Text

2002 Annual Radiological Environmental Monitoring Report for Prairie Island Nuclear Generating Plant
	ML031410154
Person / Time
Site:	Prairie Island
Issue date:	05/15/2003
From:	Solymossy J; Nuclear Management Co
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	+sunsi/sispmjr=200603, -RFPFR, ISFSI TS 6.2, L-PI-03-051, PI TS 5.6.2
	Download: ML031410154 (61)
	v • d • e

Commtted t Oed Prairie Island Nuclear Generating Plant Committed to NuclaExcetlence Operated by Nuclear Management Company, LLC L-PI-03-051 May 15, 2003 Pi TS 5.6.2 ISFSI TS 6.2 U S Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 PRAIRIE ISLAND NUCLEAR GENERATING PLANT DOCKETS 50-282, 50-306 AND 72-10 LICENSE Nos. DPR-42, DPR-60 AND SNM-2506 2002 ANNUAL RADIOLOGICAL ENVIRONMENTAL MONITORING REPORT Pursuant to Prairie Island Nuclear Generating Plant Technical Specification (PI TS) 5.6.2, Appendix A to Operating Licenses DPR-42 and DPR-60, and pursuant to Prairie Island Independent Spent Fuel Storage Installation Technical Specification (ISFSI TS) 6.2, Appendix A to Materials License DNM-2506, the Nuclear Management Company, LLC submits one copy of the Annual Radiological Environmental Monitoring Report for the period January 1, 2002 through December 31, 2002.

This letter contains no new commitments and no revisions to existing commitments.

Please address any comments or questions regarding this letter to Mr. Dale Vincent at 651-388-1121.

epM. Solymossy e-President, irie Island Nuclear Generating Plant CC Regional Administrator, USNRC, Region III Project Manager, Prairie Island Nuclear Generating Plant, USNRC, NRR NRC Resident Inspector- Prairie Island Nuclear Generating Plant Dr. John House, USNRC, Region lil Director of NMSS, USNRC Tim Donakowski, State of Minnesota

Attachment:

Annual report to the United States Nuclear Regulatory Commission, Radiation Environmental Monitoring Program, January 1 through December 31, 2002 1717 Wakonade Drive East Welch, Minnesota 55089-9642 Telephone: 651.388.1121

g. Environmental, Inc.

, Midwest Laboratory

. an Allegheny Technobogles Co.

700 Landwehr Road

Northbrook, IL 60062-2310 ph. (847) 564-0700

fax (847) 564-4517 XCEL ENERGY CORPORATION PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket No. 50-282 License No. DPR-42 50-306 DPR-60 ISFSI Docket No.72-10 SNM-2506 ANNUAL REPORT TO THE UNITED STATES NUCLEAR REGULATORY COMMISSION Radiation Environmental Monitoring Program January 1 to December 31, 2002 Prepared under Contract by ENVIRONMENTAL, Inc.

MIDWEST LABORATORY Project No. 8010 Approved:

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PREFACE The staff of Environmental, Inc., 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, operated by Nuclear Management Company, LLC for XCEL Energy Corporation.

The report was prepared by Environmental, Inc., Midwest Laboratory.

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TABLE OF CONTENTS Section Page Preface .................................................... ii List of Tables .................................................... iv List of Figures ........................................................ v.........v

1.0 INTRODUCTION

.1 2.0

SUMMARY

.2 3.0 RADIATION ENVIRONMENTAL MONITORING PROGRAM (REMP) .3 3.1 Program Design and Data Interpretation .3 3.2 Program Description .4 3.3 Program Execution .......................... 5 5:

3.4 Laboratory Procedures .5 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 Sampling Location Maps .D-1 iii

LIST OF TABLES No. Title Paqe 5.1 Sample Collection and Analysis Program ......................................... 15 5.2 Sampling Locations ......................................... 16 5.3 Missed Collections and Analyses ........................................ . 19 5.4 Radiation Environmental Monitoring Program Summary ........................................ 20 In addition, the following tables are in the Appendices:

Appendix A A-1 U.S. Environmental Protection Agency's Crosscheck Program results . Al-I 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 iv

LIST OF FIGURES No. Title Paqe 5.1 Offsite Ambient Radiation (TLDs), average of inner and outer ring indicator locations versus control, 1987-2002 ............................................ 13 5.2 Airborne Particulates; analysis for gross beta, average mean of all indicator locations (P-2,3,4,6) versus control location (P-1), 1987-2002 ............................................ 14 v

1.0 INTRODUCTION

This report summarizes and interprets results of the Radiation Environmental Monitoring Program (REMP) conducted by Environmental, Inc., Midwest Laboratory at the Prairie Island Nuclear Generating Plant, Red Wing, Minnesota, during the period January - December, 2002. 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 (Environmental, Inc., Midwest Laboratory, 2003b) available at Prairie Island Nuclear Generating Plant.

Prairie Island Nuclear Generating Plant is located on the Mississippi River in Goodhue County, Minnesota, owned by Xcel Energy Corporation and operated by Nuclear Management Company, LLC. The plant has two 575 MWe 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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2.0

SUMMARY

The Radiation Environmental Monitoring Program (REMP) required by the U.S. Nuclear Regulatory Commission (NRC) Technical Specifications for the Prairie Island Nuclear Generating Plant and the Independent Spent Fuel Storage Installation (ISFSI) is described.

Results for 2002 are summarized and discussed.

Program findings show background levels of radioactivity in the environmental samples collected in the vicinity of the Prairie Island Nuclear Generating Plant.

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3.0 RADIATION ENVIRONMENTAL MONITORING PROGRAM (REMP) 3.1 Program Design and Data Interpretation 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. The 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 total activity of fission products 10 days after reactor shutdown. On the other hand, 10 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 as calibration monitors and should not be considered radiological impact indicators.

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 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.

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3.1 Program Design and Data Interpretation (continued)

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 related 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 nuclear detonations.

3.2 Program 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, 2002). Maps of fixed sampling locations are included in Appendix D.

To monitor the air environment, airborne particulates are collected on membrane filters by continuous pumping at five locations. Airborne iodine is collected by continuous pumping through charcoal filters at these same 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 HPGe 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 CaSO 4 :Dy dosimeters with four sensitive areas at each location: ten in an inner ring in the general area of the site boundary, fifteen in the outer ring within a 4-5 mile radius, eight at special interest locations, and one control location, 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 and special interest locations are placed in the field at the same time as regular sets. The emergency set is returned to EIML quarterly for annealing and repackaging.

Ambient gamma radiation is monitored at the Independent Spent Fuel Storage Installation (ISFSI) Facility by twenty CaSO 4 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 gamma-emitting isotopes, including 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 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.

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3.2 Program Description (continued)

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.

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

(1) A partial air particulate/air iodine sample was obtained from location P-4 for the week ending 08-07-02. The probable cause is power loss due to storm activity.

(2) No air particulate/air iodine sample was available from location P-2 for the week ending 11-26-02, due to sampler pump failure.

(3) Milk samples were not available from P-37 (Welsch Farm) after October 29, 2002.

Dairy operations have been temporarily discontinued till spring, 2003.

Deviations from the program are summarized in Table 5.3.

3.4 Laboratorv Procedures All iodine-131 analyses in milk 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 HPGe detectors. Levels of airborne iodine-131 in charcoal samples were measured by gamma spectrometry.

Levels of iodine-131 in cabbage were determined by gamma spectrometry.

Tritium levels were determined by liquid scintillation technique.

Analytical Procedures used by Environmental, Inc. are on file and are available for inspection.

Procedures are based on those prescribed by the Health and Safety Laboratory of the U.S. Dep't of Energy, Edition 28, 1997, U.S. Environmental Protection Agency for Measurement of Radioactivity in Drinking Water, 1980, and the U.S. Environmental Protection Agency, EERF, Radiochemical Procedures Manual, 1984.

Environmental, Inc., Midwest Laboratory has a comprehensive quality control/quality assurance program designed to assure the reliability of the data obtained. Details of the Quality Assurance Program are presented elsewhere (Environmental, Inc., Midwest Laboratory, 2000). The program includes participation in nterlaboratory Comparison (Crosscheck) programs and results are presented in Appendix A.

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3.5 Program Modifications There were no program modifications for the year, 2002.

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 the location of the nearest milk animal, the nearest residence, and the nearest garden of greater than 500 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 program within 30 days, and sampling locations having lower calculated doses or a lower dose commitment 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 the updating of the radiation environmental monitoring program should sampling locations change within the 5 mile radius from the plant.

The 2002 Land Use Census was completed in October, 2002. There were no changes in any of the highest D/Q locations for dairy, nearest residence, or garden sites in 2002. The critical receptor location did not change in 2002, based on the results of the land use census.

No downstream irrigation of corn was discovered 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 scheduled collections and analyses were made except those listed in Table 5.3.

The 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 2002. The last reported test was conducted on October 16, 1980 by the People's Republic of China. There were no reported accidents involving a release to the environment at nuclear reactor facilities in 2002.

4.2 Summary of Preoperational 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 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/m 2 to 1,020 pCi/m2 , and these declining values are reflected throughout the various media tested.

In the air environment, ambient gamma radiation (TLDs) averaged 9.4 imR/4 weeks during preoperational studies. Gross beta in air particulates declined from levels of 0.38 to 0.037 pCim 3 . Average present day levels have stabilized at around 0.025 pCi/m 3 . Airborne radioiodine 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-1 37 and 1-131 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 lake 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 pC/L to 490 pCi/L. Present day environmental levels of tritium are below detection limits. 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 water, and 11.0 pCi/L for lake water.

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-I 37 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 pCi/g, respectively. Gross beta background 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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4.3 Program Findings Results obtained show background levels of radioactivity in the environmental samples collected in the vicinity of the Prairie Island Nuclear Generating Plant in 2002.

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 16.9 mR/91 days at inner ring locations to 17.8 mR/91 days at outer ring locations. The mean at special locations was 16.2 mR/91 days and 16.9 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 1987 through 2001. The results are tabulated below. No plant effect on ambient gamma radiation was indicated (Figure 5-1).

Average (Inner and Year Outer Rings) Control 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 1997 15.1 16.0 1998 16.7 17.3 1999 16.6 17.5 2000 17.0 17.1 2001 16.8 17.2 2002 17.4 16.9 Ambient gamma radiation as measured by thermoluminescent dosimetry.

Average quarterly dose rates (mR/91 days).

ISFSI Facility Operations Monitoring 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 87.6 mR/91 days inside the ISFSI earth berm and 20.1 mR/91 days outside the ISFSI earth berm. Three additional casks were placed on the ISFSI pad in 2002 for a total of seventeen loaded casks. The higher levels inside the earth berm are expected, due to the loaded spent fuel casks being in direct line-of-sight of 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 15.9 and 15.3 mR/91 days. Although the skyshine neutron dose rates are not directly measured, the neutron levels measured next to the casks are below the levels predicted in the ISFSI SAR Report, Table 7A-4, "TN-40 Dose Rates at Short Distances".

Therefore, the skyshine dose rates at farther distances from the casks should be at or below the calculated dose rates. No spent fuel storage effect on offsite ambient gamma radiation was indicated (Fig. 5-1).

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Airborne Particulates The average annual gross beta concentrations in airborne particulates were slightly higher at the indicator versus the control locations (0.028 pCi/m 3 and 0.023 pCi/m 3 , respectively) and similar to levels observed from 1987 through 2001. The results are tabulated below.

Average of Year Indicators Control Concentration (Ci/m3 )

1987 0.024 0.023 1988 0.030 0.030 1989 0.028 0.027 1990 0.024 0.023 1991 0.025 0.025 1992 0.023 0.021 1993 0.022 0.019 1994 0.022 0.022 1995 0.022 0.022 1996 0.023 0.020 1997 0.021 0.021 1998 0.022 0.018 1999 0.024 0.022 2000 0.025 0.025 2001 0.023 0.023 2002 0.028 0.023 Average annual gross beta concentrations in airborne particulates.

A spring peak in beta activity had been observed almost annually for many years (Wilson et al.,

1969). It had been attributed to fallout of nuclides from the stratosphere (Gold et al., 1964). It was pronounced in 1981, occurred to a lesser degree in 1982, and has not occurred since 1983.

The highest averages for gross beta occur during the months of January and December, and the first and fourth quarters, as in 1985 through 2002.

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. Secondly, an identical pattern was observed at the Monticello Nuclear Generating Plant, about 100 miles distant from the Prairie Island Nuclear Generating Plant (Xcel Energy Corp., 2003).

Gamma spectroscopic analysis of quarterly composites of air particulate filters yielded similar results for indicator and control locations. Beryllium-7, which is produced 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.

Airborne Iodine Weekly levels of airborne iodine-131 were below the lower limit of detection (LLD) of 0.07 pCi/m 3 in all samples. There was no indication of a plant effect.

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Milk lodine-131 results were below the detection limit of 1.0 pCi/L in all samples. Cs-1 37 results were below the LLD level of 15 pCVL 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 2002 show no radiological effects of the plant operation.

Drinkinq Water In drinking water from the City of Red Wing well, tritium activity measured below the LLD level of 182 pCi/L in all samples.

Gross beta concentrations averaged 8.7 pCi/L throughout the year, ranging from 5.8 - 10.8 pCi/L. These concentrations were similar to or slightly higher than levels observed from 1987 through 2001. The most likely contribution is the relatively high levels of naturally-occurring radium. Gamma spectroscopy indicates the presence of lead and bismuth isotopes, which are daughters of the radium decay chain. There is no indication from the 2002 data of any effect of plant operation.

Year Gross Beta (pCi/L) 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 1997 _ 5.1 1998 5.4 1999 5.3 2000 10.1 2001 8.3 2002 8.7 Average annual concentrations; Gross beta in drinking water.

River Water For all upstream and downstream collections, quarterly composite tritium levels measured below the LLD level of 164 pCi/L. Gamma-emitting isotopes were below detection limits in all samples.

