0183 1 0.0235 0.0159 1 0.2550 0.0171 i 0.1280 SL - 6034,6035 Aug,1997 Cs-134 0.0046 1 0.0136 0.0015 0.0020 0.0030 0.0069 SL - 6034,6035 Aug,1997 Cs-137 0.0118 i 0.0097 0.0175 1 0.0095 0.0147 i 0.0069 SL - 6034,6035 Aug,1997 Gr. Beta 2.1826 i 0.1949 1.9837 0.1773 2.0831 1 0.1317 SL - 6034,6035 Aug,1997 I-131(g) -0.0039 i 0.0134 0.0013 i 0.0060 -0.0013 0.0073 SL - 6034,6035 Aug,1997 K-40 1.6231 i 0.2940 1.4676 i 0.2750 1.5454 0.2013 CW - 6172,6173 Aug,1997 Gr. Beta 3.2828 1 1.0951 3.7336 i 1.6212 3.5082 1 0.9782 CW - 6172,6173 Aug,1997 Gr. Beta 1.2291 i l.3108 0.0271 1.1175 0.6281 0.8612 CW - 6080,6081 Aug,1997 Gr. Beta 2.4263 i l.5665 4.0378 1 1.5325 3.2321 1.0957 CW - 6080,6081 Aug,1997 Gr. Beta -0.0198 i 1.1927 0.9870 1 1.1701 0.4836 0.8354 A5-8 t_________

Table A-5. In-house " duplicate" samples.

l Concentration in pCi/L' Lab Sample First Second l Averaged l Codes

Date Analysis Result Result Result VE - 6106,6107 Aug,1997 Co-60 0.0021 0.0173 0.0019 0.0087 0.0020 1 0.0097 VE - 6106,6107 Aug,1997 Cs-137 0.0017 i 0.0057 -0.0005 0.0072 0.0006 0.0046 VE - 6149,6150 Aug,1997 Co-60 0.0043 1 0.1740 0.0004 0.0012 0.0024 i 0.0870 i VE - 6149,6150 Aug,1997 Cs-137 -0.0026 i 0.0056 0 0018 0.0060 -0.0004 1 0.0041 MI - 6203,6204 Aug,1997 Co-60 2.3200 i 83.8000 0.7940 i 1.9700 1.5570 1 41.9116 MI - 6203,6204 Aug,1997 Cs-137 0.5560 t 3.0200 1.2900 1 2.6500 0.9230 1 2.00S9

- MI- 6203,6204 Aug,1997 I-131 -0.2456 i 0.3252 -0.1688 i 0.3245 -0.2072 1 0.2297 VE - 6224,6225 Aug,1997 Co-60 -0.0042 i 0.0160 0.0045 1 0.0078 0.0002 1 0.0089 VE - 6224,6225 Aug,1997 Cs-137 -0.0057 i 0.0131 0.0071 i 0.0047 0.0007 0.0070 VE - 6251,6252 Aug,1997 Gr. Deta 3.4988 1 0.1337 3.5009 1 0.1338 3.4998 i 0.0946 VE - 6251,6252 Aug,1997 K-40 3.8744 1 0.5410 3.3980 1 0.6150 3.6362 0.4095 MI- 6335,6336 Aug,1997 I-131 0.0196 i 0.2826 0.0564 i 0.2698 0.0380 1 0.1953 MI- 6335,6336 Aug,1997 K-40 1,488.7000 i 128.0000 1,538.6000 116.0000 1,513.6500 86.3713 SL - 6982,6983 Aug,1997 Co-60 0.0869 0.0110 0.0888 i 0.0135 0.0879 i 0.0087 SL - 6982,6983 Aug,1997 Cs-137 0.0826 1 0.0110 0.0993 0.0165 0.0909 0.0099 SL - 698.2,6983 Aug,1997 Gr. Beta -0.7733 i 0.1093 -0.6988 1 0.0989 -0.7361 0.0737 WW - 6312, 6313 Aug,1997 H-3 4,401.6798 i 200.9023 4,585.7685 i 204.3507 4,493.7241 i 143.2837 LW - 6560,6561 Aug,1997 Gr. Alpha 0.4838 0.3847 0.7647 1 0.3421 0.6242 1 0.2574 {

LW - 6560,6561 Aug,1997 Gr. Beta 1.6502 1 0.3609 1.6339 i 0.3320 1.6420 1 0.2452 LW - 6560,6561 Aug,1997 H-3 164.1455 90.4249 131.5719 i 89.0337 147.8587 1 63.4501 1 LW - 6520,6521 Sep,1997 Gr. Beta 1.9762 i 0.5715 2.3786 i 0.6284 2.1774 i 0.4247 LW - 6520,6521 Sep,1997 H-3 104.7304 i 87.8580 66.4144 i 86.1708 85.5724 61.5314 CW - 6489,6490 Sep,1997 Gr. Beta 0.2448 i l.3049 1.9046 1 1.3290 1.0747 0.9313 G - 6773,6774 Sep,1997 K-40 3.7979 i 0.2420 3.5568 i 0.3270 3.6774 0.2034 CW - 6796,6797 Sep,1997 Gr. Beta 3.3658 t l.5585 5.0139 i l.1808 4.1899 1 0.9777 CW - 6796,6797 Sep,1997 Gr. Beta -1.1040 i 1.0241 -0.7623 1.0723 -0.9332 i 0.7414 SWU - 7009,7010 Sep,1997 Gr. Beta 3.2034 1 0.6793 3.2645 0.6681 3.2339 1 0.4764 SWU - 7009,7010 Sep,1997 H-3 165.8491 i 90.5715 150.5986 89.9273 158.2239 i 63.8164 l G - 6820,6821 Sep,1997 K-40 4.8113 1 0.4160 4.7307 i 0.5360 4.7710 0.3392 j M1 - 6886,6887 Sep,1997 I-131 0.0177 i 0.1519 0.0180 1 0.1520 0.0179 i 0.1074 MI - 6886,6887 Sep,1997 K-40 1,241.7000 i 155.0000 1,062.0000 156.0000 1,151.8500 109.9557 WW - 7031,7032 Sep,1997 H-3 -38.0852 i 81.4466 -19.0426 i 82.3323 -28.5639 i 57.9054 CW - 6907,6908 Sep,1997 Gr. Beta 3.8333 i 1.5682 4.5001 i 1.6814 4.1667 1.1496 CW - 6907,6908 Sep,1997 Gr. Beta -0.0397 1 1.1726 -0.1621 i 1.1478 -0.1009 i 0.8204 F - 7221,7222 Sep,1997 K-40 3.0101 i 0.3970 2.6722 1 0.4720 2.8412 0.3084 CW - 7177,7178 Sep,1997 Gr. Beta 0.5864 i 0.9867 2.3794 1.4286 1.4829 1 0.8681 CW - 7177,7178 Sep,1997 Gr. Beta -1.0971 i 1.0379 -0.1387 i 1.1507 -0.6179 i 0.7748 A5-9

Table A-5. In-house " duplicate" samples.

