L-PI-05-043, SNM-2506 - 2004 Annual Radiological Environmental Monitoring Report

SNM-2506 - 2004 Annual Radiological Environmental Monitoring Report

ML051390435
Person / Time
Site:	Prairie Island
Issue date:	05/12/2005
From:	Solymossy J Nuclear Management Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
+sunsi/sispmjr=200603, FOIA/PA-2010-0209, ISFSI TS 6.2, L-PI-05-043
Download: ML051390435 (62)

Text

c OperadMPrairie Island Nuclear Generafing Plant t tOperated by Nuclear Management Company, LLC MAY 1 2 2005 L-PI-05-043 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 Units 1 and 2 Dockets 50-282, 50-306 and 72-10 License Nos. DPR-42, DPR-60 and SNM-2506 2004 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 SNM-2506, the Nuclear Management Company, LLC submits one copy of the Annual Radiological Environmental Monitoring Report for the period January 1, 2004 through December 31, 2004.

Summary of Commitments This letter contains no new commitments and no revisions to existing commitments.

Sit Vice President airie Island Nuclear Generating Plant uclear Manageme t Company, LLC Enclosure (1)

CC Regional Administrator, USNRC, Region IlIl Project Manager, Prairie Island Nuclear Generating Plant, USNRC, NRR NRC Resident Inspector- Prairie Island Nuclear Generating Plant Dr. John House, USNRC, Region IlIl Director of NMSS, USNRC Tim Donakowski, State of Minnesota Pi Dakota Community Environmental Coordinator 1717 Wakonade Drive East

• Welch, Minnesota 55089-9642 Telephone: 651.388.1121

ENCLOSURE IAnnual Report to the United States Nuclear Regulatory Commission Radiation Environmental Monitoring Program January 1 to December 31, 2004 60 pages to follow

Environmental, Inc.

Midwest Laboratory an Allegheny Technologies Co.

700 Landwehr Road

• Northbrook, IL 60062-2310 ph. (847) 564-700

• 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 1to December 31, 2004 Prepared under Contract by ENVIRONMENTAL, Inc.

MIDWEST LABORATORY Project No. 8010 Approved:

Xronaro ,M.S.

0aborattranager

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

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 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 ... A1-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 Page 5.1 Offsite Ambient Radiation (TLDs), average of inner and outer ring indicator locations versus control ................................... 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) ................................... 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, 2004. 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, 2005b) 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 2004 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, 2004). 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-1 31. Quarterly composites of particulate filters from each location are determined by gamma spectroscopy. 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 Descrintion (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) No air particulate/air iodine sample was collected from location P-01 for the week of 11-21-04, due to a sarmpler pump failure.

(2) A partial air particulate/air iodine sample was collected from location P-04 for the week of 10-03-04, due to a power outage lasting more than eight hours.

Deviations from the program are summarized in Table 5.3.

3.4 Laboratory Procedures Analyses for iodine-131 in milk and drinking water utilize a sensitive radiochemical procedure involving the separation of the element by ion-exchange and subsequent beta counting. Gamma-spectroscopic analysis is performed using a high-purity germanium (HPGe) detector. Levels of airborne iodine-131 in charcoal samples are measured by gamma spectroscopy.

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

Tritium levels are 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, 2003). The program includes participation in Interlaboratory Comparison (Crosscheck) programs and results are presented in Appendix A.

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3.5 Program Modifications The Huppert Farm (P-41) was replaced by the Peterson Farm (P-43) in February, 2004, as a control location for milk and well water.

The Glazier garden was added to the program in July, 2004, as a sampling site for broadleaf vegetation.

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 ft 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 Land Use Census was completed in September and October, 2004. There were no changes to any of the highest D/Q locations for nearest residence or garden sites. A goat dairy was established in 2004 which has a higher D/Q than the other dairy farms. At the time of the census, all dairy goats were dry, with milking operations expected to continue in the Spring of 2005. If possible, sampling of this dairy will commence in 2005. The critical receptor location did not change in 2004, 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 2004. 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 2004.

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 2 2 fallout declined yearly from a level of 12,167 pCi/m to 1,020 pCi/m , and these declining values are reflected throughout the various media tested.

In the air environment, ambient gamma radiation (TLDs) averaged 9.4 mR/4 weeks during preoperational studies. Gross beta in air particulates declined from levels of 0.38 to 0.037 pCi/in3 . Average present day levels have stabilized at around 0.025 pCi/m . 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-137 and 1-131 are below detection levels. Agricultural crop measurements averaged 57.7 pCig 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 pCi/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-137 activity during preoperational studies in 1973 measured 0.25 pCi/g upstream and 0.21 pCi/g downstream. The lower levels occasionally observed today can still be attributed to residual activity from atmospheric fallout.

Gross beta in fish, measured in both flesh and skeletal samples, averaged 7.3 and 11.7 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 Findinqs Slight tritium activity was detected in two downstream river water composites (pg. 11). It was determined that the collections coincided with planned radioactive discharges from the plant. All other results indicate background levels of radioactivity in environmental samples collected in the vicinity of the Prairie Island Nuclear Generating Plant.

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 17.0 mR/91 days at inner ring locations to 18.0 mR/91 days at outer ring locations. The mean at special locations was 16.9 mR/91 days and 17.6 mR/91 days at the control locations.

Dose rates measured at the inner and outer ring and the control locations were similar to those observed from 1989 through 2003. The results are tabulated below. No plant effect on ambient gamma radiation was indicated (Figure 5-1).

Average (Inner and Average (Inner and Year Outer Rings) Control Year Outer Rings) Control 1989 16.5 16.7 - 1997 15.1 16.0 1990 15.9 16.3 _ 1998 16.7 17.3 1991 14.9 14.5 1999 16.6 17.5 1992 16.3 14.8 _ 2000 17.0 17.1 1993 15.9 15.4 2001 16.8 17.2 1994 15.2 16.0 _ 2002 17.4 16.9 1995 15.6 16.6 2003 16.2 16.0 1996 14.8 16.4 2004 17.6 17.6 Ambient gamma radiation as measured by thermoluminescent dosimetry.

Average quarterly dose rates (mRI91 days).

ISFSI Facility Onerations 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 84.8 mR/91 days inside the ISFSI earth berm and 25.2 mR/91 days outside the ISFSI earth berm. No additional casks were placed on the ISFSI pad in 2004, a total of seventeen loaded casks remain. 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 2004 fourth quarter TLD results for ISFSI monitoring locations P-01 IB, P-021B, P-031B, and P-081B (located north and east of the ISFSI berm) were elevated. The higher doses were due to temporary use of the adjacent area for preparing used steam generators for shipment. Now that the steam generators have been shipped, doses are expected to return to their previous levels during the first quarter of 2005.

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 16.4 and 16.0 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 lower at the 3 3 indicator versus the control locations (0.025 pCi/M and 0.026 pCi/M , respectively) and similar to levels observed from 1989 through 2003. The results are tabulated below.

_ Average of l Year Indicators Control 3

Concentration (pCi/m )

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 2003 0.027 0.025 2004 0.025 0.026 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.

Typically, the highest averages for gross beta occur during the months of January and December, and the first and fourth quarters, as in 1989 through 2004.

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., 2005).

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 pCi/L in all samples. No other gamma-emitting isotopes, except naturally-occurring potassium-40, were detected in any milk samples. This is consistent with the findings of the National Center for Radiological Health that most radiocontaminants in feed do not find their way into milk due to the selective metabolism of the cow. The common exceptions are radioisotopes of potassium, cesium, strontium, barium, and iodine (National Center for Radiological Health, 1968).

In summary, the milk data for 2004 show no radiological effects of the plant operation.

Drinking 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 9.8 pCi/L throughout the year, ranging from 8.1-11.4 pCUL. These concentrations were similar to or slightly higher than levels observed from 1989 through 2003. 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 2004 data of any effect of plant operation.

Year Gross Beta Year_ __ (pCUL) 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 2003 = 9.9 2004 9.8 Average annual concentrations; Gross beta in drinking water.

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River Water For the first and fourth quarters of 2004, measurable tritium was detected in downstream river water composites, at concentrations of 389 and 184 pCi/L, respectively. This is well below the Environmental Protection Agency's drinking water standard of 20,000 pCi/L. For the remaining upstream and downstream collections, tritium levels measured below the LLD level of 163 pCi/L.

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

Well Water At the control well P-43, Huppert Farm and four indicator wells (P-8, Community Center, P-6, Lock and Dam No. 3, P-9, Plant Well No. 2 and P-24, Suter Farm ) no tritium was detected above the LLD level of 165 pCi/L. Gamma-emitting isotopes were below detection limits in all samples.

In summary, well water data for 2004 show no radiological effects of the plant operation.

Crops Three samples of broadleaf vegetation, cabbage leaves, were collected in July and analyzed for gamma-emitting isotopes, including iodine-131. The 1-131 level was below 0.019 pCi/g wet weight in all 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.

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, 2004 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 Perinhvton Aquatic insects (invertebrates) or periphyton were collected in May and September, 2004. All gamma-emitting isotopes were below their respective detection limits. There was no indication of a plant effect.

Bottom and Shoreline Sediments Upstream, downstream and downstream recreational area shoreline sediment collections were made in May and September, 2004 and analyzed for gamma-emitting isotopes. The only gamma-emitting isotope detected was naturally-occurring 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.

-+ Indicator 20 19 18 17 16 /

r 15 ---- -

14 E 13 12 11

- I Il 10 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004

-o- Control (P-01C) 20 19 18 -

-- it _

cj 17 16 15-

- Ac- --I I 2 13 14

.----. t-----',-m-- - _I ll _

E 12 11 10 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 13

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

--- Indicators (P-2,3,4,6) 0.035 0.033 0.031 0.029 0.027 0.025 S == I_

==_ >

0.023

. X >S w _ H= > -=

0.021 0.019 0.017 X~~~~ ___ IX 0.015 1!989 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 l-- Control (P-1) l 0.035 -- _ --- - -

0.033 - - = - = - l 0.031---

0.029 --

0.027 --- -__ __ - __t 0O.025 -- -- -

0.02 L0.021= =

0.019 - 1-I - -

0.017 - 19 1992 19 1994 - 1 19 1998 - - -

0.015 - _ _ __ _

1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 2004 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)" Frequencyb Frequencyc Ambient radiation (TLD's) 54 P-01A - P-1OA C/Q Ambient gamma P-1B- P-15B P-Ols - P-08S P-OIIA - P-081A P-OlIB - P-081B P-OIIX- P-041X, P-OiC Airbome Particulates 5 P-1(C), P-2, C/W GB, GS (QC of P-3, P-4, P-6 each location)

Airborne Iodine 5 P-1(C), P-2, P-3, P4, P-6 C/W 1-131 Milk 5 P-14, P-18, P-37, P-42 G/md 1-131, GS P41 (C), P-43 (C)

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

Drinking water 1 P-Il G/W GB(MC), 1431(MC)

GS (MC), H-3 (QC)

Well water 5 P-6, P-8, P-9, P-24, G/Q H-3, GS P-41 (C), P43 (C)

Edible cultivated crops- 2 P-38(C), P-24 G/A GS (1-131) leafy green vegetables Fish (one species, edible portion) 2 P-19(C), P-13 G/SA GS Periphyton or Invertebrates 2 P-40(C), P-6 G/SA GS Bottom sediment 2 P-20(C), P-6 G/SA GS Shoreline sediment 1 P-12 G/SA GS

• Location codes are defined In Table D-2. Control stations are Indicated by (C). All other stations are Indicators.

b Collection type Is coded as follows: C/ - continuous, G/ - grab. Collection frequency Is coded as follows:

W- weekly, M - monthly, Q- quarterly, SA - semiannually, A - annually.

