L-PI-04-061, Annual Radiological Environmental Monitoring Report

Annual Radiological Environmental Monitoring Report

ML041410077
Person / Time
Site:	Prairie Island
Issue date:	05/14/2004
From:	Solymossy J Nuclear Management Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
+sunsi/sispmjr=200603, -RFPFR, L-PI-04-061
Download: ML041410077 (66)

Text

Ci t M O Praiie Island Nuclear Generating Plant Committed tof NdarExc Operated by Nuclear Management Company, LLC MAY 1 4 2004 L-PI-04-061 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 2003 Annual Radioloqical 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, 2003 through December 31, 2003.

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

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

Joseph M. Solymossy Site Vice-President, Prairie Island Nuclear Generating Plant Units 1 and 2 Nuclear Management 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 1717 Wakonade Drive East

• Welch, Minnesota 55089-9642 Telephone: 651.388.1121 l? Z5

4' .

ENCLOSURE 1 Annual report to the United States Nuclear Regulatory Commission Radiation Environmental Monitoring Program January 1 to December 31, 2003 (64 pages follow)

- Environmental, Inc.

Midwest Laboratory an Aflegheny Teduiogldes Co.

700 LUndwehr Road

• Nortbrok. ILa0062-2310 rph.(847) 564-0700

• ax (847) 564-4517 XCEL ENERGY CORPORATION PRAIRIE ISLAND NUCLEAR GENERATING PLANT Docket No. 50-282 License No. DPR-42 50-306 DPR-60 ISFSI Docket No.72-10 SNM-2506 ANNUAL REPORT TO THE UNITED STATES NUCLEAR REGULATORY COMMISSION Radiation Environmental Monitoring Program January 1 to December 31, 2003 Prepared under Contract by ENVIRONMENTAL, Inc.

MIDWEST LABORATORY Project No. 8010 Approved:

bon rrap M.S.

\ibrawlanager

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.

Ii

TABLE OF CONTENTS Section Paqe 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 InAir and Water Above Natural Background in Unrestricted Areas .C-1 D Sampling Location Maps .D-1 lii

LIST OF TABLES No. Title Page 5.1 Sample Collection and Analysis Program ............................ . 15 5.2 5.2 Sampling S m ln Locations ............

Lo a i n .......................................................................................................

16

,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:

ADpendix A A-1 U.S. Environmental Protection Agency's Crosscheck Program results . Al-1 A-2 Crosscheck Program Results; (TLDs) . A2-1 A-3 In-house "Spiked" Samples . A3-1 A-4 In-house "Blank" Samples . A4-1 A-5 In-house 'Duplicate" Samples . A5-1 A-6 Department of Energy MAPEP comparison results....................................................................... A6-1 A-7 Environmental Measurements Laboratory Quality (EML) Assessment Program comparison results.......................................................................................................... A7-1 ADpendix C C-1 Maximum Permissible Concentrations of Radioactivity in Air and Water Above Natural Background In Unrestricted Areas ........................................................ C-2 IV

LIST OF FIGURES No. Title Paqe 5.1 Offsite Ambient Radiation (TLDs), average of Inner and outer ring indicator locations versus control .................................. 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, 2003. This program monitors the levels of radioactivity In the air, terrestrial, and aquatic environments Inorder 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, 2004b) 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.

I

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 2003 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-1 31. 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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I 3.1 Program Desicn and Data Interpretation (continued)

Other means of distinguishing sources of environmental radiation are employed interpreting in 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 obtainedin 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 summarizedin Table 5.1 and briefly reviewed below. Table 5.2 defines the sampling location codes usedin 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 samplingis carried out In a reproducible manner, detailed sampling procedures have been prescribed (Prairie Island Nuclear Generating Plant, 2003). Maps of fixed sampling locations are included InAppendix D.

To monitor the air environment, airborne particulates are collected on membrane filters by continuous pumping at five locations. AIrborneiodineis 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, P4, 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: tenin 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 setis returned to EIML quarterly for annealing and repackaging.

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

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

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

River water is collected weekly at two locations, one upstream of the plant (P-5) and one downstream (P-6, Lock and Dam No.3). Monthly composites are analyzed for gamma-emitting isotopes. Quarterly composites are analyzed for tritium.

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3.2 Program Description (continued)

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

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

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

(1) A partial air particulate/air iodine sample was collected from location P-I, the week ending 10-14-03. The low volume was due to sampler pump failure.

(2) No air particulate/air iodine sample was available from location P-6 for the week ending 11-14-03, due to a sampler pump failure.

(3) Milk samples were not available from P-37 (Welsch Farm) for the months of January, February and March of 2003.

Deviations from the program are summarized InTable 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-1 31 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 InAppendix A.

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3.5 Pro-ram Modifications One extra garden location was sampled for broadleaf vegetation in 2003.

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 2003 Land Use Census was completed in September, 2003. There were no changes in any of the highest D/Q locations for dairy, nearest residence, or garden sites in 2003. The critical receptor location did not change In 2003, 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.

6

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 2003. 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 2003.

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 22 fallout declined yearly from a level of 12,167 pCiM to 1,020 pCVMi, 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 3

pCVm 3. Average present day levels have stabilized at around 0.025 pCVM . 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 pCVL. Present day measurements for both Cs-1 37 and 1-131 are below detection levels. Agricultural crop measurements averaged 57.7 pC/g for gross beta and 0.47 pC/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 pCVL 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 pCVL in downstream Mississippi River water, 8.2 pCVL for well water, and 11.0 pCVL 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 pCig upstream and 0.21 pCig 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.

7

4.3 Proaram Findings 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 15.4 mR/91 days at Inner ring locations to 16.7 mRI91 days at outer ring locations. The mean at special locations was 15.5 mRI9I days and 16.0 mR/91 days at the control location. The dose rates measured at the inner and outer ring and the control locations were similar to those observed from 1988 through 2002. The results are tabulated below. No plant effect on ambient gamma radiation was indicated (Figure 5-1).

Average (Inner and Year Outer Rins) Control 1988 15.4 16.0 1989 16.5 16.7 1990 15.9 16.3 1991 14.9 14.5 1992 16.3 14.8 1993 15.9 15.4 1994 15.2 16.0 1995 15.6 16.6 1996 14.8 16.4 1997 15.1 16.0 1998 16.7 17.3 1999 16.6 17.5 2000 17.0 17.1 2001 16.8 17.2 2002 17.4 16.9 2003 16.2 16.0 Ambient gamma radiation as measured by thermoluminescent dosimetry.

Average quarterly dose rates (mRJ91 days).

ISFSI Facility Operations Monitoring Ambient radiation was measured inside the ISFSI earth berm, outside the ISFSI earth berm and at two special locations between the plant ISFSI and the Prairie Island Indian Community. The mean dose rates measured 79.7 mR/91 days Inside the ISFSI earth berm and 18.9 mRI91 days outside the ISFSI earth berm. No additional casks were placed on the ISFSI pad in 2003, 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 ambient radiation levels measured outside the earth berm show a slight increase as compared to other offsite dose rates around the plant. If the dose rates outside the earth berm are an indication of gamma skyshine from the casks, they are consistent with predictions given in the ISFSI Safety Analysis Report, Table 7A-7, 'Total Skyshine Dose Rate". The cumulative average of the two special Prairie Island Indian Community TLDs measured 14.8 and 14.3 mR/91 days. Although the skyshine neutron dose rates are not directly measured, the neutron levels measured next to the casks are below the levels predicted in the ISFSI SAR Report, Table 7A-4, "TN-40 Dose Rates at Short Distances".

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

8

Airborne Particulates The average annual gross beta concentrations In airborne particulates were slightly higher at the indicator versus the control locations (0.027 pCiMr and 0.025 pCiMr , respectively) and similar to levels observed from 1988 through 2002. The results are tabulated below.

Average of Year Indicators Control Concentration (DCi/m )

1988 0.030 0.030 1989 0.028 0.027 1990 0.024 0.023 1991 0.025 0.025 1992 0.023 0.021 1993 0.022 0.019 1994 0.022 0.022 1995 0.022 0.022 1996 0.023 0.020 1997 0.021 0.021 1998 0.022 0.018 1999 0.024 0.022 2000 0.025 0.025 2001 0.023 0.023 2002 0.028 0.023 2003 0.027 0.025 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 1988 through 2003.

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., 2004).

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 AI-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 pCrM3 in all samples. There was no indication of a plant effect.

9

Milk lodine-131 results were below the detection limit of 1.0 pCVL in all samples. Cs-137 results were below the LLD level of 15 pCVL in all samples. No other gamma-emitting isotopes, except naturally-occurring potassium-40, were detected in any milk samples. This is consistent with the findings of the National Center for Radiological Health that most radiocontaminants in feed do not find their way into milk due to the selective metabolism of the cow. The common exceptions are radioisotopes of potassium, cesium, strontium, barium, and iodine (National Center for Radiological Health, 1968).

In summary, the milk data for 2003 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 pCiVL In all samples.

Gross beta concentrations averaged 9.9 pCiIL throughout the year, ranging from 8.1-14.3 pCVL. These concentrations were similar to or slightly higher than levels observed from 1988 through 2002. 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 2003 data of any effect of plant operation.

Year - Gross Beta 1988 8.0 1989 = 7.0 1990 7.0 1991 8.0 1992 = 7.6 1993 7.5 1994 _ 5.8 1995 3.9 1996 - 6.3 1997= 5.1 1998 5.4 1999 5.3 2000 .10.1 2001 8.3 2002 8.7 2003 9.9

=-

Average annual concentrations; Gross beta in drinking water.

10

River Water For the second and third quarters of 2003, measurable tritium was detected in downstream river water composites, at concentrations of 1135 and 259 pCVL, respectively. This is well below the Environmental Protection Agency's drinking water standard of 20,000 pCiL. For the remaining upstream and downstream collections, tritium levels measured below the LLD level of 161 pCiIL.

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

Well Water At the control well P-41, 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 163 pCiIL. Gamma-emitting isotopes were below detection limits in all samples.

In summary, well water data for 2003 show no radiological effects of the plant operation.

cro1s Three samples of broadleaf vegetation, cabbage leaves, were collected in July and analyzed for gamma-emitting isotopes, including iodine-1 31. The 1-131 level was below 0.026 pCilg 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, 2003 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 Periphvton Aquatic insects (invertebrates) or periphyton were collected in May and September, 2003. 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, 2003 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 IIII I I HI II-=iiji! I 20 19 ===_

18 17 I

16 IN 15

~I-rI- - I iE 14 13 I I .

12 11 10 k- } l_l____

1I I I!

1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 20 - - -i 18- - -

17 -- --

155 - 1 141-13----

E 12---

11 ------------ j--~ -_

10 - - - - - - - - - - -

1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 13

mean of all indicator for gross beta, average Particulates; analysis rigure 5-2. Airborne 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.I )35-0.I Ien rJ1 i

- - i i 0.ID31 I _ I._

o0.

0.t _29I II 0.t)25 - I I I_

E 0.023 -

C.)

I t1IJf JL 0.021 -

0.019 0.017 0.015 iii -

19I B8 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 C.,

I-- Control (P-i)

E V

C.

0.017- _ l _ l 1988 19 1990 199t1 19i2 I-9I i i i I It I 1988 1989 1990 1991 1992 1993 1994 1995 1996 1997 1998 1999 2000 2001 2002 2003 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-alA - P-iOA C/Q Ambient gamma P-.0+/ P-15B P.0+/-5S - P.085 P-0+/-IA - P.OSIA P.0lB -P-081B P-OtIX- P-04IX, P-01 C Airborne Particulates 5 P-iCC), 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, P-4, P-6 C/W 1-:13i Milk 5 P-14, P-18, P-37, P-41 (C), P-42 G/Md 1i31, GS River water 2 P-5(C), P-6 G/W GS(MC), H-3(QC)

Drinking water 1 P-ll G/W G8(MC), 1-131(MC)

GS (MC), H-3 (QC)

Well water 5 P46, P-8, P-9, P-24, P41 (C) G/Q H-3, GS 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 +/- P-12 *G/SA GS

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

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

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

' Analysis type Iscoded as follows: GB - gross beta, GS - gamma spectroscopy, H tritium, -3+/- - lodine-ISI.

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

dMilk Is collected biweekly during the grazing season (May -October).