Concentration in pCi/L' Lab Sample First Second Averaged Codes' Date Analysis Result Result Result LW - 7198,7199 Sep,1997 Gr. Beta 1.6523 i 0.6116 2.3619 i 0.6044 2.0071 1 0.4299 VE - 7141,7142 Sep,1997 Co-60 0.0012 i 0.0118 -0.0001 0.0004 0.0005 0.0059 VE - 7141,7142 Sep,1997 Cs-137 -0.0011 1 0.0090 0.0081 i 0.0103 0.0035 1 0.0068 SWU - 7361,7365 Sep,1997 Gr. Beta 2.4372 i 0.6226 2.7949 1 0.6153 2.6160 1 0.4377 SWU - 7364,7365 Sep,1997 H-3 245.3799 i 94.1721 26?.0627 i 95.1596 257.2213 i 66.9398 WW - 7408,7409 Sep,1997 Co-60 0.4170 i 0.8010 2.0100 i 6.7100 1.2135 i 3.3788 WW - 7408, 7409 Sep,1997 Cs-137 -0.2190 i 1.6500 0.8220 i 3.0600 0.3015 i 1.7383 WW - 7408, 7409 Sep,1997 H-3 7,907.0011 i 264.0275 7,543.2790 258.5239 7,725.1400 i 184.7601 LW - 7765,7766 Sep,1997 Gr. . Alpha 0.2614 i 0.4857 0.3882 1 0.5450 0.3248 i 0.3650 LW - 7765,7766 Sep,1997 Gr. Beta 3.6490 i 0.5140 2.7232 1 0.4728 3.1861 0.3492 LW - 7765,7766 Sep,1997 H-3 3,168.6312 i 176.2295 3,030.6146 i 173.2010 '3,099.6229 1 123.5470 AP - 8208,8209 Sep,1997 Co-60 0.0002 1 0.0004 0.0004 0.0003 0.0003 0.0005 AP - 8208,8209 Sep,1997 Cs-137 0.0003 1 0.0005 -0.0004 0.0006 -0.0000 0.0004 G - 7244,7245 Oct,1997 Gr. Beta 9.0000 i 0.3000 8.4000 i 0.3000 8.7000 1 0.2121 G - 7244,7245 Oct,1997 K-40 8.8853 i 0.7960 9.1594 i 0.7550 9.0224 i 0.54S6 G - 7244,7245 Oct,1997 Sr-89 -0.0058 i 0.0181 -0.0056 1 0.0097 -0.0057 i 0.0103 G - 7244,7245 Oct,1997 Sr-90 0.0053 i 0.0052 0.0017 i 0.0029 0.0035 1 0.0029 G - 7265,7266 Oct,1997 K-40 6.5763 1 0.5250 6.0640 1 0.6540 6.3202 i 0.4193 SW - 7313,7314 Oct,1997 Gr. Beta 24.5727 1 2.0773 21.9706 2.0623 23.2717 1 1.4636 SW - 7313,7314 Oct,1997 K-40 114.6700 1 41.9000 90.9920 37.6000 102.8310 28.1486 G - 7432,7433 Oct,1997 Co-60 0.0073 i 0.0252 0.0041 i 0.0059 0.0057 0.0129 G - 7432,7433 Oct,1997 Cs-134 0.0057 i 0.0110 0.0009 i 0.0010 0.0033 0.0055 G - 7432,7433 Oct,1997 Cs-137 0.0863 0.0217 0.0835 1 0.0247 0.0849 i 0.0164 G - 7432,7433 Oct,1997 Gr. Beta 5.3675 1 0.2025 5.3318 i 0.2123 5.3496 t 0.1467 G - 7432,7433 Oct,1997 I-131(g) -0.0038 i 0.0069 0.0218 i 0.4830 0.0090 1 0.2415 G - 7432,7433 Oct,1997 K-40 4.4899 i 0.4020 4.9632 1 0.5470 4.7266 i 0.3394 CW - 7339,7340 Oct,1997 Gr. Beta 0.2969 1 1.2051 -0.2575 0.8630 0.0197 0.7411 AP - 7537,7538 Oct,1997 Sr-89 0.0006 i 0.0008 -0.0001 1 0.0008 0.0002 i 0.0006 AP - 7537,7538 Oct,1997 Sr-90 -0.0001 i 0.0003 0.0001 i 0.0003 0.0000 0.0002 CW - 7560,7561 Oct,1997 Gr. Deta 3.7764 t 1.5088 3.7707 i 1.5155 3.7735 i 1.0692 CW - 7560,7561 Oct,1997 Gr. Beta 0.4496 1.1864 0.3374 i 1.2009 0.3935 0.8440

F - 7474,7475 Oct,1997 Co-60 -0.0010 i 0.0016 0.0020 1 0.0058 0.0005 i 0.0030 F - 7474,7475 Oct,1997 Cs-137 0.0071 i 0.0064 0.0001 0.0113 0.0036 0.0065 F - 7495,7496 Oct,1997 Co-60 0.0025 0.0076 0.0086 i 0.1430 0.0055 i 0.0716 F - 7495,7496 Oct,1997 Cs-137 0.0078 i 0.0083 0.0044 1 0.0056 0.0061 1 0.0050 F - 7626,7627 Oct,1997 K-40 2.2464 i 0.3120 1.5663 1 0.3760 ' 9064 1 0.2443 CW - 7669,7670 Oct,1997 Gr. Beta 5.7005 i 1.8448 3.6801 1 1.7132 ,.6903 i 1.2588 i

i A5-10

Table A-5. In-house " duplicate" samples.

Concentration in pCi/L' Lab Sample First Second Averaged Codef Date Analysis Result Result Result CW - 7669,7670 Oct,1997 Gr. Deta -0.0304 i 1.1674 0.1259 i 1.1344 0.0478 0.8139 WW - 7648,7649 Oct,1997 Co-60 38.3320 1 4.3000 31.7400 3.3600 35.0360 2.7285 WW - 7648, 7649 Oct,1997 Cs-137 2.8800 i 2.3000 0.5180 1.9100 1.6990 t 1.4948 WW - 7648, 7649 Oct,1997 H-3 241.3364 i 105.7031 265.5372 i 106.6226 253.4368 1 75.0692 MI - 7787,7788 Oct,1997 I-131 -0.0456 i 0.2490 0.0257 i 0.2696 -0.0099 1 0.1835 MI- 7787,7788 Oct,1997 K-40 1,514.0000 i 114.0000 1,684.0000 1 102.0000 1,599.0000 i 76.4853 S O - 8010,8011 Oct,1997 Cs-137 0.3513 1 0.0712 0.3182 0.0693 0.3347 0.0497 S O - 8010, 8011 Oct,1997 K-40 22.4300 i 1.3200 22.0830 i 1.2900 22.2565 i 0.9228 SL - 8123,8124 Oct,1997 Cs-137 0.0368 i 0.0335 0.0242 1 0.0137 0.0305 i 0.0181 SL - 8123,8124 Oct,1997 K-40 2.8000 1 0.5510 2.5777 i 0.2960 2.6889 1 0.3127 F - 7915,7916 Oct,1997 Cs-137 0.0072 1 0.0118 0.0031 i 0.0085 0.0052 1 0.0073 MI - 7968,7969 Oct,1997 I-131 -0.1451 i 0.3579 -0.4853 0.3455 -0.3152 0.2487 MI - 7968,7969 Oct,1997 K-40 1,324.1000 i 132.0000 1,313.0000 1 118.0000 1,318.5500 88.5268 MI - 7968,7969 Oct,1997 Sr-90 1.2892 i 0.4152 1.2892 i 0.7200 1.2892 i 0.4156 VE - 7934,7935 Oct,1997 Co-60 0.0071 1 0.1160 -0.0029 0.0139 0.0021 0.0584 VE - 7934,7935 Oct,1997 Cs-137 0.0022 i 0.0110 -0.0041 1 0.0099 -0.0010 i 0.0074 SWU - 8946, 8947 Oct,1997 Cr. Beta 2.9772 i 0.6530 2.2888 0.5953 2.6330 i 0.4418 SWU - 8946,8947 Oct,1997 H-3 187.7210 1 97.3682 125.5659 i 94.9331 156.6435 i 67.9943 CW - 8230,8231 Oct,1997 Gr. Beta 3.6262 i 1.7126 4.9561 1 1.7938 4.2911 1 1.2400 CW - 8230,8231 Oct,1997 Cr. Deta 1.7276 i 0.9533 0.1316 i 1.1929 0.929o i 0.7635 CW - 8100,8101 Oct,1997 Gr. Beta 4.1481 i 1.6095 4.5744 1 1.5764 4.3612 i 1.1264 CW - 8100,8101 Oct,1997 Gr. Beta -0.5655 1 0.8528 0.9791 1 1.2280 0.2068 0.7475 SS - 8501,8502 Oct,1997 Gr. Alpha 7.9580 i 3.4566 6.5709 1 3.1487 7.2645 1 2.3379 SS - 8501, 8502 Oct,1997 Gr. Beta 19.4568 t 2.9472 17.6686 i 2.6664 18.5627 1 1.9872 SS - 8501, 8502 Oct,1997 K-40 12.4630 i 0.4450 13.4420 1 0.7910 12.9525 i 0.4538 CW - 8310,8311 Oct,1997 Gr. Beta 2.1293 i 1.4423 2.1830 i 1.4550 2.1562 1.0243 CW - 8310,8311 Oct,1997 Gr. Beta 0.1798 1 1.1387 -0.0397 1.1504 0.0701 1 0.6093 CW - 8376,8377 Oct,1997 Gr. Beta 4.7932 1 2.0194 7.3047 1 1.3637 6.0490 i l.2184 l