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Well Water Tritium was detected in one quarterly (4th quarter) well water composite (P-24, Suter), at a concentration of 219 pCi/L. This is well below the Environmental Protection Agency's drinking water standard of 20,000 pCi/L. At the control well P-41, Huppert Farm and the three indicator wells (P-8, Community Center, P-6, Lock and Dam No. 3, P-9, Plant Well No. 2) no tritium was detected above the LLD level of 156 pCVL.

Gamma-emitting isotopes were below detection limits in all samples.

CroPs Two samples of broadleaf vegetation, cabbage leaves, were collected in August and analyzed for gamma-emitting isotopes, including iodine-131. The 1-131 level was below 0.008 pCi/g wet weight in both samples. With the exception of naturally-occurring potassium-40, all other gamma-emitting isotopes were below their respective detection limits. There was no indication of a plant effect.

The field sampling personnel conducted an annual land use survey and found no river water taken for irrigation into fields within 5 miles downstream from the Prairie Island Plant. The collection and analysis of corn samples was not required.

Fish Fish samples were collected in May and September, 2002 and analyzed for gamma emitting isotopes. Only naturally-occurring potassium-40 was detected, and there was no significant difference 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 September, 2002. All gamma-emitting isotopes were below their respective detection limits. There was no indication of any plant effect.

Bottom and Shoreline Sediments Upstream, downstream and downstream recreational area shoreline sediment collections were made in May and September, 2002 and analyzed for gamma-emitting isotopes. Trace levels of cesium-137 were detected in three of the six samples collected, at both indicator and control locations, averaging 0.050 pCi/g dry weight in two downstream samples and 0.052 pCi/g dry weight in one control sample, indicating the influence of fallout deposition. The only other gamma-emitting isotopes detected were naturally-occurring beryllium-7 and potassium-40. There was no indication of a plant effect.

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5.0 FIGURES AND TABLES 12

Figure 5-1. Offsite Ambient Radiation (TLDs); average of inner and outer ring indicator locations versus control location.

-- Indicatorl 20 19 F 4 +/- t 4 4- F I F 4 F-f --

18 17 l I I< == = 11 I

16 15 _I I I ,_

___~~ ==---

_ I n

14

~

i2 13 E

12 11 10 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 20 *-O- Control (P-01C)

I I I 19 18 17 n

16 15 14 I _ I _

t I _ I _ I I _ _

_ _ _ I__

13 4 +/- F 4 F 4 F 4 F - F 4 -

E 12 + + F 4 + F 4 F 4 F 4 F-4 - ____

11 4 4 + F 4 + + 4 F 4 F 4 F 4 I

A ____

10-

!i 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 13

Figure 5-2. Airborne Particulates; analysis for gross beta, average mean of all indicator locations versus control location.

j---lndicators (P-2,3,4,6) 0.035 0.033 0.031 0.029 I

0.027 0.025 E~ 0.023 a 0.021 0.019 0.017 0.015 I _ _ _ I lI I _ _ _ _ _ _ _ I _ I_

987 1988 1989 1990 1991 I! 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 l--- Control (P-1)

T 0.035

-I-0.033 -

0.031 0.029 _ __ __ _ ___ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -. _ _ _ _ _ _ _ I 0.027-7/-

- Al )--I------F +-4 + -!--+ F + 4--

0.025 -

E 0.023 lI I AFX C) 0.021 -

__ _ I _ _ _ _ I -- /--- _ _ I_ I _ I _ I -

0.019 0.017 ll l l ., l _ _l__ _l_ _ _I Il~~~~~~~~~~~

nni I j 1987 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 14

PRAIRIE ISLAND Table 5.1. Sample collection and analysis program, Prairie Island Nuclear Generating Plant.

Collection Analysis Location Type and Type and Medium No. Codes (and Type)a Frequencyb Frequencyc Ambient radiation (TLD's) 54 P-01A- P-10A C/Q Ambient gamma P-01B - P-15B P-0 1S - P-08S P-01 IA - P-081A P-01 IB - P-081B P-01 IX- P-041X, P-01C Airbome Particulates 5 P-1 (C), P-2, CNw GB, GS (QC of P-3, P-4, P-6 each location)

Airborne Iodine 5 P-1 (C), P-2, P-3, P-4, P-6 C/W 1-131 Milk 5 P-14, P-18, P-37, P-42 G/M 0 1-131, GS P-41 [C]

River water 2 P-5(C), P-6 GIW GS(MC), H-3(QC)

Drinking water 1 P-1I GIW GB(MC), 1-131 (MC)

GS (MC), H-3 (QC)

Well water 5 P-6, P-8, P-9, P-24, P-41 (C) GIQ H-3, GS Edible cultivated crops - 2 P-38(C), P-24 GA GS (1-131) leafy green vegetables Fish 2 P-19(C), P-13 G/SA GS (one species, edible portion)

Periphyton or invertebrates 2 P-40(C), P-6 G/SA GS Bottom sediment 2 P-20(C), P-6 GISA GS Shoreline sediment 1 P-12 GISA GS a Location codes are defined in Table 5.2. 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 = annually.

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).

15

PRAIRIE ISLAND Table 5.2. Sampling locations, Prairie Island Nuclear Generating Plant.

Distance and Direction from Code Typea Collection Site Sample Typeb Reactor

P-1 C Air Station P-1 AP, Al 11.8 mi @ 316 0/NNW P-2 Air Station P-2 AP, Al 0.5 mi @ 294°/WNW P-3 Air Station P-3 AP, Al 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 and Dam #3 & Air AP, Al, RW Station P-6 WW, BS, BOC 1.6 mi @ 129°/SE P-8 Community Center WW 1.0 mi @ 3210/WNW P-9 Plant Well #2 WW 0.3 mi @ 3060/NW P-11 Red Wing Service Center DW 3.3 mi @ 158°/SSE P-12 Downstream of Plant Ss 3.0 mi @ 11 6/ESE P-1 3 Downstream of Plant Fc 3.5 mi @ 113°/ESE P-14 Gustafson Farm M 2.3 ml @ 1730/S P-18 Christiansen Farm M 3.8 mi @ 88°1E P-1 9 C Upstream of Plant FC 1.3 mi @ 0°/N P-20 C Upstream of Plant BS 0.9 ml @ 45 0/NE P-24 Suter Residence VE, WW 0.6 mi @ 158°/SSE P-37 Welsch Farm M 4.1 mi @ 870/E P-38 C Cain Residence VE 14.2 mi @ 359 0/N P-40 C Upstream of Plant BOC 0.4 mi @ 0°/N P-41 C Huppert Farm M, WW 13.8 mi @ 354 0/N P-42 Rother Farm M 4.3 ml. @ 264 0/W General Area of the Site Boundary P-01A Property Line TLD 0.4 mi @ 359°/N P-02A Property Line TLD 0.3 mi @ 10°/N P-03A Property Line TLD 0.5 mi @ 1830/S P-04A Property Line TLD 0.4 mi @ 2040/SWW P-05A Property Line TLD 0.4 mi @ 2250/SW P-06A Property Line TLD 0.4 mi @ 249°lWSW 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-1 OA Property Line TLD 0.5 mi @ 3330/NNW 16

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

Distance and Direction from Code Typea Collection Site Sample Typeb Reactor Approximatelv 4 to 5 miles Distant from the Plant P-01B Thomas Killian Residence TLD 4.7 mi @ 3550/N P-02B Roy Kinneman Residence TLD 4.8 mi @ 17 0/NNE P-03B Wayne Anderson Farm TLD 4.9 mi @ 46°lNE P-04B Nelson Drive (Road) TLD 4.2 ml @ 61°/ENE P-05B County Road E and Coulee TLD 4.2 mi @ 1020/ESE P-06B William Hauschbilt Residence TLD 4.4 mi @ 112 0 /ESE P-07B Red Wing Public Works TLD 4.7 mi @ 140 0 SE P-08B David Wnuk Residence TLD 4.1 mi @ 165 0 /SSE P-09B Highway 19 South TLD 4.2 mi @ 187°/S P-1 OB Cannondale Farm TLD 4.9 mi @ 2000/SSW P-1IB Wallace Weberg Farm TLD 4.5 mi @ 221 0/SW P-12B Ray Gergen Farm TLD 4.6 mi @ 251°/WSW P-13B Thomas O'Rourke Farm TLD 4.4 mi @ 270 01W P-14B David J. Anderson Farm TLD 4.9 ml @ 306°/NW P-15B Holst Farms TLD 3.8 mi @ 3450/NNW Special Interest Locations P-01 S Federal Lock & Dam #3 TLD 1.6 mi @ 1290/SE P-02S Charles Suter Residence TLD 0.5 mi @ 155 0 SSE P-03S Carl Gustafson Farm TLD 2.2 mi @ 173°/S P-04S Richard Burt Residence TLD 2.0 mi @ 202 0/SSW P-05S Kinney Store TLD 2.0 mi @ 270 0/W P-06S Earl Flynn Farm TLD 2.5 mi @ 299°/WNW P-07S Indian Community TLD 0.7 mi @ 271 M P-08S Indian Community TLD 0.7 mi @ 287 0/NWW P-01C C Robert Kinneman Farm TLD 11.1 mi @ 331°/NNW 17

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

Approximate Type of Distance and Direction Code Typea Collection Site Sampleb from ISFSI Center.

ISFSI Area Inside Earth Berm P-01IA ISFSI Nuisance Fence TLD 190' @ 45 0/NE P-021A ISFSI Nuisance Fence TLD 360' @ 82°/E P-031A ISFSI Nuisance Fence TLD 370' @ 100°/E P-041A ISFSI Nuisance Fence TLD 200' @ 134°/SE P-051A ISFSI Nuisance Fence TLD 180' @ 219 0/SW P-061A ISFSI Nuisance Fence TLD 320' @ 258 0/WSW P-071A ISFSI Nuisance Fence TLD 320' @ 281°/WNW P-081A ISFSI Nuisance Fence TLD 190' @ 318 0/NW P-OIX ISFSI Nuisance Fence TLD 140' @ 1800/S P-021X ISFSI Nuisance Fence TLD 310' @ 270 0/W P-031X ISFSI Nuisance Fence TLD 140' @ 0°/N P-041X ISFSI Nuisance Fence TLD 360' @ 90°/E ISFSI Area Outside Earth Berm P-01 IB ISFSI Berm Area TLD 340' @ 3°/N P-0218 ISFSI Berm Area TLD 380' @ 28 0/NNE P-031B ISFSI Berm Area TLD 560'@ 850/E P-041B ISFSI Berm Area TLD - 590' @ 165 0 SSE P-051B ISFSI Berm Area TLD 690' @ 1860/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 0/NNW a "C' denotes control location. All other locations are indicators.

b Sample Codes:

AP Airbome particulates F Fish Al Airbome Iodine M Milk BS Bottom (river) sediments SS Shoreline Sediments BO Bottom organisms SW Surface Water (periphyton or macroinvertebrates) VE Vegetation/vegetables DW Drinking water WW Well water c Distance and direction data for fish and bottom organisms are approximate since availability of sample specimen may vary at any one location.

18

Table 5.3. Missed collections and analyses at the Prairie Island Nuclear Generating Plant.

All required samples were collected and analyzed as scheduled with the following exceptions:

Collection Reason for not Sample Analysis Location Date or conducting REMP Plans for Preventing Type Period as required Recurrence AP/AI Beta, P-04 8/7/2002 Storm related power outage. None required 1-131 Partial sample collected.

AP/AI Beta, P-02 11/26/2002 No sample; Sampler pump was replaced.

1-131 Sampler pump failure.

Ml Gamma, M-28 10/29/2002 Welsch farm temporarily Welsch will inform the PINGP 1-131 through out of dairy business. upon resumption of operation 12/31/2002 in Spring, 2003.

19

Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Prairie Island Nuclear Power Station Docket No. 50-282, 50-306 Location of Facility Goodhue, Minnesota Reporting Period January-December, 2002

( County, State )

Indicator Locaton with Highest Control Number Sample Type and Locatons Annual Mean Locations Non-Type Number of LLDb Mean (F)' Mean (F)c Mean (F)f Routine (Units) Analyses" Range' Locationd Range' Rangec Results' TLD (Inner Ring, Gammaf 40 3.0 16.9 (40140) P-06A 18.1 (4/4) (See Control 0 Area at Site (14.4-21.0) 0.4 mi @ 249 WSW (15.9-21.0) below.)