CAnalysis type Is coded as follows: GB - gross beta, GS - gamma spectroscopy, H tritium, 1-131 - Iodine-131.

Analysis frequency Is coded as follows: MC - monthly composite, QC - quarterly composite.

d Milk Iscollected 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 Type' Collection Site Sample Typeb Reactor P-1 C Air Station P-1 AP, Al +/-1.8 ml @316 0/NNW P-2 Air Station P-2 AP, Al 0.5 ml @294 0/WNW P-3 Air Station P-3 AP, Al 0.8 ml @ 313 0/NW P-4 Air Station P-4 AP, Al 0.4 ml @ 359 0/N P-5 C Upstream of Plant RW 1.8 ml @ 11/N P-6 Lock and Dam #3 & Air AP, Al, RW Station P-6 WW, BS, BOC 1.6 ml @ 1290/SE P-8 Community Center WW 1.0 ml @321°/WNW P-9 Plant Well #2 WW 0.3 ml @ 306°/NW P-li Red Wing Service Center DW 3.3 ml @ 1580/SSE P-12 Downstream of Plant Ss 3.0 ml @ iI6°/ESE P-13 Downstream of Plant F' 3.5 ml @113 0/ESE P-14 Gustafson Farm M 2.3 ml@ 173°/S P-18 Christiansen Farm M 3.8 ml @88°/E P-19 C Upstream of Plant F' 1.3 ml @0°/N P-20 C Upstream of Plant BS 0.9 ml @45°/NE P-24 Suter Residence VE, WW 0.6 ml@ 1580/SSE P-37 Welsch Farm M 4.1 ml @870/E P-38 C Cain Residence VE 14.2 ml @359°/N P-40 C Upstream of Plant BO' 0.4 ml@ 0°/N P-41 C Huppert Farm MWW 13.8 ml @354 0/N P-42 Rother Farm M 4.3 ml.@i 2640/W P-43 C Peterson Farm MWW 13.9 ml. @355 0/N General Area of the Site Boundary P-OlA Property Line TLD 0.4 ml @359°/N P-02A Property Line TLD 0.3 ml @100/N P-03A Property Line TLD 0.5 ml @ 183°/S P-04A Property Line TLD 0.4 ml @204°/SWW P-05A Property Line TLD 0.4 ml @225 0/SW P-46A Property Line TLD 0.4 ml @249 0/WSW P-07A Property Line TLD 0.4 ml @268 0/W P-08A Property Line TLD 0.4 ml @2910/WNW P-09A Property Line TLD 0.7 ml @ 317 0/NW P-1OA Property Line TLD 0.5 ml @ 333 0/NNW 16

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

Distance and Direction from Code Type Collection Site Sample Typeb Reactor Approximatelv 4 to 5 miles Distant from the Plant P-OlB Thomas Killian Residence TLD 4.7 ml @ 355 0/N P-02B Roy Kinneman Residence TLD 4.8 ml @17°/NNE P-03B Wayne Anderson Farm TLD 4.9 ml @ 46°/NE P-04B Nelson Drive (Road) TLD 4.2 ml @ 61°/ENE P-05B County Road E and Coulee TLD 4.2 ml @ 102 0/ESE P-06B William Hauschlblt Residence TLD 4.4 ml @ 112 0/ESE P-07B Red Wing Public Works TLD 4.7 ml @ 140 0/SE P-08B David Wnuk Residence TLD 4.1 ml @165°/SSE P-09B Highway 19 South TLD 4.2 ml @ 187°/S P-1OB Cannondale Farm TLD 4.9 ml @ 200 0/SSW P-llB Wallace Weberg Farm TLD 4.5 ml @ 221°/SW P-12B Ray Gergen Farm TLD 4.6 ml @251°/WSW P-13B Thomas O'Rourke Farm TLD 4.4 ml @ 270°/W P-14B David J. Anderson Farm TLD 4.9 ml @306°/NW P-15B Hoist Farms TLD 3.8 ml @ 345°/NNW Special Interest Locations P-01S Federal Lock & Dam #3 TLD 1.6 ml @ 1290/SE P-025 Charles Suter Residence TLD 0.5 ml @ 155°/SSE P-035 Carl Gustafson Farm TLD 2.2 ml @ 173°/S P-04S Richard Burt Residence TLD 2.0 ml t 202°/SSW P-055 Kinney Store TLD 2.0 ml @ 270°/W P-06S Earl Flynn Farm TLD 2.5 ml @ 299 0/WNW P-07S Indian Community TLD 0.7 ml 271°/W P-08S Indian Community TLD 0.7 ml @287 0/NWW P-0lC C Robert Kinneman Farm TLD 11.1 ml @ 3310/NNW 17

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

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

ISFSI Area Inside Earth Berm P-11A ISFSI Nuisance Fence TLD 190' @45 0/NE P-021A ISFSI Nuisance Fence TLD 360' © 820/E P-031A ISFSI NuisanceFence TLD 370' @ 1000/E P-041A ISFSI Nuisance Fence TLD 200' @134°/SE P-051A ISFSI Nuisance Fence TLD 180' @ 2190 /SW P-061A ISFSI Nuisance Fence TLD 320' @ 2580/WSW P-071A ISFSI Nuisance Fence TLD 320' @281!/WNW P-081A ISFSI Nuisance Fence TLD 190' @ 3180 /NW P-41IX ISFSI Nuisance Fence TLD 140' @1800/S P-021X ISFSI Nuisance Fence TLD 310 @270°/W P-031X ISFSI Nuisance Fence TLD 140' @0 0/N P-041X ISFSI Nuisance Fence TLD 360' @90*/E ISFSI Area Outside Earth Berm P-411B ISFSI Berm Area TLD 340' @3 0 /N P-021B ISFSI Berm Area TLD 380' @28 0/NNE P-031B ISFSI Berm Area TLD 560' @ 850/E P-041B ISFSI Berm Area TLD 590' @1650 /SSE P-051B ISFSI Berm Area TLD 690' @1860/S P-061B ISFSI Berm Area TLD 720' @2010/SSW P-071B ISFSI Berm Area TLD 610' @2710 /W P4081B ISFSI Berm Area TLD 360' @3320/NNW

• 'C denotes control location. All other locations are Indicators.

b Sample Codes:

AP Airborne particulates F Fish Al Airborne 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 e 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, 1-131 P-04 10/5/2004 Power outage at sampler site Portable generator used until for more than 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. power was restored.

AP/AI Beta, 1-131 P-01 11/23/2004 Sampler pump failure. Sampler pump was replaced with a calibrated spare.

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, 2004

( County, State )

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)' Mean (F)c Mean (F)e Routine (Units) Analyses _ Range' Locationd Range' Range' Resultse TLD (Inner Ring, Gamma 40 3.0 17.0 (40/40) P-06A 18.1 (414) (See Control 0 Area at Site (12.8-22.4) 0.4 ml @ 249 /WSW (16.0-22.4) below.)

Boundary) mR/91 days)

TLD (Outer Ring. Gamma 60 3.0 18.0 (60/60) P-02B. Roy Kinneman, 20.6 (414) (See Control 0 4-5 mi. distant) (13.7-25.5) 4.8 mi @ 17 INNE (18.5-25.5) below.)

mR/91 days)

TLD (Special Gamma 32 3.0 16.9 (32132) P-03S, Gustafson Farm, 20.0 (414) (See Control 0 Interest Areas) (13.6-24.4) 2.2 mi @ 173'/S (18.1-24.4) below.)

mR/91 days)

TLD (Control) Gamma 4 3.0 None P-01C, R. Kinneman, 17.6 (414) 17.6 (4/4) 0 mR/91 days) 11.1 mi @ 3310 /NNW (16.1-20.6) (16.1-20.6)

Airbome GB 259 0.005 0.025 (208/208) P-03, Air Station 0.026 (52/52) 0.026 (51/51) 0 Particulates (0.008-0.059) 0.8 mi @ 3130 /NW (0.010-0.056) (0.011-0.056)

(pCim 3)

GS 20 Be-7 0.015 0.061 (16/16) P-03, Air Station 0.065 (4/4) 0.063 (4/4) 0 (0.044-0.080) 0.8 mi @ 3130 /NW (0.049-0.080) (0.052-0.077)

Mn-54 0.0006 < LLD - - < LLD 0 Co-58 0.0005 < LLD - - < LLD 0 Co-60 0.0007 < LLD - - < LLD 0 Zn-65 0.0008 < LLD - - < LLD 0 Zr-Nb-95 0.0009 < LLD - < LLD 0 Ru-103 0.0008 < LLD - < LLD 0 Ru-1 06 0.0051 < LLD - < LLD 0 Cs-134 0.0006 < LLD - < LLD 0 Cs-137 0.0008 < LLD - < LLD 0 Ba-La-140 0.0024 < LLD < LLD 0 Ce-141 0.0018 < LLD < LLD 0 Ce-144 0.0038 < 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, 2004

( County, State )

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)' Mean (F)' Mean (F)' Routine (Units) . Analyses' Range' Locationd Range' Range' Results*

Milk (pCi/L) 1-131 90 1.0 < LLD <LLD c 0 GS 90 K-40 200 '1407 (72172) P-37, Welsch Farm 1465 (18 /18) 1364 (18/18) 0 (1168-1669) 4.1 mi@ 87/ IE (1346-1669) (1235-1550)

Cs-134 15 < LLD < LLD 0 Cs-137 15 - < LLD . < LLD 0 Ba-La-140 15 < LLD < LLD 0 River Water H-3 8 163 287 (2/4) P-4, Lock and Dam #3 287 (2/4) < LLD 0 (pCi/L) (184-389) 1.6 mi @ 129 01SE (184-389)

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 62 < 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. 2004 (County, State )

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (Ff Mean (F)' Mean (F)' Routine (Units) Analyses' Range' Locationd Range' Range' Results' Drinking Water GB 12 1.0 9.8 (12112) P-11, Red Wing S.C. 9.8 (12112) None 0 (pCi/L) (8.1-11.4) 3.3 ml @ 158° /SSE (8.1-11.4) 1-131 12 1.0 < LLD . None 0 H-3 4 163 < 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 55 < LLD - None 0 Well Water H-3 20 163 < LLD - < LLD 0 (pCiUL)

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 63 < LLD - - < LLD 0 Crops - Cabbage 1-131 3 0.019 < LLD - - < LLD 0 (pCilgwet) 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. 2004 (County, State )

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F)' Mean (F)' Mean (F)' Routine (Units) Analyses' Range' Locationd Range' Range' Results' Fish GS 4 (pCi/g wet) K-40 0.10 2.98 (212) P-13, Downstream 2.98 (212) 2.83 (212) 0 (2.56-3.39) 3.5 mi @ 1130 /ESE (2.56-3.39) (2.45-3.21)

Mn-54 0.017 < LLD <LLD c- 0 Fe-59 0.061 < LLD - - <LLD 0 Co-58 0.020 < LLD - - < LLD 0 Co-60 0.019 < LLD - - < LLD 0 Zn-65 0.032 < LLD - - < LLD 0 Zr-Nb-95 0.032 < LLD . - < LLD 0 Cs-134 0.019 < LLD - < LLD 0 Cs-137 0.020 < LLD - < LLD 0 Ba-La-140 0.050 < LLD - < LLD 0 Invertebrates GS 4 (pCi/g wet) Be-7 0.63 < LLD - < LLD 0 K-40 1.30 < LLD - < LLD 0 Mn-54 0.070 < LLD - - < LLD 0 Co-58 0.067 < LLD - - < LLD 0 Co-60 0.065 < LLD - - < LLD 0 Zn-65 0.11 < LLD - - < LLD 0 Zr-Nb-95 0.11 < LLD - - < LLD 0 Ru-103 0.079 < LLD - - < LLD 0 Ru-106 0.52 < LLD - < LLD 0 Cs-1 34 0.055 < LLD - < LLD 0 Cs-137 0.052 < LLD - < LLD 0 Ba-La-140 0.2 < LLD - < LLD 0 Ce-141 0.11 < LLD - < LLD 0 Ce-144 0.33 < 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, 2004