l CW - 8376,8377 Oct,1997 Gr. Beta 0.5653 1 1.8020 -0.0566 i 1.7632 0.2544 i 1.2606 MI - 8442,8443 Oct,1997 1-131 -0.0290 i 0.2689 0.1059 i 0.2666 0.0384 i 0.1893 l MI - 8442,8443 Oct,1997 K-40 1,591.7000 i 178.0000 1,456.0000 1 116.0000 1,523.8500 i 106.2309 l SWU - 8543,8544 Oct,1997 Gr. Beta 2.2027 i 0.6193 2.1585 1 0.6134 2.1806 0.4358 SWU - 8543,8544 Oct,1997 H-3 120.4712 i 87.0152 174.9557 i 89.2606 147.7134 i 62.3280 WW - 8473, 8474 Oct,1997 H-3 28.9600 77.6404 27.1500 i 80.2139 -0.9050 i 55.8174 WW - 8566,8567 Oct,1997 Co-60 0.4520 i 1.7400 0.3400 i 4.0500 0.3960 2.2040 WW - 8566,8567 Oct,1997 Cs-137 1.0300 1 2.2000 -0.7300 2.8600 0.1500 i 1.8041 LW - 8608,8609 Oct,1997 Gr. Deta 2.8483iF5660 2.3035 1 0.6052 2.5759 1 0.4500 A5-11 1

(I

Table A-5. In-house " duplicate samples.

Concentration in pCi/L' Lab Sample First Second Averaged {'

Codes

Date Analysis Result Result Result MI-8587,8588 Nov,1997 I-131 -0.0013 i 0.1396 0.0109 i 0.1350 0.0048 0.0971 MI- 8587,85S8 Nov,1997 K-40 1,441.6000 1 160.0000 1,499.6000 1 176.0000 1,470.6000 118.9285 WW - 8654, 8655 Nov,1997 Gr. Beta 0.6704 1 0.5213 0.8560 0.5226 0.7632 i 0.3691 I

WW - 8654,8655 Nov,1997 H-3 131.2268 i 87.3749 87.6861 i 85.5477 109.4565 61.1408 CW - 8753,8754 Nov,1997 Gr. Beta 5.4805 i 1.9992 4.3820 2.0409 4.9312 1.4285 CW - 8753,8754 Nov,1997 Gr. Beta 0.2821 i l.7806 0.1129 z 1.7701 0.1975 1 1.2554 F - 9131,9132 Nov,1997 Cs-137 0.0576 1 0.0192 0.0568 1 0.0171 0.0572 1 0.0129 F - 9131,9132 Nov,1997 Gr. Beta 2.9445 i 0.0965 3.0473 0.0919 2.9959 i 0.0666 F - 9131,9132 Nov,1997 K-40 2.3452 i 0.3460 2.4680 0.3260 2.4066 i 0.2377 CW - 8854,8855 Nov,1997 Gr. Beta 5.6208 i l.7991 3.5028 t l.6326 4.5618 1.2147 CW - 8854,8855 Nov,1997 Gr. Beta 0.0000 i 1.1731 0.6107 i 1.1604 0.3053 0.8250 WW - 9087,9088 Nov,1997 H-3 20.1985 i 81.0438 73.4489 i 83.4219 46.8237 i 58.1535 WW - 9160,9161 Nov,1997 Co-60 -0.9580 i 9.1800 -0.4340 4.2400 -0.6960 i 5.0559 WW - 9160,9161 Nov,1997 Cs-137 -0.1440 2.3300 -0.5270 2.0700 -0.3355 i 1.5583 SWT - 9341,9342 Nov,1997 Gr. Beta 1.4657 i 0.7780 2.7123 i 0.8202 2.0890 1 0.5652 CW - 9410,9411 Dec,1997 Gr. Beta 3.2958 i 1.5674 4.2062 i 1.5722 3.7510 i 1.1100 CW - 9410,9411 Dec,1997 Gr. Beta 0.6244 1.1948 -0.6229 1.0939 0.0007 i 0.8099 CW - 9466,9467 Dec,1997 Gr. Beta 1.6082 i 1.6557 2.0375 i 1.6921 1.8228 1.1837 CW - 9466,9467 Dec,1997 Gr. Beta -0.0563 i 1.7639 -1.1838 1 1.6912 -0.6201 1 1.2218 WW - 9603,9604 Dec,1997 Co-60 1.7300 i 1.7600 -0.6190 0.7560 0.5555 i 0.9577

. WW - 9603,9604 Dec,1997 Co-60 1.7300 1 1.7600 -0.0389 i 0.3420 0.8456 i 0.8965 WW - 9603, 9604 Dec,1997 Cs-137 0.4460 i 2.0800 0.0557 1 1.2900 0.2509 i 1.2238 LW - 9789,9790 Dec,1997 Co-60 0.1010 1 0.1080 0.1510 i 2.0300 0.1260 i 1.0164 ,

LW - 9789,9790 Dec,1997 Cs-137 1.0000 1 2.1300 0.9130 i 2.0300 0.9565 1.4712 LW - 9789,9790 Dec,1997 Gr. Beta 5.6924 1 1.0952 4.5180 0.7757 5.1052 0.6711 CW - 9947,9948 Dec,1997 Gr. Beta 0.9320 i 0.9447 1.5072 1 0.9762 1.2196 0.6792 AP - 10249,10250 Dec,1997 Co-60 0.0000 1 0.0001 0.0004 i 0.0016 0.0002 0.0008 l AP - 10249,10250 Dec,1997 Cs-137 0.0005 0.0008 0.0002 1 0.0003 0.0004 0.0004 f

' All concentrations ere reported in pCi/ liter, except solid samples, which are reported in pCi/ gram.