Boundary) mR191 days)

TLD (Outer Ring, Gamma' 60 3.0 17.8 (60/60) P-02B, Roy Kinneman, 20.3 (4/4) (See Control 0 4-5 mi. distant) (13.2-24.0) 4.8 mi @ 170 NNE (17.9-24.0) below.)

mR/91 days)

TLD (Special Gammaf 32 3.0 16.2 (32/32) P-03S, Gustafson Farm, 18.8 (4/4) (See Control 0 Interest Areas) (12.5-21.6) '2.2 mi @ 173' /S (16.9-21.6) below.)

mR191 days)

TLD (Control) Gammaf 4 3.0 None P-OIC, R. Kinneman, 16.9 (4t4) 16.9 (414) 0 mR/91 days) 11.1 mi @ 331° /NNW (15.0-18.9) (15.0-18.9)

Airbome GB 259 0.005 0.028 (207/207) P-06, Air Station 0.029 (52152) 0.023 (52/52) 0 Particulates (0.011-0.066) 1.6 mi @ 1290 /SE (0.013-0.062) (0.013-0.057)

(pCi/m 3)

GS 20 Be-7 0.015 0.070 (16/16) P-06, Air Station 0.071 (4/4) 0.057 (4/4) 0 (0.055-0.088) 1.6 mi @ 1290 ISE (0.059-0.088) (0.046-0.065)

Mn-54 0.0007 < LLD - - < LLD 0 Co-58 0.0008 < LLD - - < LLD 0 Co-60 0.0009 < LLD - - < LLD 0 Zn-65 0.0009 < LLD - - < LLD 0 Zr-Nb-95 0.0011 < LLD - - < LLD 0 Ru-103 0.0010 < LLD - - < LLD 0 Ru-106 0.0061 < LLD - - < LLD 0 Cs-1 34 0.0008 < LLD - - < LLD 0 Cs-1 37 0.0006 < LLD - - < LLD 0 Ba-La-140 0.0029 < LLD - - < LLD 0 Ce-141 0.0020 < LLD - - < LLD 0 Ce-144 0.0044 < LLD - - < LLD 0 Airbome Iodine 1-131 259 0.07 < LLD - - < LLD 0 3

(pCim )

20

Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Prairie Island Nuclear Power Station Docket No. 50-282, 50-306 Location of Facility Goodhue, Minnesota Reporting Period January-December, 2002 (County, State )

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)c Mean (F)c Mean (F)e Routine (Units) Analyses' Range' Locationd Range Range' Resultse Milk (pCi/L) 1-131 88 1.0 < LLD - < LLD 0 GS 88 K-40 200 1427 (70/70) P-14, Gustafson Farm 1486 (18 /18) 1415 (18118) 0 (1207-1603) 2.3 mi@ 173° IS (1406-1567) (1316-1589)

Cs-134 15 < LLD - < LLD 0 Cs-137 15 < LLD - < LLD 0 Ba-La-140 15 < LLD - - < LLD 0 River Water H-3 8 164 < LLD - - < LLD 0 (pCi/L)

GS 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 Ba-La-140 15 < LLD - - < LLD 0 Ce-144 49 < LLD - - < LLD 0 21

Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Prairie Island Nuclear Power Station Docket No. 50-282, 50-306 Location of Facility Goodhue, Minnesota Reporting Period January-December, 2002

( County, State )

Indicator Locaton with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)' Mean (F)c Mean (F)c Routine (Units) Analysesa Rangec Locationd Range' Rangec Results" Drinking Water GB 12 1.0 8.7 (12/12) P-11, Red Wing S.C. 8.7 (12/12) None 0 (pCi/L) (5.8-10.8) 3.3 mi @ 1580 /SSE (5.8-10.8) 1-131 12 1.0 < LLD - None 0 H-3 4 164 < LLD - - None 0 GS 12 Mn-54 15 < LLD - - None 0 Fe-59 30 < LLD - - None 0 Co-58 15 < LLD - - None 0 Co-60 15 < LLD - - None 0 Zn-65 30 < LLD - - None 0 Zr-Nb-95 15 < LLD - - None 0 Cs-134 10 < LLD - - None 0 Cs-137 18 < LLD - - None 0 Ba-La-140 15 < LLD - - None 0 Ce-144 51 < LLD - - None 0 Well Water H-3 20 156 219 (1/16) P-24, Suter Residence 219 (1/4) < LLD 0 (pCUL) 0.6 mi @ 158°/SSE GS 20 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 10 < LLD - - < LLD 0 Cs-137 18 < LLD - - < LLD 0 Ba-La-140 15 < LLD - - < LLD 0 Ce-144 52 < LLD - - < LLD 0 Crops - Cabbage 1-131 2 0.008 < LLD - - < LLD 0 (pCitgwet) 22

Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Prairie Island Nuclear Power Station Docket No. 50-282, 50-306 Location of Facility Goodhue, Minnesota Reporting Period January-December, 2002

( County. State )

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)0 Mean (F)c Mean (F)0 Routine (Units) Analysesa Range' Locationd Range' Range' Resultse Fish GS 4 (pCig wet) K-40 0.10 2.67 (2/2) P-19, Upstream 3.00 (212) 3.00 (2/2) 0 (2.53-2.81) 1.3 mi. @ 0 IN (2.87-3.13) (2.87-3.13)

Mn-54 0.015 < LLD - - < LLD 0 Fe-59 0.040 < LLD - - < LLD 0 Co-58 0.018 < LLD - - < LLD 0 Co-60 0.016 < LLD - - < LLD 0 Zn-65 0.037 < LLD - - < LLD 0 Zr-Nb-95 0.025 < LLD - - < LLD 0 Cs-134 0.016 < LLD - - < LLD 0 Cs-137 0.017 < LLD - - < LLD 0 Ba-La-140 0.042 < LLD - - < LLD 0 Invertebrates GS 4 (pCVg wet) Be-7 0.63 < LLD - - < LLD 0 K-40 1.63 < LLD - - < LLD 0 Mn-54 0.072 < LLD - - < LLD 0 Co-58 0.057 < LLD - - < LLD 0 Co-60 0.052 < LLD - - < LLD 0 Zn-65 0.14 < LLD - - < LLD 0 Zr-Nb-95 0.11 < LLD - - < LLD 0 Ru-103 0.080 < LLD - - < LLD 0 Ru-106 0.49 < LLD - - < LLD 0 Cs-134 0.091 < LLD - - < LLD 0 Cs-1 37 0.063 < LLD - - < LLD 0 Ba-La-140 0.26 < LLD - - < LLD 0 Ce-141 0.16 < LLD - - < LLD 0 Ce-144 0.50 < LLD - - < LLD 0 23

Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Prairie Island Nuclear Power Station Docket No. 50-282, 50-306 Location of Facility Goodhue, Minnesota Reporting Period January-December, 2002

( County, State )

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)c Mean (F)c Mean (F)c Routine (Units) Analyses" Range' Locationd Rangec Rangec Resultse Bottom and GS 6 Shoreline Be-7 0.25 1.05 (1/4) P-6. Lock and Dam #3 1.05 (1/2) 0.56 (112) 0 Sediments 1.6 mi @ 129°/SE 0 (pCUg dry) K-40 0.10 7.63 (4/4) P-20, Upstream 9.43 (212) 9.43 (2/2) 0 (6.02-8.80) 0.9 mi. @ 45 /NE (8.03-10.83) (8.03-10.83)

Mn-54 0.019 < LLD - - < LLD 0 Co-58 0.025 < LLD - - < LLD 0 Co-60 0.021 < LLD - - < LLD 0 Zn-65 0.061 < LLD - - < LLD 0 Zr-Nb-95 0.043 < LLD - - < LLD 0 Ru-i 03 0.036 < LLD - - < LLD 0 Ru-106 0.17 < LLD - - < LLD 0 Cs-134 0.025 < LLD - - < LLD 0 Cs-137 0.017 0.050 (2/4) P-6, Lock and Dam #3 0.053 (1/2) 0.052 (1/2) 0 (0.046-0.053) 1.6 mi @ 1290/SE Ba-La-140 0.16 < LLD - < LLD 0 Ce-141 0.068 < LLD -- < LLD 0 Ce-144 0.10 < LLD < LLD 0 0 GB = gross beta, GS = gamma scan.

b LLD = nominal lower limit of detection based on a 4.66 sigma counting error for background sample.

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/or station code (Table 2) and (2) by distance (miles) and direction relative to reactor site.

e Non-routine results are those which exceed ten tmes the control station value. If no control station value is available, the result is considered non-routine if it exceeds ten Ume the typical preoperational value for the medium or location.

24

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.

Environmental, Inc., Midwest Laboratory 2001a through 2003a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January-December, 2000 through 2002.

2001 b through 2003b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December, 2000-2002.

2000. Quality Assurance Program Manual, Rev. 0, 11 October 2000.

2000. Quality Control Procedures Manual, Rev. 0, 21 September 2000.

2000. Quality Control Program, Rew 0, 12 October 2000.

Gold, S., H. W. Barkhau, B. Shlein, and B. Kahn, 1964. Measurement of Naturally Occurring Radionuclides in Air, in the Natural Environment, 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.

1979b to 1983b. Radiation Environmental 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, No. 12, 730-746.

Northem 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.

1979 to 2000. Prairie Island Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 1978 through 1999. Minneapolis, Minnesota.

25

6.0 REFERENCES

CITED (continued)

Prairie Island Nuclear Generating Plant, 2002. Radiological Environmental Monitoring for Prairie Island Nuclear Generating Plant, Radiation Protection Implementing Procedures, 4700 series.

Teledyne Brown Engineering Environmental Services, Midwest Laboratory. 1984a to 2000a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January - December, 1983 through 1999.

1984b to 2000b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December, 1983 through 1999.

U.S. Dep't of Energy 1997 HASL-300, Edition 28, Procedures Manual, Environmental Measurements Laboratory, New York, NY.

U.S. Environmental Protection Agency . 1980. Prescribed Procedures for Measurement of Radioactivity in Drinking Water, Cincinnati, Ohio (EPA-600/4-80-032).

1984. Eastern Environmental Radiation Facility, Radiochemistry Procedures Manual, Montgomery, Alabama (EPA-520/5-84-006).

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

Xcel Energy Corporation. 2003. Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 2002 (prepared by Environmental, Inc., Midwest Laboratory). Northbrook, Illinois 26

-CroEnvironmental, Inc.

cMdwest Laboratory an Abgheny Techndoges Co.

7=LanlIRoa .NothbCkIL MM822 C847)58440oo t(44-4"tT APPENDIX A INTERLABORATORY COMPARISON PROGRAM RESULTS NOTE: Environmental Inc., Midwest Laboratory participates in intercomparison studies administered by Environmental Resources Associates, and serves as a replacement for studies conducted previously by the U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada. Results are reported in Appendix A. TLD Intercomparison results, in-house spikes, blanks, duplicates and mixed analyte performance evaluation program results are also reported. Appendix A Is updated four Umes a year; the complete Appendix is Included in March, June, September and December monthly progress reports only.

January, 2002 through December, 2002

Appendix A Interlaboratorv Comparison Pro-ram Results Environmental, Inc., Midwest Laboratory, formerly Teledyne Brown Engineering Environmental Services Midwest Laboratory 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 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 a laboratory's analytical procedures and to alert it of 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 control limits indicate a need to check the instruments or procedures used.

Results in Table A-1 were obtained through participation in the environmental sample crosscheck program administered by Environmental Resources Associates, serving as a replacement for studies conducted previously by the U.S. EPA Environmental Monitoring Systems Laboratory, Las Vegas, Nevada.

The results in Table A-2 were obtained for Thermoluminescent Dosimeters (TLDs), via International Intercomparison of Environmental Dosimeters under the sponsorships listed in Table A-2. Results of internal laboratory testing is also 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. 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

Attachment A ACCEPTANCE CRITERIA FOR 'SPIKED' SAMPLES LABORATORY PRECISION: ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSESa One standard deviation Analysis Level for single determination Gamma Emitters 5 to 100 pCiliter or kg 5.0 pCilliter

> 100 pCiAiter or kg 5%of known value Strontium_89b 5 to 50 pCilliter or kg 5.0 pCiJliter

> 50 pCiAiter or kg 10% of known value Strontium-9Ob 2 to 30 pCiliter or kg 5.0 pCiAiter

> 30 pCiliter or kg 10% of known value Potassium-40 > 0.1 gliter or kg 5%/. of known value Gross alpha 20 pCiJiter 5.0 pCiliter

> 20 pCi/liter 25% of known value Gross beta 100 pCi/liter 5.0 pCiAiter

> 100 pCiAiter 5% of known value Tritium 4,000 pCi/liter 1s = (pCi/liter) 169.85 x (known) 0 0933

> 4,000 pCi/liter 10% of known value Radium-226,-228 0.1 pCi/liter 15% of known value Plutonium 0.1 pCiAiter, gram, or sample 10% of known value Iodine-131, 55 pCi/liter 6.0 pCiliter Iodine-129b > 55 pCiliter 10% of known value Uranium-238, 35 pCi/iter 6.0 pCi/liter Nickel-63b > 35 pCi/liter 15% of known value Technetium_99b Iron-55b 50 to 100 pCi/liter 10 pCi/liter

> 100 pCi/iter 10% of known value Othersb 20% of known value

' From EPA publicaUon, 'Environmental Radioactivity Laboratory Intercomparison Studies Program, Fiscal Year, 1981-1982. EPA-6004-81004.

b Laboratory limit.

A2

TABLE A-1. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)'.

Concentration (pCiVL)