15

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

Distance and Direction from Code Type' Collection Site Sample Type" Reactor P-i C Air Station P-i AP, Al 11.8 ml @316°/NNW P-2 Air Station P-2

• AP,AI 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 @3590/N P-5 C Upstream of Plant RW 1.8 ml@ I°/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-ll Red Wing Service Center DW 3.3 ml@ 158°/SSE P-12 Downstream of Plant Ss 3.0 ml @116 0/ESE P-13 Downstream of Plant M 3.5 ml @113 0/ESE P-14 Gustafson Farm M 2.3 ml @173 0/S P-18 Christlansen Farm M 3.8 ml @880/E P-19 C Upstream of Plant 1.3 ml @0°/N P-20 C Upstream of Plant BS 0.9 ml0 45°/NE P-24 Suter Residence VE, WW 0.6 ml 0 158 0/SSE P-37 Welsch Farm M 4.1 ml @87°/E P-38 C Cain Residence VE 14.2 ml @ 3590/N P.40 C Upstream of Plant BO' 0.4 ml 0 0°/N P-41 C Huppert Farm M,WW 13.8 ml @354°/N P42 Rother Farm M 4.3 ml. @264 0/W General Area of the Site Boundary P-OiA Property Une TLD 0.4 ml @ 359 0/N P-02A Property Line TLD 0.3 ml @ 10°/N P-03A Property Line TLD 0.5 ml 01830/S P-04A Property Line TLD 0.4 ml 0204 0/SWW P-05A Property Line TLD 0.4 ml 0 2250/SW P-06A Property Line TLD 0.4 ml 0 249 0/WSW P-07A Property Line TLD 0.4 ml 0 2680/W P-08A Property Line TLD 0.4 ml 0 291°/WNW P-09A Property Line TLD 0.7 ml 0 317°/NW P-1OA Property Line TLD 0.5 ml 0 333°/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 ADproximately 4 to 5 miles Distant from the Plant P41B8 Thomas Killian Residence TLD 4.7 ml @ 355°/N P-02B Roy Kinneman Residence TLD 4.8 ml @ 170/NNE P-03B Wayne Anderson Farm TLD 4.9 ml @ 46 0/NE P-04B Nelson Drive (Road) TLD 4.2 ml 6 61°/ENE P-05B County Road E and Coulee TLD 4.2 ml @ 102°/ESE P-06B WillIam Hauschlblt Residence TLD 4.4 ml @ 112°/ESE P-07B Red Wing Public Works TLD 4.7 ml @ 140°/SE P-08B David Wnuk Residence TLD 4.1 ml @ 165 0 /SSE P-09B Highway 19 South TLD 4.2 ml @ 1870 /S P-1OB Cannondale Farm TLD 4.9 ml @ 2000 /SSW P-llB Wallace Weberg Farm TLD 4.5 ml 0 221°/SW P-12B Ray Gergen Farm TLD 4.6 ml 0 2510 /WSW P-13B Thomas O'Rourke Farm TLD 4.4 ml 0 270°/W P-14B David J. Anderson Farm TLD 4.9 ml 0 306°/NW P-15B Hoist Farms TLD 3.8 ml @ 345 0/NNW Soeclal Interest Locations P-Ois Federal Lock & Dam #3 TLD 1.6 ml @129 0/SE P-02S Charles Suter Residence TLD 0.5 ml 0 155°/SSE P-03S Carl Gustafson Farm TLD 2.2 ml 0173°/S P-04S Richard Burt Residence TLD 2.0 ml 0 202°/SSW P-05S Kinney Store TLD 2.0 ml 0270°/W P.065 Earl Flynn Farm TLD 2.5 ml @299°/WNW P-07S Indian Community TLD 0.7 ml i 271°/W P-8SS Indian Community TLD 0.7 ml 0 2870/NWW P-Oic C Robert Klnneman Farm TLD 11.i ml 0 331°/NNW 17

PRAIRIE ISLAND Table 52. 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-QUA ISFSI Nuisance Fence TLD 190' @45°/NE P-021A ISFSI Nuisance Fence TLD 360' @82°/E P-031A ISFSI Nuisance Fence TLD 370' @ 10 0 °/E P-041A ISFSI Nuisance Fence TLD 200'+/-1340/SE P-051A ISFSI Nuisance Fence TLD 180' © 219°/SW P-061A ISFSI Nuisance Fence TLD 320'0 258°/WSW P-071A ISFSI Nuisance Fence TLD 320' @2810/WNW P-081A ISFSI Nuisance Fence TLD 190' © 318°/NW P.Oilx ISFSI Nuisance Fence TLD 140' © +/-80°/S P-021X ISFSI Nuisance Fence TLD 3+/-0' © 270°/W P-031X ISFSI Nuisance Fence TLD 140' ©0°/N P-041X ISFSI Nuisance Fence TLD 360'@ 900/E ISFSI Area Outside Earth Berm P-0+/-IB ISFSI Berm Area TLD 340'© 3°/N P-021B ISFSI Berm Area TLD 380' ©28°/NNE P-03I8 ISFSI Berm Area TLD 560' ©85°/E P-041B ISFSI Berm Area TLD 590' ©165°/SSE P-051B ISFSI Berm Area TLD 690' ©1860/S P-0 GIB ISFSI Berm Area TLD 720' ©201°/SSW P-071B ISFSI Berm Area TLD 610'Q 271°/W P-08 lB ISFSI Berm Area TLD 360' ©332 0/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

' 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 Ml Gamma, P-37 1/15/2003 Welsch farm temporarily Welsch will Inform the PINGP 1-131 through out of dairy business. upon resumption of operation 314/2003 In Spring, 2003.

AP/AI Beta, 1-131 P-01 10/14/2003 Partial sample collected; low Sampler pump was replaced.

volume due to open fuse.

AP/AI Beta, 1-131 P-06 11/14/2003 Sampler pump failure; Sampler pump was replaced.

open fuse.

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. 2003 (County, State)

Indicator Location with Highest Control Number Sample Type and .Locations Annual Mean Locations Non-Type Number of LLDb Mean (Ff Mean (F)c Mean (Ff Routine (Units) Analyses' Range Locationd Rangec Range Results TLD (Inner Ring. Gamma 40 3.0 15.4 (40140) P-06A 16.2 (4/4) (See Control 0 Area at Site (12.7-17.5) OA ml @ 2490 /WSW (14.5-17.5) below.)

Boundary) mR191 days)

TLD (Outer Ring, Gamma 60 3.0 16.7 (60/60) P-02B, Roy Kinneman, 18.9 (414) (See Control 0 4-5 ml. distant) (12.9-20.1) 4.8 ml @ 17' NNE (18.0-19.9) below.)

mR191 days)

TLD (Special Gamma 32 3.0 15.5 (32/32) P-03S, Gustafson Farm, 18.5 (414) (See Control 0 Interest Areas) (12.6-20.2) 2.2 mi @ 173 /S (16.6-20.2) below.)

mR191 days)

TLD (Control) Gamma 4 3.0 None P-O1C, R. Kinneman, 16.0 (4/4) 16.0 (414) 0 mR191 days) 11.1 mi @331' /NNW (15.0-17.0) (15.0-17.0)

Airborne GB 259 0.005 0.027 (207/207) P-06, Air Station 0.028 (51 /51) 0.025 (52/52) 0 Particulates (0.005-0.049) 1.6 mi @ 129' /SE (0.014-0.048) (0.011-0.047)

(pCUmn)

GS 20 Be-7 0.015 0.064 (16/16) P-06, Air Station 0.067 (414) 0.055 (4/4) 0 (0.036-0.083) 1.6 mi @ 129' /SE (0.051-0.076) (0.034-0.067)

Mn-54 0.0007 <LLD . <LLD 0 Co-58 0.0006 < LLD <LLD 0 Co-60 0.0007 <LLD -<LLD 0 Zn-65 0.0011 <LLD <LLD 0 Zr-Nb-95 0.0010 <LLD <LLD 0

, Ru-1i03 0.0007 <LLD <LLD 0 Ru-1 06 0.0063 <LLD <LLD 0 Cs-1 34 0.0007 <LLD - < LLD 0 Cs-1 37 0.0006 < LLD - < LLD 0 Ba-La-140 0.0016 < LLD - < LLD 0 Ce-141 0.0014 <LLD - <LLD 0 Ce-144 0.0039 <LLD - < LLD 0 Airbome Iodine 1-131 259 0.07 <LLD <LLD 0 (pCUmn3) 20

Table 5.4 Radiological Environmental Monitoring Program Summary Name of Facility Prairie Island Nudear Power Station Docket No. 50-282, 50-306 Location of Facility Goodhue, Minnesota Reporting Period January-December, 2003

( 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)c Routine (Units) Analysesa Range' Locationd Range' Range' Results' Milk (pCUL) 1-131 87 1.0 < LLD - < LLD 0 GS 87 K-40 200 1403 (69169) P-37, Welsch Farm 1439 (15 115) 1381 (18118) 0 (1197-1602) 4.1 mi @ 87 IE (1275-1602) (1202-1584)

Cs-134 15 < LLD < LLD 0 Cs-137 15 < LLD < LLD 0 Ba-La-140 15 < LLD < LLD 0 River Water H-3 8 161 697 (2/4) P-6, Lock and Dam #3 697 (2/4) < LLD 0 (pCUL) (259-1135) 1.6 mi @ 129°/SE (259-1135)

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 57 < 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, 2003

( 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) Analysesa Range Locationd Range Range' Results' Drinking Water GB 12 1.0 9.9 (12112) P-i1. Red Wing S.C. 9.9 (12112) None 0 (pCUL) (8.1-14.3) 3.3 mi @ 158' ISSE (8.1-14.3) 1-131 12 1.0 < LLD None 0 H-3 4 161 < 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 57 < LLD - None 0 Well Water H-3 20 163 < LLD - < LLD 0 (pCiL)

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 55 < LLD < LLD 0 Crops- Cabbage 1-131 3 0.026 < LLD < LLD 0 (pClgwet) 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, 2003 (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)c Routine (Units) Analyses' Range' Locationd Range' Range' Results!

Fish GS 4 (pCig wet) K-40 0.10 2.84 (2/2) P-19, Upstream 2.86 (2/2) 2.86 (2/2) 0 (2.39-3.29) 1.3 ml. @ 0 /N (2.59-3.13) (2.59-3.13)

Mn-54 0.016 < LLD . < LLD 0 Fe-59 0.046 < LLD < LLD 0 Co-58 0.015 < LLD . < LLD 0 Co-60 0.016 < LLD - < LLD 0 Zn-65 0.042 < LLD - - < LLD 0 Zr-Nb-95 0.025 < LLD - - < LLD 0 Cs-134 0.020 < LLD - - < LLD 0 Cs-137 0.017 < LLD - - < LLD 0 Ba-La-140 0.19 < LLD - < LLD 0 Invertebrates GS 4 (pCIg wet) Be-7 0.44 < LLD - < LLD 0 K-40 0.98 < LLD P-40, Upstream 1.59 (1t2) 1.59 (1/2) 0 0.4 ml @0°/N -

Mn-54 0.045 < LLD < LLD 0 Co-58 0.049 < LLD < LLD 0 Co-60 0.044 < LLD < LLD 0 Zn-65 0.080 < LLD < LLD 0 Zr-Nb-95 0.060 < LLD - < LLD 0 Ru-103 0.058 < LLD - - < LLD 0 Ru-106 0.32 < LLD - - < LLD 0 Cs-134 0.045 < LLD - - < LLD 0 Cs-137 0.039 < LLD - - < LLD 0 Ba-La-140 0.26 < LLD - - < LLD 0 Ce-141 0.079 < LLD - < LLD 0 Ce-144 0.20 < 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. 2003

( 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) Routine (Units) Analyses' Rangec Locationd Range' Range' Results' Bottom and GS 6 Shoreline Be-7 0.18 < LLD - < LLD 0 Sediments (pCVg dry) K-40 0.10 6.96 (414) P-20. Upstream 9.05 (212) 9.05 (2/2) 0 (5.89-7.85) 0.9 mi. @ 45 /NE (8.79-9.30) (8.79-9.30)

Mn-54 0.022 < LLD < LLD 0 Co-58 0.026 < LLD < LLD 0 Co-60 0.016 < LLD < LLD 0 Zn-65 0.063 < LD - < LLD 0 Zr-Nb-95 0.040 < LLD - < LLD 0 Ru-103 0.027 < LLD - < LLD 0 Ru-106 0.17 < LLD - < LLD 0 Cs-134 0.028 < LLD < LLD 0 Cs-137 0.020 < LLD < LLD 0 Ba-La-140 0.17 < LLD < LLD 0 Ce-141 0.047 < LLD < LLD c 0 Ce-144 0.11 < LLD < LLD 0 a GB = gross beta, GS = gamma scan.

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

c Mean and range are based on detectable measurements only. Fraction of detectable measurements at specified locations Is Indicated In parentheses (F).

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

• 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 2004a. Radiation Environmental Monitoring for Monticello Nuclear Generating Plant, Complete Analysis Data Tables, January-December, 2000 through 2003.