6 Lab codes are comprised of the sample media and the sample numbers. Client codes have been eliminated to l protect client anonymity.

l A5-12 L___-__________

Table A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP),

comparison of MAPEP and Teledyne's Midwest Laboratory results for various sample media'.

Concentration

Lab Sample Date Teledyne Results d MAPEP Result Control Code Type Collected Analysis iStandard Deviation

1s, N=1 Limits STW-751 WATER Sep,1995 Am-241 1.370 1 0.120 1.320 0.070 1.056 - 1.584 STW-751 WATER Sep,1995 Co-57 91.000 1 0.950 92.380 0.600 73.904 - 110.856 STW-751 WATER Sep,1995 Cs-137 55.000 i 0.500 58.770 1 0.730 47.016 - 70.524 STW-751 WATER Sep,1995 Mn-54 99.170 t 1.600 99.080 1 1.000 79.264 - 118.896 STW-751 WATER Sep,1995 Pu-238 1.700 i 0.040 1.830 1 0.080 1.464 - 2.196 STW-751 WATER Sep,1995 Pu-239 1.380 i 0.220 1.340 1 0.060 1.072 - 1.608 STW-751 WATER Sep,1995 Sr-90 13.730 1 0.950 15.690 0.300 12.552 - 18.828 STW-751 WATER Sep,1995 U-234 0.630 i 0.070 0.650 1 0.050 0.520 - 0.780 STW-751 WATER Sep,1995 U-238 0.700 i 0.020 0.650 0.050 0.520 - 0.780 STSO-776 SOIL Sep,1996 Am-241 27.000 28.700 1 2.830 20.900 - 37.310 Standard deviation for three determinations not reported in Mixed Analyte Performance Evaluation Program Summary Report.

STSO-776 SOIL Sep,1996 Co-60 879.000 812.000 83.S00 568.400 - 1,055.600 STSO-776 SO!L Sep,1996 Cs-137 1,716.000 1,531.000 193.420 1,071.700 - 1,990.300 STSO-776 SOIL Sep,1996 Pu-238 13.000 15.900 1.770 11.130 - 20.670 STSO-776 SOIL Sep,1996 Pu-239/240 18.000 19.700 i 1.960 13.790 - 25.610 STSO-776 SOIL Sep,1996 Sr-90 441.000 536.000 57.110 375.200 - 696.800 STSO-776 SOIL Sep,1996 U-234/233 59.000 63.900 7.270 44.730 - 83.070 STSO-776 SOIL Sep,1996 U-238 60.000 64.000 6.360 44.800 - 83.200

' Results obtained by Teledyne Brown Engineering Environmental Services Midwest Laboratory as a participant in the Department of Energy's Mixed Analyte Performance Evaluation Program, Idaho Operations office, Idaho Falls, Idaho.

All results are in Bq/kg or Bq/L as requested by the Department of Energy.

Unless otherwise indicated, the TBEESML results are given as the mean I standard deviations for three determinations.

d MAPEP results are presented as the known values and expected laboratory precision (1 sigma, I determination) and control limits as defined by the MAPEP.

A6-1

Table A-7. Environmental Measurements Laboratory Quality Assessment Program (EML),

comparison of EML and Teledyne's Midwest Laboratory results for various sample media'.

Concentration in Bq/L6 Lab Sample Date Control Code Type Collected Analysis Teledyne Result

EML Result d

Limits' STW-755 WATER Mar,1996 Am-241 0.800 1 0.100 0.766 i 0.013 0.660 - 1.560 STW-755 WATER Mar,1996 Co-60 33.600 1 1.000 32.800 i 0.580 0.870 - 1.170 STW-755 WATER Mar,1996 Cs-137 42.800 i 1.300 38.300 0.881 0.900 - 1.250 STW-755 WATER Mar,1996 Fe-55 109.000 1 21.700 83.000 1 3.440 0.270 - 1.620 STW-755 WATER Mar,1996 H-3 434.000 1 34.100 251.000 1 11.400 0.690 - 1.910 STW-755 WATER Mar,1996 Mn-54 41.900 1 1.400 38.400 1 1.160 0.880 - 1.210 STW-755 WATER Mar,1996 Pu-238 0.900 1 0.100 0.982 1 0.074 0.680 - 1.330 STW '755 WATER Mar,1996 Pu-239 0.700 0.100 0.772 i 0.056 0.620 - 1.380 STW-755 WATER Mar,1996 Sr-90 2.200 1 0.700 1.450 0.034 0.730 - 1.650 STW-756 WATER Mar,1996 Gr. Alpha 2,180.000 53.500 1,850.000 1 185.000 0.550 - 1.310 STW-756 WATER Mar,1996 Gr. Beta 872.000 27.000 744.000 74.000 0.750 - 1.650 STSO-757 SOIL Mar,1996 Am-241 6.230 1 2.880 3.690 0.454 0.520 - 2.410 STSO-757 SOIL Mar,1996 Cs-137 404.000 i 0.150 359.000 i 10.000 0.740 - 1.400 STSO-757 SOIL Mar,1996 K-40 525.000 1 23.300 465.000 30.000 0.700 - 1.590 STSO-757 SOIL Mar,1996 Pu-238 42.300 1 1.590 43.000 1 2.440 0.220 - 1.990 STSO-757 > SOIL Mar,1996 Pu-239 9.000 1 0.700 9.230 0.346 0.620 - 1.990 STSO-757 SOIL Mar,1996 Sr-90 1,200.000 32.300 1,340.000 1 11i000 0.580 - 2.960 STSO-757 SOIL 1iar,1996 Uranium 68.200 i 2.400 71.700 4.150 0.270 - 1.4SO STVE-758 VEGETATION Mar,1996 Am-241 6.100 1 1.300 5.600 1 0.184 0.580 - 2.860 STVE-758 VEGETATION Mar,1996 Cm-244 6.000 1 1.200 4.440 1 0.202 0.400 - 1.870 STVE-758 VEGETATION Mar,1996 Co-60 65.600 1 4.000 59.700 i 0.963 0.640 - 1.490 STVE-758 VEGETATION Mar,1996 Cs-137 1,100.000 1 12.600 944.000 i 16.200 0.750 - 1.480 STVE-758 VEGETATION Mar,1996 K-40 1,190.000 61.600 1,030.000 1 33.000 0.450 - 1.510 STVE-758 VEGETATION Mar,1996 Pu-239 9.200 i 1.300 9.820 i 1.220 0.600 - 1.980 STVE-758 VEGETATION Mar,1996 Sr-90 1,210.000 i 32.200 1,300.000 i 52.400 0.500 - 1.370 STAF-759 AIR FILTER Mar,1996 .Am-241 0.270 i 0.040 0.189 i 0.007 0.620 - 1.930 STAF-759 AIR FILTER Mar,1996 Ce-144 23.200 i l.020 33.300 3.300 0.610 - 1.310 STAF-759 AIR FILTER Mar,1996 Co-57 6.050 i 0.130 8.900 i 0.900 0.630 - 1.290 STAF-759 AIR FILTER Mar,1996 Co-60 26.500 i 0.430 29.500 1 2.900 0.740 - 1.250 STAF-759 AIR FILTER Mar,1996 Cs-134 12.900 1 0.280 14.700 1.460 0.700 - 1.210 STAF-759 AIR FILTER Mar,1996 Cs-137 6.200 1 0.900 6.640 i 0.700 0.720 - 1.320 STAF-759 AIR FILTER Mar,1996 Mn-54 3.270 1 0.350 3.440 1 0.380 0.760 - 1.330 STAF-759 AlR FILTER Mar,1996 Pu-238 0.080 t 0.020 0.096 1 0.002 0.610 - 1.550 STAF-759 AIR FILTER Mar,1996 Pu-239 0.090 i 0.026 0.093 i 0.003 0.670 - 1.580 STAF-759 AlR FILTER Mar,1996 Ru-106 10.200 1.850 11.600 1.440 0.540 - 1.590 STAF-759 AIR FILTER Mar,1996 Sb-125 10.100 i 0.750 ?.780 1.030 0.350 - 1.400 STAF-759 AlR FILTER Mar,1996 Sr-90 1.070 1 0.230 1.t'6010.037 0.620 - 2.260 STAF-759 AIR FILTER Mar,1996 Uranium 0.118 i 0.020 0.107 1 0.003 0.790 - 2.880 A7-1

Table A-7. Environmental Measurements Laboratory Quality Assessment Frogram (EML),

comparison of EML and Teledyne's Midwest Laboratory results for various sample media'.