( County, State )

Indicator Location with Highest Control Number Sample Type and Locations Annual Mean Locations Non-Type Number of LLDb Mean (F) Mean (F) Mean (F) Routine (Units) Analyses' Range' Locationd Rangec Range' Results" Bottom and GS 6 Shoreline Be-7 0.25 < LLD - < LLD 0 Sediments (pCi/g dry) K-40 0.10 8.31 (414) P-20. Upstream 10.05 (2/2) 10.05 (2/2) 0 (6.41-9.22) 0.9 mi. @ 45° /NE (9.98-10.11) (9.98-10.11)

Mn-54 0.023 < LLD < LLD 0 Co-58 0.033 < LLD - . <LLD 0 Co-60 0.023 < LLD < LLD 0 Zn-65 0.079 < LLD < LLD 0 Zr-Nb-95 0.034 < LLD < LLD 0 Ru-103 0.023 < LLD < LLD 0 Ru-106 0.18 < LLD < LLD 0 Cs-134 0.038 < LLD < LLD 0 Cs-137 0.027 < LLD < LLD 0 Ba-La-140 0.083 < LLD < LLD 0 Ce-141 0.044 < LLD < LLD 0 Ce-144 0.10 < LLD < LLD 0 oGB = 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.

• Non-routine results are those which exceed ten times the control station value. If no control station value is available, the result is considered non-routine If it exceeds ten time 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 2005a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January-December, 2000 through 2004.

____ 2001b through 2005b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December, 2000-2004.

2003. Quality Assurance Program Manual, Rev. 0, 01 October 2003.

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

2003. Quality Control Program, Rev. 0, 21 August 2003.

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.

Northern States Power Company.

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

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

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

1979 to 2003. Prairie Island Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 1978 through 2002. Minneapolis, Minnesota.

25

6.0 REFERENCES

CITED (continued)

Prairie Island Nuclear Generating Plant, 2004. 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-52015-84-006).

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. 2005. Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January I to December 31, 2004 (prepared by Environmental, Inc., Midwest Laboratory). Northbrook, Illinois 26

Environmental, Inc.

Mdw est Laboratory an Aflegheny Technldoges Co.

700 Landwhr Road

• Notbro&k IL 600622 (847)W540700 fv (84) 5a4-4517 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 times a year; the complete Appendix is included in March, June, September and December monthly progress reports only.

January through December, 2004

Appendix A Interlaboratorv Comparison Program 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 list results for thermoluminescent dosimeters (TLDs), via International Intercomparison of Environmental Dosimeters, when available, and internal laboratory testing.

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

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

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

The results in Table A-6 were obtained through participation in the Mixed Analyte Performance Evaluation Program.

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

Attachment A lists acceptance criteria for 'spiked' samples.

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

Al

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 pCi/liter or kg 5.0 pCi/liter

> 100 pCi/liter or kg 5% of known value Strontium_89b 5 to 50 pCi/liter or kg 5.0 pCi/liter

> 50 pCilliter or kg 10% of known value Strontium_90b 2 to 30 pCilliter or kg 5.0 pCi/liter

> 30 pCi/liter or kg 10% of known value Potassium-40 2 0.1 galiter or kg 5% of known value Gross alpha s 20 pCi/liter 5.0 pCi/liter

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

> 100 pCinliter 5% of known value Tritium s 4,000 pCi/liter lIa = (pCi/liter) =

169.85 x (known) 00 93 3

> 4,000 pCiliter 10% of known value Radium-226,-228 2 0.1 pCiliter 15% of known value Plutonium 2 0.1 pCiliter, gram, or sample 10% of known value lodine-131, 5 55 pCi/liter 6.0 pCi/liter lodine-129b > 55 pCi/liter 10% of known value Uranium-238, s 35 pCiniter 6.0 pCiliter Nickel-63b > 35 pCi/liter 15% of known value Technetium-99b Iron-55b 50 to 100 pCi/liter 10 pCi/liter

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

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

b Laboratory limit.

A2

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

Concentration (pCi/L)

Lab Code Date Analysis Laboratory ERA Control Resultb Resultc Limits STW-1005 02/17/04 Sr-89 36.5 +/- 6.5 44.9 +/-4.5 36.2 - 53.6 STW-1005 02/17/04 Sr-90 13.4 +/-0.8 11.6 +/- 1.2 2.9 - 20.3 STW-1006 02/17/04 Ba-133 60.9 +/- 2.8 63.2 +/- 6.3 52.3 - 74.1 STW-1006 02/17/04 Co-60 95.2 +/- 1.5 96.4 +/- 9.6 87.7 - 105.0 STW-1006 02/17/04 Cs-134 71.2 +/- 5.4 75.8 +/- 7.6 67.1 - 84.5 STW-1006 02/17/04 Cs-137 157.0 +/- 6.5 155.0 +/- 15.5 142.0 - 168.0 STW-1006 02/17/04 Zn-65 103.0 +/- 1.1 102.0 +/- 10.2 84.4 - 120.0 STW-1007 02/17/04 Gr. Alpha 15.6 +/- 1.2 16.6 +/- 1.7 7.9 - 25.3 STW-1007 02/17/04 Gr. Beta 46.3 +/- 4.4 41.5 +/- 4.2 32.8 - 50.2 STW-1008 02/17/04 Ra-226 8.7 +/- 0.2 9.3 +/- 0.0 6.9 - 11.7 STW-1008 02/17/04 Ra-228 16.6 +/- 0.4 18.2 +/- 1.8 10.3 - 26.1 STW-1008 02/17/04 Uranium 34.2 +/- 0.8 33.0 +/- 3.3 27.8 - 38.2 STW-1015 05/18/04 Sr-89 39.7 +/- 3.3 45.9 +/- 5.0 37.2 - 54.6 STW-1015 05/18/04 Sr-90 12.4 +/-0.9 11.6 +/-5.0 2.9 - 20.3 STW-1016 05/18/04 Ba-1 33 96.9 +/- 2.4 101.0 +/- 10.1 83.5 - 118.0 STW-1016 05/18/04 Co-60 39.9 +/- 0.5 41.6 +/- 5.0 32.9 - 50.3 STW-1016 05/18/04 Cs-134 48.8 +/- 0.8 50.5 +/- 5.0 41.8 - 59.2 STW-1016 05/18/04 Cs-137 82.6 +/- 2.3 82.5 +/- 5.0 73.8 - 91.2 STW-1016 05/18/04 Zn-65 77.5 +/- 1.5 75.2 +/- 7.5 62.2 -88.2 STW-1017 05/18/04 Gr. Alpha 32.4 +/-2.1 38.8 +/- 9.7 22.0 - 55.6 STW-1017 05/18/04 Gr. Beta 63.4 +/- 3.5 59.6 +/- 10.0 42.3 - 76.9 STW-1018 05/18/04 1-131 25.2 +/- 0.4 25.1 +/-3.0 19.9 - 30.3 STW-1019 05/18/04 Ra-226 16.0 +/- 1.1 17.3 +/-2.6 12.8 - 21.8 STW-1019 05/18/04 Ra-228 12.6 +/- 0.9 10.3 +/-2.6 5.8 - 14.8 STW-1 019 05/18/04 Uranium 13.0 +/- 0.0 12.7 +/-3.0 7.5 - 17.9 STW-1 020 05/18/04 H-3 32043 +/- 166 30900 +/- 3090 25600 - 36200 STW-1028 08/17/04 Sr-89 16.1 +/-1.9 20.0 +/- 2.0 11.3 - 28.7 STW-1028 08/17/04 Sr-90 13.4 +/- 0.1 13.6 +/- 1.4 4.9 - 22.3 STvW-1029 08/17/04 Ba-133 30.2 +/- 3.9 32.1 +/- 3.2 23.4 - 40.8 STW-1029 08/17/04 Co-60 24.9 +/- 1.9 24.0 +/- 2.4 15.3 - 32.7 STW-1029 08/17/04 Cs-134 21.4 +/-3.4 21.6 +/- 2.2 12.9 - 30.3 STW-1029 08/17/04 Cs-1 37 205.6 +/- 4.3 193.0 +/- 19.3 176.0 - 210.0 STW-1029 08/17/04 Zn-65 145.5 +/- 3.0 143.0 +/-14.3 118.0 - 168.0 STW-1030 08/17/04 Gr. Alpha 47.7 +/- 9.1 57.0 +/- 5.7 32.3 - 81.7 STW-1030 08/17/04 Gr. Beta 28.1 +/- 2.5 20.0 +/- 2.0 11.3 - 28.7 STW-1030 08117/04 Gr. Beta 28.1 +/- 2.5 20.0 +/- 2.0 11.3 - 28.7 STW-1031 08/17104 Ra-226 6.9 +/- 0.5 6.3 +/- 0.6 4.6 - 7.9 STW-1031 08/17/04 Ra-228 13.1 +/-1.4 14.7 +/- 1.5 8.3 - 21.1 STW-1031 08117/04 Uranium 6.0 +/- 0.1 6.2 +/- 0.6 1.0 - 11.4 A1-I

TABLE A-1. Interlaboratory Comparison Crosscheck program, Environmental Resource Associates (ERA) 8.

Concentration (pCilL)

Lab Code Date Analysis Laboratory ERA Control Resulte Result' Limits STW-1037 11/15/04 Sr-89 42.2 i 3.5 45.7 +/-5.0 37.0 - 51.5 STW-1037 11/15/04 Sr-90 37.3 +/-1.3 36.6 +/-5.0 27.9 - 45.3 STW-1 038 11/15/04 Ba-133 75.5 +/-0.8 78.4 +/- 7.8 64.8 - 92.0 STW-1038 11/15/04 Co-60 12.2 +/-0.7 11.7 +/- 5.0 3.0 - 20.4 STW-1038 11/15104 Cs-1 34 43.6 i 0.5 42.9 +/-5.0 34.2 - 51.6 STW-1038 11/15/04 Cs-1 37 59.5 +/-2.9 60.1 +/-5.0 51.4 - 68.8 STW-1038 11/15/04 Zn-65 50.7 l 3.2 50.9 +/-5.1 42.1 - 59.7 STW-1039 11/15/04 Gr. Alpha 23.9 +/-2.2 31.7 +/- 7.9 18.0 -45.4 STW-1039 11/15/04 Gr. Beta 35.8 +/-1.3 36.3 +/- 5.0 27.6 - 45.0 STW-1040 11/15/104 1-131 22.4 +/-1;9 22.0 +/- 5.0 16.9 - 27.3 STW-1041 11/15/04 Ra-226 9.8 i 0.4 9.2 +/- 1.4 6.8 - 11.6 STW-1041 11/15/04 Ra-228 8.6 +/-0.3 7.1 +/- 1.8 7.0 - 10.2 STW-1041 11/15/04 Uranium 11.1 +/-0.3 11.4 +/-3.0 6.2 - 16.6 STW-1042 11/15/04 H-3 21218.0 +/- 285.0 20700.0 +/- 2070.0 17100.0 - 24300.0

' Results obtained by Environmental, Inc., Midwest Laboratory as a participant in the crosscheck program for proficiency testing in drinking water conducted by Environmental Resources Associates (ERA).

b Unless otherwise Indicated, the laboratory result Is given as the mean i standard deviation for three determinations.