Lab Code Date Analysis Laboratory ERA Control Resultb Result Limits STW-940 02/20/02 Sr-89 53.0 +/-2.5 55.3 +/- 5.0 46.6 - 64.0 STW-940 02/20102 Sr-90 16.6 0.5 15.9 +/-5.0 7.2 - 24.6 STW-942 02/20102 Gr. Alpha 6.5 +/-0.6 8.0 +/- 5.0 0.0 - 16.7 STW-942 02120/02 Gr. Beta 45.7 +/-3.1 48.3 +/- 5.0 39.6 - 57.0 S1W-944 02t20102 Ba-I 33 25.8 +/-1.5 28.9 +/- 5.0 20.2 - 37.6 STW-944 02120/02 Co-60 76.9 +/-2.7 73.4 +/- 5.0 64.7 - 82.1 STW-944 02120/02 Cs-134 38.7 +/- 1.6 42.1 +/- 5.0 33.4 - 50.8 S1W-944 02t20102 Cs-i 37 92.9 + 2.7 88.8 +/- 5.0 80.1 - 97.5 STW-944 02t20/02 Ra-226 15.3 +/-0.7 14.3 +/- 2.2 10.6 - 18.0 STW-944 02/20/02 Ra-228 17.5 +/-0.4 16.9 4.2 9.6 - 24.2 STW-944 02/20/02 Uranium 23.8 +/- 1.1 28.3 +/- 3.0 23.1 - 33.5 STW-944 02/20/02 Zn-65 361.0 +/- 9.2 359.0 +/- 35.9 298.0 - 420.0 STW-951 05/22/02 Gr. Alpha 23.9 +/- 2.5 22.8 +/- 5.7 13.0 - 32.6 S1W-951 05122/02 Ra-226 5.9 +/- 0.5 6.1 +/-0.9 4.5 - 7.7 STW-951 05/22/02 Ra-228 5.6 +/-0.9 4.5 + 1.1 2.6 - 6.5 STW-951 05122/02 Uranium 7.6 +/- 0.2 9.3 +/- 3.0 4.1 - 14.5 S1W-952 05/22/02 Co-60 37.9 +/- 0.7 39.1 +/-5.0 30.4 - 47.8 STW-952 05/22/02 Cs-134 14.5 *0.8 17.1 +/-5.0 8.4 - 25.8 STW-952 05/22102 Cs-137 50.0 +/-2.0 52.1 +/-5.0 43.4 - 60.8 STW-952 05/22102 Gr. Beta 171.0 +/-2.5 189.0 +/-28.4 140.0 - 238.0 STVV-952 05/22102 Sr-89 28.4 +/-4.8 31.7 +/-5.0 23.0 - 40.4 S1W-952 05122102 Sr-90 32.4 +/-3.1 28.3 +/- 5.0 19.6 - 37.0 STW-953 d 05/22/02 H-3 13900.0 +/- 100.0 17400.0 +/- 1740.0 14400.0 - 20400.0 STW-954 05/22/02 1-131 14.6 +/-0.3 14.7 +/-2.0 11.2 - 18.2 STW-965 08/21/02 Ba-133 71.9 +/-2.1 80.0 +/- 8.0 66.4 - 93.6 STW-965 08(21/02 Co-60 23.8 +/- 1.0 23.3 +/-5.0 14.6 - 32.0 STW-965 08/21(02 Cs-134e 62.9 1.2 71.7 +/- 5.0 63.0 - 80.4 STW-965 08121/02 Cs-137 219.3 +/- 10.7 214.0 +/- 10.7 195.0 - 233.0 STW-965 08/21102 Gr. Alpha 74.4 +/- 0.6 58.8 +/- 14.7 33.5 - 84.1 STW-965 08121/02 Gr. Beta 26.7 +/- OA 21.9 +/- 2.2 13.2 - 30.6 STW-965 08/21/02 Ra-226 5.0 +/- 0.5 5.0 *0.8 3.7 - 6.3 STW-965 08/21/02 Ra-228 6.0 +/- 0.7 4.7 +/- 1.2 2.7 - 6.7 STW-965 08/21/02 Sr-89 28A +/- 1.5 29.0 5.0 20.3 - 37.7 STW-965 08/21/02 Sr-90 36.5 +/-1.1 36.4 +/- 5.0 27.7 - 45.1 STW-965 08/21102 Uranium 4.1 +/- 0.1 5.0 +/- 3.0 0.0 - 10.2 STW-965 08/21102 Zn-65 92.4 + 2.2 95.7 +/- 9.6 79.4 - 112.0 STW-966 11/20/02 Gr. Alpha 9.3 +/- 0.4 12.2 +/- 5.0 3.5 - 20.9 STW-966 11/20/02 Gr. Beta 44.7 +/- 1.0 47.0 +/- 5.0 38.3 - 55.7 STW-967 11120/02 H-3 10100.0 +/- 38.7 10200.0 1020.0 8440.0 - 12000.0 STW-968 11/20/02 Ra-226 11.6 +/-0.1 12.1 +/-1.8 9.0 - 15.2 STW-968 11(20102 Ra-228 16.0 +/-1.4 15.1 +/-3.8 8.6 - 21.6 STW-968 11/20/02 Uranium 15.5 +/- 0.5 19.2 +/-3.0 14.0 - 24.4 STW:969 11/20/02 1-131 6.0 +/- 0.4 6.8 +/- 2.0 3.3 - 102 Al-I

TABLE A-1. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA)'.

Concentration (pCiL)

Lab Code Date Analysis Laboratory ERA Control Resultb Result' Limits STW-970 11/20/02 Co-60 104.0 +/- 7.1 104.0 +/- 5.2 95.0 - 113.0 STW-970 11120/02 Cs-1 34 48.2 +/-2.3 55.5 +/- 5.0 46.8 - 64.2 STW-970 11/20/02 Cs-137 109.0 +/-12.6 117.0 +/- 5.9 107.0 - 127.0 STW-970 11/20102 Gr. Beta 252.0 +/- 26.8 288.0 +/- 49.5 244.0 - 416.0 STW-970 11/20102 Sr-89 43.2 +/- 0.7 47.6 +/- 5.0 38.9 - 56.3 S1W-970 11120/02 Sr-90 7.5 +/- 0.2 7.6 +/- 5.0 0.0 - 16.2 STW-971 11/20/02 Gr. Alpha 74.9 +/-1.5 103.0 +/- 25.8 58.4 - 148.0 STW-971 11/20/02 Ra-226 8.9 0.0 9.1 +/-1.4 6.7 - 11.5 S1W-971 11120102 Ra-228 15.3 +/-0.1 17.8 +/- 4.5 10.1 - 25.5 STW-971. 11/20/02 Uranium 51.7 +/-1.6 61.7 +/- 6.2 51.0 - 72.4

' Results obtained by Environmental, Inc., Midwest Laboratory as a partcipant In the environmental samples crosscheck program operated by Environmental Resources Associates (ERA).

t Unless otherwise Indicated, the laboratory result Isgiven as the mean +/- standard deviation for three determinations.

' Results are presented as the known values, expected laboratory precsion (1 sigma, 1 determination) and control limits as provided by ERA.

d Analysis was repeated; result of reanalysis: 16114+/-487 pCi/L.

' ERA acknowledged an unacceptably high percentage of failure for Cs-134 and questioned Its own control limits.

No problems were Identified in the analysis.

A1-2

TABLE A-2. Crosscheck program results; Thermoluminescent Dosimetry, (TLDs).

mR Lab Code TLD Type Date Measurement Known Lab Result Control Value +/- 2 sigma Limits Environmental. Inc.

2001-1 CaSO4: Dy Cards 1212412001 Reader 1, #1 3.98 3.71 0.12 2.79 - 5.17 2001-1 CaSO4: Dy Cards 12124/2001 Reader 1,#1 3.98 3.38 +/- 0.09 2.79 - 5.17 2001-1 CaSO4: Dy Cards 12124/2001 Reader 1 #2 7.07 7.89 +/- 0.18 4.95 - 9.19 2001-1 CaSO4: Dy Cards 12/24/2001 Reader 1, #2 7.07 7.64 +/- 0.25 4.95 - 9.19 2001-1 CaSO4: Dy Cards 12/24/2001 Reader 1,#3 15.9 18.62 +/- 0.40 11.13 - 20.67 2001-1 CaSO4: Dy Cards 12/2412001 Reader 1, #3 15.9 19.58 +/-0.12 11.13 - 20.67 2001-1 CaSO4: Dy Cards 1212412001 Reader 1, #4 63.61 78.24 +/- 1.23 44.53 - 82.69 2001-1 CaSO4: Dy Cards 12/24/2001 Reader 1, #4 63.61 79.89 +/- 2.47 44.53 - 82.69 Environmental, Inc.

2002-1 CaSO4: Dy Cards 5/28/2002 Reader 1,#1 4.84 4.44 0.16 3.39 - 6.29 2002-1 CaSO4: Dy Cards 5/28/2002 Reader 1, #1 4.84 4.37 0.20 3.39 - 6.29 2002-1 CaSO4: Dy Cards 5/28/2002 Reader 1,#2 8.60 9.08 0.14 6.02 - 11.18 2002-1 CaSO4: Dy Cards 5/28/2002 Reader 1, #2 8.60 8.76 0.16 6.02 - 11.18 2002-1 CaSO4: Dy Cards 5/28/2002 Reader 1, #3 19.34 22.14 +/- 0.27 13.54 - 25.14 2002-1 CaSO4: Dy Cards 5/28/2002 Reader 1,#3 19.34 24.03 +/- 0.30 13.54 - 25.14 2002-1 CaSO4: Dy Cards 5/2812002 Reader 1,#4 77.36 92.77 +/- 0.58 54.15 - 100.57 2002-1 CaSO4: Dy Cards 5/28/2002 Reader 1, #4 77.36 85.25 +/- 0.37 54.15 - 100.57 Environmental. Inc.

2002-2 CaSO4: Dy Cards 12113/2002 Reader 1,30 56.73 71.61 +/-1.79 39.71 - 73.75 2002-2 CaSO4: Dy Cards 12113/2002 Reader l,45a 25.21 33.49 +/- 1.38 17.65 - 32.77 a Precision of the distance (cm) measurement can significantly increase the error. The placement of the card holder on the table could account for the higher error.

2002-2 CaSO4: Dy Cards 12113/2002 Reader 1,60 14.18 17.37 +/- 1.24 9.93 - 18.43 2002-2 CaSO4: Dy Cards 12/13/2002 Reader 1,75 9.08 10.65 +/- 1.02 6.36 - 11.80

,2002-2 CaSO4: Dy Cards 12113/2002 Reader 1,90 6.30 6.37 +/- 0.54 4.41 - 8.19 2002-2 CaSO4: Dy Cards 12/13/2002 Reader1, 120 3.55 4.60 +/- 0.41 2.49 - 4.62 2002-2 CaSO4: Dy Cards 12/13/2002 Reader 1,135 2.80 2.51 +/- 0.23 1.96 - 3.64 2002-2 CaSO4: Dy Cards 12113/2002 Reader 1,150 2.28 2.22 +/- 0.28 1.60 - 2.96 A2-1

TABLEA-3. In-House"Spike"Samples Concentration (pCiUL)3 Lab Code Sample Date Analysis Laboratory results Known Control Type 2s. n=1 b Activity Limitsc SPW-11552 Water 1/72002 Gr. Alpha 35.33 +/- 1.83 34.57 17.29 - 51.86 SPW-1 1552 Water 117/2002 Gr. Beta 112.62 +/-2A4 107.70 96.93 - 118.47 SPMI-595 Milk 1/31/2002 Cs-134 29.63 +/- 4.98 27.10 17.10 - 37.10 SPMI-595 Milk 1/31/2002 Cs-I 37 51.31 +/-7.55 50.89 40.89 - 60.89 SPMI-597 Milk 1/31/2002 Co-60 44.18 +/- 7.76 41.36 31.36 - 51.36 SPMI-597 Milk 1/31/2002 Cs-134 20.15 +/- 5.08 22.59 12.59 - 32.59 SPMI-597 Milk 1/31/2002 Cs-137 54.88 +/- 8.32 50.89 40.89 - 60.89 SPAP-594 Air Filter 216/2002 Gr. Beta 1.58 +/- 0.02 1.55 0.00 -11.55 SPW-599 Water 2/19/2002 H-3 47607 +/-595 50189 40151 +/-60227 SPMI-1446 Milk 3/8/2002 1-131(G) 87.84 +/- 11.47 85.20 75.20 - 95.20 SPW-1446 Water 3/8/2002 1-131 82.98 +/- 1.20 85.20 68.16 - 102.24 SPW-1446 Water 3/812002 1-131 (G) 92.75 12.87 85.20 75.20 - 95.20 SPMI-1448 Milk 3/8/2002 1-131 88.00 +/- 1.13 85.20 68.16 - 102.24 SPVE-1444 Vegetation 3111/2002 1-131 (G) 0.39 +/- 0.04 0.42 0.25 - 0.58 SPAP-2078 Air Filter 418/2002 Gr. Beta 1.43 +/- 0.01 1.55 0.00 - 11.55 SPW-2080 Water 4/5/2002 H-3 49121 +/-608 46912 37530 +/- 56294 SPF-2082 Fish 4/5/2002 Cs-134 0.83 +/- 0.04 0.83 0.50 -1.16 SPF-2082 Fish 4/5/2002 Cs-137 1.29 +/- 0.07 1.35 0.81 - 1.89 SPMI-2084 Milk 418/2002 Cs-I 34 20.93 +/- 5.82 24.69 14.69 - 34.69 SPMI-2084 Milk 4/8/2002 Cs-137 51.83 +/- 10.23 50.56 40.56 - 60.56 SPMI-2084 Milk 4/812002 1-131 87.72 +/- 1.28 88.37 70.70 - 106.04 SPMI-2084 Milk 4/8/2002 1-131(G) 84.08 +/- 10.75 88.37 78.37 - 98.37 SPMI-2084 Milk 4/8/2002 Sr-90 62.81 +/- 1.99 66.85 53.48 - 80.22 SPW-2115 Water 4/812002 1-131 82.42 +/- 1.27 88.37 70.70 - 106.04 SPW-2116 Water 4/8/2002 Co-60 32.47 +/- 5.78 33.09 23.09 - 43.09 SPW-2116 Water 4/8/2002 Cs-I 34 30.80 +/- 3.60 28.80 18.80 - 38.80 SPW-2116 Water 4/8/2002 Cs-137 53.85 +/- 7.07 50.56 40.56 - 60.56 SPW-2116 Water 4/8/2002 1-131(G) 79.09 +/- 7.58 88.37 78.37 - 98.37 SPW-2116 Water 4/812002 Sr-90 70.35 +/- 2.32 66.85 53.48 - 80.22 SPW-2019 Water 513/2002 Gr. Alpha 25.89 +/- 1.71 34.57 17.29 - 51.86 SPW-2019 Water 5/3/2002 Gr. Beta 101.19 +/- 2.37 107.70 96.93 - 118A7 SPCH-3064 Charcoal 5/11/2002 1-131 (G) 0.74 +/- 0.04 0.85 0.51 - 1.18 SPW-4682 Water 7/17/2002 H-3 40856 +/-548 46179 36943 +/-55415 SPAP-4685 Air Filter 7/17/2002 Gr. Beta 1.58 +/- 0.02 1.55 0.00 - 11.55 W-71702S Water 7117/2002 Fe-55 10463.00 +/- 126.00 12200.60 9760.48 - 14640.72 W-71702S Water 07/17/02 H-3 45779 +/-583 46179 36943 +/- 55415 W-71702S Water 07/17/02 Ni-63 17.02 +/- 1.50 17.10 10.26 - 23.94 SPVE-4910 Vegetation 07/22102 Sr-90 10.22 +/- 0.80 9.04 0.00 - 19.04 W-72302S Water 07/23/02 Sr-90 21.43 i 0.97 26.55 16.55 - 36.55 W-80102S Water 08101/02 Gr. Alpha 41.25 i4.58 34.45 17.23 - 51.68 W-80102S Water 08/01102 Gr. Beta 113.66 +/-5.30 107.70 96.93 - 118.47 W-80202S Water 08102/02 Tc-99 16.39 i0.72 14.13 2.13 - 26.13 SPW-7188 Water 10/25/02 Fe-55 20396 +/- 265 22778 18222 -27334 SPW-7190 Water 10/25/02 Ni-63 227.18 +/- 11.60 170.80 102.48 - 239.12 A3-1

TABLE A-3. In-House "Spike Samples Concentration (pCi/L)

Lab Code Sample Date Analysis Laboratory results Known Control Type 2s, n= 1b Activity Limitsc SPW-7192 Water 10125102 H-3 96310 +/- 871 90963 72770 - 109156 SPW-7194 Water 10125/02 C-14 42938 +/- 167 49661 29796 - 69525 SPAP-7198 Air Filter 10/25/02 Gr. Beta 1.65 +/- 0.02 1.53 0.00 - 11.53 SPW-7335 Water 10130/02 Co-60 39.67 +/- 7.38 37.05 27.05 - 47.05 SPW-7335 Water 10/30/02 Cs-1 34 33.09 +/- 5.96 34.11 24.11 - 44.11 SPW-7335 Water 10/30102 Cs-137 46.80 +/- 10.39 49.90 39.90 - 59.90 SPMI-7336 Milk 10/30/02 Cs-134 34.40 +/-4.99 34.11 24.11 -44.11 SPMI-7336 Milk 10/30102 Cs-i 37 46.52 +/- 8.52 49.91 39.91 - 59.91 SPF-7340 Fish 10/30102 Cs-134 0.66 +/- 0.03 0.68 0.41 - 0.95 SPF-7340 Fish 10/30/02 Cs-1 37 1.35 +/- 0.05 1.33 0.80 - 1.86 SPS-8102 Sediment 11/01/02 Sr-90 14.69 +/- 0.67 13.45 3.45 -23.45 a Results are reported in units of pCi/L, except for air filters (pCi/Filter), food products, vegetation, soil, sediment (pCi/g).

bResults are based on single determinations.

cControl limits are based on Attachment A, Page A2 of this report.