____ 2001b through 2004b. Radiation Environmental Monitoring for Prairie Island Nuclear Generating Plant, Complete Analysis Data Tables, January - December, 2000-2003.

2000. Quality Assurance Program Manual, Rev. 0, 01 October 2003.

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

2000. 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, 2003. Radiological Environmental Monitoring for Prairie Island Nuclear Generating Plant, Radiation Protection Implementing Procedures, 4700 series.

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

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

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

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

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

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

Xcel Energy Corporation. 2004. Monticello Nuclear Generating Plant, Annual Radiation Environmental Monitoring Report to the U.S. Nuclear Regulatory Commission, January 1 to December 31, 2003 (prepared by Environmental, Inc., Midwest Laboratory). Northbrook, Illinois 26

e PRAIRIE ISLAND Table D-1. Sample collection and analysis program, Prairie Island Nuclear Generating Plant.

Collection Analysis Location Type and Type and Medium No. Codes (and Type)a Frequencyb Frequency' Ambient radiation (TLD s) 54 P-01A- P-10A C/Q Ambient gamma P-01B - P-15B P-01S - P-08S P-01 IA - P-081A P-011B - P-0818 P-01 IX- P-041X, P-01 C Airborne 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, P-4, P-6 C/W 1-131 Milk 5 P-14, P-18, P-37, P-42 G/Md 1-131, GS P-41 [C]

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

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

GS (MC), H-3 (QC)

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

Periphyton or invertebrates 2 P-40(C), P-6 G/SA GS Bottom sediment 2 P-20(C), P-6. G/SA GS Shoreline sediment I P-12 G/SA GS 8Location codes are defined In Table D-2. Control stations are Indicated by (C). All other stations are Indicators.

bCollection type Is coded as follows: C/ = continuous, GI = 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-3 = tritium, 1-131 =

Iodine 131. Analysis frequency Is coded as follows: MC = monthly composite, QC = quarterly composite.

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

D-1

T PRAIRIE ISLAND Table D-2. Sampling locations, Prairie Island Nuclear Generating Plant.

Distance and Direction from Code Typea Collection Site Sample Typeb Reactor P-1 C Air Station P-1 AP, Al 11.8 mi @ 316 0/NNW P-2 Air Station P-2 AP, Al 0.5 mi @ 294 0/WNW P-3 Air Station P-3 AP, Al 0.8 ml @ 313 0/NW P4 Air Station P-4 AP, Al 0.4 ml @ 359 0 /N P-5 C Upstream of Plant RW 1.8 mi @ 11°/N P-6 Lock and Dam #3 & Air AP, Al, RW Station P-6 WW, BS, BOo 1.6 ml @ 1290/SE P-8 Community Center WW 1.0 mi @ 321 0/WNW P-9 Plant Well #2 WW 0.3 mi @ 306 0/NW P-1I Red Wing Service Center DW 3.3 mi @ 158°/SSE P-12 Downstream of Plant SS 3.0 ml @ 1160 /ESE P-13 Downstream of Plant Fe 3.5 ml @ 1130 /ESE P-14 Gustafson Farm M 2.3 ml @ 1730/S P-1 8 Christiansen Farm M 3.8 ml @ 880 /E P-19 C Upstream of Plant Fc 1.3 mi @ 0/1N P-20 C Upstream of Plant BS 0.9 ml @ 450/NE P-24 Suter Residence VE, WW 0.6 mi @ 158°/SSE P-37 Welsch Farm M 4.1 mi @ 870 /E P-38 C Cain Residence VE 14.2 ml @ 3590 /N P-40 C Upstream of Plant BOEC 0.4 mi @ 0°/N P-41 C Huppert Farm M,WW 13.8 ml @ 3540 /N P-42 Rother Farm M 4.3 ml. @ 264°/W General Area of the Site Boundarv P-01A Property Line TLD 0.4 ml ©3590/N P-02A Property Line TLD 0.3 ml @ 100/N P-03A Property Line TLD 0.5 ml @ 1830/S P-04A Property Line TLD 0.4 mi @ 204 0/SWW P-05A Property Line TLD 0.4 ml @ 225 0/SW P-06A Property Line TLD 0.4 ml @ 249°/WSW P-07A Property Line TLD 0.4 mi @ 268°/W P-08A Property Line TLD 0.4 mi @ 291°/WNW P-09A Property Line TLD 0.7 ml @ 31r/NW P-10A Property Line TLD 0.5 ml @ 333°/NNW D-2

PRAIRIE ISLAND Table D-2. Sampling locations, Prairie Island Nuclear Generating Plant, (continued).

Distance and Direction from Code Type" Collection Site Sample Typeb Reactor Approximately 4 to 5 miles Distant from the Plant P-01B Thomas Killian Residence TLD 4.7 mi @ 355°/N P-02B Roy Kinneman Residence TLD 4.8 mi @ 170/NNE P-03B Wayne Anderson Farm TLD 4.9 ml @ 46°/NE P-04B Nelson Drive (Road) TLD 4.2 mi @ 61°/ENE P-05B County Road E and Coulee TLD 4.2 mi @ 102°/ESE P-06B William Hauschbilt Residence TLD 4.4 ml 0 112°/ESE P-07B Red Wing Public Works TLD 4.7 mi @ 140°/SE P-08B David Wnuk Residence TLD 4.1 ml @ 165 0/SSE P-09B Highway 19 South TLD 4.2 ml @ 187°/S P-1OB Cannondale Farm TLD 4.9 ml @ 200°/SSW P-11B 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 mi @ 270°/W P-14B David J. Anderson Farm TLD 4.9 ml @ 3060/NW P-15B Hoist Farms TLD 3.8 ml @ 345 0/NNW Special Interest Locations P.015 Federal Lock & Dam #3 TLD 1.6 ml @ 1290/SE P-02S Charles Suter Residence TLD 0.5 mi @ 155 0/SSE P-03S Carl Gustafson Farm TLD 2.2 ml @ 1730/S P-04S Richard Burt Residence TLD 2.0 ml ©2020/SSW P-05S Kinney Store TLD 2.0 ml @ 270°NW P-06S Earl Flynn Farm TLD 2.5 ml @ 2990 1WNW P-07S Indian Community TLD 0.7 ml @ 2710°W P-085 Indian Community TLD 0.7 ml ©287°/NWW P-O1 C C Robert Kinneman Farm TLD 11.1 ml @ 3310 /NNW D-3

PRAIRIE ISLAND Table D-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-0IIA ISFSI Nuisance Fence TLD 190' @ 45°/NE P-021A ISFSI Nuisance Fence TLD 360' @ 820°E P-031A ISFSI Nuisance Fence TLD 370' @ 100°/E P-041A ISFSI Nuisance Fence TLD 200' @ 134°/SE P-051A ISFSI Nuisance Fence TLD 180' @ 219 0/SW P-061A ISFSI Nuisance Fence TLD 320' @ 258°/SW P-071A ISFSI Nuisance Fence TLD 320' @ 281°/WNW P-081A ISFSI Nuisance Fence TLD 190' @ 318°/NW P-01IX ISFSI Nuisance Fence TLD 140' @ 1800/S P-021X ISFSI Nuisance Fence TLD 310' @ 2700°W P-031X ISFSI Nuisance Fence TLD 140' @ 00/N P-041X ISFSI Nuisance Fence TLD 360' @ 90 01E ISFSI Area Outside Earth Berm P-011B ISFSI Berm Area TLD 340' @30/N P-021B ISFSI Berm Area TLD 380' @ 280/NNE P-031B ISFSI Berm Area TLD 560' @ 850/E P-041B ISFSI Berm Area TLD 590' @ 165 0/SSE P-051B ISFSI Berm Area TLD 690' @ 186°/S P-061B ISFSI Berm Area TLD 720' @ 201 0/SSW P-071B ISFSI Berm Area TLD 610' @ 271°/W P-081B ISFSI Berm Area TLD 360' @ 332°/NNW a C denotes control location. All other locations are Indicators.

b Sample Codes:

AP Airborne particulates F Fish Al Alrbome 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

' Distance and direction data for fish and bottom organisms are approximate since availability of sample specimen may vary at any one location.

D-4

- Environmental, inc.

Mdw est Laboratory to AJbgheny Techotoges Co.

700Ladwetr Road *INthbmck IL a0002-(847) 540700 z (847)584-4517 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 InMarch, June, September and December monthly progress reports only.

January, 2003 through December, 2003

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

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

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

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

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

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

Attachment A lists acceptance criteria for 'spiked' samples.

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

Al

Attachment A ACCEPTANCE CRITERIA FOR OSPIKED' SAMPLES LABORATORY PRECISION: ONE STANDARD DEVIATION VALUES FOR VARIOUS ANALYSES' One standard deviation Analys is Level for single determination Gammi a Emitters 5 to 100 pCi/liter or kg 5.0 pCi/liter

> 100 pCi/liter or kg 5% of known value Stronti um_89b 5 to 50 pCi/iter or kg 5.0 pCi/liter

> 50 pCiliter or kg 10% of known value Strontii um.90b 2 to 30 pCi/liter or kg 5.0 pCi/liter

> 30 pCi/liter or kg 10% of known value Potass ium40 > 0.1 g/liter or kg 5%of known value Gross; alpha . 20 pCi/liter 5.0 pCi/liter

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

> 100 pCi/liter . 5% of known value Tritium 4,000 pCi/liter Is = (pCi/liter) 169.85 x (known)0 933

> 4,000 pCi/liter 10% of known value Radiun n-226,-228 0.1 pCi/liter 15% of known value Plutoni uum 0.1 pCi/liter, gram, or sample 10% of known value Iodine- 131, 55 pCi/liter 6.0 pCi/liter Iodin e-1 2 9 b > 55 pCi/liter 10% of known value Uraniuim-238, 35 pCi/liter 6.0 pCi/liter Nick( -b> 35 pCiliter 15% of known value Techn etium-99b Iron-55;b 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 Intercomparlson 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)8 .

Concentration (pCiIL)

Lab Code Date Analysis Laboratory ERA Control Resutb. Result' Limits STW-973 02117/03 Sr-89 17.0

• 0.5 15.9 +/- 5.0 7.2 - 24.6 STW-973 02/17/03 Sr-90 8.9

• 0.3 9.0 +/- 5.0 0.4 - 17.7 STW-974 02/17/03 Ba-133 14.5 +/- 0.9 19.5 +/- 5.0 10.8 - 28.2 STW-974 02/17/03 Co-60 37.5 +/- 0.9 37.4 +/- 5.0 28.7 - 46.1 STW-974 02/17/03 Cs-1 34 18.2 +/-0.6 17.8 +/- 5.0 9.1 - 26.5 STW-974 02117/03 Cs-137 42.7

• 1.0 44.2 +/- 5.0 35.5 - 52.9 S1W-974 02/17/03 Zn-65 56.8 +/- 2.2 60.3 +/- 6.0 49.9 - 70.7 STW-975 02/17/03 Gr. Alpha 18.4 +/-0.3 37.6 +/- 9.4 21.3 - 53.9 STW-975 02117103 Gr. Beta 11.7 +/-0.5 8.6 +/- 5.0 0.0 - 17.2 STW-976 02117/03 Ra-226 4.1 +/- 0.1 4.7 *0.7 3.5 - 6.0 STW-976 02117/03 Ra-228 7.6 +/- 0.5 6.5 +/- 1.6 3.7 -9.3 S1W-976 02/17/03 Uranium 52.9 +/-1.9 53.7 +/- 5.4 44.4 - 63.0 STW-983 05/19103 H-3 1290.0 +/- 25.0 1250.0 +/- 331.0 678.0 - 1820.0 STW-984 05/19103 1-131 19.7 +/-1.3 20.8 +/- 3.0 15.6 - 26.0 STW-985 05/19/03 Gr. Alpha 54.4 +/- 3.0 70.3 +/- 17.6 39.9 - 101.0 STW-985 05119/03 Ra-226 14.9