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

A1-2

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

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

2003-1 CaSO4: Dy Cards 8/8/2003 Reader 1,120 4.69 4.74 +/- 0.54 3.28 - 6.10 2003-1 CaSO4: Dy Cards 8/8/2003 Reader 1,150 3.00 3.02 +/- 0.20 2.10 - 3.90 2003-1 CaSO4: Dy Cards 8/8/2003 Reader 1, 180 2.08 1.89 +/- 0.45 1.46 - 2.70 2003-1 CaSO4: Dy Cards 8/812003 Reader 1,180 2.08 2.11 +/- 0.22 1.46 - 2.70 2003-1 CaSO4: Dy Cards 8/8/2003 Reader 1,30 75.00 84.40 +/- 4.87 52.50 - 97.50 2003-1 CaSO4: Dy Cards 8/812003 Reader 1,60 18.75 19.11 +/- 1.86 13.13 - 24.38 2003-1 CaSO4: Dy Cards 8/8/2003 Reader 1,60 18.75 22.82 +/- 5.41 13.13 - 24.38 2003-1 CaSO4: Dy Cards 8/8/2003 Reader 1,90 8.33 9.05 +/- 1.17 5.83 - 10.83 2003-1 CaSO4: Dy Cards 8/8/2003 Reader 1, 90 8.33 7.60 +/- 1.08 5.83 - 10.83 Environmental. Inc.

2003-2 CaSO4: Dy Cards 1/12/2004 Reader 1, 30 61.96 73.50 +/- 2.58 43.37 - 80.55 2003-2 CaSO4: Dy Cards 1/1212004 Reader 1,60 15.49 19.70 +/- 0.51 10.84 - 20.14 2003-2 CaSO4: Dy Cards 1/12/2004 Reader 1,60 15.49 16.93 +/- 1.37 10.84 - 20.14 2003-2 CaSO4: Dy Cards 1/12/2004 Reader 1,90 6.88 8.06 +/- 0.60 4.82 - 8.94 2003-2 CaSO4: Dy Cards 1/12/2004 Reader 1,90 6.88 6.64 +/- 0.58 4.82 - 8.94 2003-2 CaSO4: Dy Cards 1/12/2004 Reader 1,120 3.87 4.39 +/- 0.17 2.71 - 5.03 2003-2 CaSO4: Dy Cards 1/12/2004 Reader 1, 150 2.48 2.34 +/- 0.18 1.74 - 3.22 2003-2 CaSO4: Dy Cards 1/12/2004 Reader 1,150 2.48 2.51 +/- 0.16 1.74 - 3.22 2003-2 CaSO4: Dy Cards 1/12/2004 Reader 1, 180 1.72 2.01 +/- 0.13 1.20 - 2.24 Environmental. Inc.

2004-1 CaSO4: Dy Cards 7/12/2004 Reader 1, 30 cm 55.23 61.07 +/- 4.38 38.66 - 71.80 2004-1 CaSO4: Dy Cards 7/12/2004 Reader 1, 30 cm 55.23 62.82 +/- 1.75 38.66 - 71.80 2004-1 CaSO4: Dy Cards 7/12/2004 Reader 1, 60 cm 13.81 14.10 +/- 0.56 9.67 - 17.95 2004-1 CaSO4: Dy Cards 7/12/2004 Reader 1,60 cm 13.81 14.03 +/- 0.48 9.67 - 17.95 2004-1 CaSO4: Dy Cards 7/12/2004 Reader 1, 90 cm 6.14 5.97 +/- 0.21 4.30 - 7.98 2004-1 CaSO4: Dy Cards 7/12/2004 Reader 1, 90 cm 6.14 6.26 +/- 0.14 4.30 - 7.98 2004-1 CaSO4: Dy Cards 7/12/2004 Reader 1, 120 cm 3.45 4.40 +/- 0.63 2.42 - 4.49 2004-1 CaSO4: Dy Cards 7/12/2004 Reader 1, 150 cm 2.21 2.34 +/- 0.12 1.55 - 2.87 2004-1 CaSO4: Dy Cards 7/12/2004 Reader 1, 180 cm 1.53 1.65 +/- 0.02 1.07 - 1.99 A2-1

TABLE A-3. In-House "Spike' Samples Concentration (pCiIL)9 Lab Code Sample Date Analysis Laboratory results Known Control Type 2s, n=1b Activity Limitsc SPVE-707 Vegetation 2/20/2004 1-131 (G) 5.68 i 0.15 4.93 2.96 - 6.90 SPCH-711 Charcoal 2/20/2004 1-131(G) 6.35 +/- 0.11 6.94 0.00 - 16.94 SPW-721 water 2/2012004 Ni-63 161.00 +/- 13.20 169.00 101.40 - 236.60 SPAP-733 Air Filter 2/25/2004 Gr. Beta 1.39 +/- 0.02 1.48 0.00 - 11.48 SPW-735 water 2/25/2004 Cs-134 41.59 i 7.02 39.10 29.10 - 49.10 SPW-735 water 21/25/2004 Cs-137 64.11 +/-7.39 64.56 54.56 - 74.56 SPW-735 water 2/25/2004 1-131 36.55 i 0.48 40.08 28.08 - 52.08 SPW-735 water 2125/2004 1-131 41.97 i 8.93 40.08 28.08 - 52.08 SPMI-737 Milk 2/25/2004 Cs-134 37.40 +/- 5.40 39.10 29.10 - 49.10 SPMI-737 Milk 212512004 Cs-137 69.13 i 9.58 64.56 54.56 - 74.56 SPMI-737 Milk 2/25/2004 1-131 45.03 +/- 0.53 40.08 28.08 - 52.08 SPMI-737 Milk 2/25/2004 1-131 44.43 +/- 9.22 40.08 28.08 - 52.08 SPW-1 109 water 3/18/2004 Fe-55 39.98 +/- 1.72 39.98 23.99 - 55.97 SPW-1496 water 4/7/2004 H-3 80006.60 +/- 776.00 83896.00 67116.80 - 100675.20 SPMI-1683 Milk 4/16/2004 Sr-90 42.80 +/- 1.81 43.43 34.74 - 52.12 SPW-1683 water 4/16/2004 1-131 54.47 +/- 0.73 66.60 53.28 - 79.92 SPW-1683 water 4/16/2004 1-131(G) 65.82 +/- 8.86 66.60 56.60 - 76.60 SPMI-1685 Milk 4/16/2004 Cs-134 33.60 +/- 4.24 37.29 27.29 - 47.29 SPMI-1685 Milk 4/16/2004 Cs-137 61.77 i 7.59 64.36 54.36 - 74.36 SPMI-1685 Milk 4/16/2004 1-131 65.85 +/- 0.79 66.60 53.28 - 79.92 SPMI-1685 Milk 4/16/2004 1-131 (G) 75.56 +/- 11.86 66.60 56.60 - 76.60 SPMI-1685 Milk 4/16/2004 Sr-90 42.56 +/- 1.66 43.43 34.74 - 52.12 SPW-1686 water 4116/2004 Cs-134 39.31 i4.35 37.29 27.29 - 47.29 SPW-1686 water 4/16/2004 Cs-1 37 67.73 +/- 7.92 64.36 54.36 - 74.36 SPVE-1862 Vegetation 4/26/2004 1-131 (G) 1.32 +/- 0.03 1.12 0.67 - 1.57 SPCH-1886 Charcoal 4/26/2004 1-131(G) 2.90 i 0.07 2.80 1.68 - 3.92 SPAP-1888 Air Filter 4127/2004 Gr. Beta 1.35 +/- 0.02 1.48 0.00 - 11.48 SPF-1917 Fish 4/29/2004 Cs-I 34 1.44 +/- 0.04 1.47 0.88 - 2.06 SPF-1917 Fish 4J29/2004 Cs-1 37 1.33 i 0.06 1.29 0.77 - 1.81 SPW-3151 water 6/24/2004 Fe-55 33.85 +/- 1.61 37.32 22.39 - 52.25 SPW-4232 water 8/412004 H-3 80225.00 +/- 785.00 82380.00 65904.00 - 98856.00 SPAP-4234 Air Filter 8/4/2004 Gr. Beta 1.63 +/- 0.02 1.46 0.00 - 11.46 SPW-5712 water 10/6/2004 Cs-1 34 61.04 +/-2.51 63.61 53.61 - 73.61 SPW-5712 water 10/6/2004 Cs-1 37 62.01 +/-2.76 63.66 53.66 - 73.66 SPW-5712 water 1016/2004 Sr-90 48.40 +/- 2.00 42.94 34.35 - 51.53 SPMI-5714 Milk 1016/2004 Sr-90 41.61 i1.57 42.94 34.35 - 51.53 A3-1

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

Lab Code Sample Date Analysis Laboratory results Known Control Type 2s, n=1 b Activity Limitsc SPMI-7418 Milk 12/22/2004 Cs-134 59.09 +/-2.59 59.25 49.25 -69.25 SPMI-7418 Milk 12/22/2004 Cs-1 37 65.45 +/- 5.61 63.35 53.35 -73.35 SPW-7420 water 12/22/2004 Cs-134 58.42 +/- 1.99 59.25 49.25 - 69.25 SPW-7420 water 12/22/2004 Cs-137 64.26 +/- 4.18 63.35 53.35 -73.35 SPW-7420 water 12/22/2004 Sr-89 105.26 +/- 4.21 103.47 82.78 - 124.16 SPW-7420 water 12/22/2004 Sr-90 48.24 +/- 1.70 42.72 34.18 - 51.26 SPAP-7437 Air Filter 12/22/2004 Gr. Beta 1.65 +/- 0.02 1.45 0.00 - 11.45 SPF-7524 Fish 12/29/2004 Cs-134 1.11 +/- 0.03 1.27 0.76 - 1.78 SPF-7524 Fish 12/29/2004 Cs-137 1.21 +/- 0.05 1.19 0.71 - 1.67 SPW-7526 water 12/29/2004 H-3 78615.70 +/- 773.70 80543.00 64434.40 -96651.60 SPW-7532 water 12/29/2004 Fe-55 30894.00 +/- 1484.00 32752.00 26201.60 - 39302.40 SPW-7540 water 12/29/2004 Tc-99 30.28 +/- 1.11 32.98 20.98 - 44.98

• Liquid sample results are reported InpCi/Liter, air filters (pCi/m3), charcoal (pCi/i 3), and solid samples (pCi/g).

b Results 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)2 Lab Code Sample Date Analysis Laboratory results (4.66a) Acceptance Type LLD Activityb Criteria (4.66 c)