NOTE: For fish, Jello is used for the Spike matrix. For Vegetation, cabbage is used for the Spike matrix.

A3-2

TABLE A-4. In-House "Blank" Samples Concentration (pCi/L)

Lab Code Sample Date Analysis Laboratory results (4.66o) Acceptance Type LLD Activityb Criteria (4.66 o)

SPW-11551 water 1f7/2002 Gr. Alpha 0.47 0.45 +/- 0.39 I SPW-1 1551 water 1/7/2002 Gr. Beta 1.37 0.55 + 1.03 3.2 SPAP-590 Air Filter 1131/2002 Co-60 1.78 100 SPAP-590 Air Filter 1/31/2002 Cs-134 3.42 100 SPAP-590 Air Filter 1/31/2002 Cs-I 37 2.33 100 SPAP-590 Air Filter 1/3112002 Gr. Beta 0.74 -0.096 +/- 0.38 3.2 SPMI-596 Milk 1/31/2002 Co-60 3.54 10 SPMI-596 Milk 1/31/2002 Cs-1 34 3.24 10 SPMI-596 Milk 1/3112002 Cs-137 3.89 - 10 SPMI-596 Milk 1/31/2002 K-40 1472.1 *101.50 0 SPW-598 water 1/31/2002 Co-60 2.30 10 SPW-598 water 1/31/2002 Cs-134 3.74 10 SPW-598 water 1/31/2002 Cs-1 37 3.23 10 SPW-600 water 1/31/2002 H-3 138.80 -96.5 i 63A0 200 SPMI-1447 Milk 3/7/2002 1-131 (G) 7.63 20 SPVE-1443 Vegetation 3/8/2002 1-131 (G) 0.02 20 SPW-1445 water 3/8/2002 Co-60 2.76 10 SPW-1445 water 3/8/2002 Cs-134 2.87 10 SPW-1445 water 318/2002 Cs-1 37 4.34 10 SPW-1445 water 3/8/2002 1-131 0.45 0.17 i 0.31 0.5 SPW-1445 water 3/8/2002 1-131 (G) 6.50 20 SPMI-1447 Milk 3/812002 1-131 0.31 0.15 + 0.22 0.5 SPAP-2077 Air Filter 41812002 Gr. Beta 0.32 -0.055 +/- 0.19 3.2 SPW-2079 water 4/5/2002 H-3 134.17 16.13 +/-67.39 200 SPF-2081 Fish 4/5/2002 Cs-134 7.67 100 SPF-2081 Fish 4/512002 Cs-137 9.54 100 SPMI-2083 Milk 418/2002 Cs-134 2.90 10 SPMI-2083 Milk 4/8/2002 Cs-137 3.03 10 SPMI-2083 Milk 4/812002 1-131 0.52 -0.38 + 0.34 0.5 SPMI-2083 Milk! 4/8/2002 Sr-90 0.48 1.29 +/- 0.36 1 SPW-2115 water 4/8/2002 Co-60 1.49 10 SPW-2115 water 4/812002 Cs-I 34 2.09 10 SPW-2115 water 4/812002 Cs-137 3.78 10 SPW-2115 water 418/2002 1-131 0.50 -0.16 *0.33 0.5 SPW-2115 water 4/8/2002 1-131(G) 3.30 20 SPW-2115 water 41812002 Sr-90 0.66 0.10 +/- 0.32 1 SPW-2018 water 4/22/2002 Gr. Alpha 0.56 -0.24 + 0.38 SPW-2018 water 4/22/2002 Gr. Beta 1.38 3.19 +/- 1.03 3.2 SPch-3063 Charcoal 511112002 1-131(G) 8.27 9.6 SPW-4683 water 7/17/2002 H-3 129.00 -62.8 +/- 60.30 200 W-71702 water 7/17/2002 Fe-55 33.61 -1.72 +/- 15.63 1000 W-71702 water 7/17/2002 Ni-63 2.56 0.71 1.37 20 W-71802B water 7/18/2002 Gr. AJpha 0.48 0.31 0.36 1 W-71802B water 7/1812002 Gr. Beta 1.33 0.9 + 0.95 3.2 A4-1

TABLE A-4. In-House "Blank" Samples Concentration (pCUL)a Lab Code Sample Date Analysis Laboratory results (4.66a) Acceptance Type LLD Activity? Criteria (4.66 a)

W-72302 water 7123/2002 Sr-90 0.27 0.027 0.13 I W-80202 water 8/2/2002 Tc-99 0.34 -0.051 +/-0.16 10 SPW-7189 water 10/25/2002 Fe-55 978.21 21.77 +/- 595.33 1000 SPW-7191 water 10/25/2002 NI-63 11.74 4.47 +/- 7.24 20 SPW-7193 water 10/2512002 H-3 146.00 -92 :t 65.00 200 SPAP-7199 Alr Filter 10/25/2002 Gr. Beta 0.00 -0.0024 +/- 0.00 3.2 SPMI-7333 Milk 10/3012002 Cs-I 34 5.30 10 SPMI-7333 Milk 10/30/2002 Cs-I 37 4.80 10 SPW-7334 water 10/30/2002 Co-60 3.69 10 SPW-7334 water 10130/2002 Cs-134 5.37 10 SPW-7334 water 10/30/2002 Cs-I 37 3.90 10 SPF-7339 Fish 1013012002 Cs-1 34 4.69 100 SPF-7339 Fish 10/30/2002 Cs-137 11.18 100 Uquid sample results are reported InpCW/Lter, air f lters( pC/filter), charcoal (pCi/charcoal canister), and solid samples (pCikg).

b The acUvity reported Is the net acUvity resulL

' Low levels of Sr-90 are sUll detected In the environmenL A concentration of (1-5 pCUL) n milk Isnot unusual.

A4-2

TABLE A-5. In-House Duplicate Samples Concentrafion (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result CF-20,21 .1/2/2002 Be-7 0.47 i 0.25 0.37 +/- 0.12 0.42 +/- 0.14 CF-20. 21 1/2/2002 Gr. Beta 7.82 i 0.20 7.95 +/- 0.21 7.89 +/- 0.14 CF-20, 21 1/2/2002 K-40 6.65 +/- 0.55 6.53 +/- 0.36 6.59 +/- 0.33 CF-20, 21 1/2/2002 Sr-90 0.01 0.01 0.01 +/-0.01 0.01 +/- 0.00 AP-11804, 11805 1/2/2002 Be-7 0.054 f 0.011 0.049 +/- 0.019 0.052 +/- 0.011 AP-11825, 11826 1/2/2002 Be-7 0.053 +/-0.013 0.043 +/- 0.013 0.048 +/- 0.009 AP-11846, 11847 112J2002 Be-7 0.054 +/- 0.018 0.048 +/- 0.016 0.051 +/-0.012 WW-150, 151 11712002 Gr. Beta 1.26 +/- 0.50 1.04 +/- 0.46 1.15 +/-0.34 MI-124, 125 1/812002 K-40 1332.30 +/- 158.90 1271.70 +/- 151.50 1302.00 +/- 109.77 W-172, 173 118/2002 H-3 153.00 +/- 68.00 148.00 +/- 68.00 150.50 +/-48.08 SW-11698, 11699 1/812002 Gr. Alpha 2.51 +/- 1.36 3.71 +/- 1.80 3.11 +/- 1.13 SW-11698, 11699 1/8/2002 Gr. Beta 7.68 +/- 1.33 8.49 +/- 1.43 8.09 +/- 0.98 U-275, 276 1/10/2002 Gr. Alpha 1.40 +/- 1.00 1.10 +/- 1.20 1.25 +/- 0.78 LW-356,357. 1/16/2002 Gr. Beta 3.47 +/- 0.65 2.94 +/- 0.61 3.21 +/- 0.45 LW-377, 378 1/1612002 Gr. Beta 2.75 +/- 0.68 2.84 +/- 0.61 2.79 OA6 SW-525, 526 1/3012002 Gr. Alpha 0.56 +/- 0.35 0.24 +/- 0.35 0.40 +/-025 SW-525, 526 1/3012002 Gr. Beta 2.29 +/- A1 2.58 +/- 0.39 2.43 i0.28 DW-504, 505 1/31/2002 Gr. Alpha 2.30 +/- 1.70 3.90 i 1.40 3.10 i1.10 MI-649, 650 21512002 K-40 1319.40 +/- 176.70 1210.80 +/-118.20 1265.10 +/-106.29 DW-697, 698 2/6/2002 Gr. Beta 5.10 +/- 1.20 4.70 +/- 1.20 4.90 +/- 0.85 DW-927, 928 2/8/2002 Sr-90 0.69 i 0.29 0.71 +/-0.29 0.70 +/-0.21 W-973, 974 2/18/2002 Fe-55 7.29 +/- 0.97 6.86 +/- 0.94 7.08 +/-0.68 W-1673, 1674 2/2512002 H-3 2640.00 +/- 155.00 2908.00 +/- 161.00 2774.00 +/- 111.74 SWT-1395, 1396 2/26/2002 Gr. Beta 2.96 +/- 0.59 2.29 +/- 0.53 2.63 +/- 0.40 Ml-1268, 1269 2/27/2002 K-40 1460.50 +/- 162.50 1573.00 +/- 168.00 1516.75 +/- 116.87 MI-1268, 1269 2127/2002 Sr-90 0.77 +/- 036 0.95 +/- 0.40 0.86 +/-0.27 Ml-1332, 1333 3/5/2002 K-40 1503.00 +/- 164.00 1305.00 +/-168.00 1404.00 +/-117.39 MI-1332, 1333 3/512002 Sr-90 1.35 +/- 0.38 1.07 +/- 0.40 1.21 +/-0.28 MI-1458, 1459 3/6/2002 K-40 1411.70 + 166.70 1390.00 +/- 172.30 1400.85 +/- 119.87 DW-10100, 10101 3/9/2002 Gr. Alpha 4.10 +/- 1.70 1.80 +/-1.60 2.95 +/- 1.17 DW-10111. 10112 3/912002 Gr. Alpha 7.10 +/- 2.00 8.30 +/- 2.30 7.70 +/- 1.52 MI-1521, 1522 3/11/2002 K-40 1270.80 +/- 103.30 1369.10 +/- 121.60" 1319.95 I 79.78 Ml-1521, 1522 3/11/2002 Sr-90 1.69 +/- 0.46 2.46 +/-0.49 2.07 +/-0.34 MI-1541, 1542 3/11/2002 K-40 1562.20 +/- 122.80 1529.30 +/- 126.10 1545.75 +/- 88.01 M-1541, 1542 3/11/2002 Sr-90 0.85 +/- 0.57 1.48 +/-0.43 1.16 +/- 0.36 LW-1651, 1652 3/14/2002 Gr. Beta 2.90 +/- 0.57 2.57 +/- 0.56 2.74 +/-0.40 DW-10134, 10135 3/1612002 Gr. Alpha 5.60 +/- 1.90 5.40 +/- 1.60 5.50 +/-1.24 WW-1694, 1695 3/18/2002 Gr. Beta 1.79 +/- 0.59 1.53 +/- 0.50 1.66 +/- 0.39 SO-1715, 1716 3/19/2002 Cs-137 0.03 + 0.01 0.02 +/- 0.01 0.03 +/- 0.01 SO-1715, 1716 3/19/2002. Gr. Beta 18.50 +/- 1.70 19.10 +/- 1.70 18.80 +/- 1.20 DW-10302, 10303 3120/2002 Gr. Alpha 2.30 +/- 1.40 3.30 +/- 1.60 2.80 +/- 1.06 W-1758, 1759 3/25/2002 Gr. Alpha 2.50 +/- 0.70 2.30 +/- 0.60 2.40 +/- OA6 W-1758, 1759 3/25/2002 Gr. Beta 4.10 +/- 1.20 2.50 +/-1.10 3.30 +/- 0.81 A5-1