6 Concentration in Eq/L Lab Sample Date Control Code Type Collected Analysis Teledyne Result

EML Result d Limits' STAF-760 AIR FILTER Mar,1996 Gr. Alpha 2.210 i 0.050 1.620 0.150 0.820 - 1.580 STAF-760 AlR FILTER Mar,1996 Gr. Beta 1.950 0.040 1.770 1 0.150 0.750 - 1.940 STW-770 WATER Sep,1996 Am-241 1.300 i 0.200 1.080 0.040 0.640 - 1.730 STW-770 WATER Sep,1996 Co-60 65.000 1 2.210 61.100 0.730 0.920 - 1.180 STW-770 WATER Sep,1996 Cs-137 96.100 i 3.010 89.500 1 1.360 0.900 - 1.280 STW-770 WATER Sep,1996 Gr. Alpha 993.000 12.200 1,210.000 121.000 0.500 - 1.290 STW-770 WATER Sep,1996 Gr. Beta 579.000 1 8.070 540.000 1 54.000 0.600 - 1.640 STW-770 WATER Sep,1996 H-3 488.000 i 34.600 587.000 1 58.000 0.650 - 1.910 STW-770 WATER Sep,1996 Mn-54 65.000 1 2.960 60.500 0.550 0.870 - 1.220 STW-770 WATER Sep,1996 Pu-238 1.320 0.333 1.910 i 0.070 0.740 - 1.270 An investigation was conducted. No errors in calculations or transcription were noted. The analysis was repeated in duplicate under the observation of the Technical Lead. No discrepancies were noted in the performance of the procedure. The result of the reanalysis was 2.1410.11 Bq/L. No further action is plarmed.

STW-770 WATER Sep,1996 Pu-239 0.6981 0.247 0.840 0.030 0.780 - 1.420 STW-770 WATER Sep,1996 Sr-90 3.600 0.700 2.710 0.240 0.720 - 1.660 STW-770 WATER Sep,1996 U-234 0.517 i 0.196 0.480 i 0.040 0.770 - 1.530 STW-770 WATER Sep,1996 U-238 0.416 i 0.118 0.480 1 0.370 0.770 - 1.350 STSO-771 SOIL Sep,1996 Am-241 15.600 3.830 13.500 1 0.510 0.520 - 2.650 STSO-771 SOIL Sep,1996 Co-60 4.030 2.500 2.920 1 0.210 0.500 - 1.500 STSO-771 SOIL Sep,1996 Cs-137 1,750.000 1 24.400 1,550.000 1 22.200 0.800 - 1.340 STSO-771 SOIL Sep,1996 K-40 369.000 i 59.500 300.000 25.000 0.730 - 1.670 I STSO-771 SOIL Sep,1996 Pu-238 0.770 1 0.360 1.130 0.240 0.400 - 1.900 STSO-771 SOIL Sep,1996 Pu-239 24.000 1.940 21.800 i l.080 0.660 - 1.930 STSO-771 SOIL Sep,1996 Sr-90 63.600 3.950 69.900 t 5.100 0.460 - 2.840 STSO-771 SOIL Sep,1996 U-234 37.200 1 3.750 39.200 2.440 0.380 - 1.260 l STSO-771 SOIL Sep,1996 U-238 40.800 3.980 41.600 i 0.610 0.350 - 1.550 STVE-772 VEGETATION Sep,1996 Am-241 1.530 1 0.884 1.230 i 0.410 0.680 - 2.780 STVE-772 VEGETATION Sep,1996 Cm-244 0.612 i 0.495 0.830 0.120 0.490 - 1.690 STVE-772 VEGETATION Sep,1996 Co-60 14.000 4.420 10.900 1 0.710 0.620 - 1.420 STVE-772 VEGETATION Sep,1996 Cs-137 219.000 1 10.100 190.000 i 6.680 0.810 - 1.450 STVE-772 VEGETATION Sep,1996 K-40 1,160.000 1 99.400 992.000 29.000 0.790 - 1.500 '

STVE-772 VEGETATION Sep,1996 Sr-90 1,420.000 i 35.100 1,390.000 12.000 0.480 - 1.290 STAP-773 AIR FILTER Sep,1996 Co-57 11.800 1 0.296 14.800 1 0.814 0.620 - 1.220 STAP-773 AIR FILTER Sep,1996 Co-60 9.230 1 0.402 8.640 1 0.431 0.740 - 1.240 STAP-773 AIR FILTER Sep,1996 Cs-134 9.620 i 0.376 10.800 0.392 0.720 - 1.210 STAP-773 AIR FILTER Sep,1996 Cs-137 8.720 i 0.403 8.520 1 0.366 0.720 - 1 320 STAP-773 AIR FILTER Sep,1996 Gr. Alpha 0.731 1 0.037 1.150 0.110 0.830 - 1.550 An investigation was conducted and a transcription error while calculating the result was discovered. The recalculated value is 1.1510.01Bq/ filter. No further action is planned. j l

A7-2

Table A-7. Environmental Measurements Laboratory Quality Assessment Program (EML),

comparison of EML and Teledyne's Midwest Laboratory results for various sample media'.

Concentration in Bq/L" Lab Sample Date Control Code Type Collected Analysis Teledyne Result' EML Result d Limits' STAP-773 AIR FILTER Sep,1996 Gr. Beta 0.540 1 0.037 0.500 1 0.050 0.730 - 1.840 STAP-773 AIR FILTER Sep,1996 Mn-54 7.060 i 0.472 6.350 1 0.270 0.750 - 1.270 STAP-773 A1R FILTER Sep,1996 Ru-106 11.500 3.190 10.800 1.140 0.580 - 1.300 STAP-773 AIR FILTER Sep,1996 Sb-125 12.400 0.965 10.800 1 0.540 0.600 - 1.390 STW-788 WATER Mar,1997 Am-241 0.840 i 0.220 0.837 i 0.028 0.640 - 1.730 STW-788 WATER Mar,1997 Co-60 96.000 1 3.500 90.850 1 1.150 0.920 - 1.180 STW-788 WATER Mar,1997 Cs-137 77.000 3.500 69.780 1.230 0.900 - 1.280 STW-788 WATER Mar,1997 Fe-55 175.500 25.400 235.000 20.000 0.310 - 1.540 STW-788 WATER Mar,1997 Gr. Alpha 1,042.600 i 36.800 1,130.000 10.000 0.500 - 1.290 STW-788 WATER Mar,1997 Gr. Beta 591.400 t 23.300 744.000 10.000 0.600 - 1.640 STW-788 WATER Mar,1997 H-3 272.000 1 29.700 250.300 4.200 0.650 - 1.910 STW-788 WATER Mar,1997 Mn-54 23.700 1 3.400 20.850 i 0.310 0.870 - 1.220 STW-788 WATER Mar,1997 Pu-238 1.400 i 0.200 1.291 0.063 0.740 - 1.270 STW-788 WATER Mar,1997 Pu-239 0.900 1 0.100 0.850 0.050 0.780 - 1.420 STW-788 WATER Mar,1997 St-90 25.500 i l.700 23.200 1.350 0.720 - 1.660 STW-788 WATER Mar,1997 U 1.500 0.200 1.105 0.050 0.350 - 1.420 STSO-790 SOIL Mar,1997 Am-241 6.740 3.730 5.680 i 0.500 0.520 - 2.650 STSO-790 SOIL Mar,1997 Co-60 2.010 1 1.170 1.060 0.120 0.500 - 1.500 The sample size was too small for an accurate measurement. The activity error overlap the known value.