• 0.2 16.5 +/-2.5 12.2 - 20.8 STW-985 05/19/03 Ra-228 13.1 +/- 0.6 10.3

• 2.6 5.8 - 14.8 STW-985 05/19103 Uranium 14.5 +/- OA 15.1 +/-3.0

• 9.9 - 20.3 STW-986 051i9/03 Co-60 56.9 +/- 8.6 63.8 +/- 5.0 55.1 - 72.5 STW-986' 05119/03 Cs-I 34 61.6 +/- 6.6 75.7 +/- 5.0 67.0 - 84.4 STW-986 05/19103 Cs-I 37 143.0 +/- 1.2 150.0 +/- 7.5 137.0 - 163.0 STW-986 05119103 Gr. Beta 309.0 +/- 2.7 363.0 +/- 54.5 269.0 - 457.0 STW-986 05/19/03 Sr-89 33.1 +/-0.2 31.3 +/- 5.0 22.6 - 40.0 STW-986 05119/03 Sr-90 28.8 +/-1.3 27.4 +/- 5.0 18.7 - 36.1 STW-988 08/18/03 Ra-226 13.3 +/- 1.1 13.4 +/-2.0 9.9 -16.9 S1W-988 08/18/03 Ra-228 11.5 +/- 1.0 12.5 +/- 3.1 7.1 - 17.9 S1W-988 08118/03 Uranium 12.3 +/- 0.4 11.4 +/-L3.0 6.2 -16.6 STW-989 08/18/03 Ba-133 18.1 *1.9 20.7 *t 5.0 12.0 - 29.4 STW-989 08/18/03 Co-60 35.9 +/- 1.3 37.4 +/- 5.0 28.7 - 46.1 STW-989 08/18/03 Cs-134 32.6 +/- 1.8 32.6 +/- 5.0 23.9 - 41.3 STW-989 08/18103 Cs-137 48.3

• 0.6 44.3 +/-E5.0 35.6 - 53.0 STW-989 08/18/03 Zn-65 58.9 *2.1 60.2

• 6.0 49.8 - 70.6 STW-990 08/18/03 Gr. Alpha 41.8 +/- 3.4 56.2 +/- 16.3 36.9 - 93.3 STW-990 ' 08/18/03 Gr. Beta 51.3 +/- 3.0 31.6 +/- 5.0 22.9 - 40.3 STW-991 08/18/03 Sr-89 57.2 +/-4.3 58.8 +/- 5.0 50.1 - 67.5 STW-991 08/18/03 Sr-90 21.2

• 0.9 20.6 +/- 5.0 11.9 - 29.3 Al-I

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

Concentration (pCUL)

Lab Code Date Analysis Laboratory ERA Control Resultb Result' Limits STW-997 11/18/03 Gr. Alpha 37.0 ::2.0 29.5 +/- 7.4 16.7 - 42.3 S1W-997 11/18/03 Gr. Beta 26.5 *h0.8 26.3 +/- 5.0 17.6 - 35.0 STW-998 11/18103 1-131 14.8 +/-0.3 16.5

• 3.0 11.3 -21.7 STW-999 11/18/03 Ra-226 17.2

• 1.1 17.8

• 2.7 13.2 - 22.4 STW-999 11/18103 Ra-228 6.6

• 0.3 6.8

• 1.7 3.8 - 9.7 STW-999 11/18103 Uranium 11.7 +/-0.3 11.7 *3.0 6.5 - 16.9 STW-1000 11/18103 H-3 15900.0 +/- 174.0 14300.0 +/- 1430.0 11800.0 - 16800.0 STW-1001 11/18/03 Gr. Alpha *32.9 +/- 0.3 54.2 *3.0 30.7 - 77.7 STW-1001 11/18/03 Ra-226 16.5 +/- 0.9 16.1 +/-2.4 11.9 - 20.3 STW-1001 11/18/03 Ra-228 6.2

• 0.5 5.5

• 1.4 3.1 -7.9 STW-1001 11/18/03 Uranium 9.7 +/- 1.5 9.3 +/-13.6 4.1 -14.5 STW-1002 11/18103 Co-60 27.7 : 1.9 27.7 +/- 5.0 19.0 - 36.4 STW-1002 11/18/03 Cs-134 21.5 +/-1.1 23.4

• 5.0 17.6 - 29.2 STW-1002 11/18/03 Cs-137 66.3 *2.8 64.2

• 5.0 55.5 - 72.9 STW-1002 11/18/03 Gr. Beta 159.0 +/- 2.5 168.0 i 5.0 124.0 - 212.0 STW-1002 11/18/03 Sr-89 48.5 0.4 50.4

• 5.0 41.7 - 59.1 STW-1002 11118/03 Sr-90 10.1 +/-3.0 10.2 +/- 25.2 1.5 - 18.9

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

• b Unless otherwise Indicated, the laboratory result Is given as the mean +/-standard deviation for three determinations.

' Results are presented as the known values, expected laboratory precision (I sigma, I determination) and control limits as provided by ERA d Recount of the original sample still low. The ERA blank was spiked In the lab; known value of 20.1 pCUL, measured 21.5 +/- 1.1 pCVL No explanaton for ERA test failure.

• Lower bias observed for gamma spectroscopic analysis. The undiluted sample was reanalyzed; Results of reanalysis, Co-60: 62.3 pCUL., Cs-134: 69.2 pCUL., Cs-137: 152.3 pCUL

'Reason for devIation unknown. A recount of the original planchets averaged 43.4 pCUL.

Cs-137activity by gamma spectroscopy; 28.3 pCUL. Result of reanalysis: 29.3 pCUL.

A1-2

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

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

2003-1 CaSO4: Dy Cards 81812003 Reader 1,120 4.69 4.74 +/-t 0.54 3.28 - 6.10 2003-1 CaSO4: Dy Cards 81812003 Reader 1,150 3.00 3.02 +/- 0.20 2.10 - 3.90 2003-1 CaSO4: Dy Cards 818/2003 Reader 1,180 2.08 1.89 +/- 0.45 1.46 - 2.70 2003-1 CaSO4: Dy Cards 818/2003 Reader 1,180 2.08 2.11 + 0.22 1.46 - 2.70 2003-1 CaSO4: Dy Cards 81812003 Reader 1,30 75.00 84.40 +/- 4.87 52.50 - 97.50 2003-1 CaSO4: Dy Cards 818/2003 Reader 1,60 18.75 19.11 +/- 1.86 13.13 - 24.38 2003-1 CaSO4: Dy Cards 81812003 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 818/2003 Reader 1,90 8.33 7.60 i 1.08 5.83 - 10.83 Environmental, Inc.

2003-2 CaSO4: Dy Cards 1/1212004 Reader 1,30 61.96 73.50 +/- 2.58 43.37 - 80.55 2003-2 CaSO4: Dy Cards 1/12/2004 Reader 1,60 15.49 19.70 +/-E0.51 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 1/1212004 Reader 1,90 6.88 6.64 i 0.58 4.82 - 8.94 2003-2 CaSO4: Dy Cards 111212004 Reader 1,120 3.87 4.39 +/-0.17 2.71 - 5.03 2003-2 CaSO4: Dy Cards 111212004 Reader 1,150 2.48 2.34 +/-0.18 1.74 - 3.22 2003-2 CaSO4: Dy Cards 1/1212004 Reader 1,150 2.48 2.51 +/-0.16 1.74 - 3.22 2003-2 CaSO4: Dy Cards 1/1212004 Reader 1,180 1.72 2.01 +/-0.13 1.20 - 2.24 A2-1

TABLE A-3. In-House 'Spikew Samples Concentration (pCi/L)a Lab Code Sample Date Analysis Laboratory results Known Control Type 2s, n=lb Activity Limits" SPW-356 water 1/2/2003 Sr-90 34.04 i 1.57 30.93 24.74 - 37.12 W-10303 water 1/3/2003 Gr. Beta 63.24 +/- 1.20 63.90 53.90 - 73.90 W-1 1303 water 1/1312003 Gr. Beta 59.75 +/- 1.10 63.90 53.90 - 73.90 W-12103 water 1/21/2003 Gr. Beta 61.56 +/- 1.59 63.99 53.99 - 73.99 SPAP-446 Air Filter 1/31/2003 Gr. Beta 1.49 +/-0.02 1.52 -8.48 -11.52 SPW-468 water 1/31/2003 H-3 95982.00 +/- 865.00 89607.00 71685.60 - 107528.40 W-20703 water 2/7/2003 Fe-55 9095.00 +/- 114.00 10587.00 8469.60 - 12704.40 SPU-1 347 Urine 3/1/2003 H-3 1724.00 +/-412.00 1784.33 1101.27 - 2467.39 DW-30303 water 3/3/2003 Gr. Beta 65.44 +/- 0.59 63.90 53.90 - 73.90 SPCH-964 Charcoal 3/8/2003 1-131(G) 73.37 +/- 0.28 69.45 59.45 - 79.45 SPMI-1086 Milk 3/13/2003 Cs-137 57.18 +/- 8.03 49.50 39.50 - 59.50 SPMI-1086 Milk 3113/2003 1-131 75.13 +/- 12.01 67.60 54.08 - 81.12 SPMI-1086 Milk 3/1312003 1-131 (G) 65.81 +/- 1.06 67.56 57.56 - 77.56 SPW-1088 water 3/13/2003 Co-60 27.16 +/- 4.79 28.20 18.20 - 38.20 SPW-1088 water 3/13/2003 Cs-137 51.74 +/- 9.15 49.50 39.50 - 59.50 SPW-1 088 water 3/13/2003 1-131 (G) 68.14 +/- 12.92 67.60 57.60 - 77.60 SPW-1088 water 3/13/2003 1-131 76.94 +/- 1.13 67.56 54.05 - 81.07 SPVE-1110 Vegetation, 3/14/2003 1-131 (G) 122.80 +/- 16.80 124.00 111.60 -136.40 SPW-1194 water 3/21/2003 Co-60 31.09 +/- 6.28 28.15 .18.15 - 38.15 SPW-1194 water 3/21/2003 Cs-137 55.11 +/- 0.13 49.50 39.50 - 59.50 SPW-1 194 water 3/21/2003 1-131 (G) 66.17 +/- 9.15 67.60 57.60 - 77.60 W-32103 water 3/21/2003 C-14 5201.00

• 16.60 4966.00 2979.60 - 6952.40 SPCH-1429 Charcoal 4/1/2003 1-131 (G) 8.83 +/- 0.11 9.18 -0.82 - 19.18 W-40103 water 4/1/2003 Gr. Beta 67.74 +/- 0.52 63.39 53.39 - 73.39 SPF-1407 Fish 4/2/2003 Cs-1 34 0.58

• 0.03 0.59 0.35 - 0.83 SPF-1407 Fish 4/2/2003 Cs-137 1.29 i 0.06 1.32 0.79 - 1.85 SPAP-1409 Air Filter 4/2/2003 Gr. Beta 1.44 +/- 0.02 1.51 -8.49 - 11.51 SPU-41203 Urine 4/12/2003 H-3 1798.50 +/- 409.30 1784.33 1101.27 - 2467.39 SPU-41703 Urine 4117/2003 H-3 1625.10 +/- 401.30 1784.33 1101.27 - 2467.39 SPW-2022 water 4/25/2003 H-3 89007.00 +/- 798.00 88463.00 70770A0 - 106155.60 SPW-2053 water 4/28/2003 Cs-137 45.70 +/- 9.44 49.35 39.35 - 59.35 SPW-2053 water 4/28/2003 Sr-90 47.51

• 1.87 44.47 35.58 - 53.36 SPMI-2055 Milk 4/28/2003 Cs-137 61.65

• 7.17 65.80 55.80 - 75.80 SPMI-2055 Milk 4/28/2003 Sr-9o 38.45 +/-1.59 44.74 35.79 - 53.69 W-50603 water 5/6/2003 Gr. Beta 70.95 +/- 0.53 63.39 53.39 - 73.39 W-60303 water 6/3/2003 Gr. Beta 63.00 +/- 0.51 65.73 55.73 - 75.73 SPW-3960 water 7/15/2003 H-3 88700.00 +/- 822.00 87369.00 69895.20 - 104842.80 SPMI-4019 Milk 7/18/2003 Cs-137 47.17 *7.22 49.11 39.11 - 59.11 SPMI-4019 Milk 7/18/2003 Sr-89 40.95

• 4.88 49.49 39.49 - 59.49 SPMI-4019 Milk 7/18/2003 Sr-90 45.30 +/- 1.73 44.24 35.39 - 53.09 SPW-4023 water 7/18/2003 Cs-137 51.92 +/- 6.24 49.11 39.11 - 59.11 SPW-4023 water 7/18/2003 Sr-89 42.49

• 10.23 49.49 39.49 - 59.49 SPW-4023 water 7/18/2003 Sr-90 49.69 +/- 3.04 44.24 35.39 - 53.09 SPW-4518 water 8/8/2003 Fe-55 8176.00 +/- 107.00 9330.00 7464.00 - 11196.00 A3-1

TABLE A-3. In-House "Spike Samples Concentration (pCVL)

Lab Code Sample Date Analysis Laboratory results Known Control Type 2s, n=1b Activity Llmitsc SPW-6197 water 10/16/2003 Tc-99 540.14 t 54.00 539.73 377.81 -701.65 SPAP-3958 Air Filter 10/28/2003 Gr. Beta 1.45 i 0.02 1.50 -8.50 - 11.50 SPW-6401 water 10/28(2003 H--3 84867.00