SPCH-712 Charcoal 2/20/2004 1-131 (G) 2.24 9.6 SPW-722 Water 2/2012004 Ni-63 2.64 -0.78 +/- 1.58 20 SPAP-734 Air Filter 2/25/2004 Gr. Beta 0.96 -1.02 +/- 0.42 3.2 SPW-736 Water 2/25/2004 Cs-134 2.47 10 SPW-736 Water 2125/2004 Cs-137 1.91 10 SPW-736 Water 2/25/2004 1-131 0.15 -0.031 +/-0.10 0.5 SPW-736 Water 2/25/2004 1-131(G) 3.24 20 SPMI-738 Milk 2/25/2004 Cs-134 2.54 10 SPMI-738 Milk 2/25/2004 Cs-137 5.34 10 SPMI-738 Milk 2/25/2004 1-131 0.16 -0.071 +/- 0.10 0.5 SPMI-738 Milk 2/25/2004 1-131 (G) 5.36 20 SPW-1110 Water 3/18/2004 Fe-55 772.70 168.4 +/- 480.90 1000 SPW-1497 Water 4/7/2004 H-3 152.30 81.4 +/- 79.40 200 SPW-1684 Water 4/16/2004 Cs-1 34 2.43 10 SPW-1684 Water 4/16/2004 Cs-1 37 2.53 10 SPW-1684 Water 4/16/2004 1-131 0.50 0.21 +/- 0.26 0.5 SPW-1684 Water 4/16/2004 1-131(G) 4.49 20 SPW-1684 Water 4/16/2004 Sr-89 0.64 0.19 +/- 0.52 5 SPW-1684 Water 4/16/2004 Sr-90 0.64 0.13 +/- 0.31 1 SPMI-1686 Milk 4/16/2004 Cs-1 34 5.00 10 SPMI-1686 Milk 4/16/2004 Cs-1 37 4.16 10 SPMI-1686 Milk 4/16/2004 1-131 0.45 0.13 +/- 0.24 0.5 SPMI-1686 Milk 4/16/2004 1-131(G) 6.53 20 SPMI-1686 Milk 4/16/2004 Sr-89 0.71 0.11 +/- 0.70 5 SPMI-1686 Milk 4/16/2004 Sr-90 0.71 0.66 +/- 0.40 1 SPVE-1 863 Vegetation 4/26/2004 1-131(G) 3.55 20 SPCH-1887 Charcoal 4/26/2004 1-131 (G) 7.04 9.6 SPAP-1889 Air Filter 4/27/2004 Gr. Beta 0.74 -0.96 +/- 0.35 3.2 SPF-1918 Fish 4/29/2004 Cs-1 34 7.13 100 SPF-1918 Fish 4/29/2004 Cs-1 37 6.59 100 SPW-3152 Water 6/24/2004 Fe-55 790.30 -70.0 +/- 474.50 1000 SPW-4233 Water 8/4/2004 H-3 154.23 102.67 +/- 81.38 200 SPAP-4235 Air Filter 8/4/2004 Gr. Beta 0.96 -0.99 +/- 0.38 3.2 SPW-5711 Water 10/6/2004 Co-60 4.26 10 SPW-5711 Water 10/6/2004 Cs-1 34 6.02 10 SPW-5711 Water 10/6/2004 Cs-137 5.28 10 SPW-5711 Water 10/6/2004 Sr-90 0.61 -0.13 +/- 0.27 1 A4-1

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

SPMI-5713 Milk 10/6/2004 Cs-134 4.60 10 SPMI-5713 Milk 10/6/2004 Cs-137 5.81 10 SPMI-5713 Milk 10/6/2004 1-131(G) 6.07 20 SPMI-5713 Milk 10/612004 Sr-90 0.68 1.4 +/- 0.45 1 SPMI-7419 Milk 12/22/2004 Cs-134 8.66 10 SPMI-7419 Milk 12/22/2004 Cs-137 5.61 10 SPMI-7419 Milk 12/22/2004 Sr-90 0.82 1.67 +/- 0.48 1 SPW-7421 Water 1212212004 Sr-89 1.21 0.58 +/- 0.94 5 SPW-7421 Water 12122/2004 Sr-90 0.82 0.26 +/- 0.41 1 SPAP-7438 Air Filter 12/22/2004 Gr. Beta 0.93 -0.78 +/- 0.40 3.2 SPF-7525 Fish 12/29/2004 Cs-134 8.27 100 SPF-7525 Fish 12/29/2004 Cs-1 37 10.60 100 SPW-7526 Water 12/29/2004 H-3 164.80 -47.0 +/- 84.60 200 SPW-7533 Water 12/29/2004 Fe-55 753.00 118.6 +/- 465.80 1000 SPW-7535 Water 12/29/2004 Ni-63 13.10 4.3 +/- 8.10 20 SPW-7540 Water 12129/2004 Tc-99 1.19 -0.036 +/- 0.72 10

• Liquid sample results are reported In pCi/Liter, air filters( pCi/filter), charcoal (pCi/charcoal canister), and solid samples (pCilg).

b Activity reported is a net activity result. For gamma spectroscopic analysis, activity detected below the LLD value is not reportec

' 1-131 (G); iodine-131 as analyzed by gamma spectroscopy.

d Low levels of Sr-90 are still detected in the environment. A concentration of (1-5 pCUL) in milk is not unusual.

A4-2

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L) 8 Averaged Lab Code Date Analysis First Result Second Result Result E-30, 31 1/5/2004 Gr. Beta 1.27 i 0.06 1.26 +/- 0.05 1.27 i 0.04 E-30, 31 1/5/2004 K-40 1.33 i 0.21 1.11 +/-0.20 1.22 +/- 0.15 WW-58, 59 1/5/2004 Gr. Beta 4.20 +/- 1.33 4.46 +/- 1.34 4.33 i 0.94 WW-58, 59 1/5/2004 K-40 2.30 +/- 0.23 2.70 +/- 0.27 2.50 i 0.18 TD-7889, 7890 1/5/2004 H-3 16582.00 +/- 366.00 16060.00 +/- 360.00 16321.00 +/- 256.69 MI-79, 80 17/2004 K-40 1451.50 +/- 125.90 1383.60 +/- 115.50 1417.55 i 85.43 MI-79, 80 17/2004 Sr-90 0.90 +/- 0.31 1.05 +/- 0.34 0.97 +/- 0.23 S-100, 101 1/13/2004 Cs-137 8.50 +/- 0.23 8.52 +/- 0.21 8.51 i0.16 SW-225, 226 1/13/2004 Gr. Alpha 2.62 +/- 1.26 2.05 +/- 1.16 2.34 +/- 0.86 SW-225, 226 1/13/2004 Gr. Beta 6.37 i 1.15 4.92 +/- 1.06 5.65 +/- 0.78 U-304, 305 1/16/2004 Gr. Beta 5.18 i 1.38 7.04 +/- 1.53 6.11 +/- 1.03 SW-345, 346 1/27/2004 1-131 1.32 i 0.24 1.56 +/- 0.21 1.44 i 0.16 SWT-423,424 1/27/2004 Gr. Beta 2.34 i 0.54 2.38 +/- 0.52 2.36 +/- 0.38 SWU-469, 470 1/27/2004 Gr. Beta 2.99 i 0.57 3.09 +/- 0.67 3.04 i 0.44 TD-545, 546 2/2/2004 H-3 658.40 i 104.60 712.30 +/- 106.60 685.35 +/- 74.67 MI-524, 525 2/4/2004 K-40 1240.00 i 147.90 1265.60 +/- 166.30 1252.80 +/- 111.28 MI-567, 568 2/9/2004 K-40 1322.90 i 105.50 1340.80 +/- 112.80 1331.85 +/- 77.22 MI-567, 568 2/9/2004 Sr-90 0.98 +/- 0.48 0.79 +/- 0.42 0.89 +/- 0.32 MI-588, 589 2/11/2004 K-40 1185.70 +/- 157.80 1337.70 +/- 160.00 1261.70 +/-112.36 SWU-778, 779 2/24/2004 Gr. Beta 2.55 +/- 0.54 2.53 +/- 0.56 2.54 +/- 0.39 LW-1014,1015 3/1/2004 Gr. Beta 1.78 +/- 0.56 2.06 +/- 0.57 1.92 +/- 0.40 SW-966, 967 3/9/2004 Gr. Alpha 2.70 +/- 1.43 2.96 +/- 1.63 2.83 +/- 1.08 SW-966, 967 3/9/2004 Gr. Beta 8.06 +/- 1.20 7.33 +/- 1.21 7.69 +/- 0.85 SW-966, 967 3/9/2004 H-3 182.04 i 86.24 198.87 +/- 86.97 190.45 +/- 61.24 SW-1249, 1250 3/31/2004 Gr. Beta 4.71 i1.11 5.25 +/- 1.10 4.98 +/- 0.78 LW-1464,1465 3/31/2004 Gr. Beta 2.13 i 0.52 2.39 +/- 0.53 2.26 +/- 0.37 AP-1 633, 1634 3/31/2004 Be-7 0.05 i 0.02 0.05 +/- 0.02 0.05 +/- 0.01 AP-1714, 1715 3/31/2004 Be-7 0.04 +/- 0.01 0.05 +/- 0.01 0.05 +/- 0.01 TD-1489, 1490 4/1/2004 H-3 681.00 i 110.00 709.00 +/- 111.00 695.00 +/- 78.14 SWT-1299, 1300 4/2/2004 Gr. Beta 3.13 +/- 0.57 3.64 +/- 0.60 3.39 +/- 0.41 DW-1420,1421 4/2/2004 Gr. Beta 1.29 +/- 0.83 1.62 +/- 0.87 1.46 +/- 0.60 DW-1510,1511 4/2/2004 1-131 0.68 +/- 0.27 0.62 +/- 0.36 0.65 +/- 0.23 BS-1537,1538 4/6/2004 Gr. Beta 6.81 +/- 1.20 6.76 +/- 1.23 6.78 +/- 0.86 WW-1654,1655 4/13/2O04 Gr. Beta 6.83 +/- 1.17 5.60 +/- 1.12 6.21 +/-0.81 LW-1680, 1681 4/13/2004 Gr. Beta 2.45 +/- 0.64 2.93 +/- 0.62 2.69 +/- 0.45 MI-1735,1736 4/14/2004 K-40 1384.90 +/- 182.00 1408.20 +/- 187.90 1396.55 +/- 130.80 MI-1802,1803 4/19/2004 K-40 1327.50 +/- 109.10 1206.30 +/- 113.30 1266.90 +/- 78.64 MI-1802, 1803 4/19/2004 Sr-90 0.72 +/- 0.40 0.77 +/- 0.41 0.74 +/- 0.28 U-1781,1782 4/21/2004 Gr. Alpha 0.20 +/- 1.90 -0.30 +/- 2.40 -0.05 i 1.53 SWT-1933,1934 4/27/2004 Gr. Beta 2.60 +/- 0.55 2.33 +/- 0.52 2.46 +/- 0.38 F-1912,1913 4/29/2004 H-3 8875.00 +/- 250.00 9119.00 +/- 253.00 8997.00 +/- 177.84 F-1912,1913 4/29/2004 K-40 3406.90 +/- 533.30 3550.60 +/- 581.40 3478.75 +/- 394.47 LW-1960, 1961 4/29/2004 Gr. Beta 2.23 +/- 0.55 2.38 +/- 0.57 2.31 +/- 0.40 A5-1