STSO-790 SOIL Mar,1997 Cs-137 918.640 8.400 825.500 i 14.100 0.800 - 1.340 STSO-790 SO!L Mar,1997 K-40 359.140 i 32.100 334.250 1 7.140 0.730 - 1.670 STSO-790 SOIL Mar,1997 Pu-238 0.300 i 0.200 0.530 1 0.110 0.400 - 1.900 STSO-790 SOIL Mar,1997 Pu-239 132.420 5.170 134.930 17.100 0.660 - 1.930 STSO-790 SOIL Mar,1997 Sr-90 38.830 i 5.770 40.310 1 0.420 0.460 - 2.840 STSO-790 SOIL Mar,1997 U 79.260 i 3.800 81.270 4.830 0.270 - 1.360 STVE-791 VEGETATION Mar,1997 Am-241 1.673 1 0.688 1.183 i O.113 0.680 - 2.780 STVE-791 VEGETATION Mar,1997 Cm-244 0.688 i 0.468 0.900 i 0.050 0.490 - 1.690 STVE-791 VEGETATION Mar,1997 Co-60 16.914 i 3.580 12.500 0.320 0.620 - 1.420 STVE-791 VEGETATION Mar,1997 Cs-137 216.667 i 9.383 189.250 1 7.270 0.810 - 1.450 STVE-791 VEGETATION Mar,1997 Pu-239 1.771 1 0.817 1.942 i 0.222 0.650 - 1.950 STVE-791 VEGETATION Mar,1997 Sr-90 361.130 19.715 361.000 i 43.300 0.480 - 1.290 STAP-792 AIR FILTER Mar,1997 Co-57 9.528 1 0.230 10.810 1.000 0.620 - 1.220 STAP-792 AlR FILTER Mar,1997 Co-60 5.325 i 0.266 5.010 i 0.300 0.740 - 1.240 STAP-792 AIR FILTER Mar,1997 Cs-134 10.767 1 0.337 10.880 1.000 0.720 - 1.210 STAP-792 AIR FILTER Mar,1997 Cs-137 9.116 i 0.404 8.700 1 0.800 0.720 - 1.320 STAP-792 AIR FILTER Mar,1997 Gr. Alpha 1.199 0.045 0.960 i 0.050 0.830 - 1.550 STAP-792 AIR FILTER Mar,1997 Gr. Beta 0.608 1 0.024 0.450 0.030 0.730 - 1.840 STAP-792 AIR FILTER Mar,1997 Mn-54 8.494 0.429 7.620 0.600 0.750 - 1.270 A7-3

Table A-7. Environmental Measurements Laboratory Quality Assessment Program (EML),

comparison of EML and Teledyne's Midwest Laboratory results for various sample media'.

Concentration in Bq/L' Lab Sample Date Control Code Type Collected Analysis Teledyne Result

EML Result d Limits' STAP-792 AIR FILTER Mar,1997 Pu-238 0.022 1 0.016 0.100 1 0.006 0.620 - 1.460 The cause of the deviation for the transuranic analysis (Pu-238,239, U) is unknown. A dilution error is suspected.The analysis is being repeated.

STAP-792 AIR FILTER Mar,1997 Pu-239 0.031 x 0.010 0.119 0.006 0.500 - 1.500 STAP-792 AIR FILTER Mar,1997 Sb-125 14.118 1 1.099 12.330 1 1.000 0.600 - 1.390 STAP-792 AIR FILTER Mar,1997 Sr-90 1.291 1 0.275 1.450 0.149 0.660 - 2.650 STAP-792 AIR FILTER Mar,1997 U 0.150 i 0.020 0.211 0.008 0.808 - 3.360 STW-805 WATER Sep,1997 Co-60 23.630 i 1.450 23.300 1.200 0.920 - 1.180 STW-805 WATER Sep,1997 Cs-134 63.500 i 2.600 66.000 2.600 0.500 - 1.500 STW-805 WATER Sep,1997 Cs-137 34.880 1 2.430 34.300 1 1.700 0.900 - 1.280 STW-805 WATER Sep,1997 Fe-55 101.730 1 33.530 113.000 i 10.000 0.310 - 1.540 STW 805 WATER Sep,1997 Gr. Alpha 597.000 i 12.000 557.000 1 60.000 0.500 - 1.290 STW-805 WATER Sep,1997 Gr. Beta 985.000 i 13.000 712.000 1 70.000 0.600 - 1.640 STW-805 WATER Sep,1997 H-3 227.600 i l.800 115.000 6.000 0.650 - 1.910 The sample was acidic, causing a breakdown of resin in the tritium column. The sample was neutralized to pH 7 and reanalyzed. Results of reanalysis: 116.2 3.6 Bq/L.

STW-805 WATER Sep,1997 Mn-54 38.480 i 3.230 37.800 i 1.900 0.870 - 1.220 STW-805 WATER Sep,1997 St-90 3.4601 0.690 2.940 1 0.180 0.720 - 1.660 STVE-806 VEGETATION Sep,1997 Co-60 32.330 i 5.560 32.400 1.600 0.620 - 1.420 STVE-806 VEGETATION Sep,1997 Cs-137 627.330 1 16.670 624.000 i 31.000 0.810 - 1.450 STVE-806 VEGETATION Sep,1997 K-40 1,091.670 95.180 1,130.000 70.000 0.790 - 1.500 - !

STVE-806 VEGETATION Sep,1997 St-90 1,335.000 32.000 1,434.000 75.000 0.480 - 1.290 l STSO-807 SOIL Sep,1997 Cs-137 1,239.440 i 22.460 810.000 40.000 0.800 - 1.340 l The sample size was not standard. The sample was reanalyzed using a different geometry. Results of reanalysis: Cs-137 - 813.119.0 Bq/kg; K 275.9134.6 Bq/kg. i' STSO-807 SOIL Sep,1997 K-40 478.000 i 29.000 315.000 1 70.020 0.730 - 1.670 STSO-807 SOIL Sep,1997 Pu-239 10.800 1 0.400 10.160 0.370 0.660 - 1.930 STSO-807 SOIL Sep,1997 Sr-90 31.480 i 5.560 34.750 1 1.000 0.460 - 2.840 STSO-807 SOIL Sep,1997 U 57.000 1.100 72.900 0.850 0.270 - 1.360 STAP-808 AIR FILTER Sep,1997 Gr. Alpha 1.820 0.080 1.490 i 0.090 0.830 - 1.550 STAP-808 AIR FILTER Sep,1997 Gr. Beta 3.250 1 0.080 3.000 0.140 0.730 - 1.840 STAP-808 AIR FILTER Sep,1997 Pu-238 0.230 i 0.100 0.210 0.007 0.620 - 1.460 STAP-808 AIR FILTER Sep,1997 U 0.130 i 0.100 0.110 0.004 0.800 - 3.360 STAP-809 AIR FILTER Sep,1997 Ce-144 16.250 1 1.670 19.120 1 0.700 0.500 - 1.500 l STAP-809 AIR FILTER Sep,1997 Co-57 10.570 i 0.270 12.640 1 0.430 0.620 - 1.220 l STAP-809 AIR FILTER Sep,1997 Co-60 9.820 1 0.270 10.730 10.900 0.740 - 1.240 STAP-809 AIR FILTER Sep,1997 Cs-134 24.700 0.490 28.170 0.730 0.720 - 1.210 STAP-809 AIR FILTER Sep,1997 Cs-137 7.240 1 0.370 7.310 0.250 0.720 - 1.320 STAP-809 AIR FILTER Sep,1997 Mn-54 6.800 1 0.430 6.720 0.270 0.750 - 1.270 A7-4