• 826.00 85984.00 68787.20 - 103180.80 SPAP-6403 Air Filter 10128/2003 Gr. Beta 1.71 t 0.02 1.49 -8.51 -11.49 SPF-6418 Fish 10/28/2003 Cs-1 34 0.50

• 0.02 0.49 0.29 -0.69 SPF-6418 Fish 10/28/2003 Cs-137 1.37 +/- 0.05 1.30 0.78 - 1.82 SPW-6421 water 10/28/2003 Fe-55 104.18 +/-E1.26 88.18 68.18 - 108.18 SPMI-7459 Milk 12112/2003 Cs-134 41.06 +/-t 2.45 41.88 31.88 - 51.88 SPMI-7459 Milk 1211212003 Cs-137 48.48 +/- 4.99 48.64 38.64 - 58.64 SPMI-7459 Milk 1211212003 Sr-89 55.94

• 4.12 65.80 52.64 -78.96 SPMI-7459 Milk 1211212003 Sr-90 41.86 +/- 1.57 43.80 35.04 - 52.56 SPW-7461 water 12/12/2003 Cs-134 44.07 +/- 1.A9 41.88 31.88 - 51.88 SPW-7461 water 12/12/2003 Cs-137 50.26

• 2.67 48.64 38.64 - 58.64 SPW-7461 water 12/12/2003 Sr-89 56.41 +/-4.87 65.80 52.64 -78.96 SPW-7461 water 12112/2003 Sr-90 48.44 +/- 1.84 43.80

• 35.04 - 52.56 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/VLr Lab Code Sample Date Analysis Laboratory results (4.66a) Acceptance Type LLD Activityb Criteria (4.66 a)

SPW-357 water 1/2w2003 Sr-9o 0.50 0.12 i 0.25 1 W-10303 water 1/3/2003 Gr. Beta 0.12 0.022 +/- 0.10 3.2 1113/2003 W-11303 water 1/13/2003 Gr. Beta 0.14 0.035

• 0.10 3.2 W-12103 water 1/21/2003 Gr. Beta 0.12 0.029 +/- 0.09 3.2 SPAP-447 Air Filter 1/31/2003 Gr. Beta 0.00 -0.0034 + 0.00 3.2 SPW-469 water 1/31/2003 H-3 160.20 19.3 +/- 80.30 200 W-20103 water 2/1/2003 Gr. Beta 0.17 0.0 +/- 0.12 3.2 W-20703 water 2/7/2003 Fe-55 802.00 149 +/- 498.00 1000 DW-30303 3/3/2003 Gr. Beta 0.15 0.007

• 0.11 3.2 SPCH-965 Charcoal Cani: 3/8/2003 1-131 (G) 0.01 9.6 SPMI-1087 Milk 3/13/2003 Cs-134 7.49 10 SPMI-1087 Milk 3/13/2003 Cs-137 7.90 10 SPMI-1087 Milk 3/13/2003 1-131 0.33 -0.013 +/- 0.18 0.5 SPMI-1087 Milk 3/13/2003 1-131(G) 7.76 20 SPW-1089 water 3113/2003 Co-60 4.48 10 SPW-1089 water 3/13/2003 Cs-I 34 5.60 10 SPW-1089 water 3/13/2003 Cs-I 37 4.32 10 SPW-1089 water 3/13/2003 1-131 0.29 -0.050 i 0.16 0.5 SPVE-1111 Vegetation 3/14/2003 1-131 (G) 7.53 20 W-32103 water 3/21/2003 C-14 17.50 -0.4 +/- 9.200 200 SPCH-1430 Charcoal Cani: 4/1/2003 1-131 (G) 0.01 9.6 W-40103 water 4/1/2003 Gr. Beta 0.14 -0.11 +/-0.100 3.2 SPF-1408 Fish 4/2/2003 Cs-I 34 0.01 100 SPF-1408 Fish 4/2/2003 Cs-1 37 0.01 100 SPAP-1410 Air Filter 4/2/2003 Gr. Beta 0.00 -0.0029 i 0.002 3.2 SPU-41203 Urine 4/12/2003 H-3 653.99 542.28 +/- 364.780 200 SPU-41703 Urine 4/17/2003 H-3 648.35 100.1 +/-344.800 200 SPW-2054 water 4/28/2003 Cs-1 37 3.16 10 SPW-2054 water 4/28/2003 Sr-89 0.55 0.45 i 0.50 5 SPW-2054 water 4/28/2003 Sr-90 0.55 0.072

• 0.260 1 SPMI-2056 ' Milk 4/28/2003 Sr-90 0.77 0.66 +/- 0.430 1 SPMI-2056 Milk 4/28/2003 Cs-137 2.74 10 SPMI-2056 Milk 4/28/2003 1-131 (G) 3.54 20 W-50603 water 5/6/2003 Gr. Beta 0.12 0 0.090 3.2 W-60303 water 6/3/2003 Gr. Beta 0.14 -0.035 +/- 0.095 3.2 SPW-3960 water 7/15/2003 H-3 156.60 53.4 +/- 80.200 200 SPMI-4018 Milk 7/1812003 Cs-137 4.10 10 SPMI-4018 Milk 7/18/2003 Sr-89 0.73 0.39 +/- 0.880 5 SPMI-4018 Milk 7/18/2003 Sr-90 0.51 0.93 +/- 0.340 1 SPW-4024 water 7/18/2003 Sr-89 0.83 0.21 +/- 0.730 5 SPW-4024 water 7/18/2003 Sr-90 0.62 0.09 +/- 0.300 1 SPW-4519 water 8/812003 Fe-55 527.00 87 +/- 369.000 1000 SPW-6401 water 10/28/2003 H-3 163.80 -23.8 +/- 85.000 200 A4-1

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

SPAP-6404 Air Filter 10128/2003 Gr. Beta 0.87 -0.99

• 0.440 3.2 SPF-641 9 Fish 10/28/2003 Cs-134 0.01 100 SPF-6419 Fish 10/28/2003 Cs-137 0.01 100 SPMI-7460 Milk 12/12/2003 Cs-134 4.52 10 I SPMI-7460 Milk 12/12/2003 Cs-137 5.77 10 SPMI.7460c Milk 12/12/2003 Sr-90 0.50 1.26 i 0.370 1

' Uquid sample results are reported InpCILIIter, air filters( pCIfilter), charcoal (pCIcharcoal canister), and solid samples (pCIkg).

b The acUvity reported Is the net activity result.

' Low levels of Sr-90 are still detected in the environment A concentration of (1-5 pCVL) Inmilk Isnot unusual.

A4-2

TABLEA-5. In-House'Duplicate'Sarribles Concentration (pCUL)'

Averaged Lab Code Date Analysis First Result Second Result Result MI-24, 25 112/2003 K-40 1362.00 i 117.00 1377.00 +/- 188.00 1369.50 +/- 110.72 MI-24, 25 112/2003 Sr-90 1.45 +/- 0.40 2.21 +/- 0.50 1.83 +/- 0.32 CF-47,48 11212003 Gr. Beta 2.72 +/-0.10 2.84 +/- 0.10 2.78 +/- 0.07 CF-47,48 1/2/2003 K-40 2.61 +/- 0.31 2.32 +/- 0.12 2.47 +/- 0.17 AP-8827, 8828 1212003 Be-7 0.06 +/- 0.01 0.05 +/- 0.02 0.05 +/- 0.01 AP-8869, 8870 112/2003 Be-7 0.04 +/- 0.02 0.05 +/- 0.02 0.05 +/- 0.01 MI-119,120 118/2003 K-40 1351.90 +/-116.10 1234.70 +/- 108.70 1293.30 +/- 79.52 MI-119,120 1/8/2003 Sr-90 2.22 +/- 0.43 1.88 +/- 0.40 2.05 +/- 0.30 MI-213,214 1/14/2003 K-40 1372.30 +/- 104.80 1303.80 +/- 109.10 1338.05 +/- 75.64 MI-213, 214 1/14/2003 Sr-9o 1.81 +/-0.41 2.29 +/- 0.45 2.05 +/- 0.31 MI-262,263 1/15/2003 K-40 1399.20 +/- 200.70 1347.70 +/- 126.40 1373.45 +/- 118.59 S-696,697 112912003 Gr. Alpha 24.70 +/-4.89 23.23 +/- 4.64 23.97 +/- 3.37 S-696, 697 1/29/2003 Gr. Beta 22.89 +/- 2.67 22.71 +/- 2.73 22.80 +/- 1.91 MI-448,449 2/3/2003 K-40 1159.70 +/- 157.90 1396.40 +/- 106.20 1278.05 +/- 95.15 SW-470,471 2/3/2003 Gr. Beta 13.62 +/- 1.23 15.21 +/- 1.21 14.42 +/- 0.86 SW-470,471 213/2003 K-40 (ICP) 5.10 +/- 0.51 5.20 +/- 0.52 5.15 +/- 0.36 SW-470,471 2/3/2003 K-40 5.80 +/- 0.51 5.90 +/- 0.52 5.85 +/- 0.36 MI-517, 518 2/412003 K-40 1437.70 +/- 125.50 1357.70 +/- 188.00 1397.70 +/- 113.02 MI-541, 542 2/5/2003 K-40 1443.00 +/- 194.80 1385.20 +/- 190.10 1414.10 +/- 136.09 MI-620, 621 2/11/2003 K-40 1294.70 +/- 115.10 1234.10 +/- 165.10 1264.40 +/- 100.63 DW-922,923 3/4/2003 1-131 0.67 +/- 0.16 0.79 +/- 0.16 0.73 +/- 0.11 CF-1048,1049 b 3/10/2003 K-40 3.09 +/- 0.12 2.67 +/- 0.07 2.88 +/- 0.07 LW-1152,1153 3113/2003 H-3 1147.26 +/- 122.56 1094.42 +/- 120.92 1120.84 +/- 86.09 F-1120,1121 3/1412003 Cs-137 0.04 +/- 0.02 0.05 +/- 0.01 0.05 +/- 0.01 F-1120,1121 311412003 Gr. Beta 2.04 +/- 0.06 2.11 +/- 0.06 2.08 +/- 0.04 F-1120,1121 3114/2003 K40 1.93 +/- 0.38 1.89 +/- 0.25 1.91 +/- 0.23 DW-1278,1279 3/25/2003 1-131 0.37 i 0.22 0.34 +/- 0.29 0.36 +/-0.18 SO-1380, 1381 3125/2003 Gr. Beta 18.60 +/- 2.68 20.53 +/- 2.83 19.57 +/- 1.95 LW-1299,1300 3/27/2003 Gr. Beta 2.35 +/- 0.55 2.48 +/- 0.56 2.42 +/- 0.39 LW-1320, 1321 3/27/2003 H-3 487.12 +/- 104.43 422.00 +/- 102.00 454.56 +/- 72.99 W-1403,1404 3/31/2003 Sr-90 0.96 +/- 0.32 1.10 +/-0.42 1.03 +/- 0.26 AP-2019, 2020 3/31/2003 Be-7 0.07 +/- 0.01 0.08 +/- 0.01 0.07 +/- 0.01 MI-1422,1423 4/1/2003 K-40 1410.00 +/- 176.00 1340.00 +/- 114.00 1375.00 +/- 104.85 MI-2170, 2171 411/2003 K-40 1452.30 +/- 129.10 1472.50 +/- 191.00 1462.40 +/- 115.27 MI-1422,1423 4/2/2003 Sr-90 1.84 +/- 0.42 1.15 +/- 0.39 1.50 +/- 0.29 AP-1633,1634 4/212003 Be-7 0.05 +/- 0.01 0.06 +/- 0.01 0.06 +/- 0.01 AP-1871,1872 41212003 Be-7 0.07 +/- 0.01 0.07 +/- 0.01 0.07 +/- 0.01 AP-1 974, 1975 4/2/2003 Be-7 0.08 +/- 0.02 0.07 +/- 0.02 0.08 +/- 0.01 LW-1828,1829 4/11/2003 Gr. Beta 2.49 +/- 0.58 3.42 +/- 0.63 2.96 +/- 0.43 S-1544,1545 4/1512003 K-40 15.84 +/- 2.36 15A1 +/- 2.02 15.63 +/-1.55 DW-1913,1914 4/15/2003 1-131 0.29 +/- 0.21 0.42 +/- 0.19 0.36 +/- 0.14 MI-1996,1997 4/21/2003 Sr-90 2.05 +/- 0.74 3.25 +/- 0.91 2.65 +/- 0.58 MI-1996,1997 4/22/2003 K-40 1580.20 +/- 118.90 1602.10 +/- 120.40 1591.15 +/- 84.61 A5-1