TABLE A-5. In-House "Duplicate" Samples Concentration (pCilL)a Averaged Lab Code Date Analysis First Result Second Result Result BS-2083, 2084 5/3/2004 Be-7 1.10 +/- 0.44 1.17 +/- 0.20 1.14 +/- 0.24 BS-2083, 2084 5/3/2004 Gr. Beta 28.44 +/- 2.27 25.56 +/- 2.04 27.00 +/- 1.53 BS-2083, 2084 5/3/2004 K-40 6.75 +/- 0.89 6.35 +/- 0.53 6.55 +/- 0.52 BS-2083, 2084 5/312004 Sr-90 0.12 +/- 0.04 0.17 +/- 0.05 0.15 +/- 0.03 MI-2225, 2226 5/11/2004 K-40 1396.30 +/- 124.20 1227.60 +/- 125.40 1311.95 +/- 88.25 SW-2267, 2268 5/11/2004 Gr. Alpha 2.95 +/- 1.44 2.41 +/- 1.37 2.68 +/- 0.99 SW-2267, 2268 5/11/2004 Gr. Beta 6.80 +/-1.18 7.25 +/- 1.21 7.03 +/- 0.84 MI-2437, 2438 5/17/2004 K-40 1549.00 +/- 123.40 1566.20 +/- 118.60 1557.60 +/- 85.58 MI-2437, 2438 5/17/2004 Sr-90 1.83 +/- 0.44 1.99 +/- 0.42 1.91 +/- 0.30 F-2413, 2414 5/2012004 K-40 2844.60 +/- 550.40 2963.00 +/- 532.30 2903.80 +/- 382.85 S0-2578, 2579 5/26/2004 Cs-137 0.16 +/- 0.02 0.21 +/- 0.05 0.18 +/- 0.03 SO-2578, 2579 5/26/2004 Gr. Beta 28.07 +/- 3.24 28.73 +/- 3.00 28.40 +/- 2.21 S0-2578, 2579 512612004 K-40 19.41 +/- 0.78 18.93 +/- 1.04 19.17 +/- 0.65 SS-2603, 2604 5/2612004 Cs-I 37 0.06 +/- 0.02 0.06 +/- 0.02 0.06 +/- 0.02 SS-2603, 2604 5/2612004 K-40 10.18 +/- 0.63 10.43 +/- 0.56 10.30 +/- 0.42 G-2677, 2678 6/1/2004 Be-7 1.31 +/- 0.25 1.25 +/- 0.23 1.28 +/- 0.17 G-2677, 2678 6/1/2004 Gr. Beta 5.73 +/- 0.12 5.86 +/- 0.12 5.79 +/- 0.09 G-2677, 2678 6/1/2004 K-40 5.56 +/- 0.49 5.78 +/- 0.50 5.67 +/- 0.35 G-2677, 2678 6/1/2004 Sr-90 0.01 +/- 0.00 0.01 +/- 0.01 0.01 +/- 0.00 DW-2700, 2701 6/1/2004 Gr. Beta 1.82 +/- 1.01 2.66 +/- 0.94 2.24 +/- 0.69 TD-2876, 2877 6/1/2004 H-3 13116.00 +/- 324.00 12746.00 +/- 320.00 12931.00 +/- 227.69 Ml-2724, 2725 6/3/2004 K-40 1509.00 +/- 116.10 1489.20 +/- 126.10 1499.10 +/- 85.70 MI-2724, 2725 6/3/2004 Sr-90 1.64 +/- 0.46 1.81 +/- 0.44 1.73 +/- 0.32 BS-2921. 2922 6/3/2004 K-40 8.32 +/- 0.63 8.55 +/- 0.62 8.44 +/- 0.44 TD-2876, 2877 6/4/2004 H-3 13116.00 +/- 324.00 12746.00 +/- 320.00 12931.00 +/- 227.69 BS-2897, 2898 6/4/2004 Gr. Beta 9.31 +/- 1.43 8.82 +/- 1.39 9.06 +/- 1.00 SWU-3092, 3093 6/912004 Gr. Beta 1.95 +/- 0.71 2.55 +/- 0.76 2.25 +/- 0.52 CF-2986, 2987 6/14/2004 Be-7 0.69 +/- 0.12 0.84 +/- 0.19 0.76 +/- 0.11 CF-2986, 2987 6/1412004 K-40 4.50 +/- 0.32 3.82 +/- 0.48 4.16 +/- 0.29 MI-2977, 2978 6/15/2004 K-40 1486.70 +/- 120.10 1291.60 +/- 167.40 1389.15 +/- 103.01 MI-3007, 3008 6/1512004 K-40 1333.90 +/- 121.30 1355.80 +/- 176.50 1344.85 +/- 107.08 W-3031, 3032 6/1812004 H-3 642.00 +/- 108.00 562.00 +/- 105.00 602.00 +/- 75.31 W-3071, 3072 6/2112004 H-3 273.00 +/- 94.00 203.00 +/- 92.00 238.00 +/- 65.76 SW-3145, 3 1 46 b 6/22/2004 1-131 0.97 +/- 0.20 1.43 +/- 0.20 1.20 +/- 0.14 DW-3278, 3279 6/25t2004 1-131 0.67 +/- 0.26 0.48 +/- 0.25 0.57 +/- 0.18 AP-3922, 3923 6/2812004 Be-7 0.08 +/- 0.01 0.07 +/- 0.01 0.07 +/- 0.01 AP-3637, 3638 612912004 Be-7 0.08 +/- 0.01 0.07 +/- 0.01 0.07 +/- 0.01 LW-3589, 3590 6/30/2004 Gr. Alpha 0.28 +/- 0.55 1.29 +/- 0.89 0.79 +/- 0.53 LW-3589, 3590 6/30/2004 Gr. Beta 1.91 +/- 0.64 2.86 +/- 0.70 2.39 +/- 0.48 LW-3589, 3590 6/3012004 H-3 8369.20 +/- 262.57 8226.01 +/- 260.51 8297.61 +/- 184.94 AP-3943, 3944 6/30/2004 Be-7 0.08 +/- 0.02 0.09 +/- 0.02 0.08 +/- 0.01 A5-2

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)a Averaged Lab Code Date Analysis First Result Second Result Result E-3327, 3328 7/1/2004 Gr. Beta 1.21 +/- 0.06 1.35 +/- 0.07 1.28 +/- 0.05 E-3327, 3328 7/1/2004 K-40 1.08 +/- 0.20 1.30 +/- 0.22 1.19 +/- 0.15 G-3377, 3378 7/112004 Be-7 1.10 +/-0.13 1.16 +/- 0.16 1.13 +/-0.10 G-3377, 3378 7/1/2004 Gr. Beta 6.42 +/- 0.19 6.28 +/- 0.19 6.35 +/- 0.13 G-3377, 3378 7/1/2004 K-40 5.26 +/- 0.31 5.36 +/- 0.28 5.31 +/- 0.21 VE-3681, 3682 7/13/2004 K-40 2.65 +/- 0.45 2.90 +/- 0.61 2.77 +/- 0.38 CF-3707, 3708 7/13/2004 Be-7 1.97 +/- 0.44 2.11 +/-0.25 2.04 +/- 0.25 CF-3707, 3708 7/13/2004 K.40 5.39 +/- 0.44 4.98 +/- 0.42 5.19 +/- 0.30 SW-3773, 3774 7/14/2004 H-3 10697.20 +/- 295.70 10689.60 +/- 295.70 10693.40 +/- 209.09 LW-3849, 3850 7/14/2004 Gr. Beta 2.21 +/- 0.54 2.32 +/- 0.65 2.27 +/- 0.42 SWU-4307, 4308 7/14/2004 Gr. Beta 3.49 +/- 0.57 3.68 +/- 0.61 3.59 +/- 0.42 MI-4051, 4052 7/28/2004 K-40 1190.70 +/- 204.60 1357.00 +/- 145.90 1273.85 +/- 125.65 VE-4079, 4080 7/28/2004 K-40 4.90 +/- 0.51 4.62 +/- 0.61 4.76 +/- 0.40 MI-4163, 4164 7/2812004 K-40 1422.40 +/- 186.50 1330.80 +/- 181.00 1376.60 +/- 129.95 MI-4163, 4164 7/2812004 Sr-90 0.87 +/- 0.32 1.00 +/- 0.35 0.93 +/- 0.24 WW-4387, 4388 8/312004 Gr. Beta 5.94 +/- 0.76 6.28 +/- 0.76 6.11 +/-0.54 MI-4286, 4287 8/4/2004 K-40 1435.20 +/- 76.90 1404.70 +/- 80.54 1419.95 +/- 55.68 MI-4286, 4287 8/4/2004 Sr-90 1.88 +/- 0.40 1.31 +/- 0.35 1.59 +/- 0.26 VE-4370, 4371 8/4/2004 H-3 0.54 +/- 0.08 0.62 +/- 0.08 0.58 +/- 0.06 VE-4408, 4409 8/5/2004 K-40 2.03 +/- 0.39 2.12 +/- 0.32 2.08 +/- 0.25 VE-4467, 4468 8/9/2004 K-40 6.28 +/- 0.76 6.11 +/- 0.75 6.20 +/- 0.53 MI-4492, 4493 8/10/2004 K-40 1478.70 +/- 116.70 1472.50 +/- 105.10 1475.60 +/- 78.53 MI-4492, 4493 8/10/2004 Sr-90 1.35 +/- 0.40 1.08 +/- 0.42 1.22 +/- 0.29 MI-4518, 4519 8/11/2004 K-40 1197.30 +/- 158.50 1350.20 +/- 202.30 1273.75 +/- 128.50 VE-4748, 4749 8/25/2004 Gr. Beta 2.31 +/- 0.05 2.32 +/- 0.05 2.31 +/-0.04 VE-4748, 4749 8/25/2004 K-40 1.70 +/- 0.25 1.94 +/- 0.31 1.82 +/- 0.20 LW-4769, 4770 8126/2004 Gr. Beta 2.00 +/- 0.58 2.07 +/- 0.58 2.04 +/- 0.41 ME-4905, 4906 9/1/2004 Gr. Beta 3.06 +/- 0.10 2.93 +/- 0.10 3.00 +/- 0.07 ME-4905, 4906 9/1/2004 K-40 2.33 +/- 0.67 3.26 +/- 0.58 2.80 +/- 0.44 MI-4926, 4927 9/1/2004 K-40 1316.20 +/- 115.40 1285.80 +/- 117.30 1301.00 +/- 82.27 MI-4926, 4927 9/1/2004 Sr-90 3.62 +/- 0.52 2.07 +/- 0.43 2.84 +/- 0.34 VE-5027, 5028 9/2/2004 Gr. Beta 2.43 +/- 0.07 2.39 +/- 0.06 2.41 +/- 0.05 VE-5027, 5028 9/2/2004 K-40 1.77 +/- 0.20 1.94 +/- 0.31 1.86 +/- 0.18 SW-5003, 5004 9/7/2004 1-131 1.69 +/- 0.23 1.50 +/- 0.25 1.59 +/- 0.17 MI-5050, 5051 9/7/2004 K-40 1559.40 +/- 131.80 1560.70 +/- 121.20 1560.05 +/- 89.53 MI-5050, 5051 9/7/2004 Sr-90 2.26 +/- 0.52 1.61 +/- 0.47 1.94 +/- 0.35 WW-5072, 5073 9/7/2004 Gr. Beta 4.31 +/- 0.70 4.11 +/-0.69 4.21 +/- 0.49 SW-5216, 5217 9/1412004 Gr. Alpha 4.34 +/- 1.71 4.30 +/- 1.77 4.32 +/- 1.23 SW-5216. 5217 9/14/2004 Gr. Beta 7.97 +/- 1.24 8.58 +/- 1.29 8.27 +/- 0.89 A5-3