a Table A-7. Environmental Measurements Laboratory Quality Assessment Program (EML),

comparison of EML and Teledyne's Midwest Laboratory results for various sample media'.

Concentration in Bq/L*

Lab Sample Date Control Code Type Collected Analysis Teledyne Result' EML Result d Limits' STAP-809 AIR FILTER Sep,1997 Sb-125 17.980 1.270 16.120 0.790 0.600 - 1.390 STAP-809 AIR FILTER Sep,1997 Sr-90 2.830 i 0.370 2.760 0.100 0.660 - 2.650

' The Environmental Measurements Laboratory provides the following nuclear species : Air Filters, Soil, Tissue, Vegetation and Water. Teledyne does not participate in the Tissue program.

Results are reported in Bq/L with the following exceptions: Air Filter results are reported in Bq/ Filter, Soil results are reported in Bq/Kg, Vegetation results are reported in Bq/Kg.

Teledyne results are reported as the mean of three determinationsistandard deviation, d

The EML result listed is the mean of replicate determinations for each nuclidetthe standard error of the mean.

The control limits are reported by EML as the ratio of Reported Value / EML Value and are established from percentiles of historic data distributions (1982-1992). The evaluation of this historic data and the development of the controllimits is presented in DOE report EML-564.

1 l-I I

A7-5

APPENDIX B DATA REPORTING CONVENTIONS l

l I B-1 L_-__-_-_-____---_ . - - .

Data Reoorting Conventions 1.0. All activities except gross alpha and gross beta are decay corrected to collection time or the end of the collection period.

2.0. Sincie Measurements Each single measurement is reported as follows:

xis where x = value of the measurement; s = 2a counting uncertainty (corresponding to the 95% confidence level).

In cases where the activity is found to be below the lower limit of detection L it is reported as

<L where L = the lower limit of detection based on 4.660 uncertainty for a background sample.

3.0. Duolicate analyses 3.1 Individual results: x1 i si x2 i s2 Reported result: x s where x = (1/2)(x1 + x2) s = (1/2) k s2 , ,

3.2. Individual results: <L3

<L2 Reoorted result: <L where L = lower of Li and L2 l 3.3. Individual results: x i s

<L

& ported result: x i s if x 2 L;

<L otherwise B- 2 i

i l

l 4.0. Computation of Averages and Standard Deviations 4.1 Averages and standard deviations listed in the tables are computed from all of the individual measurements over the period averaged; for example, an annual standard deviation would not be the average of quarterly standard deviations. The average I and standard deviation s of a set of n numbers xi, x2. . . xnare defined as follows:

x= Ex S= -I(x-i)2 n-1 4.2 Values below the highest lower limit of detection are not included in the average.

4.3 If all of the values in the averaging group are less than the highest LLD, the highest LLD is reported.

4.4 If all but one of the values are less than the highest LLD, the single value x and associated two sigma error is reported.

4.5 In rounding off, the following rules are followed:

4.5.1. If the figure following those to be retained is less than 5, the figure is dropped, and the retained figures are kept unchanged. As an example,11.443 is rounded off to 11.44.

4.5.2. If the figure following those to be retained is equal to or greater than 5, the figure is dropped and the last retained figure is raised by 1. As an example,11.445 is rounded off to 11.45.

l B- 3

.___________d

APPENDIX C Maximum Permissible Concentrations of Radioactivity in Air and Water Above Background in Unrestricted Areas C-1

1 l

Table C-1. Maximum permissible concentrations of radioactivity in air and water above natural background in unrestricted areasa ,

1 Air Water Gross alpha 3 pCi/m'3 Strontium-89 3,000 pCi/L l Gross beta 100 pCi/m3 Strontium-90 300 pCi/L Iodine-131b 0.14 pCi/m 3 Cesium-137 20,000 pCi/L Barium-140 20,000 pCi/L Iodine-131 300 pCi/L Potassium-40C 3,000 pCi/L Gross alpha 30 pCi/L Gross beta 100 pCi/L l

Tritium 3 x 106 pCi/L a Taken from Table II of Appendix B to Code of Federal Regulations Title 10, Part 20.1-20.601, and appropriate footnotes. Concentrations may be averaged ever a period not greater than one '. ear.

b From 10 CFR 20.1-20.601 but adjusted by a factor of 700 to reduce the dose resulting from the air-grass-cow-milk-child pathway.

c A natural radionuclides.

C-2 1

I l

- _ - _ _ _ _ _ _ _ _ _ . _ _ _ _ - - _ . l

APPENDIX D SpecialGround and Well Water Samples D-1

1.0 INTRODUCTION

This appendix to the Radiation Environmental Monitoring Program Annual Report to the United States Regulatory Commission summarizes and interprets results of the special well and seepage water samples taken at the Prairie Island Nuclear Generating Plant, Red Wing, Minnesota, during the period January - December,1997. This supplemental special sampling program was established in December of 1989 when higher than expected levels of tritium were detected in a nearby residence well sample.

Tabulations of the special sampling program individual analyses made during the year are included in this appendix, A summary table of tritium analyses is also included in this appendix.

j l

i D-2 l

l

I l l l 2.0

SUMMARY

This special sampling program was established following the detection of tritiura in a residence well water sample south of the PINGP during 1989. This program is described and the results for 1997 are summarized and discussed.

i Program findings for 1997 detect low levels of tritium in nearby residence wells and some I ground water seepage samples at or near the expected natural background levels. The 1997 sample results ranged from <19 pCi/L to 272 pCi/L. All tritium results are far below the Environmental Protection Agency's drinking water standard of 20,000 pCi/L and present no harm to any members of the public.

l l

D-3 1

3.0 Soecial Tritium Sampline Program 3.1 Program Design and Data Interpretation The purpose of this sampling program is to assess the impact of any tritium leaching into the environment (ground water system) from the PINGP discharge canal. For this purpose, special water samples are collected and analyzed for radioactive content.

3.2 Program Description The sampling and analysis schedule for the special water sampling program is summarized in Table 4.1 and briefly reviewed below. Table 4.2 defines the additional sample locations and codes for the special water sampling program.

Special well and ground water samples were collected semi-annually at nine locations:

one sample from the PINGP Environmental Laboratory (P-30); one from the nearest residence deep well (P-24d, Suter residence); two ground water seepages from near Birch Lake (P-31 and P-32); well water from the Prairie Island Training Center (P-26); well water from the Prairie Island Indian Community (P-8); and three other nearby residences (P-27, Nauer residence; P-28, Allyn (Perkins) residence; P-29, Childs residence). The Rohl farm well (part of the quarterly REMP sampling) is used as a control location for these special samples.