TABLE A-5. In-House "Duplicate" Samples Concentration (pCVL)8 Averaged Lab Code Date Analysis First Result Second Result Result LW-2063, 2064 4/28/2003 Gr. Beta 2.33 +/- 0.66 2.68 +/- 0.60 2.51

• 0.45 SWU-2275, 2276 4t2812003 Gr. Beta 3.62

• 0.67 4.60 +/- 0.71 4.11 +/-0.49 G-2149, 2150 4/3012003 Be-7 0.71 *00.19 0.69 +/- 0.20 0.70 +/- 0.14 TD-2339, 2340 5/1/2003 H-3 221.00 +/- 91.00 161.00

• 88.00 191.00 +/- 63.29 SO-2381, 2382 5/112003 Cs-137 0.11 0.03 0.10 +/- 0.02 0.10 +/- 0.02 SO-2381, 2382 5/1/2003 Gr. Alpha 11.14 *5.15 10.39 +/- 5.60 10.77 +/- 3.80 SO-2381, 2382 5/1/2003 Gr. Beta 35.18 *4.69 39.66 +/- 5.24 37.42 +/- 3.52 SO-2381, 2382 5/1/2003 K-40 18.29 +/- 0.84 17.83 +/- 0.84 18.06 +/- 0.59 SO-2381, 2382 5/1/2003 Sr-90 0.06 +/- 0.02 0.10

• 0.02 0.08 +/- 0.01 DW-2317, 2318 5/6/2003 1-131 1.77 +/- 0.27 1.47 +/- 0.26 1.62 +/- 0.19 BS-2595,2596 5/6/2003 Cs-137 0.06 +/- 0.02 0.06 +/- 0.02 0.06 +/- 0.02 BS-2595, 2596 5/6/2003 K-40 13.74 +/-0.62 14.10

• 0.73 13.92 +/- 0.48 U-2484, 2485 5/9/2003 H-3 512.00 +/- 100.00 370.00 +/- 95.00 441.00 +/- 68.97 SO-2645, 2646 5/14/2003 Be-7 1.18 +/- 0.42 1.21

• 0.35 1.19 +/- 0.27 S0-2645,2646 5/14/2003 Cs-137 0.11 +/- 0.04 0.09

• 0.05 0.10 +/- 0.03 SO-2645,2646 5/14/2003 K-40 16.50

• 1.13 15.33 *1.09 15.91 +/-0.79 MI-2696. 2697 5119/2003 K-40 1320.40 +/- 124.50 1394.10 +/- 113.00 1357.25 +/- 84.07 MI-2696, 2697 5/19/2003 Sr-90 1.49 +/- 0.47 2.01 i 0.45 1.75 +/- 0.32 SO-2787, 2788 5/28/2003 Cs-I 37 0.27 +/- 0.04 0.23 +/- 0.04 0.25 +/- 0.03 SO-2787, 2788 5/28/2003 Gr. Beta 19.62 +/- 1.73 20.81

• 1.72 20.21 +/- 1.22 SO-2787, 2788 5/28/2003 K-40 14.77

• 1.02 14.41

• 1.00 14.59

• 0.71 MI-2840,2841 5/28/2003 K-40 1179.50 +/- 167.80 1401.70 +/- 120.20 1290.60 +/- 103.20 SWU-2864, 2865 5/28/2003 Gr. Beta 3.39 +/- 0.59 3.41 +/- 0.64 3.40 +/- 0.43 BS-2888, 2889 5/29/2003 Cs-137 0.05 +/- 0.02 0.07 +/- 0.04 0.06 +/- 0.02 BS-2888,2889 5/29/2003 K-40 9.70

• 0.83 10.17

• 0.87 9.93 +/- 0.60 W-3230, 3231 5/30/2003 Gr. Beta 4.33 +/- 1.00 3.28 +/- 1.22 3.81 +/- 0.79 TD-3036,3037 6/2/2003 H-3 529.50

• 100.00 585.50 +/- 102.00 557.50

• 71.42 SL-2909, 2910 b 6/3/2003 Gr. Beta 7.10 +/-0.15 7.60 +/- 0.16 7.35 +/- 0.11 SL-2909, 2910 6/3/2003 K-40 3.90 +/- 0.67 3.49 +/- 0.52 3.70

• 0.42 SW-3080,3081 6/10/2003 Gr. Alpha 4.63

• 1.90 4.47 +/- 1.71 4.55 +/- 1.28 SW-3080,3081 6/10/2003 Gr. Beta 9.07

• 1.29 8.98 +/- 1.28 9.02 +/- 0.91 VE-3172, 3173 6/111/2003 K-40 2.62 +/- 0.35 3.17 +/- 0.58 2.90 +/- 0.34 F-3742, 3743 6/11/2003 Gr. Beta 3.47 +/- 0.13 3.71 +/- 0.14 3.59 +/- 0.10 F-3742,3743 6/11/2003 K-40 2.94 +/- 0.39 2.70 +/- 0.40 2.82 +/- 0.28 SO-3325,3326 6/13/2003 Gr. Beta 20.95

• 1.88 19.97 i 2.01 20.46 +/- 1.38 MI-3253,3254 6/17/2003 K-40 1329.40 +/- 121.80 1417.60

• 130.90 1373.50 +/- 89.40 MI-3297,3298 6/17/2003 Sr-90 2.14 +/- 0.57 2.27

• 0.50 2.21 +/- 0.38 WW-3380, 3381 6/23/2003 Gr. Beta 5.58 +/- 0.69 5.03

• 0.69 5.31 +/- 0.49 SWT-3403,3404 6/24/2003 Gr. Beta 2.80 +/- 0.56 2.63 i 0.55 2.72 +/- 0.39 MI-3424,3425 6/24/2003 K-40 1422.80 +/- 185.40 1216.20

• 170.10 1319.50 +/- 125.80 SW-3862,3863 6/24/2003 Gr. Beta 3.66 +/- 1.18 3.70

• 1.22 3.68 +/- 0.85 G-3479, 3480 6/25/2003 Be-7 1.52 +/- 0.25 1.43

• 0.28 1.47 +/- 0.19 G-3479,3480 6/25/2003 K-40 5.02 +/- 0.45 5.10

• 0.48 5.06 +/- 0.33 LW-3809, 3810 6/30/2003 Gr. Beta 2.12 +/- 0.76 2.39 +/- 0.72 2.25

• 0.52 A5-2

TABLE A-5. In-House "Duplicate" Samples Concentration (pCi/L)s Averaged Lah Code Daqte .

Analvsis First Result Second Result Result LW-3809, 3810 6/3012003 H-3 2814.09

• 167.99 2812.17 +/-167.94 2813.13 +/- 118.77 AP-4105,4106 6/30/2003 Be-7 0.07 +/-0.01 0.07 + 0.01 0.07 +/- 0.01 G-3572,3573 7/1/2003 Be-7 0.91 +/-0.24 0.81 i0.28 0.86 +/- 0.18 G-3572,3573 7/1/2003 Gr. Beta 6.35 +/-0.15 6.35 +/- 0.15 6.35 +/- 0.11 G-3572,3573 7/1/2003 K-40 5.44 +/-0.55 5.68 +/- 0.28 5.56 +/- 0.31 G-3572,3573 7/1/2003 Sr-90 0.01 +/-0.00 0.02 +/- 0.00 0.01 +/- 0.00 MI-3601, 3602 7/1/2003 K-40 1318.60 +/-117.40 1435.10 +/-117.80 1376.85 +/- 83.16 MI-3601, 3602 7/1/2003 Sr-90 0.86 +/-0.51 1.74 +/-0.60 1.30 +/- 0.39 AP-3933, 3934 7/1/2003 Be-7 0.07 +/-0.01 0.07 +/-0.01 0.07 +/- 0.01 AP-4061, 4062 7/2/2003 Be-7 0.07  : 0.01 0.08 i 0.01 0.08 +/- 0.01 AP-4147,4148 7/2/2003 Be-7 0.08 +/-0.01 0.07 i 0.01 0.07 +/- 0.01 AP-4084,4085 7/3/2003 Be-7 0.09 +/-0.02 0.08 i 0.02 0.08 +/- 0.01 LW-3786,3787 7/9/2003 Gr. Beta 2.13 +/-0.56 2.93 +/-0.62 2.53 +/- 0.42 WW-4168, 4169 7/11/2003 Gr. Beta 3.79 +/-1.87 4.48 +/- 1.98 4.14 +/- 1.36 CF-3975, 3976 7/14/2003 Be-7 1.64 +/-0.81 1.66 +/- 0.57 1.65 +/- 0.50 CF-3975, 3976 7/14/2003 K-40 6.54 +/-t0.75 6.19 +/- 0.50 6.36 +/- 0.45 MI-4020,4021 7/16/2003 K-40 1350.90 +/- 174.90 1199.80 +/- 153.20 1275.35 +/- 116.25 DW-4272,4273 7/29/2003 Gr. Beta 2.35 +/- 0.92 2.29 +/- 0.89 2.32 +/- 0.64 SWU-4461,4462 7/30/2003 Gr. Beta 2.28 +/- 0.44 1.93 +/- 0.43 2.10 +/- 0.31 SL-4398,4399 8/4/2003 Be-7 4.55 +/-1.05 4.50 +/- 1.10 4.53 +/- 0.76 SL-4398,4399 b 8/4/2003 Gr. Beta 3.41 +/-0.12 3.12 +/- 0.11 3.27 +/- 0.08 SL-4398,4399 8/4/2003 K-40 2.47 +/-0.67 2A4 +/- 0.87 2.46 +/- 0.55 G-4419.4420 8/4/2003 Be-7 3.98 + 0.63 3.93 +/- 0.57 3.96 +/- 0.42 G-4419,4420 8/4/2003 Gr. Beta 5.38 f 0.14 5.35 +/- 0.16 5.37 +/- 0.11 G-4419,4420 8/4/2003 K-40 4.42 +/-0.66 4.32 +/- 0.74 4.37 +/- 0.50 TD-4550,4551 8/4/2003 H-3 327.30 i 95.10 390.20 +/- 92.10 358.75 +/- 66.19 MI-4482,4483 8/6/2003 K-40 1301.40

• 115.20 1370.30 +/- 116.80 1335.85 +/- 82.03 MI-4482,4483 8/6/2003 Sr-90 0.81 +/-0.30 0.85 +/- 0.31 0.83 +/- 0.21 G-4526,4527 8/6/2003 Be-7 1.47

• 0.29 1.42 +/- 0.28 1.45 +/- 0.20 G-4526,4527 8/6/2003 K-40 5.42 + 0.56 5.21 +/- 0.63 5.31 +/- 0.42 SWU-4609,4610 8/6/2003 Gr. Beta 3.22 +/-0.63 2.67 +/- 0.64 2.95 +/- 0.45 CW-4694,4695 8/6/2003 Gr. Beta 1.48

• 0.34 1.09 +/- 0.34 1.29 +/- 0.24 CW-4694,4695 8/6/2003 H-3 22776.41

• 428.73 21831.75 +/- 420.10 22304.08 +/- 300.12 LW-4673,4674 8/13/2003 Gr. Beta 2.86

• 0.65 3.75 +/- 0.71 3.30 +/- 0.48 MI-4735,4736 8/19/2003 K-40 1396.30 +/-127.90 1410.10 +/- 120.20 1403.20 +/- 87.76 MI-4756,4757 8/19/2003 Sr-90 1.66

• 0.47 1.53 +/- 0.44 1.60 +/- 0.32 VE-4832,4833 8/20/2003 K-40 1.96

• 0.50 1.43 +/- 0.47 1.70 +/- 0.34 MI-4860,4861 8/26/2003 K-40 1312.10 +/-191.80 1307.80 +/- 109.30 1309.95 +/- 110.38 SO-5082, 5083 8/28/2003 Cs-137 0.01 *0.00 0.01 +/- 0.00 0.01 +/- 0.00 SO-5082,5083 8/28/2003 Gr. Beta 20.02

• 1.84 20.92 +/- 2.03 20.47 +/- 1.37 CW-5349,5350 8/31/2003 Gr. Beta 1.45

• 0.39 1.55 +/- 0.45 1.50 +/- 0.30 CW-5349, 5350 8/31/2003 H-3 24429.50

• 444.42 24744.25 +/-447.18 24586.88 +/-315.23 ME-4968,4969 9/2/2003 Gr. Beta 4.90 +/-0.23 5.18 +/- 0.24 5.04 +/- 0.17 ME-4968,4969 9/2/2003 K-40 2.46 F 0.41 2.68 +/- 0.37 2.57. 0.28 A5-3