TABLE A-5. In-House "Duplicate Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result MI-1926, 1927 3126/2002 K-40 1414.00 +/- 115.00 1316.00 +/- 128.00 1365.00 +/- 86.04 MI-1926,1927 3/26/2002 Sr-90 2.30 +/- 0.70 2.40 +/- 0.70 2.35 +/-OA9 SWU-2010, 2011 3/2612002 Gr. Beta 2.90 i 0.60 2.20 +/- 0.50 2.55 +/- 0.39 DW-10376,10377 3127/2002 Gr. Beta 10.50 +/- 1.30 10.10 +/- 1.50 10.30 +/- 0.99 AP-2479. 2480 3/28/2002 Be-7 0.064 i 0.023 0.068 +/- 0.014 0.066 +/- 0.013 DW-10395, 10396 3/2912002 Gr. Alpha 10.20 2.10 14.60 +/- 2.40 12.40 +/-1.59 LW-2181, 2182 3131/2002 Gr. Beta 2.98 0.68 1.99 +/- 0.70 2.48 +/-0.49 LW-2181, 2182 3/31/2002 H-3 2694.43 156.53 2688.84 +/- 156.40 2691.64 +/- 110.64 CW-2437, 2438 3/3112002 Gr. Beta 1.09 0.61 1.14 +/- 0.58 1.11 i+/-OA2 CW-2437, 2438 3/31/2002 H-3 6456.70 +/- 22920 6292.80 +/- 226.52 6374.75 +/- 161.12 MI-1947,1948 4/11/2002 K-40 1421A0 +/- 130.90 1256.80 +/- 104.20 1339.10 +/- 83.65 AP-2458, 2459 411/2002 Be-7 0.077 +/- 0.011 0.081 +/- 0.010 0.079 +/- 0.008 DW-10409,10410 41112002 Gr. Alpha 39.30 +/- 4.00 35.30 +/- 3.60 37.30 +/- 2.69 MI-2052, 2053 413/2002 K-40 1283.70 +/- 103.20 1434.80 +/-147.90 1359.25 +/- 90.17 MI-2052, 2053 4/3/2002 Sr-90 0.81 0.36 0.75 +/-0.35 0.78 +/-0.25 AP-2711. 2712 4/3/2002 8e-7 0.071 +/- 0.01 0.07 +/- 0.01 0.07 +/- 0.01 W-938, 939 4/912002 Ni-63 1.73 +/-0.10 1.82 +/- 0.10 1.78 +/- 0.07 SS-2202, 2203 4/9/2002 Gr. Beta 5.83 +/- 1.16 5.52 +/-1.19 5.67 +/- 0.83 SS-2202, 2203 4/9/2002 K-40 5.75 +/- 0.48 6.11 +/-0.51 5.93 +/- 0.35 F-2307, 2308 411012002 K-40 2.75 +/- 0.27 2.49 +/- 0.32 2.62 +/- 0.21 DW-10476,10477 4/12/2002 Gr. Alpha 5.10 1.30 3.90 +/-1.60 4.50 +/- 1.03 W-2244, 2245 4/15/2002 Gr. Beta 1.70 +/- 1.10 1.60 +/- 1.00 1.65 +/- 0.74 DW-10509,10510 4117/2002 Gr. Alpha 6.00 +/- 2.00 7.30 +/- 1.80 6.65 +/- 1.35 SW-2690, 2691 4/24/2002 Gr. Beta 2.25 +/- 0.68 2.15 +/- 0.59 2.20 +/- O.45 S0-2903, 2904 4/24/2002 Be-7 1.22 +/- 0.57 0.78 +/- 0.43 1.00 +/- 0.36 S0-2903, 2904 4/24/2002 Cs-I 37 0.13 +/- 0.05 0.09 +/- 0.05 0.11 +/- 0.04 SO-2903, 2904 4/24/2002 K-40 21.06 +/- 1.48 19.91 +/-1.16 20.48 +/- 0.94 DW-10562,10563 4124/2002 Gr. Alpha 2.17 +/- 1.13 3.25 +/-1.54 2.71 +/- 0.96 DW-10578,10579 412912002 Gr.Alpha 8.20 +/- 2.20 7AO +/- 2.00 7.80 +/-i1A9 S0-2861, 2862 4130/2002 Cs-137 236.40 +/- 46.00 200.70 +/- 52.60 218.55 +/- 34.94 SO-2861, 2862 413012002 K-40 10191.00 +/-784.60 11025.00 +/- 941.30 10608.00 +/- 612.71 SL-2819, 2820 5/1/2002 Be-7 805.70 +/- 301.50 860.73 +/- 164.80' 833.22 +/- 171.80 SL-2819, 2820 511/2002 Gr. Beta 5566.00 +/- 124.00 5359.00 +/- 122.00 5462.50 +/- 86.98 SL-2819, 2820 5/1/2002 K-40 5524.00 +/- 632.90 5277.50 +/- 431.40 5400.75 +/- 382.97 SL-2840, 2841 5/1/2002 Be-7 1010.00 +/- 352.10 872.95 +/- 181.70 941.46 +/- 198.11 SL-2840, 2841 511/2002 Gr. Beta 4399.00 +/- 221.80 4593.00 +/-276.00 4496.00 +/- 177.04 SL-2840, 2841 511/2002 K-40 2422.80 +/-352.10 2254.10 +/- 371.AO 2338.45 +/- 255.89 MI-2971, 2972 5/5/2002 K-40 1338.90 +/- 83.44 1345.80 +/- 100.90 1342.35 +/- 65.47 MI-2971, 2972 5/5/2002 Sr-90 0.83 i 0.47 1.65 +/- 0.46 1.24 +/- 0.33 DW-10603, 10604 5/612002 Gr. Alpha 6.30 +/- 1.70 5.50 +/- 1.60 5.90 +/- 1.17 SS-3037, 3038 51912002 K-40 11585.00 +/- 749.00 11612.00 +/- 787.00 11598.50 +/- 543.22 MI-3124, 3125 5/13/2002 K-40 1329.50 +/- 103.80 1373.00 +/- 107.40 1351.25 +/-74.68 MI-3208, 3209 5/14/2002 K-40 1494.60 +/- 158.40 1462.60 +/- 182.50 1478.60 +/- 120.83 LW-3250, 3251 5115/2002 Gr. Beta 3.14 +/- 0.55 3.28 +/- 0.63 3.21 +/- 0.42 A5-2

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)r veraged Lab Code Date Analysis First Result Second Result Result CF-3292, 3293 5120/2002 K-40 1.33 i 0.99 1.14 +/- 0.91 1.23 +/- 0.67 MI-3376. 3377 5t26/2002 K-40 1333.30 159.40 1090.70 +/- 143.40 1212.00 +/- 107.21 MI-3418, 3419 5/28/2002 K-40 1423.70 121.30 1443.30 +/- 164.30 1433.50 +/-102.11 SWT-3461, 3462 5/28/2002 Gr. Beta 2.65 + 0.54 3.28 +/- 0.60 2.97 +/- 0.40 S-3503, 3504 5/29/2002 Cs-1 37 0.17 0.04 0.18 +/- 0.05 0.18 +/- 0.03 SO-3503, 3504 5/29/2002 Gr. Beta 27.72 2.26 25.45 +/- 2.03 26.58 +/-1.52 SO-3503, 3504 5/29/2002 K-40 20.24 1.19 20.54 +/- 1.24 20.39 +/- 0.86 SL-3545, 3546 6/3/2002 Gr. Beta 4436.00 i 90.00 4281.00 +/- 89.00 4358.50 +/- 63.29 SL-3545, 3546 6/3/2002 K-40 4684.20 734.40 5242.50 +/- 884.50 4963.35 +/- 574.82 DW-10754, 10755 6/6/2002 Sr-90 0.50 +/-t 0.30 0.60 +/- 0.30 0.55 +/-0.21 SW-3, 3778 6/11/2002 Gr. Alpha 4A2 1.50 2.97 +/- 1.40 3.70 +/- 1.02 SW-3777, 3778 6/11/2002 Gr. Beta 7.57 i 1.22 6.83 +/- 1.16 7.20 +/- 0.84 MI-3798, 3799 6/112002 K-40 1433.40 +/- 124.20 1401.20 i 96.96 1417.30 +/- 78.78 LW-3924, 3925 6/13/2002 Gr. Beta 3.05 +/- 0.59 3.38 +/- 0.72 3.21 +/-0.46 MI-3966, 3967 6/18/2002 K40 1245.20 i 109.20 1340.20 +121.90 1292.70 +/- 81.83 MI-3966, 3967 6/18/2002 Sr-90 2.38 +/- 0.51 2.63 +/- 0.52 2.51 +/- 0.36 MI-3987, 3988 6/19/2002 Sr-90 0.98 +/- 0.35 0.97 +/- 0.35 0.98 +/- 0.25 MI-4095, 4096 6/25/2002 K-40 1256.10 +/- 138.20 1199.00 +/- 128.30 1227.55 +/- 94.29 SWU-4221, 4222 6/25/2002 Gr. Beta 6.89 +/- 1.97 5.38 +/- 1.93 6.13 +/-1.38 LW-4179, 4180 612712002 Gr. Beta 2.37 +/- 0.58 2.00 +/- 0.62 2.19 +/- 0.42 G-4329, 4330 7/1/2002 Be-7 1394.80 +/-538.40 1098.10 +/- 437.40 1246.45 +/-346.84 G-4329, 4330 7/1/2002 Gr. Beta 8.10 +/-027 8.00 +/- 0.25 8.05 +/- 0.18 G-4329, 4330 7/1/2002 K-40 7758.20 +/- 1100.00 8399.80 +/- 929.30 8079.00 +/- 720.00 SL-4337, 4338 7/1/2002 Be-7 1480.90 +/- 223.80 1726.40 +/-552.60 1603.65 +/-298.10 SL4337, 4338 7/1/2002 Cs-137 32.30 +/- 14.70 50.97 +/- 27.10 41.64 +/-15.42 SL-4337, 4338 7/112002 Gr. Beta 5262.40 +/- 522.10 5432.40 +/- 540.00 5347.40 +/- 375.56 SL-4337, 4338 7/1/2002 K-40 2249.00 +/- 381.90 2989.90 +/- 509.60 2619.45 +/- 318.41 AP4864, 4865 7/1/2002 Be-7 0.085 0.009 0.085 +/- 0.006 0.085 +/- 0.006 MI-4359, 4360 7/2/2002 K-40 1390.10 +/- 168.30 1567.40 i 194.30 1478.75 +/- 128.53 AP-4569, 4570 7/2/2002 Be-7 0.068 +/- 0.016 0.086 +/- 0.018 0.077 +/- 0.012 AP-4843, 4844 7/2/2002 Be-7 0.077 +/- 0.016 0.090 +/- 0.020 0.084 +/- O.013 AP-4789, 4790 7/3/2002 Be-7 0.080 +/- 0.013 0.078 +/- 0.015 0.079 +/- 0.010 SWU-4810, 4811 7/3/2002 Gr. Beta 2.40 +/- 0.84 2.47 +/-0.88 2.43 +/-0.61 MI-4548, 4549 7/9/2002 K-40 1511.80 +/- 127.00 1446.80 +/- 101.80 1479.30 i81.38 DW4737, 4738 7/1212002 1-131 0.52 +/- 0.20 0.49 +/- 0.29 0.51 +/- 0.18 MI-4632, 4633 7/15/2002 K-40 1198.40 +/- 114.10 1371.30 +/- 146.90 1284.85 i 93.00 MI-5054, 5055 7/30/2002 K-40 1428.80 +/- 105.60 1344.30 +/- 106.40 1386.55 +/-74.95 G-5075, 5076 7/30/2002 Gr. Beta 7.11 +/- 0.07 6.99 +/- 0.07 7.05 +/- 0.05 SWU-5124, 5125 7/30/2002 Gr. Beta 1.75 +/- 0.84 1,90 +/- 0.78 1.82 +/- 0.57 G-5151, 5152 7/31/2002 Be-7 1.82 +/- 0.30 2.05 +/- 0.32 1.93 +/- 0.22 G-5151, 5152 7/31/2002 K-40 5.13 +/- 0.66 5.72 +/- 0.70 5.42 +/- 0.48 MI-5103, 5104 8/2/2002 K-40 1415.90 70.57 1423.80 +/- 129.20 1419.85 +/- 73.61 LW-5434, 5435 8/5/2002 Gr. Beta 2.77 +/- 0.35 2.26 +/- 0.35 2.52 +/- 0.25 Ml-5215, 5216 8/7/2002 K-40 1361.10 +/- 111.90 1358.30 +/- 115.80 1359.70 +/-80.52 A5-3

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result MI-5355, 5356 8/13/2002 K-40 1405.00 +/- 165.80 1549.30

114.40 1477.15 +/- 100.72 F-5413, 5414 8/15/2002 Gr. Beta 2.37 i 0.10 2.55 +/-k0.10 2.46 +/- 0.07 F-5413, 5414 8/15/2002 K-40 1.47 t 0.32 1.73 + 0.43 1.60 +/- 0.27 MI-5603, 5604 8126/2002 1-131 0.64 +/- 0.34 0.52 + 0.36 0.58 +/- 0.25 MI-5603, 5604 8/26/2002 K-40 1353.60

83.13 1261.40 i 117.80 1307.50 +/- 72.09 MI-5578, 5579 8/27/2002 K-40 1301.50 +/- 161.70 1381.60

111.20 1341.55 +/- 98.12 VE-5682, 5683 8/28/2002 Be-7 0.29 +/- 0.10 0.25 +/- 0.11 0.27 +/- 0.08 VE-5682, 5683 8/28/2002 Gr. Beta 3.79 +/- 0.08 3.80 + 0.08 3.79 +/- 0.06 VE-5682, 5683 8/28/2002 K-40 3.06 +/- 0.29 3.31 +/-0.42 3.18 +/-0.25 WW-6188, 6189 8/31/2002 Gr. Beta 2.70 +/- 0.57 2.30 +/- 0.57 2.50 +/- 0.41 SL-5724, 5725 9/3/2002 Be-7 0.92 +/- 0.19 1.04 +/- 0.23 0.98 +/- 0.15 SL-5724, 5725 913/2002 Cs-137 0.05

0.02 0.05 +/- 0.02 0.05 +/- 0.01 SL-5724, 5725 9/3/2002 K40 2.09 +/- 0.31 2.28 +/- 0.48 2.19 +/- 0.29 MI-5877, 5878 9/912002 K-40 1340.70 +/- 165.00 1168.50 +/- 172.50 1254.60 +/- 119.35 MI-6157, 6158 9/19/2002 K-40 1372.10 +/- 115.10 1136.50