In order to detect low levels of tritium at or below natural background %vels, analyses of the samples have been contracted to a laboratory (University of Wateiloo Laboratories) capable of detecting tritium concentrations down to 19 pCi/L. Waterloo Laboratories report tritium analyses results in Tritium Units (1 TU = 3.2 pCi/L). The tritium results in this report are indicated in pCi/L.

3.3 Procram Execution The special water sampling was executed as described in the preceding section.

3.4 Procram Modifications There were no changes to the program in 1997.

3.5 Results and Discussion Results obtained show tritium in well water and ground water samples at or near expected natural background levels. Table 4.4 provides the complete data table of results for each period and sampling location.

The tritium level annual averages have shown a downward trend since the special sampling begun in 1989. Annual averages for the nearest resident south of the plant were:

1430 pCi/L in 1989,1360 pCi/L in 1990,960 pCi/L in 1991, 835 pCi/L in 1992, 516 pCi/L in 1993,370 pCi/L in 1994,170 pCi/L in 1995,64 pCi/L in 1996 and 61 pCi/L in 1997.

The 1997 levels are within the range of expected background tritium levels in shallow ground water and surface water due to tritium concentrations measured in precipitation.

Sampling points in North America have shown tritium concentrations in precipitation D-4

Results and Discussion (continued) ranging from 5 pCi/L to 157 pCi/L (Environmental Isotope Data No.10; World Survey of Isotope Concentration in Precipitation (1988-1991)).

The higher level results at Suter and Birch Lake in 1989 were possibly due to seepage from the PINGP discharge canal water into the ground water. This is thought to occur due to the elevation difference between the Vermillion River and the discharge canal. The Suter residence is located between the discharge canal and Birch Lake, which connects to the Vermillion River. The PINGP discharge canal piping was lengthened during 1991, so that liquid discharges from the plant are released near the end of the discharge canal, diffused and discharged to the Mississippi River. In 1992, the underground liquid discharge pipe from the plant to the discharge canal pi;3ing was replaced with a double walled leak detectable piping system. It is expectec that these modifications will eliminate the suspected radioactive effluent flow into the local ground water. The sample results from 1995,1996 and 1997 support this expectation.

l 1

D-5

' Table D-4.1 Sample collection and analysis program for special well and seepage water samples, Prairie Island Nuclear Generating Plant,1997.

Medium - No. Location codes Collection type Analysis typec and typea and frequencyb Well water 8- P-24d, P-25 (C), G/SA H-3 semi-annual P-26, P-27, P-28, P-29, P-30, P-8 Ground water 2 P-31, P-32 G/SA H-3 a Location codes are defined in table D-4.2. Control Station are indicated by (C). All other stations are indicators.

b Collection type is codes as follows: C/ = continuous; G/ = grab. Collection frequency is coded as follows: W = weekly; M = monthly; Q = quarterly; SA = semi-annually; A

= annually; X = no specified frequency or one time.

c Analysis type is coded as follows: GB = gross beta; GS, = gamma spectroscopy; H-3 =

tritium; I-131 = iodine 131.

l l? D-6 ,,

1

)

l

. l Table D-4.2. Sampling locations for special well and seepage water samples, Prairie Island Nuclear Generating Plant,1997 Code type a Collection site Type of sampleb Distance and direction from site j stack a P-24d Suter residence, deep well WW 0.6 mi. @ 158'/SSE P-25 C Rohl farm WW 12.9 mi @ 352 /N )

P-26 PITC WW. 0.4 mi. @ 258"/WSW P-27 Nauer residence WW 0.9 mi. @ 154"/SSE P-28 Allyn (Perkins) WW 1.0 mi. @ 152 /SSE residence P-29 Childs residence WW 1.2 mi. @ 149 /SSE P PINGP Environmental Laboratory WW 0.2 mi. @ 32 /NNE P-31 Birch Lake Seepage #1 GW 0.7 mi. @ 179 /S P-32 Birch Lake Seepage #2 GW 0.8 mi. @ 169 /SSE P-8 Prairie Island Indian Community Well WW 1.0 mi. @ 321"/WNW

. a "C" denotes control location. All other locations are indicators.

b Sample codes: WW = Well water; GW = Ground Water.

l l.

L .

D-7 a-_-___________-_. _ - - -_ .- - _ - . - - .b

r-l Table D-4.3 Radiation Environmental Monitoring Program Summary: Special well and seepage water samples.

! Name of Facility _PrairieIsland Nuclear PowerStation Dodet No. 50-282, 50-3(6

Location of Facility Goodhue, Minnesota Reporting Penod January - December 1997 j

j. (County, State) !

Indicator Location with Ilighest Control Numtwr Sample Type and Locations Semi-Annual Mean Locations Non-Type Number of LLob Mean (F)C Mean (F)C Routine Mean (F)c (Units) Analywsa hnge c locationd Rangec Range Results' Well Water H-3 16 19 117 (9/14) P-29, .

166 (2/2) 59 (2/2) 0 (pCi/L) (22-176) Child well, (156-176) (51-67) .

1.2 mi.01490/SSE Ground Water H-3 6 19 171 (4/4) P-31, Birch Lake . 232 (2/2) 59 (2/2) 0 ;

(pCi/L) (112-272) Seepage #1, (192-272) (51-67) 1 0.7 mi. 01790 /S ;

I a H-3 = tritium b

LLD = Nominal lower limit of detectioa based on 4.66 sigma error for background sample. Value shown is lowest for the period.

C Mean and range are based on detectable measurements only. Fraction of detectable measurements at specified locations is indicated in parentheses (F).

d Locations are specified: (1) by name, and code (Table 2) and (2) by distance, direction and sector relative to reactor site.

Non-routinc results are those which exceed ten times the control station value.

I J

1 D-8 1 l

l

_ . _ _ _ . _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ . _ _ . . _ _ _ _ _ . - -l

Table D-4.4 Radiological Environmental Monitoring Program , Complete Data Table,1997.

SAMPLE DATES MAY, JUNE OCT.

1997 1997 SAMPLE LOCATIONS pCi/ L pCi/ L Suter residence 22 99 Rohl Farm (Control) 51 67 PITC 77 134 Nauer residence <19 80 Allyn (Perkin) residence 147 160 Child residence 156 176 Environmental Lab <19 <19 Birch Lake Seepage #1 272 192 Birch Lake Seepage #2 112 109 Prairie Island Indian <19 <19 Community Well l

l D-9 l

l t

APPENDIX E Sampling Location Maps I

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A AIR SAMPttNG point io NUMBERS P-1. P-2, P-3. P 4 P-6 4yINvERrEsRATES P-6,P-40 rorNr la NuMsERS L*.A WATER SAMPLING POINT 10 NUMBERS & SE0! MENT SAMPLING POINT 10 NUMBERS P-5. P-6, P-8, P 81, P-ll, P 25 W P-6, P 12, P-20 YEGETATION / VECETABLES 10 NUMBERS P-24,P-38 r,s S AMP 01.DGN l

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WATER SAMPL]NC PolNT 10 NUMB (R$ g $ColM(NT $AMPLlNG PQlNT 10 NipiSCR$

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. VEGETATION / VEGETABLES 10 NUMBERS P 24,P 38 E-7 SAMP02.DGN w -_-__ ____ _ _ _- __ - _- _ _

ML20247G162

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