TABLEA-5. In-House"Duplicate"SSarples Concentration (pCVL)-

Averaged Lab Code Date Analysis First Result Second Result Result*

DW-4989, 4990 9/212003 Gr. Beta 2.20 +/- 1.04 3.19 +/- 1.14 2.70 +/- 0.77 MI-5154, 5155 9/8/2003 K-40 1365.50 +/- 116.70 1456.70 +/- 119.10 1411.10 i 83.37 MI-5154, 5155 918/2003 Sr-90 1.19 +/-0.39 1.39 +/- 0.39 1.29 i 0.28 AP-6177, 6178 9/29/2003 Be-7 0.07 +/- 0.01 0.06 +/- 0.01 0.06

• 0.01 SWU-5773, 5774 9/30/2003 Gr. Beta 2.55 +/- 0.63 2.83 +/- 0.60 2.69 +/- 0.44 AP-6102, 6103 9/30/2003 Be-7 0.07 +/- 0.01 0.05 +/- 0.01 0.06 i 0.01 G-5631, 5632 10/1/2003 Be-7 1.88 +/-0.48 2.21 +/- 0.40 2.05 i 0.31 G-5631, 5632 10/1/2003 Gr. Beta 5.87 +/- 0.09 5.85 +/- 0.08 5.86

• 0.06 G-5631, 5632 10/11/2003 K-40 5.24 *d0.77 5.26 +/- 0.58 5.25 i 0.48 S0-5660, 5661 10/1/2003 Cs-137 0.15 +/- 0.04 0.16 +/- 0.05 0.16

• 0.03 SO-5660, 5661 10/1/2003 Gr. Alpha 12.72 +/- 3.72 14.86 +/- 3.88 13.79 +/- 2.69 SO-5660, 5661 1011/2003 Gr. Beta 32A2 +/- 3.09 33.60 +/- 3.04 33.01 +/- 2.17 SO-5660, 5661 1011/2003 K-40 18.93 +/- 0.87 18.25 +/- 1.19 18.59

• 0.74 SO-5660, 5661 10/1/2003 Sr-90 0.03

• 0.01 0.03 i 0.01 0.03 i 0.01 AP-6334, 6335 10/1/2003 Be-7 0.06 *E0.01 0.06 +/- 0.01 0.06 i 0.01 AP-6363, 6364 10/212003 Be-7 0.07

• 0.02 0.07 +/- 0.02 0.07 +/-0.01 MI-5794. 5795 10/6/2003 Sr-90 1.37 +/- 0.37 1.02 +/- 0.37 1.19 i0.26 MI-5838, 5839 10/8/2003 K-40 1364.30

• 124.10 1414.40 +/-110.40 1389.35 i 83.05 MI-5838, 5839 10/8/2003 Sr-90 0.76 +/- 0.30 1.00 +/- 0.34 0.88 i 0.23 BS-5938, 5939 1018/2003 Cs-I 37 0.18 +/- 0.03 0.20 +/- 0.05 0.19 i 0.03 BS-5938, 5939 10/812003 K-40 15.59 +/- 0.70 16.69 +/- 0.80 16.14 i0.53 SS-5959, 5960 10113/2003 K-40 7A9 +/- 0.42 7.29 +/- 0.63 7.39 i 0.38 MI-6011, 6012 10113/2003 K-40 1165.20 +/- 118.70 1191.20 +/- 99.50 1178.20 i77A4 MI-6034, 6035 10/14/2003 Sr-90 0.86 +/- 0.33 0.90 +/- 0.34 0.88 +/- 0.24 VE-6055, 6056 1011512003 Gr. Beta 5.18 +/- 0.18 5.33 +/- 0.18 5.25 +/- 0.13 VE-6055, 6056 10/15/2003 K-40 5.31 +/- 0.57 4.52 +/- 0.51 4.92 +/- 0.38 MI-6291, 6292 10/21/2003 K-40 1935.60 +/- 147.70 1936.10

• 116.50 1935.85 +/- 94.06 MI-6291, 6292 10/21/2003 Sr-90 1.22

• 0.39 1.41 +/- 0.37 1.31 +/- 0.27 SS-6435, 6436 10/21/2003 Cs-I 37 0.05

• 0.02 0.05 +/- 0.03 0.05 +/- 0.02 SS-6435, 6436 10121/2003 K-40 14.08

• 0.54 14.28 +/- 0.80 14.18 +/- 0.48 CF-6313, 6314 10/22/2003 K-40 14.56 +/- 0.45 14.70 +/- 0.95 14.63 +/- 0.53 SO-6528, 6529 10/22/2003 Cs-I 37 0.15

• 0.03 0.16 +/- 0.05 0.16 +/- 0.03 SO-6528, 6529 10/22/2003 K-40 17.46 +/- 0.69 17.90 +/- 1.05 17.68 +/- 0.63 SO-6393, 6394 10125/2003 Cs-I 37 0.09 +/- 0.03 0.10 +/- 0.04 0.10 +/- 0.03 SO-6393, 6394 10125/2003 Gr. Beta 23.21

• 1.98 21.76 +/- 1.91 22.48 +/- 1.38 SO-6393, 6394 10125/2003 K-40 13.98 +/- 0.80 14.57 +/- 0.86 14.27 i0.59 SWT-6507, 6508 1012812003 Gr. Beta 2.64

• 0.52 2.63 +/- 0.53 2.63 i 0.37 DW-6647, 6648 10/31/2003 1-131 0.46 +/- 0.27 0.61 i0.31 0.53 i 0.21 BS-6603, 6604 11/3/2003 Cs-137 9.03 +/- 0.82 8.60 +/- 1.13 8.82 i 0.70 BS-6603, 6604 11/3/2003 Gr. Beta 26.83 +/- 1.94 27.18 +/- 1.95 27.01 +/- 1.38 S0-6670, 6671 11/512003 Cs-137 0.15

• 0.04 0.13 +/- 0.04 0.14 +/- 0.03 S0-6670, 6671 11/512003 K-40 12.96 +/- 0.66 12.95 +/- 0.72 12.96 +/- 0.49 S-7067, 7068 11/1012003 Cs-137 0.21 +/- 0.05 0.19 i 0.08 0.20

• 0.05 MI-6818, 6819 11/11/2003 K-40 1695.50 -t 129.80 1709.40 +/- 143.00 1702.45 +/- 96.56 A5-4

TABLEA-5. In-House"Duplicate Samples Concentration (pCVL)a Averaged Lab Code Date Analysis First Result Second Result Result MI-6818,6819 11/11/2003 Sr-90 2.01

• 0.41 1.59

• 0.39 1.80 +/- 0.28 WL-6987, 6988 11117/2003 Fe-55 603.49 +/- 53.32 619.65 +/-53.97 611.57 + 37.93 SO-7156, 7157 11/21/2003 Cs-1 37 0.74 +/- 0.08 0.77

• 0.07 0.76 +/- 0.06 SO-7156, 7157 11/21/2003 Gr. Alpha 14.90 i 4.24 19.25 *4.45 17.07 +/- 3.07 SO-7156,7157 11/21/2003 Gr. Beta 22.97 +/- 3.12 25.51 +/- 2.98 24.24 +/- 2.16 SO-7156, 7157 11/21/2003 K-40 12.51 *E1.06 12.94

• 1.07 12.73 +/- 0.75 S-7281, 7282 11/24/2003 Cs-1 37 0.82

• 0.15 1.16 +/- 0.20 0.99 +/- 0.12 SWU-7198, 7199 11/25/2003 Gr. Beta 2.60 +/- 0.53 2.54 +/- 0.55 2.57 +/- 0.38 DW-7221, 7222 11/25/2003 Gr. Beta 12.32 +/- 1.40 12.38 +/- 1.43 12.35 +/- 1.00 SW-7133, 7134 12/1/2003 Gr. Beta 2.10

• 0.23 2.46 +/- 0.23 2.28 +/- 0.16 SW-7133,7134 12/1/2003 K-40 1.50 +/- 0.15 1.40 +/- 0.14 1.45 +/- 0.10 W-7519, 7520 12/1/2003 Fe-55 3.03 +/- 0.65 3.12 +/- 0.64 3.08 +/- 0.46 SW-7805,7806 12/1/2003 Sr-90 0.59 +/- 0.32 0.56

• 0.33 0.58 +/- 0.23 VE-7399, 7400 12/9/2003 Gr. Beta 4.99 +/- 0.15 5.24 +/- 0.15 5.11 +/-0.11 VE-7399, 7400 12/9/2003 K-40 5.04 +/- 0.46 5.34 +/- 0.74 5.19.+/- 0.43 SW-7540, 7541 12/9/2003 Gr. Alpha 2.64 +/- 1.36 2.10 +/- 1.19 2.37 +/-0 .91 SW-7540,7541 12/9/2003 Gr. Beta 6.62 +/-1.22 5.89

• 1.35 6.25 +/- 0.91 LW-7736, 7737 12/26/2003 Gr. Beta 2.62 +/- 0.54 2.83 +/- 0.56 2.73 +/- 0.39 AP-7868,7869 12/30/2003 Be-7 0.05 +/- 0.01 0.04

• 0.01 0.04 +/- 0.01 AP-7952,7953 12/30/2003 Be-7 0.04 +/- 0.01 0.04

• 0.01 0.04 +/- 0.01 AP-7994, 7995 12/31/2003 Be-7 0.05 +/- 0.02 0.05

• 0.01 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.

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

b 200 minute count time or longer, resulting In lower error.

A5-5

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

Concentrationb Known Control Lab Code Type Date Analysis Laboratory result Activity Limits' STW-972 water 12101/02 Am-241 0.56 + 0.06 0.58 +/- 0.09 0.40 - 0.75 STW-972 water 12101102 Co-57 57.10 i 1.90 57.00 +/- 5.70 39.90 - 74.10 STW-972 water 12/01/02 Co-60 38.30 i 0.60 38.20 +/- 3.82 26.74 - 49.66 STW-972 water 12/01/02 Cs-134 395.30 i 10.10 421.00 +/- 42.10 294.70 - 547.30 STW-972 water 12/01/02 Cs-137 316.40 +/-5.30 329.00 +/- 32.90 230.30 - 427.70 STW-972 water 12/01/02 Fe-55 94.90 +/- 24.50 96.00 *9.60 67.20 - 124.80 STW-972 water 12/01102 Mn-54 33.40 +/- 0.10 32.90 *3.29 23.03 -42.77 STW-972 water 12/01/02 Ni-63 123.80 +/- 5.50 136.50 +/- 13.70 95.55 - 177.45 STW-972 water 12/01/02 Pu-238 0.66 +/- 0.06 0.83 +/- 0.08 0.58 - 1.08 STW-972 water 12/01/02 Pu-239/40 0.061 +/- 0.001 0.000 +/- 0.000 0.000 - 0.005 STW-972 water 12/01/02 Sr-90 13.80 +/- 1.00 12.31 +/- 1.23 8.62 - 16.00 STW-972 water 12/01/02 Tc-99 128.10 +/- 3.80 132.00

• 13.20 92.40 - 171.60 STW-972 water 12101/02 U-233/4 1.60 +/- 0.09 1.54

• 0.15 1.08 - 2.00 STW-972 water 12/01/02 U-238 1.64 +/- 0.09 1.60 +/- 0.16 1.12 - 2.08 STW-972 water 12/01102 Zn-65 540.40 +/- 9.90 516.00 +/- 51.60 361.20 - 670.80 STSO-987 soil 01/01/03 Co-57 534.36 +/- 2.61 530.00

• 53.00 371.00 - 689.00 STSO-987 soil 01/01/03 Co-60 442.16 +/- 2.31 420.00 +/- 42.00 294.00 - 546.00 STSO-987 soil 01/01/03 Cs-134 211.00 +/- 2.30 238.00

• 23.80 166.60 - 309.40 STSO-987 soil 01/01/03 Cs-1 37 849.50 +/- 3.30 832.00 +/- 83.20 582.40 - 1081.60 STSO-987 soil 01/01/03 K-40 716.50 +/- 12.80 652.00

• 65.20 456.40 - 847.60 STSO-987 soil 01/01/03 Mn-54 148.76 +/- 2.84 137.00 +/- 13.70 95.90 - 178.10 STSO-987 soil 01/01/03 Ni-63 597.10 +/- 23.50 770.00 +/- 77.00 539.00 - 1001.00 STSO-987 soil 01/01/03 Pu-238 67.05 +/- 3.10 66.90 +/- 6.70 46.83 - 86.97 STSO-987 soil 01/01/03 Pu-239/40 52.80 +/- 3.60 52.70 +/- 5.30 36.90 - 68.50 STSO-987 soil 01/01/03 Sr-90 609.50 +/- 9.80 714.00 +/- 71.40 499.80 - 928.20 STSO-987 soil 01/01/03 U-23314 99.50 +/- 7.60 89.00 +/- 8.90 62.30 - 115.70 STSO-987 soil 01/01/03 U-238 508.60 +/- 42.20 421.00 +/-42.10 294.70 - 547.30 STSO-987 soil 01/01/03 Zn-65 492.70 +/-28.10 490.00 +/-49.00 343.00 - 637.00

' Results obtained by Environmental, Inc. ,Midwest Laboratory as a participant in the Department of Energy's Mixed Analyte Performance Evaluation Program, Idaho Operations office, Idaho Falls, Idaho b All results are in Bq/kg or Bq/L as requested by the Department of Energy.