222.70 1254.30 +/- 125.34 MI-6258, 6259 9/24/2002 K-40 1328.60 +/- 201.00 1312.60 +/- 118.60 1320.60 +/- 116.69 LW-6278, 6279 9/30/2002 Gr. Beta 2.15 +/- 0.51 1.70 +/- 0.50 1.93 +/- 0.36 MI-6385, 6386 10/1/2002 K-40 1297.10 +/- 168.90 1310.10 +/- 128.30 1303.60 +/- 106.05 8S-6453, 6454 1011/2002 Cs-137 0.43 +/- 0.03 0.44 +/- 0.03 0.44 +/- 0.02 BS-6453, 6454 10/1/2002 K40 16.50 +/- 0.51 16.80 +/- 0.61 16.65 +/- 0.40 SO6478, 6479 10/1/2002 Cs-I 37 0.074 +/- 0.016 - 0.070 +/- 0.016 0.072 +/- 0.011 S0-6478, 6479 1011/2002 Gr. Alpha 8.01 4.36 7.55 +/- 4.57 7.78 +/-3.16 SO-6478. 6479 10/1/2002 Gr. Beta 30.41 4.07 33.04 +/-4.28 31.73 +/- 2.95 SO-6478, 6479 10/1/2002 K40 19.82 +/- 0.53 20.39 +/- 0.58 20.10 +/- 0.39 S0-6478, 6479 10/1/2002 Sr-90 0.087 +/- 0.017 0.094 +/- 0.020 0.091 +/- 0.013 AP-6641, 6642 10/1/2002 Be-7 0.070 +/- 0.016 0.080 +/- 0.015 0.075 +/- 0.011 MI-6544, 6545 10/2/2002 K-40 1331.60 +/- 125.20 1326.50 +/- 171.60 1329.05 +/- 106.21 AP-6857, 6858 1013/2002 Be-7 0.062 +/- 0.015 0.071 +/-0.015 0.066 +/- 0.010 AP-6857, 6858 1013/2002 Be-7 0.062 +/- 0.015 0.071 +/-0.015 0.066 +/- 0.010 AP-6857, 6858 10/3/2002 Be-7 0.062 +/-0.015 0.071 +/-0.015 0.066 +/- 0.010 3S-6620, 6621 1017/2002 Co-60 0.090 +/- 0.020 0.11 i 0.02 0.10 +/- 0.01 BS-6620, 6621 1017/2002 Cs-137 0.62 +/- 0.04 0.63 +/- 0.03 0.62 +/- 0.02 BS-6620, 6621 10/7/2002 K40 11.38 +/- 0.48 10.78 +/- 0.52 11.08 +/- 0.35 MI-6651, 6652 1018/2002 K-40 1565.50 +/- 141.00 1640.60 +/- 189.20 1603.05 +/- 117.98 G-6760, 6761 10/9/2002 Be-7 2.17 +/- 0.49 2.31 +/- 0.34 2.24 +/- 0.30 G-6760, 6761 1019/2002 K40 6.24 +/- 1.00 6.61 +/- 0.60 6A2 +/- 0.58 SWU-7054, 7055 10/10/2002 Gr. Beta 3.09 +/- 0.57 2.06 +/- 0.52 2.57 +/- 0.39 U-7126, 7127 10/1112002 Gr. Beta 2.61 +/- 1.24 2.61 +/- 1.08 2.61 +/- 0.82 XW-7768, 7769 1011412002 Cs-137 2.25

0.25 2.09 +/- 0.18 2.17 +/- 0.15 XW-7768, 7769 10114/2002 H-3 2.63 +/- 0.10 2.64 +/- 0.10 2.64 +/- 0.07 F-7148, 7149 10/15/2002 K-40 2.57

0.28 2.98 +/- 0.44 2.77 +/- 0.26 3S-7337, 7338 10/23/2002 Co-60 0.083

0.025 0.073 +/- 0.031 0.078 +/- 0.020 BS-7337, 7338 1012312002 Cs-137 0.082 +/- 0.019 0.11 +/- 0.04 0.10 +/- 0.02 8S-7337, 7338 10/23/2002 Gr. Beta 12.54 +/-2.34 12.99 +/- 2.22 12.77 +/- 1.61 SO-7407, 7408 10/29/2002 Cs-I 37 0.14 +/- 0.03 0.15 +/- 0.03 0.15 +/- 0.02 S-7407, 7408 10/2912002 Gr. Beta 16.73 +/- 2.21 16.62 +/- 2.27 16.67

1.58 S0-7407, 7408 10/29/2002 K-40 12.05 +/- 0.61 12.27 +/- 0.81 12.16 +/- 0.51 A5-4

TABLE A-5. In-House Duplicate" Sarples Concentration (pCVL)a Averaged Lab Code Date Analysis First Result Second Result Result MI-7428,7429 10129/2002 K-40 1542.60 213.00 1355.80 185.70 1449.20 + 141.29 pw-7621, 7622 10/30/2002 Gr. Beta 2.22 i 0.92 2.08 +/-t 0.83 2.15 0.62 TD-7653,7654 10/31/2002 H-3 11122.00 +/-387.00 11259.00 +/-390.00 11190.50 +/-274.71 SW-7569, 7570 1115/2002 Gr. Beta 15.90 +/- 1.25 16.24 +/- 1.27 16.07 +/- 0.89 SW-7569, 7570 1115/2002 K-40 14.79 +/- 1.48 14.79 +/- 1.48 14.79 +/- 1.05 SO-8010,8011 1117/2002 Cs-137 0.11 0.02 0.11 +/- 0.03 0.11 +/-0.02 SO-8010, 8011 11/712002 K-40 6.91 +/- 0.54 7.21 +/-0.54 7.06 +/-0.38 VE-7747,7748 11/11/2002 Gr. Beta 3.59 +/- 0.05 3.25 +/- 0.05 3.42 0.03 VE-7747,7748 11/1112002 K-40 3.17 +/- 0.36 3.26 +/- 0.46 3.22 0.29 MI-7789, 7790 11/13/2002 K-40 1319.30 +/- 167.60 1301.20 +/- 140.70 1310.25 +/- 109.41 DW-8082,8083 11/29/2002 1-131 0.83 +/- 0.24 0.98 +/-022 0.90 +/- 0.16 SW-8054, 8055 12/2/2002 Gr. Beta 2.60 +/- 0.46 2.21 +/- 0.39 2.41.+/- 0.30 SW-8054, 8055 12/2/2002 K-40 1A4 0.14 1.43 +/- 0.14 1.44 +/- 0.10 Mi-8105, 8106 12/412002 K-40 1300.60 +/- 111.30 1315.40 +/- 108.90 1308.00 +/- 77.86 TD-8298.8299 12/512002 H-3 355.00 +/- 94.00 469.00 +/- 99.00 412.00 i 68.26 MI-8396, 8397 12/17/2002 K-40 1409.20 +/- 117.30 1449.60 +/-108.60 1429.40 +/-79.93 SWT-8654, 8655 12/30/2002 Gr. Beta 1.63 +/- 0.50 1A0 +/- 0.47. 1.51 +/- 0.34 AP-8783,8784 12/31/2002 Be-7 0.044 +/- 0.009 0.042 +/- 0.008 0.043 +/- 0.006 Note: Duplicate analyses are performed on every twentieth sample received In-house. Results are not listed for those analyses with activities that measure below the LLD.

a Results are reported in units of pCi/L, except for air filters (pCi/Filter), food products, vegetation, soil, sediment (pCVg).

A5-5

TABLE A-6. Department of Energy's Mixed Analyte Performance Evaluation Program (MAPEP) 3 .

Concentrationb Known Control Lab Code Type Date Analysis Laboratory result Activity Limits STW-939 water 12/01/01 Am-241 1.25 +/-0.0 1.19 +/-0.0 0.83 - 1.6 STW-939 water 12/01101 Co-57 138.9 +/- 0.5 143 +/-14.3 100.1 - 185.9 STW-939 water 12/01/01 Co-60 139.1 +/-0.5 141 +/-14.1 98.7 - 183.3 STW-939 water 12101/01 Cs-134 25.16 +/-0.2 28.5 +/-0.3 19.95 -37.1 STW-939 water 12/01/01 Cs-137 279.96 +/- 0.9 286 +/- 28.6 200.2 - 371.8 STW-939d water 12/01/01 Fe-55 19.68 +/- 23.2 9.2 +/- 0.9 6.44 - 12.0 STW-939 water 12/01/01 Mn-54 253.64 +/- 0.9 246 +/- 0.2 172.2 - 319.8 STW-939 water 12/01101 Ni-63 65.88 +/- 1.9 88.3 +/- 8.8 61.81 - 114.8 STW-939e water 12/01/01 Pu-238 0.060 +/- 0.01 0.0 +/- 0.0 STW-939 water 12101/01 Pu-239140 2.79 +/- 0.0 2.99 +/-0.3 2.09 - 3.9 STW-939 water 12/01/01 Sr-90 4.88 +/- 0.3 4.8 +/- 0.5 3.36 - 6.2 STW-939 water 12/01/01 U-233/4 0.89 +/- 0.0 0.98 +/- 0.1 0.69 - 1.3 STW-939 water 12101/01 U-238 6.75 +/- 0.0 7.8 +/-0.8 5.46 - 10.1 STW-939 water 12101/01 Zn-65 70.6 +/- 1.1 67.3 +/- 6.7 47.11 - 87.5 STSO-955 soil 10/16/02 Am-241 40.54 +/- 2.7 43.5 +/- 4A 30.45 -56.6 STSO-955 soil 10/16/02 Co-57 210.58 +/- 2.0 246 +/-24.6 172.2 -319.8 STSO-955 soil 10/16/02 Co-60 84.38 +/- 0.9 87.5 +/- 8.8 61.25 - 113.8 STSO-955 soil 10116/02 Cs-134 692.6 +/- 2.1 862 +/- 86.0 603.4 - 1120.6 STSO-955 soil 10/16102 Cs-137 96.98 +/- 1.7 111 11.1 77.7 - 144.3 STSO-955 soil 10/16102 Fe-55 1714.6 +/- 299.6 1870 187.0 1309 -2431.0 STSO-955 soil 10/16/02 Mn-54 509.74 +/- 3.4 546 +/-54.6 382.2 -709.8 STSO-955 soil 10/16/02 Ni-63 890.6 +/- 22.4 1180 +/- 118.0 826 - 1534.0 STSO-955 soil 10/16/02 Pu-238 34.04 +/- 6.0 33.3 + 3.3 23.31 -43.3 STSO-955 soil 10116/02 Pu-239/40 68.7 +/- 3.7 72.9 +/-7.3 51.03 - 94.8 STSO-955e soil 10/16/02 Sr-90 1.5 +/- 3.0 0.0 +/- 0.0 STSO-955 soil 10/16/02 U-23314 166.33 +/- 3.8 229 22.9 160.3 - 297.7 STSO-955 soil 10/16/02 U-238 169.76 +/-3.8 220 +/-22.0 154 -286.0 STSO-955 soil 10/16/02 Zn-65 783.59 +/- 6.4 809 +/- 80.9 566.3 - 1051.7 "Results obtained by Environmental, Inc. ,Midwest Laboratory as. a participant in the Department of Energy's Mixed Analyte Performance Evaluation Program, Idaho Operations office, Idaho Falls, Idaho b All results are in Bq/kg or Bq/L'as requested by the Department of Energy.

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

d Known activity below the laboratory LLD. The sample was recounted for 2000 minutes; result:11.52 i 5.55 Bq /L

' Included In the testing series as a 'false positive'. No activity expected.