TABLE A-5. In-House "Duplicate" Samples Concentration (pC iL)a Averaged Lab Code Date Analysis First Result Second Result Result G-5237, 5238 9/15/2004 Be-7 1.18 i 0.23 1.28 +/- 0.24 1.23 +/- 0.17 G-5237, 5238 9/15/2004 K-40 7.16 +/- 0.58 7.56 +/- 0.55 7.36 +/- 0.40 LW-5316, 5317 9/16/2004 Gr. Beta 2.76 +/- 0.58 2.64 +/-0.54 2.70 +/- 0.40 SS-5450, 5451 9/24/2004 K-40 10.33 +/- 0.66 10.10 +/-0.74 10.22 +/- 0.50 AP-6308, 6309 9/27/2004 Be-7 0.08 +/- 0.01 0.08 i 0.01 0.08 +/- 0.01 SWU-5495, 5496 9/28/2004 Gr. Beta 3.38 +/- 1.78 4.41 i 1.94 3.90 +/- 1.32 AP-6070, 6071 9/28/2004 Be-7 0.08 +/- 0.01 0.08 +/- 0.01 0.08 +/- 0.01 G-5516, 5517 9/29/2004 Be-7 1.81 +/- 0.29 1.74 +/- 0.30 1.77 +/- 0.21 G-5516, 5517 9/29/2004 K-40 7.35 +/- 0.70 7.43 +/- 0.62 7.39 +/- 0.47 AP-6258, 6259 9/29/2004 Be-7 0.07 +/- 0.01 0.07 +/- 0.01 0.07 +/- 0.01 F-7211, 7212 9/2912004 Cs-1 37 0.04 0.01 0.05 +/- 0.02 0.05 +/- 0.01 F-7211, 7212 9/29/2004 K-40 2.76 +/- 0.27 3.07 +/- 0.26 2.92 +/- 0.19 BS-5902, 5903 10/1/2004 Co-60 0.25 i 0.05 0.26 i 0.03 0.25 +/- 0.03 BS-5902, 5903 10/1/2004 Co-60 2.53 i 0.11 2.52 i 0.06 2.52 +/- 0.06 E-5654, 5655 10/4/2004 Gr. Beta 1.40 i 0.06 1.32 i 0.06 1.36 +/- 0.04 E-5654, 5655 10/4/2004 K-40 1.32 +/- 0.26 1.22 +/- 0.24 1.27 +/- 0.18 MI-5676, 5677 10/412004 K-40 1311.00 i 122.00 1398.00 i 125.00 1354.50 +/- 87.33 S0-5756, 5757 10/412004 Gr. Alpha 7.12 i 3.09 6.69 +/- 2.92 6.91 +/- 2.13 SO-5756, 5757 10/4/2004 Gr. Beta 19.66 +/- 2.63 22.32 i 2.65 20.99 +/- 1.87 S0-5756, 5757 10/4/2004 K-40 16.45 +/- 0.86 17.52 i0.78 16.99 +/- 0.58 VE-6483, 6484 10/6/2004 K-40 9.35 +/- 0.55 9.88 +/- 0.23 9.61 +/- 0.30 MI-5923, 5924 10/12/2004 K-40 1333.60 +/- 183.50 1552.40 +/- 179.20 1443.00 +/- 128.24 SS-6046, 6047 10/1312004 Cs-137 0.02 +/- 0.01 0.02 +/- 0.01 0.02 +/- 0.01 SS-6046, 6047 10/13/2004 Gr. Beta 7.93 +/- 1.72 9.57 +/- 1.88 8.75 +/- 1.27 SS-6046, 6047 10/13/2004 K-40 5.77 +/- 0.42 5.77 +/- 0.40 5.77 +/- 0.29 DW-6208, 6209 10/15/2004 1-131 0.89 +/- 0.26 0.65 +/- 0.27 0.77 +/- 0.19 BS-6694, 6695 10/19/2004 K-40 11.84 i 0.67 12.75 i 0.79 12.29 +/- 0.52 VE-6354. 6355 10/25/2004 Gr. Beta 4.82 0.14 0 4.76 i 0.14 4.79 +/- 0.10 VE-6354, 6355 10/2512004 K-40 4.71 i0.54 4.82 +/- 0.61 4.77 +/- 0.41 DW-6462, 6463 10/27/2004 Gr. Beta 8.46 i 1.27 8.22 i 1.24 8.34 +/- 0.89 LW-6377, 6378 10128/2004 Gr. Beta 2.18 0.54 0 2.33 i 0.53 2.25 +/- 0.38 SS-6504. 6505 10/29/2004 K-40 9.28 +/- 0.61 8.51 i 0.78 8.89 +/- 0.50 LW-6762, 6763 10/31/2004 Gr. Beta 1.85 +/- 0.66 1.69 i 0.64 1.77 +/- 0.46 BS-6576, 6577 11/1/2004 Gr. Beta 11.02 +/- 1.54 13.77 +/- 1.77 12.40 +/- 1.17 BS-6576, 6577 11/11/2004 K-40 9.43 +/- 0.71 8.84 i 0.68 9.14 +/- 0.49 SO-6715, 6716 11/2/2004 Cs-1 37 0.29 +/- 0.04 0.33 +/- 0.06 0.31 +/- 0.04 SO-6715, 6716 11/2/2004 Gr. Alpha 10.94 +/- 3.95 14.72 +/-4.16 12.83 +/- 2.87 SO-6715, 6716 11/2/2004 Gr. Beta 21.33 +/- 3.10 24.82 +/- 3.10 23.07 +/- 2.19 SO-6715, 6716 11/2/2004 K-40 10.42 +/- 0.71 12.16 +/- 1.06 11.29 +/- 0.64 VE-6673, 6674 11/812004 Gr. Alpha 0.07 +/- 0.04 0.14 +/- 0.05 0.11 +/- 0.03 VE-6673, 6674 11/8/2004 Gr. Beta 4.50 +/- 0.12 4.48 +/- 0.12 4.49 +/- 0.09 VE-6673, 6674 11/8/2004 K-40 4.05 +/- 0.49 4.65 i 0.55 4.35 +/- 0.37 A5-4

TABLE A-5. In-House "Duplicate" Samples Concentration (pCiIL)a Averaged Lab Code Date Analysis First Result Second Result Result SO-6820,6821 11/1012004 K-40 14.41 +/- 1.03 15.01 +/-1.09 14.71 +/- 0.75 SO-6820, 6821 11/10/2004 Sr-90 0.04 +/- 0.02 0.07 +/- 0.02 0.06 +/- 0.02 SWU-7160, 7161 11/30/2004 Gr. Beta 4.39 +/- 1.98 3.09 +/- 1.77 3.74 +/- 1.33 MI-7062, 7063 12/112004 K-40 1456.00 +/- 124.80 1640.50 +/- 131.40 1548.25 +/- 90.61 MI-7062, 7063 121112004 Sr-90 1.13 +/- 0.41 0.98 i 0.43 1.06 +/- 0.30 S-7281, 7282 1215/2004 Cs-137 0.82 +/- 0.15 1.16 +/- 0.20 0.99 +/- 0.12 VE-7343, 7344 12/13/2004 Gr. Beta 5.25 +/- 0.14 5.08 +/- 0.14 5.16 +/- 0.10 VE-7343, 7344 12/13/2004 K-40 4.23 +/- 0.71 4.33 +/- 0.69 4.28 +/- 0.49 MI-7317, 7318 12/14/2004 K-40 1702.80 +/- 129.70 1536.80 +/- 115.10 1619.80 +/- 86.70 WW-7375. 7376 12/14/2004 Gr. Beta 14.13 +/- 1.03 15.22 +/- 1.06 14.68 +/- 0.74 SWU-7507,7508 12114/2004 Gr. Beta 4.48 +/- 0.66 5.31 +/- 0.69 4.89 +/- 0.48 DW-7563, 7564 12/2712004 Gr. Beta 1.88 +/- 0.51 2.34 +/- 0.52 2.11 +/- 0.37 P-7698, 7699 12/27/2004 H-3 246.01 +/- 95.00 259.06 +/- 95.51 252.53 +/- 67.35 AP-7741, 7742 12/28/2004 Be-7 0.06 +/- 0.02 0.05 +/- 0.02 0.05 +/- 0.01 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.

' Results are reported in units of pCifL, except for air filters (pCi/Filter), food products, vegetation, soil, sediment (pCilg).

b 600 minute count time or longer, resulting in lower error.

A5-5

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

Concentrationb Known Control Lab Code Type Date Analysis Laboratory result Activity Limits' STSO-1022 soil 05/01/04 Am-241 65.90 +/- 4.50 66.97 +/- 6.70 46.88 - 87.06 STSO-1022 soil 05/01/04 Co-57 388.90 +/- 4.00 399.60 +/- 40.00 279.72 - 519.48 STSO-1022 soil 05/01/04 Co-60 524.80 i7.10 518.00 +/- 51.80 362.60 - 673.40 STSO-1022 soil 05/01/04 Cs-1 34 403.40 +/- 4.60 414.40 +/- 41.40 290.08 - 538.72 STSO-1022 soil 05/01104 Cs-137 829.10 +/- 7.60 836.20 +/- 83.62 585.34 - 1088.00 STSO-1022 soil 05/01/04 K-40 620.60 +/- 29.50 604.00 +/- 60.40 422.80 - 785.20 STSO-1022 soil 05/01/04 Ni-63 254.80 +/- 8.40 357.05 +/- 35.70 249.94 - 464.17 STSO-1022 d. soil 05/01/04 Tc-99 59.00 +/- 6.00 117.66 +/- 11.78 82.36 - 152.96 STSO-1022 d Il 05/01/04 U-23314 24.70 +/- 3.60 37.00 +/- 3.70 25.90 - 48.40 STSO-1022 d.I soil 05/01/04 U-238 24.20 +/- 3.50 38.85 +/- 3.90 27.20 - 50.51 STSO-1022 soil 05/01/04 Zn-65 743.00 +/- 13.10 699.30 +/- 69.90 489.51 - 909.09 STAP-1 023 Air Filter 05/01/04 Gr. Alpha 0.06 +/- 0.02 0.40 +/- 0.04 0.00 - 0.80 STAP-1 023 Air Filter 05/01/04 Gr. Beta 1.37 +/- 0.08 1.20 +/- 0.12 0.60 - 1.80 STAP-1024 Air Filter 05/01/04 Am-241 0.08 +/- 0.03 0.10 +/- 0.01 0.07 - 0.13 STAP-1 024 Air Filter 05/01/04 Co-57 2.07 +/- 0.06 2.40 +/- 0.24 1.68 - 3.12 STAP-1 024 Air Filter 05/01/04 Co-60 2.11 i0.08 2.30 +/- 0.23 1.61 - 2.99 STAP-1 024 g Air Filter 05/01/04 Cs-1 34 1.78 +/- 0.08 2.90 +/- 0.29 2.03 - 3.77 STAP-1 024 Air Filter 05/01/04 Cs-1 37 1.76 +/- 0.08 2.00 +/- 0.20 1.40 - 2.60 STAP-1 024 Air Filter 05/01/04 Mn-54 2.84 +/- 0.11 3.00 +/- 0.30 2.10 - 3.90 STAP-1 024 Air Filter 05/01/04 Pu-238 0.12 +/- 0.01 0.13 +/- 0.01 0.09 - 0.17 STAP-1024 Air Filter 05/01/04 Pu-239/40 0.08 +/- 0.01 0.09 +/- 0.01 0.06 - 0.12 STAP-1024 Air Filter 05/01/04 Sr-90 0.66 +/- 0.19 0.80 +/- 0.08 0.56 - 1.04 STAP-1024 Air Filter 05/01/04 U-233/4 0.23 +/- 0.03 0.21 +/- 0.02 0.15 - 0.27 STAP-1024 Air Filter 05/01/04 U-238 0.23 +/- 0.03 0.22 +/- 0.02 0.15 - 0.29 STAP-1 024 Air Filter 05/01/04 Zn-65 3.90 +/- 0.22 4.00 +/- 0.40 2.80 - 5.20 STW-1026 water 05/01/04 Am-241 0.56 +/- 0.07 0.60 +/- 0.06 0.42 - 0.78 STW-1026 water 05/01/04 Co-57 184.10 +/- 13.50 185.00 +/- 18.50 129.50 - 240.50 STW-1026 water 05/01/04 Co-60 164.40 +/- 11.70 163.00 +/- 16.30 114.10 - 211.90 STW-1026 water 05/01/04 Cs-134 201.10 +/- 14.00 208.00 +/- 20.80 145.60 - 270.40 STW-1026 water 05/01/04 Cs-1 37 245.50 +/- 15.80 250.00 +/- 25.00 175.00 - 325.00 STW-1026 water 05/01/04 Fe-55 37.60 +/- 25.30 33.00 +/- 3.30 23.10 - 42.90 STW-1026 water 05/01/04 H-3 76.50 +/- 5.40 83.00 +/- 8.30 58.10 - 107.90 STW-1 026 water 05/01/04 Mn-54 272.10 +/- 17.50 267.00 +/- 26.70 186.90 - 347.10 STW-1026 water 05/01/04 Ni-63 94.40 +/- 3.20 100.00 +/- 10.00 70.00 - 130.00 STW-1026 water 05/01/04 Pu-238 1.11 +/-0.09 1.20 +/- 0.12 0.84 - 1.56 STW-1026 water 05/01/04 Pu-239/40 0.01 +/- 0.01 0.00 +/- 0.00 0.00 - 0.10 STW-1026 water 05/01/04 Sr-90 6.20 +/- 1.10 7.00 +/- 0.70 4.90 - 9.10 STW-1026 water 05/01/04 Tc-99 10.70 +/- 1.00 10.00 +/- 1.00 7.00 - 13.00 A6-1