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

A6-1

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

Concentration" EML Control Lab Code Type Date Analysis Laboratory results Result0 Limits' STW-977 water 03101103 Gr. Alpha 304.30 *h53.10 377.50 0.58 - 1.29 STW-977 water 03/01103 Gr. Beta 615.80 +/- 14.70 627.50 0.61 - 1.43 STW-978 water 03/01103 Am-24i 2.00 +/- 0.10 2.13 0.79 - 1A1 STW-978 water 03/01103 Co-60 221.30 +/- 1.20 234.00 0.80 - 1.20 STW-978 water 03101iO3 Cs-134 23.30 +/- 1.10 30.50 0.80 - 1.30 STW-978 water 03/01/03 Cs-137 61.40 *k0.60 63.80 0.80 - 1.22 STW-978 e water 03101/03 H-3 341.90 i 22.70 390.00 0.78 - 2.45 STW-978 water 03/01/03 Pu-238 3.70 +/- 0.20 3.33 0.74 - 1.20 STW-978 water 03/01/03 Pu-239/40 4A.0 +/-0.10 3.92 0.79 - 1.20 STW-978 water 03/01/03 Sr-90 4.60 +/- 0.30 4.34 0.69 - 1.34 STW-978 water 03/01103 Uranium 5.10 +/- 0.60 4.29 0.75 - 1.33 STSO-979 soil 03/01/03 Ac-228 55.60 +/-2.50 57.60 0.80 - 1.38 STSO-979 soil 03/01/03 Am-241 12.42 +/- 0.90 15.60 0.65 - 2.28 STSO-979 soil 03/01/03 BI-212 57.70 +/-3.20 60.60 0.50 - 1.34 STSO-979 soil 03/01/03 Bi-214 60.40 +/- 3.20 67.00 0.78 - 1.42 STSO-979 soil 03/01/03 Cs-137 1416.80 +/- 70.00 1450.00 0.80 - 1.25 STSO-979 soil 03101/03 K-40 653.80 +/- 11.90 636.00 0.80 - 1.32 STSO-979 soil 03/01/03 Pb-212 51.10 +/- 5.20 57.90 0.78 - 1.32 STSO-979 soil 03/01/03 Pb-214 64.70 +/- 5.10 71.10 0.76 - 1.46 STSO-979 soil 03/01/03 Pu-239/40 24.40 +/- 0.30 23.40 0.71 - 1.30 STSO-979 soil 03/01/03 Sr-90 54.50 +/- 2.60 64.40 0.67 - 2.90 STSO-979 soil 03/01103 Uranium 245.00 +/- 1.50 249.00 0.71 - 1.32 STVE-980 Vegetation 03/01/03 Am-241 3.10 +/- 0.20 3.51 0.73 -2.02 STVE-980 Vegetation 03/01/03 Cm-244 1.40 +/- 0.50 2.01 0.61 - 1.59 STVE-980 Vegetation 03/01/03 Co-60 12.60 +/- 0.40 12.10 0.80 - 1.44 STVE-980 Vegetation 03/01/03 Cs-137 449.70 +/- 6.20 444.00 0.80 - 1.31 STVE-980 Vegetation 03/01/03 K-40 1159.00 +/-38.60 1120.00 0.79 -1.39 STVE-980 Vegetation 03/01103 Pu-239140 4.80 +/- 0.40 5.17 0.69 - 1.31 STVE-980 Vegetation 03/01/03 Sr-90 659.70 +/- 50.40 650.00 0.55 -1.21 STAP-981 Air Filter 03/01/03 Arn-241 0.27 +/- 0.10 0.34 0.70 -2.34 STAP-981 Air Filter 03/01/03 Co-60 30.20 +/- 0.30 33.50 0.80 - 1.26 STAP-981 Air Filter 03/01/03 Cs-137 90.30

• 1.30 99.70 0.80 - 1.32 STAP-981 Air Filter 03/01/03 Mn-54 41.80 +/- 0.60 43.80 0.80 - 1.35 STAP-981 Air Filter 03101/03 Pu-238 0.52 +/- 0.10 0.52 0.67 - 1.33 STAP-981 Air Filter 03/01/03 Pu-239/40 0.35 +/- 0.10 0.33 0.73 - 1.26 STAP-981 Air Filter 03/01/03 Sr-90 2.50 +/- 0.10 2.80 0.53 - 1.84 STAP-981 Air Filter 03/01103 Uranium 0.51 +/- 0.10 0.50 0.79 -2.10 STAP-982 Air Filter 03/01103 Gr. Alpha 0.90 i 0.10 1.17 0.73 - 1.43 STAP-982 Air Filter 03/01/03 Gr. Beta 1.50 +/- 0.10 1.50 0.76 - 1.36 A7-1

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

Concentration' EML Control Lab Code Type Date Analysis Laboratory results Result limits0 STW-992 water 09102103 Am-241 9.78

• 0.32 8.76 0.79 - 1.41 The September, 2003 results are preliminary. Control limits used were taken from the March, 2003 data.

Control limits may vary slightly when the final study is published.

STW-992 water 09/02/03 Co-60 468.30

• 4.10 513.00 0.80 - 1.20 STW-992 water 09/02103 Cs-134 53.90 i 0.80 63.00 0.80 - 1.30 STW-992 water 09/02/03 Cs-137 76.10

• 1.40 80.30 0.80 - 1.22 STW-992 water 09/02/03 H-3 355.20

• 12.80 446.30 0.78 - 2A5 STW-992 water 09102/03 Pu-238 1.71

• 0.07 2.07 0.74 -1.20 STW-992 water 09/02103 Pu-239140 4.24 +/- 0.01 4.99 0.79 - 1.20 STW-992 water 09/02/03 Sr-90 6.70

• 0.50 7.04 0.69 - 1.34 STW-992 water 09/02103 Uranium 6.03 + 0.14 5.69 0.75 - 1.33 STW-993 water 09/02/03 Gr. Alpha 688.00 i 7.60 622.00 0.58 - 1.29 STW-993 water 09/02103 Gr. Beta 1985.00

• 111.00 1948.00 0.61 - 1.43 STSO-994 soil 09/02/03 Am-241 19.70

• 1.50 18A0 0.65 - 2.28 STSO-994 soil 09/02103 Cs-137 1928.00 *E19.00 1973.00 0.80 -1.25 STSO-994 soil 09102/03 K-40 533.00

• 79.00 488.00 0.80 - 1.32 STSO-994 soil 09102/03 Pu-238 15.30

• 0.80 14.60 0.59 - 2.88 STSO-994 soil 09/02103 Pu-239140 32.50 i 2.30 30.40 0.71 - 1.30 STSO-994 soil 09102103 Sr-90 69.80 i 2.30 80.30 0.67 - 2.90 STSO-994 soil 09/02103 Uranium 228.30 +/- 17.10 259.30 0.71 - 1.32 STAP-995 Air Filter 09/02103 Am-241 0.64

• 0.05 0.44 0.70 - 2.34 STAP-995 Air Filter 09/02/03 Co-60 48.50

• 0.40 55.10 0.80 - 1.26 STAP-995 Air Filter 09/02/03 Cs-137 51.20 +/- 1.10 54.80 0.80 - 1.32 STAP-995 Air Filter 09/02103 Mn-54 *53.70

• 1.10 58.00 0.80 -1.35 STAP-995 Air Filter 09/02/03 Pu-238 0.24 i 0.05 0.23 0.67 - 1.33 STAP-995 Air Filter 09102/03 Pu-239140 0.41 +/-0.10 0.40 0.73 - 1.26 STAP-995 Air Filter 09/02/03 Sr-90 1.90 I 0.10 2.06 0.53 -1.84 STAP-995 Air Filter 09102103 Uranium 0.80  : 0.06 0.82 0.79 -2.10 STAP-996 Air Filter 09/02/03 Gr. Aipha 3.23

• 0.07 3.11 0.73 - 1.43 STAP-996 Air Filter 09102/03 Gr. Beta 4.168

• 0.03 3.89 0.76 - 1.36 Results are reported In Bq/L with the following exceptions: Air Filters (Bq/Filter), Soil and Vegetation (Bq/kg).

b The EML result listed Is the mean of replicate determinations for each nuclide

• the standard error of the mean.

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

d A low bias for Cs-134 activity has been observed Inthe past. No errors have been found In the library or efficiency.

Additional spike analyses will be performed and a correction factored Into the calculation.

• Reporting error.

A7-2

APPENDIX B DATA REPORTING CONVENTIONS B-1

Data Reporting 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 +/- st and X2 +/- s2 Reoorted result: x +/- s; where x = (1/2) (xi + x2) and s = (1/2) 1 +52 3.2. Individual results: <LI , <2 Reported result: <L, where L = lower of Li and L2 3.3. Individual results: x + s, AL Reported result: x i s if x aL; <L otherwise.

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

x = Lx.

• EX x~\ S= , xn-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-1

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

Air (pCVm 3 ) Water (pCiL)

Gross alpha I xIO0-3 Strontium-89 8,000 Gross beta 1 Strontium-90 500 Iodine-I 31 b 2.8 x 10-1 Cesium-137 1,000 Barium-140 8,000 Iodine-131 1,000 Potassium-40c 4,000 Gross alpha 2 Gross beta 10 Tritium I x106 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 JI PLANT AREA ENLARGED PLAN [1.00 MILE RADIUS)

ENO SCALE] .

MONITORING LEGEND:

Q N.S.P. TLO POINTS D-2 TL.O01 .DGN D-2 TL001.DGN

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

Q N.S.P. TLD POINTS D-3 TL002.OGN

TLO LOCATIONS FIVE MILE RADIUS MONITORING LEGEND:

(i) N.S.P. TLD POINTS D4 TLOO3.DGN D-4 TL003.OGN

ENVIRONMENTAL SAMPLING POINTS ONE MILE RADIUS I 'I -.

PLANT AREA ENLARGED PLAN (1.00 MILE RADIUS]

[NO SCALE]

MONITORING LEGEND MILK SAMPLING POINT 10 NUMBERS FISH SAMPLING POINT ID NUMBERS P-14. P-18. P-25, P-37. P-39 P-13. P-l1 A AIR SAMPLING POINT 10 NUMBERS P-l. P-2, P-3, P-4. P-6 0 INVERTEBRATES POINT IO NUMBERS P-E. P-40 waTER SAMPLING POINT IO NUMBERS SEDIMENT SAMPLING POINT IO NUMBERS P-. P-8. P-i. P-ll, P-25

.P-5, P-6. P-12. P-20 E VEGETABLES ID NUMBERS ElVEGETATION P-24, P-38

/

D-5 SAMP01.OGN D-5 SAMP01.OGN

ENVIRONMENTAL SAMPLING POINTS FIVE MILE RADIUS MONITORING LEGENO MILX SAMPLMG POINT I0 JOMERS A FISHSAMPLNG POINT I0 "BERS v P-34. P-1S. P-25. P-37. P-3 P- Pl-li

^ AIR SAMPLING POINT 10 SBEAS INVERTESRATES POINT 10 N"ERS A P P.3.P2. P-4.P-6 P-.SP.48 WATER SAHPLING POINT 10MJMBERS SECIMENT SAMPLING POINT 10 SIEURS 0 P. *% t; P-C. 10-11. teP-25 P-4 P-12. P-21 f VECETATION / VEGETABLES 10 ERS D-6 SAMP03.DGN

- I ENVIRONMENTAL SAMPLING POINTS

)Huppert Far., W10430 St Rd 29, River Falls, WI

- Cain Residence, N7395 950th St, River Falls, WI CONTROL POINTS PRESCOTT, WISCONSIN Monitoring Legend A Milk Sampling Point ID Numbers P-14, P-18, P-37, P-39, P-41

^ Air Sampling Point ID Numbers P-1, P-2, P-3, P-4, P-6 Q Water Sampling Point ID Numbers P-5, P-6, P-8, P-9, P-11, P.41 Ef Vegetation I Vegetables Point ID Numbers P-24, P.38 D-7 D-7 SAMP02.DGN' SAMP02.DGN