A6-1

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

Concentration" EML Control Lab Code Type Date Analysis Laboratory results Resultb Limitsc STW-945 Water 03/01/02 Am-241 1.68 i 0.14 1.47 0.79 - 1.41 STW-945 Water 03101/02 Co-60 349.20 + 2.60 347.33 0.80 - 1.20 STW-945 Water 03/01/02 Cs-134 3.40 +/-E0.60 3.36 0.80 - 1.30 STW-945 Water 03/01/02 Cs-137 57.20 +/- 1.70 56.07 0.80 - 1.22 STW-945 Water 03/01102 Pu-238 0.45 +/- 0.11 0.49 0.74 -1.20 STW-945 Water 03101102 Pu-239140 4.47 +/- 0.28 4.22 0.79 - 1.20 STW-945 Water 03101/02 Sr-90 7.40 +/- 1.30 7.58 0.69 - 1.34 STW-945 Water 03/01/02 Uranium 3.27 +/- 0.43 2.84 0.75 - 1.33 STW-946 Water 03/01/02 Gr. Alpha 265.40 +/- 7.70 375.00 0.58 - 1.29 STW-946 Water 03/01/02 Gr. Beta 930.60 +/- 12.00 1030.00 0.61 - 1.43 STW-946 Water 03/01/02 H-3 226.30 +/- 32.70 283.70 0.78 - 2.45 STSO-947 Soil 03/01/02 Ac-228 55.00 +/- 5.50 51.17 0.80 - 1.38 STSO-947 Soil 03/01102 Am-241 8.30 +/- 3.30 10.93 0.65 -2.28 STSO-947 Soil 03/01/02 Bi-212 49.20 +/- 12.40 53.43 0.50 - 1.34 STSO-947 Soil 03/01/02 Bi-214 46.60 +/- 3.10 53.93 0.78 - 1.42 STSO-947 Soil 03/01/02 Cs-i 37 . 1401.60 +/- 9.10 1326.67 0.80 - 1.25 STSO-947 Soil 03/01/02 K-40 613.10 +/- 28.10 621.67 0.80 - 1.32 STSO-947 Soil 03/01/02 Pb-212 51.60 +/- 2.60 51.10 0.78 -1.32 STSO-947 Soil 03/01/02 Pb-214 52.00 +/- 3.60 54.37 0.76 - 1.46 STSO-947 Soil 03/01/02 Pu-239/40 14.70 +/- 3.50 19.10 0.71 - 1.30 STSO-947 Soil 03/01/02 Sr-90 52.10 +/-6.30 53.76 0.67 -2.90 STSO-947 Soil 03/01/02 Th-234 122.40 +/- 6.30 89.30 0.63 -2.35 STSO-947 Soil 03101/02 Uranium 143.40 +/- 9.40 194.77 0.71 - 1.32 STVE-948 Vegetation 03/01/02 Am-241 3.10 +/- 2.20 2.23 0.73 - 2.02 STVE-948 Vegetation 03/01/02 Cm-244 0.90 +/- 0.80 1.32 0.61 - 1.59 STVE-948 Vegetation 03/01/02 Co-60 13.50 +/- 2.10 11.23 0.80 - 1.44 STVE-948 Vegetation 03/01/02 Cs-1 37 350.40 +/- 6.30 313.67 0.80 - 1.31 STVE-948 Vegetation 03/01/02 K-40 940.80 +/- 45.60 864.33 0.79 - 1.39 STVE-948d Vegetation 03/01/02 Pu-239/40 16.90 +/- 0.70 3.54 0.69 - 1.31 STVE-948 Vegetation 03101/02 Sr-90 543.40 +/- 24.90 586.28 0.55 - 1.21 STAP-949 Air Filter 03/01102 Am-241 0.09 +/- 0.05 0.09 0.70 - 2.34 STAP-949 Air Filter 03/01/02 Co-60 30.10 +/- 0.30 30.52 0.80 - 1.26 STAP-949 Air Filter 03/01/02 Cs-137 29.90 +/- 0.30 28.23 0.80 - 1.32 STAP-949 Air Filter 03/01/02 Mn-54 40.40 +/- 0.40 38.53 0.80 - 1.35 STAP-949 Air Filter 03101/02 Pu-238 0.05 +/- 0.02 0.06 0.67 - 1.33 STAP-949 Air Filter 03/01/02 Pu-239/40 0.15 +/- 0.02 0.19 0.73 - 1.26 STAP-949 Air Filter 03/01/02 Sr-90 3.40 +/- 0.40 4.83 0.53 - 1.84 STAP-949 Air Filter 03/01/02 Uranium 0.80 +/- 0.20 0.61 0.79 - 2.10 STAP-950 Air Filter 03101/02 Gr. Alpha 0.43 +/- 0.04 0.53 0.73 - 1.43 STAP-950 Air Filter 03101/02 Gr. Beta 1.34 +/- 0.05 1.30 0.76 - 1.36 STW-959 Water 09/01/02 Am-241 3.00 i 0.10 3.04 0.79 - 1.41 STW-959 Water 09101/02 Co-60 258.40 i 2.30 268.67 0.80 - 1.20 STW-959 Water 09/01/02 Cs-134 50.80 +/- 3.30 60.20 0.80 - 1.30 STW-959 Water 09/01/02 Cs-137 80.10 i 0.30 81.43 0.80 - 1.22 STW-959 Water 09101/02 Cs-1 37 80.10 i 0.30 81.43 0.80 - 1.22 STW-959 Water 09/01/02 Am-241 3.00 +/- 0.10 3.04 0.79 - 1.41 A7-1

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

Concentrationb EML Control Lab Code Type Date Analysis Laboratory results Resulte Limitsd STW-959 Water 09/01/02 Am-241 3.00 + 0.10 3.04 0.79 - 1.41 STW-959 Water 09/01/02 Co-60 258.40 +/- 2.30 268.67 0.80 - 1.20 STW-959 Water 09101/02 Cs-134 50.80 +/- 3.30 60.20 0.80 - 1.30 STW-959 Water 09/01/02 Cs-137 80.10 0.30 81.43 0.80 -1.22 STW-959 Water 09101102 H-3 271.90 +/- 20.90 227.30 0.78 - 2.45 STW-959 Water 09/01/02 Pu-238 4.40 +/- 0.20 4.33 0.74 - 1.20 STW-959 Water 09/01/02 Pu-239/40 2.10 +/- 0.10 2.07 0.79 - 1.20 STW-959 Water 09/01/02 Sr-90 9.70 +/- 0.20 8.69 0.69 - 1.34 STW-959 Water 09/01(02 Uranium 5.60 +/- 0.10 6.84 0.75 - 1.33 STW-960 Water 09/01/02 Gr. Alpha 204.90 +/- 3.20 210.00 0.58 - 1.29 STW-960 Water 09101/02 Gr. Beta 852.00 +/- 26.50 900.00 0.61 - 1.43 STSO-961 Soil 09/01/02 Ac-228 47.60 +/- 1.90 42.30 0.80 - 1.38 STSO-961 Soil 09/01/02 Am-241 7.80 +/- 1.40 6.77 0.65 - 2.28 STSO-961 Soil 09/01/02 Bi-212 45.60 +/- 1.70 45.93 0.50 - 1.34 STSO-961e Soil 09/01/02 Bi-214 48.80 +/- 4.90 33.63 0.78 - 1.42 STSO-961 Soil 09/01102 Cs-137 819.60 +/- 16.60 829.33 0.80 - 1.25 STSO-961 Soil 09/01/02 K-40 705.30 +/- 31.40 637.67 0.80 - 1.32 STSO-961 Soil 09/01/02 Pb-212 48.60 +/- 3.40 43.43 0.78 - 1.32 STSO-961 Soil 09/01/02 Pb-214 51.10 +/- 5.10 35.20 0.76 - 1A6 STSO-961' Soil 09/1Of/02 Pu-239/40 20.20 +/- 0.80 12.90 0.71 - 1.30 STSO-961 Soil 09/01/02 Sr-90 38.50 +/- 0.10 41.16 0.67 - 2.90 STSOQ9619 Soil 09/01/02 Uranium 58.90 +/- 0.70 87.21 0.71 - 1.32 STVE-962 Vegetation 09/01/02 Arn-241 2.10 +/- 0.30 2.25 0.73 -2.02 STVE-962 Vegetation 09/01/02 Cm-244 1.00 +/- 0.30 1.25 0.61 - 1.59 STVE-962 Vegetation 09/01/02 Co-60 11.80 +/- 1.50 9.66 0.80 - 1.44 STVE-962 Vegetation 09/01/02 Cs-137 340.30 +/- 16.80 300.67 0.80 - 1.31 STVE-962 Vegetation 09/01/02 K-40 1646.00 +/- 74.40 1480.00 0.79 - 1.39 STVE-962 Vegetation 09/01/02 Pu-239/40 3.00 +/- 0.30 3.43 0.69 - 1.31 SIVE-962 Vegetation 09/01/02 Sr-90 345.60 +/- 97.80 476.26 0.55 -1.21 STAP-963h Air Filter 09/01/02 Am-241 0.20 +/- 0.01 0.19 0.70 -2.34 STAP-963 Air Filter 09/01/02 Co-60 24.90 +/- 0.60 23.00 0.80 -1.26 STAP-963 Air Filter 09/01/02 Cs-1 37 38.00 +/- 1.30 32.50 0.80 - 1.32 STAP-963 Air Filter 09/01/02 Mn-54 60.80 +/- 1.90 52.20 0.80 - 1.35 STAP-963h Air Filter 09101/02 Pu-238 0.11 +/- 0.02 0.12 0.67 - 1.33 STAP-963h Air Filter 09/01/02 Pu-239/40 0.21 +/- 0.01 0.21 0.73 - 1.26 STAP-963 Air Filter 09/01/02 Sr-90 5.20 +/- 0.20 5.56 0.53 - 1.84 STAP-963h Air Filter 09/01/02 Uranium 0.41 +/- 0.04 0.47 0.79 -2.10 STAP-964 Air Filter 09/01/02 Gr. Alpha 0.40 +/- 0.10 0.29 0.73 - 1.43 STAP-964 Air Filter 09/01/02 Gr. Beta 0.80 +/- 0.10 0.87 0.76 - 1.36

' Results are reported In Bq/L with the following exceptions: Air Filters (Bq/Filter), Soil and Vegetabon (Bqlkg).

t The EML result listed Is the mean of replicate determinations for each nuclide +/- the standard error of the mean.

c Control limits are reported by EML as the ratio of Reported Value / EML value.

dAn error was found in the conversion from pCi/g to Bq/kg. Corrected result: 2.84 +/- 0.59 Bqlkg.

e Naturally-occurring radium daughters are present In the shield background, and a probable cause of the higher bias seen for isotopes of lead and bismuth.

Reporting error.The average result of the triplicate analyses was 14.1+/- 5.7 Bqlkg.

9 The analysis was repeated in duplicate; result of reanalysis, 87.05 +/- 7.64 Bqlkg.

" STAP-963, Calculations for the transuranics analyses (Am-241, Uranium, Pu-238, -239140) were not converted to Bq/total filter.

The data listed Isthe result of recalculaton.

A7-2

APPENDIX B DATA REPORTING CONVENTIONS B-1

Data Renorting 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. Single Measurements Each single measurement is reported as follows: x+/-s where: x = value of the measurement; s = 2s counting uncertainty (corresponding to the 95% confidence level).

In cases where the activity is less than the lower limit of detection L, it is reported as: <L, where L = the lower limit of detection based on 4.66s uncertainty for a background sample.

3.0. Duplicate analyses 3.1 Individual results: For two analysis results; xl +/- si and X2 +/- S2 Reported result: x +/- s; where x = (1i2) (xl + x2) and s = (1/2) s +22S2 3.2. Individual results: <LI, <2 Reported result: <L, where L = lower of Li and L2 3.3. Individual results: x +/- s, <L Reported result: x +/- s if x 2L; <L otherwise.

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 x and standard deviation s of a set of n numbers x 1 , x2 ... xn are defined as follows:

X= -n EX s= _J n(-1) 4.2 Values below the highest lower limit of detection are not included in the average.

4.3 If all 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 number following those to be retained is less than 5, the number is dropped, and the retained number s are kept unchanged. As an example, 11.443 is rounded off to 11.44.

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

B-2

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

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

Air (pCilm3 ) Water (pCVL)

Gross alpha I x10-3 Strontium-89 8,000 Gross beta I Strontium-90 500 Iodine-131b 2.8 x 10-1 Cesium-1 37 1,000 Barium-140 8,000 lodine-I 31 1,000 Potassium-40C 4,000 Gross alpha 2 Gross beta 10 Tritium 1 x 106 a Taken from Table 2 of Appendix B to Code of Federal Regulations Title 10, Part 20, and appropriate footnotes.

Concentrations may be averaged over a period not greater than one year.

b Value adjusted by a factor of 700 to reduce the dose resulting from the air-grass-cow-milk-child pathway.

c A natural radionuclide.

C-2

APPENDIX D Sampling Location Maps

TLO LOCATIONS ONE MILE RADIUS PLANT AREA ENLARGED PLAN (1.00 MILE RADIUS]

[NO SCALE]

MONITORING LEGEND:

0 N.S.P. TLD POINTS D-2 TLD01I.DGN TLOOI SOON D-2

TLD LOCATIONS CONTROL POINTS PRESCOTT, WISCONSIN ISFSI AREA TLO LOCATIONS MONITORING LEGEND:

0 N.S.P. TLD POINTS D3 TL002.0GN D-3 TL002.OGN

TLO LOCATIONS FIVE MILE RADIUS MONITORING LEGEND:

i N.S.P. TLD POINTS D-4 TLD03.OGN D-4 TLDS3.OON

ENVIRONMENTAL SAMPLING POINTS ONE MILE RADIUS J

PLANT AREA ENLARGED PLAN [1.00 MILE RDIUS]

(NO SCALE]

MONITORING LEGEND

< MILK SAMPLING POINT ID NUMBERS FISH SAMPLING POINT ID NUMBERS P-14, P-18. P-25, P-37, P-39,P-41,P-42 0 P-13,P-19 A AIR SAMPLING POINT ID NUMBERS INVERTEBRATES POINT I NUMBERS P-l. P-2, P-3. P-4, P-6 P-6. P-40 G WATER SAMPLING POINT I NUMBERS SEDIMENT SAMPLING POINT I NUMBERS P-5, P-6. P-8. P-9. P-l1. P-25 P-6. P-12. P-20 El ElVEGETATION P-24, P-38

/ VEGETABLES I NUMBERS D- SAMP01.DGN D-5 SAMP01.DGN

ENVIRONMENTAL SAMPLING POINTS FIVE MILE RADIUS MONITORING LEGEND MILK SAMPLING POINT 10 NUMBERS FISH SAMPLING POINT ID NUMBERS P-14, P-IS. P-25. P-37. P-39 P-41.P-42 P-13. P-19 A AIR SAMPLING POINT ID NUMBERS IN INVERTEBRATES POINT ID NUMBERS P-I. P-2. P-3. P-4. P-6 'V P-6, P-40 -

C)

WATER SAMPLING POINT ID NUMBERS P_S, P-6, P-8. P-9. P-It. P-25 ep eMSEDIMENT-SAMPLING POINT ID NUMBERS P-B. P-12. P-20 91 VEGETATION / VEGETABLES 10 NUMBERS P-24, P-38 D-6 SAMP03.DGN D-6 SPiMP03.DGN

/-

ENVIRONMENTAL SAMPLING POINTS P-1 0

(i HUPERT FARM.W 10430 ST RD 29. RIVERFALLS.Wt.

ID CAIN RESIDENCE.

N7395 950th ST.RIVERFALLS. WI.

CONTROL POINTS PRESCOTT, WISCONSIN MONITORING LEGEND MILK SAMPLING POINT ID NUMBERS P-14. P-18. P-25. P-37. P-39. P-41,P-42 A AIR SAMPLING POINT 10 NUMBERS P-1. P-2. P-3. P-4. P-6 0DWATER SAMPLING POINT ID NUMBERS P-5. P-S, P-8, P-9, P-ll, P-25 El VEGETATION P-24, P-38

/ VEGETABLES ID NUMBERS D7 SAMP02.DGN D-7 SAMP02.DGN

L-PI-03-051, 2002 Annual Radiological Environmental Monitoring Report for Prairie Island Nuclear Generating Plant

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L-PI-03-051, 2002 Annual Radiological Environmental Monitoring Report for Prairie Island Nuclear Generating Plant

Text

Attachment:

1.0 INTRODUCTION

SUMMARY

6.0 REFERENCES

1.0 INTRODUCTION

SUMMARY

6.0 REFERENCES

6.0 REFERENCES

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