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

Concentrationb Known Control Lab Code Type Date Analysis Laboratory result Activity Limitse STW-1026 water 05/01/04 U-233/4 0.14 i0.02 0.12 +/- 0.01 0.08 - 0.16 STW-1026 water 05/01/04 U-238 0.94 +/- 0.05 0.90 +/- 0.09 0.63 - 1.17 STW-1026 water 05/01/04 Zn-65 219.60 +/-27.90 208.00 +/- 20.80 145.60 -270.40 STW-1027 water 05/01/04 Gr. Alpha 1.20 +/-0.10 1.20 +/-0.12 0.00 -2.40 STW-1027 water 05/01/04 Gr. Beta 4.30 +/- 0.10 4.10 +/- 0.41 2.05 - 6.15 a Results obtained by Environmental, Inc. Midwest Laboratory as a participant in the Department of Energys Mixed Analyte Performance Evaluation Program, Idaho Operations office, Idaho Falls, Idaho b All results are in Bqlkg or BqIL as requested by the Department of Energy.

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

d The cause of the deviation seems to be incomplete dissolution of the sample.

A spiked soil sample was prepared. Known activity; 32.98 pCi/g; laboratory result 33.47 pCi/g.

' The sample was reanalyzed with the same results. Investigation is in progress.

° Based on the results of gamma emitting isotopes (Cs-137 and Co-60), the filter geometry appears to be biased by -10%. Addition of the summation peak at 1400 KeV results in a recalculation of 2.12 +/- 0.15 Bq/sample.

A6-2

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

Concentrationa EML Control Lab Code Type Date Analysis Laboratory results Resultb Limitsc STW-1009 water 03/01/04 Am-241 1.21 +/- 0.02 1.31 0.66 - 1.56 STW-1009 water 03/01/04 Co-60 152.30 +/- 0.30 163.20 0.87 - 1.17 STW-1009 water 03/01/04 Cs-1 37 50.40 +/- 0.90 51.95 0.90 - 1.25 STW-1009 water 03/01/04 H-3 263.50 +/- 10.00 186.60 0.69 - 1.91 STW-1009 water 03/01/04 Pu-238 1.03 +/- 0.04 1.10 0.68 - 1.33 STW-1009 water 03/01/04 Pu-239/40 2.90 +/- 0.10 3.08 0.62 - 1.38 STW-1009 water 03/01/04 Sr-90 5.20 +/- 0.30 4.76 0.73 - 1.65 STW-1009 water 03/01/04 Uranium 4.35 +/- 0.21 4.62 0.40 - 1.45 STW-1010 water 03/01/04 Gr. Alpha 208.00 +/- 20.70 326.00 0.55 - 1.31 STW-1010 water 03/01/04 Gr. Beta 1063.00 +/- 27.00 1170.00 0.75 - 1.65 STSO-1011 Soil 03/01/04 Am-241 14.10 +/- 4.30 13.00 0.52 - 2.41 STSO-1011 Soil 03/01/04 Cs-137 1292.00 +/- 13.00 1323.00 0.74 - 1.40 STSO-1011 Soil 03/01/04 K-40 563.00 +/- 83.00 539.00 0.70 - 1.59 STSO-1011 Soil 03/01/04 Pu-239/40 20.70 +/- 1.10 22.82 0.62 - 1.99 STSO-1011 Soil 03/01/04 Sr-90 72.10 +/- 5.80 51.00 0.58 - 2.96 STSO-1011 Soil 03/01/04 Uranium 139.10 +/- 10.20 180.22 0.27 - 1.48 STVE-1012 Vegetation 03/01/04 Am-241 4.50 +/- 0.20 4.93 0.58 - 2.86 STVE-1012 Vegetation 03/01/04 Co-60 14.10 +/- 0.40 14.47 0.64,- 1.49 STVE-1012 Vegetation 03/01/04 Cs- 37 573.90 +/- 6.00 584.67 0.75 - 1.48 STVE-1012 Vegetation 03/01/04 K-40 709.00 +/- 19.30 720.00 0.45 - 1.51 STVE-1012 Vegetation 03/01/04 Pu-239/40 6.60 +/- 0.50 6.81 0.60 - 1.98 STVE-1012 Vegetation 03/01/04 Sr-90 766.50 +/- 51.30 734.00 0.50 - 1.37 STAP-1013 Air Filter 03/01/04 Am-241 0.11 +/- 0.01 0.10 0.62 - 1.93 STAP-1013 Air Filter 03/01/04 Co-60 30.90 +/- 1.08 35.40 0.74 - 1.25 STAP-1013 d Air Filter 03/01/04 Cs-1 34 12.30 +/- 1.30 18.20 0.70 - 1.21 STAP-1013 Air Filter 03/01/04 Cs-137 24.90 +/- 0.60 26.40 0.72 - 1.32 STAP-1013 Air Filter 03/01/04 Pu-238 0.04 +/- 0.01 0.04 0.61 - 1.55 STAP-1013 Air Filter 03/01/04 Pu-239/40 0.17 +/- 0.02 0.16 0.67 - 1.58 STAP-1013 Air Filter 03/01/04 Sr-90 1.80 +/- 0.20 1.76 0.62 - 2.26 STAP-1013 Air Filter 03/01/04 Uranium 0.17 +/- 0.01 0.17 0.79 - 2.88 STAP-1014 Air Filter 03/01/04 Gr. Alpha 1.09 +/- 0.06 1.20 0.82 - 1.58 STAP-1014 Air Filter 03/01/04 Gr. Beta 2.68 +/- 0.05 2.85 0.75 - 1.94 a Results are reported in Bq/L with the following exceptions: Air Filters (Bq/Filter), Soil and Vegetation (Bqlkg).

b The EML result listed is the mean of replicate determinations for each nuclide i the standard error of the mean.

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

d Probable effect of summation peaks and slight difference in filter geometry.

A7-1

APPENDIX B DATA REPORTING CONVENTIONS B-1

Data Reportina 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; xi si and X2 S2 Reported result: x +/- s; where x = (1/2) (xi + x2) and s = (1/2) 3.2. Individual results: L1 , <L2 Reported result: <L, where L = lower of L1 and L2 3.3. Individual results: x +/- s, <L Reported result: x +/- s if x AL; <L otherwise.

4.0. Computation of Averaaes 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 X1 , x2 . . . xn are defined as follows:

xn Ex = -I 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-I

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

Air (pCI/r 3 ) Water (pCiIL)

Gross alpha I x 10- 3 Strontium-89 8,000 Gross beta I Strontium -90 500 Iodine-I13 1 b 2.8 x 10-1 Cesium-I137 1,000 Barium-I140 8,000 Iodine-I131 1.000 Potassium-40c 4,000 Gross alpha 2 Gross beta 10 Tritium I 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

TLD LOCATIONS ONE MILE RADIUS E

J PLANT AREA ENLARGED PLAN [1.00 MILE RADIUS]

ENO SCALE]

MONITORING LEGEND:

0 PRAIRIE ISLAND TLD POINTS REV. 1I D-2 TLOD01.DGN TL001.DGN

. __ ^ _ _^-e _ He- _- - . 1

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

0 PRAIRIE ISLAND TLD POINTS REV. 1 D3 TLD02.DGN REV. 1 D-3 TLD2.DGN

TLD LOCATIONS FIVE MILE RADIUS MONITORING LEGEND:

PRAIRIE ISLAND TLD POINTS REV. 1 D-4 TLD03.DGN

ENVIRONMENTAL SAMPLING POINTS ONE MILE RADIUS E

I J PLANT AREA ENLARGED PLAN [1.00 MILE RADIUS]

tNO SCALE]

MONITORING LEGEND (A MILK SAMPLING POINT ID NUMBERS fIYI FISH SAMPLING POINT ID NUMBERS

'P-14. P-18. P-37, P-42, P-43. P-44 ICJ ' P-13. P-19 A AIR SAMPLING POINT IO NUMBERS P-l. P-2. P-3. P-4. P-S

> .INVERTEBRATES POINT IC NUMBERS P-6. P-40 Q WATER SAMPLING POINT 10 3MBERS 5V SEDIMENT SAMPLING POINT 10 NUMBERS P-5. P-G. P-8. P-9. P-ll. P-24. P-43 \W P-G. P-12. P-20 VEGETATION / VEGETABLES ID NUMMBERS P-24. P-38, P-45 RE\/ .1 D5 SAMPOI .DGN REV 0-5 SAMP0I.DGN

ENVIRONMENTAL SAMPLING POINTS FIVE MILE RADIUS I I

.3, MONITORING LEGEND MILK SAMPLING POINT 10 NUMBERS FISH SAMPLING POINT 10 NUMBERS P-14. P-l8, P-37. P-42. P-43. P-44 P-13, P-1q A AIR SAMPLING POINT 10 NUMBERS INVERTEBRATES POINT 10 NUMBERS P-6. P-40 P-l. P-2. P-3. P-4. P-6 Q) WATER SAMPLING POINT 10 NUMBERS SEDIMENT SAMPLING POINT ID NUMBERS P-5. P-6. P-B, P-q, P-l1. P-24. P-43 P-6. P-12. P-20 EJ VEGETATION /'VEGETABLES ID NUMBERS P-24. P-38. P-45 REV.t1 D-6 'SAMP03.DGN REV. - . .. - _ .._6 _3.- SAM-P0

ENVIRONMENTAL SAMPLING POINTS 0 P.41, Huppert Farm, W10430 St Rd 29, Rver Fass, Wl P-43, Peterson Farm, W10322 St Rd 29, Rlver Fails, Wi E P48, Cain Residence, N7395 950th St, River Falls, Wi CONTROL POINTS PRESCOTT, WISCONSIN MONITORING LEGEND

< MILK SAMPLING POINT ID NUMBERS P-14, P-1S, P47, P.41, P.42, P.43, P.44 A AIR SAMPUNG POINT IDNUMBERS P-1,P-2, P4,4, P4

_ WATER SAMIPUNG POINT IDNUMBERS P-S. P4,,P1 P-9, P11. P-43 83 VEGETATION IVEGETABLES ID NUMBERS P.24, P4X8, PA4S D-7